ML20083K435

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Inservice Insp Rept,Class I & II Sys, for 830606-840103
ML20083K435
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/29/1984
From: Mroczka E
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
MP-5927, TAC-51574, NUDOCS 8404160171
Download: ML20083K435 (44)
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Text

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s Inservice Inspection Report Class I & II SYSTEM -

Millstone Nuclear Power Station c' '

Unit # 2 P.O. Box 128 '

Waterford, Connecticut 06385

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j Owner: ,

l i Northeast Nuclear Energy Company P.O. Box 270 l .

l Hartford, Connecticut 06101 3

Commercial Service Date:> I > ~

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' , December 26, 1975 i

Report Date: N

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FEBRUARY 29,198'e k

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840416 171 840229 PDR ADOCKsv05000336

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PAGE 2 D

NUSCO I

Table of Contents Section Title I Owner's Data Report (Form NIS-1)

II Introduction III Definitions IV NDE Procedures, Equipment and Personnel Qualifications V Exclusions and Exceptions VI Conditions Noted VII EXAMINATION RESULTS I

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FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules G

V 1. Owner Northeast Nuclear Energy Co., P.O. Box 270, Hartford, Ct. 06101 (Name and Address of Owner)

2. Plant Millstone Nuclear Power Station, P.O. Box 128, Waterford, Ct. 06385 (Name and Address of Plant)
3. Plant Unit 4. Owner Certificate of Authorization (if required) (NR)
5. Commercial Service Date 12/26/75 6. National Board Number for Unit 20914
7. Components Inspected By: Northeast Utilities Service Co.

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No, M. - u:;

S. G. #1 I. - Bechtel NA NA 20928 M. - CE S. G. #2 I. - Bechtel NA NA 20929 Piping, Valves, and Pumps I. - Bechtel NA NA NA Support Mernbe2 s

& Cuuporaants I. - Bechtel NA NA NA Przr. Manway (PRZR)

Studs M. - CE NA NA 20918 Class 1 Systern

( Hydro NA NA NA IR L 7. a. Comporents Inspected By: CE Pcwer Systems Beactor Vessc]

56 Welds M-CE, 67110 NA 20914 57 Insp.

Areas --

Steam Generatc'r

  1. 2 Stay Cylin- M-CE 67511 NA 20929 der Welds _ _

Primary Pipinc'

> nni- Ton al u_<v 502-19 NA None 3 Weld 5 _ _

Primary Pipinc' Hot Iag #2 M-CE 502-19 NA None 3 Welds.

Class.I Systert Isak Test I-Bechtel NA NA NA 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 eact sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

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

! FORM NIS-1 (back) o 8. Examination Dates 6/6/83 to 1/3/84 9. inspection interval from R /?A /R2 to 19 /?x /95

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. 169 examinations were perforned. '1his is approximately 33%

of the inspections required this interval.

11. Abstract of Conditions Noted.

See Attached.

12. Abstract of Corrective Measures Recommended and Taken
See Attached.

We certify that the statements made in this report are correct and the examinations and corrective men-

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

Date OIOUL #-

  • A7 19 k Signed Nhmnn B Owner (J. J. ley, Bucerintendent Millstone Unit 2)

Certificate of Authorization No. (if applicable) (NA) Expiration Date (NA)

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Cf and employed by N8 _f / f of W4 Thal have inj)pected the. components and state that todescribed the best of in mythis Owners' andData belief,Report during the perio 4/4#2 to // /ff knowledge the Owner k J has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

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By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore,

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

Date 5 Y 19 VY

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. [W Commissions OI ///9 /88 98@/M National Board, State, Province and No.

- Inspeffor's Signature ~

Abbreviations: NUSGo- Northeast Utilities Service Co.

'I@E00 Northeast Nuclear Energy Co.

Htfd Stm Boiler Hartford Steam Boiler CE Otrnbustion Engineering.Inc.

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ATTACHMENT TO FORM NIS-1 O Northeast Nuclear Energy Co.

P.O. Box 270 Hartford, CT 06101 Millstone Nuclear Power Station Unit 2

11. Abstract of Conditions Noted -

Of the 65 welds ultrasonically examined in the reactor vessel, primary pipe and steam generator stay cylinders, there were 38 indications recorded, 22 were due to geometry and the remaining 16 were evaluated and found acceptable.

Of the 57 areas inspected visually (Reactor Vessel and internals) there were 2. recordable indications detected. One was evaluated to

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be acceptable by informat.icnal eddy current techniques and the oth'r e was confirmed by informational ultrasonic and eddy current techniques. Analysis of the latter lead to a major . repair program which lasted from September to December, 1983 and is the subject of CE Report-IR-ISI-031, Reactor Vessel Core Support Barrel Nondestructive Examination Report.

A recordable indication on weld SG-2-THS-2 was detected using the

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liquid penetrant. method. Recordable indications detected using the.

ultrasonic method were determined to be geometric in nature and

_. acceptable.

Ultrasonic examination of weld X-74 in the shutdown cooling system detected an'inside diameter recordable indication. The inside surface was. liquid penetrant examined and found to be acceptable.

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This confirmed that.the ultrasonic indication was~ properly classified as-geometric.

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e O 12. abstract or corrective seasures Recommended and Taken The thermal shield was removed from the core barrel. Flaws in the core barrel were removed by machining.

The indication in Weld SG-2-THS-2 was removed by light grinding.

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INTRODUCTION This report contains the results of the 1983 Refueling Outage, Class I A II inservice inspection of the Millstone Nuclear Power Station Unit #2 The examinations were preformed to meet the requirements of the ASME Boiler and Pressure Vessel Code Section XI, 1974 Edition, including the Summer 1975 Addenda. The method of examination as outlined in the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Winter Addenda was us-ed for categories C-E-1 and C-F. This is permissable under 10CFR50.55a, paragraph (g)(4)(iv).

l The examinations were performed by personnel from the Northeast Utilities Service Co., Nuclear Engineering & Operations group and The Combustion Engineering Inc., C E Power Systems Division.

L All records, exr.mination data sheets, personnel certifications, equipment and material certifications for the examinations performed are on file at the Millstone Nuclear Power Station Unit # 2.

l All items listed in this report are creditable items in the

. Inservice Inspection Ten-Year Class I and Class II Program, with the exception of the exploratory examinations of the shutdown cooling welds, the steam generator baffle plate lug Walds and weld SG-1-THS-2.

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PAGE 7 10 1 DEFINITIONS r Volumetric: Ultrasonic Test (U.T.)

l Visual: Visual Examination (V.T.)

, Surface: Penetrant Test (P.T.); Magnetic Particle (M.T.)

Reportable indications (U.T.): Those indications which equal or exceed the recording-raquirements of the respective procedure and that are determined not to be geometric reflectors after evaluation by a level III.

, . No reportable indications (U.T.): A) Those indications which are less

than the recording requirements of the respective procedure.

B) Those indications which equal or exceed the recording requirements of the respective procedure but that are determined to be caused by geometric reflectors after evaluation by a level III.

Satisfactory (V.T.): Those visual examinations for which no degradation i of component integrity was observed, that meets the requirements of the respective procedure.

No reportable indications (P.T.): Those surface examinations which

- resulted in findings within the acceptance criteria listed in the

respective procedure.

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NUSCO -

NDE PROCEDURES Procedure Number Revision & Date Title NU-UT-1 3 12/13/82 Ultrasonic Examination Procedure General Requirements NU-UT-2 1 12/13/82 Ultrasonic Examination Procedure For Austanetic Piping Walds NU-UT-3 1 12/13/82 Ultrasonic Examination Procedure For Ferritic And Dissimiliar Metal Piping Welds NU-UT-5 0 3/18/83 Ultrasonic Examination Procedure For Thickness Measurements NU-UT-18 0 3/18/81 Ultrasonic Examination Procedure For Steam Generator f Welds NU-VT-1 3 12/13/82 Procedure For Inservice Visual Examination NU-LP-1 2 12/13/82 Procedure For Liquid Penetrant Examination NU-MP-1 2 12/13/82 Procedure For Magnetic Particle Examination 4

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j COMBUSTION ENGINEERING NONDESTRUCTIVE EXAMINATION PROCEDURES 1- Procedure Number Revision Title 6272-ISI-001 0 Automated Ultrasonic Examination Procedure For Reactor Vessel Welds 6272-ISI-004 4 Ultrasonic Examination Procedure For Reactor Vessel To Flange Wald 4

6272-ISI-005 1 Ultrasonic Examination Procedure i For Reactor Vessel Flange Ligament Areas 00000-ISI-029 3 Generic Manual Ultrasonic Examina-tion Procedure 6272-ISI-053 0 Procedure For ID Examination of The Reactor Pressure Vessel

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6272-151-056 1 Automated Ultrasonic Examination Procedure For Steam Genator Stay Cylinder Welds i

6272-ISI-065 1 Procedure For The Remote Visual Examination Of A Reactor Pressure Vessel, Closure Head And Its In-ternals 00000-ISI-069 1 Procedure For The crianation And Setup Of The Inservice Inspection Positioning System.For The Inside i '

Surface Examination of Reactor Pressure Vessels 6272-ISI-076 0 Procedure For The Eddy Current Examination Of The Nozzle Por-dections 00000-ESS-117 -

3 Ultrasonic Instrument Linearity Verification

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! lo COMBUSTION ENGINEERING ENGINEERING NOTICES I

EN NUMBER AFFECTED DOCUMENT NUMBER ISSUE'DATE

~MP-2-045 6272-ISI-001 REV.0 07/06/83 j MP-2-U46 6272-ISI-001 REV.0 08/31/83 MP-2-047 IR-ISI-016 REV.0 12/07/83

. MP-2-048 6272-ISI-056 REV.1 11/13/83 MP-2-049 6272-ISI-056 REV.1 11/15/83

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PAGE 11 sp6 NUSCO 10 PERSONNEL QUALIFICATIONS NUSCo Method ASNT-TC-1A Level Peter J. Durand VT,PT,UT,RT,MT II,II,I,II,II Richard J. Fuller, Jr. VT,PT,UT,MT II,II,II,II John F. Pinto VT,PT,MT,RT II,II,II,II '

Steven L. Sikorski VT,PT,UT,RT III,III,III,III Raymond A. West VT,PT,UT,RT,MT II,II,II,II,II 4

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PAGE 12 COMBUSTION ENGINEERING PERSONNEL QUAIFICATIONS Name Method Level of Qualifications B. E. Allbee UT,VT II,II T. J. Batzinger UT,VT I,II J. L. Brignac UT,VT I,II D. A. Brunner VT II R..S. Devlin UT II G. Fink ET I J. R. Fox UT III L. E. Germer UT I (ISI-25 Operator-PAR)

(~O S. B. Gore UT I M. A. Jutton UT,ET I,I i

R.S. Kusy UT,VT II,II J. P. Lareau UT,ET,VT III,III,III M. C. McCahill ET I A. S. Nelson UT,ET IICE),II l J. J. Pelletier UT I W. T. Sampson UTC+) I (ISI-2B Operator-PAR)

A. Sialauke UT,VT IICE),II D. M. Warren VT II (ISI-25 Operator-PAR)

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, NUSCO ULTRASONIC TEST INSTRUMENT LIST Mpnufacturer Model Serial Number Krautkramer Branson USL-38 210158 Krautkramer Branson USL-38 210449 Krautkramer Branson USL-38 211178 Krautkramer Branson USL-37 211849 NUSCO ULTRASONIC TRANSDUCER LIST Manufacturer Model Serial Number Frequencv(MHz)

Areo-Tech. Gamma 1/2x1" K23010 1.5 MHz 4 Areo-Tech. Gamma 1/2x1" B26091 2.25 MHz

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( . Area Tech. Gamma 1/2" dia. H08961 2.25 MHz

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1 Areo Tech Gamma 3/4" dia. J05932 2.25 MHz Areo-Tech Gamma 1/2x1" 00841T 2.25 MHz Areo-Tech Gamma 1/2" dia. 802363 2.25 Mhz Areo-Tech . Gamma 1/2" dia. K02124 2.25 MHz Areo-Tech MWB60-N4 #1 4.0 MHz Areo-Tech MW560-N4 #3 4.0 MHz Areo-Tech MWB45-N4 #5 4.0 MHz Areo-Tech MWs45-N4 #9 4.0 MHz Areo-Tech MWB60 53476 4.0 MHz Areo-Tech Gamma 3/8" dia. G02027 5.0 MHz Sonic GDD52 1/2" dia. 00783T 5.0 MHz Alpha 3/8" dia D14303 10.0 MHz f

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! k NUSCO MAGNETIC PARTICLE TEST INSTRUMENT LIST Manufacturer Model Seeial Number Parker Probe 7215 i

MATERIAL LIST l

Item Manufacturer Type Batch Number i

UT Couplant Areo-Tech Exosen 20 0701802001 l UT Couplant Areo-Tech Exosen 20 0903801401 l-UT Couplant Areo-Tech Exosen 20 80798 Spotcheck:

Cleaner Magnaflux SKC-5 82G078 Penetrant Magnaflux SKL-HF/SKLS 81D100 Developer Magnaflux SKD-NF/ZP95 82G073

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COMBUSTION ENGINEERING LIST OF NDE EQUIPMENT ULTRASONIC TEST INSTRUMENTS Manufacturer Model Serial Number KBI-6000 311344 l

1 KRI-6000 312865 l

ULTRASONIC TRANSDUCER LIST 3

Manufacturer Frecuency Size Serial Number SUSI 2.25 MHz 3" Dia. 974 Panametrics 2.25 MHz 1" Dia. 58296 Panametrics 2.25 MHz 58292

) 1" Dia.

Panametrics 2.25 MHz 1" Dia. 58295 Panametrics 1 MHz 1" Dia. 58321 Panametrics 1 MHz 1" Dia. 58323

( Panametrics 1 MHz 1" Dia. 57771 Panametrics 1 MHZ 1" Dia. 57775 i

Panametrics 2.25 MHz 1" Dia. 50958 Panametrics 1 MHz 1" Dia. 54212 Panametrics 1 MHz 1" Dia. 54211 Panametrics 1 MHz 1" Dia. 57772 Panametrics 1 MHz 1" Dia. 58320 f-Panametrics 2.25 MHz 1" Dia. 50954 Panametrics 1 MHz- 1" Dia. 58324

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! Panameteies 1 MHz 1" Dia. 57773

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i Panametrics 1 MHz 1" Dia. 57776

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a PAGE 17 COMBUSTION ENGINEERING LIST OF NDE EQUIPMENT (Cont'd.)

Manufacturep Frecuenev Size Serial Number

! Panametrics 1 MHZ 1" Dia. 57774 Panametrics 2.25 MHz 1" Dia. 57786 Panametrics 2.25 MHz 1" Dia. 50959

Panametrics 2.25 MHz 1" Dia. 50058 1

, Panametrics 2.25 MHz 1" Dia. 54115 Panametrics 2.25 MHz 1" Dia. 40342 j Panametrics , 2.25 MHz 1" Dia. 40341 i

~. Panametrics 2.25 MHz 1" Dia. 58293 f~O l Panametrics 2.25 MHz 1" Dia. 58291 Panametrics 2.25 MHz 1" Dia. 57785 Harsonic 2.25 MHz 1" Dia. W7615 Harsonic 2.25 MHz 1" Dia. W7612 Harsonic 2.25 MHz 1" Dia. W7613' Harsonic 2.25 MHz 1" Dia. W7611 Harsonic 2.25 MHz 1" Dia. W7614 Harsonic- 2.25 MHz 1" Dia.. W7616 Harsonic 2.25 MHz 1" Dia. W7617 L ()

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PAGE 18 COMBUSTION ENGINEERING '

CALIBRATION STANDARDS Block Number Drawine Number Revision UT-1 B-245-391 3 UT-2 B-245-390 2 UT-3 B-245-389 2 UT-4 B-245-388 2 UT-5 B-245-387 3 UT-6 5-246-356 2 UT-7 B-246-372 3

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UT-8 C-245-364 2 l UT-9 C-NEU-661-076 0 UT-10 D-NEU-661-076 2 l

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M This calibration standard was borrowed from Maine Yankee Atomic Power Company

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' . EXCLUSIONS AND EXCEPTIONS i

. 1. ASME Section XI Code Category B-I-l examinations (clad patch) i n the i reactor vessel and closure head were deleted per the USNRC Docket

No. 50-336. In addition, the Summer 1976 Addenda of Section XI de-lated the requirement to perforn these examinations. g i
2. Article I-4110 and I-4120 of Section XI were not performed daily (reactor vessel examination only) as required. Instead linearities

. Were performed in accordance with the USNRC Regulatory Guide 1.150, Ravision 1.

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Conditions Noted a

Volumetric, Surface and Visual Examinations were performed as required

. by Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition
including the Summer 1975 Addenda.

Rcordable indication on Wald THS-2, steam Generator g2, was detected using the Liquid Penetrant Method. This indication was ground out, reexamined and found to be acceptable.

' The recordable indications that were detected using the Ultrasonic Angle Beam Method uera determined to be geometry in nature and j acceptable.

The indications that were detected by the Straight Beam Mathod all uere within the acceptable limits of the referenced Code.

There was an extensive anaylsis of the ultrasonic indication detected in the Steam Generator welds SG-1-THS-2 and SG-2-THS-2, during the last refueling outage. These indications were found to be acceptable by the Northeast Utilities Engineering Department and the Level III Ultrasonic Specialist.

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The ultrasonic examination conducted of weld X-74, in the shut-down cooling line detected a recordable indication that was suspected to be attributed to IGSCC. An exploratory examination was performed by cutting a 2 inch hole into the pipe adjacent to the weld. The inside surface of the area of interest was liquid penetrant examined and i

found to be acceptable. Based on this examination the ultrasonic in-dication was riassified as geometry by our Engineering Department and Level III Ultrasonic Specialist.  :

The various deficient conditions noted on the Support Members Valves and Pumps were subsequently repair-of ed the er evaluated componentsandfor Piping,to be acceptable by engineering personnel.

verified 4

Of the 65 welds ultrasonically examined in the reactorvessel, pri-

- mary pipe and staan generator stay cylinders, there were 38 indications

recorded, 22 were due to geometry and the remianing 16 were evaluated and found acceptable,

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Of the 57 areas inspected visually (Reactor vessel and' Internals) i

'there were 2 recordable indications detected. One was evaluated to be

acceptable by informational addy current techniques and the other was confrimed by informational ultrasonic and addy current techniques. Analy sis of the latter lead to a major -repair program which lasted from Sep-tamber to December, 1983 and is the subject of C-E Report IR-ISI-031, Reactor Vessel Core Barrel Mondestructive Examination Report.

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NUSCO CATEGORY B-J Examination Area: Pressure Retaining Welds In Piping Examination Method: Volumetric (UT), or When Noted Surface (PT) 1 Examination Item Results Remarks BPY-C-5003 No Reportable Indications None l

BPY-C-5005 No Reportable Indications None BPY-C-5007 No Reportable Indications None BPY-C-3009 No Reportable Indications None BPY-C-5011 No Reportable Indications None BPY-C-5013 No Reportable Indications None BPY-C-5015 No Reportable Indications None BPY-C-5019 No Reportable Indications None BPY-C-5021 No Reportable Indications PT

} BPY-C-5023 No Reportable Indications PT BPY-C-5025 No Reportable Indications PT BPY-C-5027 No Reportable Indications PT BSI-C-1021 No Reportable Indications None BSI-C-1023 No Reportable Indications None BSI-C-3022 No Reportable Indications None BSI-C-3020 No Reportable Indications None BSI-C-4018 No Reportable Indications None BSI-C-4020 No Reportable Indications None l

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NUSCO i

! CATEGORY B-K-2 Examination Area: Support Components For Piping, Valves And Pumps Examination Method: Visual Examination Item Results Remarks SIAH-14 Satisfactory None SIAH-38 Satisfactory None

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SIAH-13 Satisfactory None SIAH-12 Satisfactory None SIAH-11 Satisfactory None SIAH-10 Satisfactory None SIAH-9 Satisfactory None SIAH-8 Satisfactory None

' f~~ Satisfactory None SIBH-20

) Satisfactory None SIBH-9 SISH-17 Satisfactory None SIDH-6 Satisfactory None SIDH-10 Satisfactory .None psH-27 Satisfactory None psh-20 Satisfactory None i- PSH-30 Satisfactory None i PSH-31 Satisfactory None PSH-23 Satisfactory None PSH-24 Satisfactory None PSH-34 Satisfactory None PSS-7 Satisfactory None PSS-7 Satisfactory None PSS-11 -Satisfactory None-

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NUSCO CATEGORY B-K-2 i Examination Area: Support Components For Piping, Valves and Pumps Examination Method: Visual Examination Item Results Remarks

CVCH-32 Satisfactory None I CVCH-34 Satisfactory None CVCH-36 Satisfactory None PSH-6 Satisfactory None DP-8 Satisfactory Hone DP-158 Satisfactory None t- DP-156 Satisfactory Hone CCLH-2 Satisfactory None

, CCLH-4 Satisfactory None DP-518 Satisfactory None DP-535 Satisfactory None CCLH-1 . Satisfactory None

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PAGE 24 lO NUSCO CATEGORY C-A Examination Area: Pressure Retaining Welds In Pressure Vessels Examination Method: Volumetric Examination Item Results Remarks 1-SC-3 No Reportable Indication None SG-1-TNS-1 No Reportable Indication None SG-1-TNS-2 Indication,See Appendices Information only not for code credit.

SIBC-Al No Reportable Indications None

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NUSCO

, CATEGORY C-B Examination Area: Pressure Retaining Nozzle Walds In Vessels Examination Method: Volumetric (UT) Or When Noted Surface (PT)

Examination Item Results Remarks SG-2-MS-1 Reportable Indication Acceptable By Analysis SIBC-B2 No Reportable Indications PT b

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(O 1 NUSCO CATEGORY C-C Examination Area: Integrally Welded Attachments To Vessels Examination Method:'$urface (MT) 4 4

"xamination E Item Resq1ts Remarks SG-1-CC-1 None Deferred SG-1-CC-2 Nona Deferred SG-1-CC-3 No Recordable Indications None SG-1-CC-4 No Recordable Indications None SG-1-CC-5 No Recordable Indications None SG-1-CC-6 No Recordable Indications None SG-1-CC-7 ' No Recordable Indications None

$G-1-CC-8 No Recordable Indications None 0

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I PAGE 27 NUSCO CATEGORY C-E-1 Examination Area: Support Members For Piping, Valves And Pumps Examination Method: Surface CVT)

Examination Item Results Remarks 502004 Satisfactory None 502014 Satisfactory None 402078 Satisfactory None 399457 Satisfactory None 402060 Satisfactory Hone 412017 Satisfactory None 404020 Satisfactory Nona l

i 307009 Satisfactory None

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NUSCO CATEGORY C-E-2 Examination Area: Support Components For Piping, Valves And Pu:aps Examination Method: Visual (VT) i Examination Item Results Remarks 402052 Sati sfractory None

402114 Satisfactory None 302034 Satisfactory None

'402043 Satisfactory None 407001 Satisfactory None 312009 Satisfactory None I

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CATEGORY C-F i Examination Area
Pressure Retaining Welds In Piping, Pumps,And Valves In Systems Which Circulate Reactor Coolant 1

Examination Method: Surface (PT) and when noted Volumetric (UT)

Examination Item Results Remarks SI-CF-X-47 No Reportable Indications None SI-CF-X-57 No Reportable Indications None SI-CF-X-32 No Reportable Indications None SI-CF-X-36 No Reportable Indications None SI-CF-A-40 No Reportable Indications None SI-CF-B-49 No Reportable Indications UT SI-CF-C-8 No Reportable Indications None

-s SI-CF-D-5 No Reportable Indications None SI-CF-D-9 No Reportable Indications None

'[ SI-CF-A-106 No Reportable Indications None

[ SI-CF-A-108 No Reportable Indications None

! SI-CF-B-112 No Reportable Indications None SI-CF-B-116 No Reportable. Indications None SI-CF-B-124 No reportable Indications None

.SI-CF-B-129 No reportable Indications None SI-CF-A-2 No reportable Indications None SI-CF-A-36 No reportable Indications None SI-CF-X-63 Ne reportable Indications None SI-CF-X No Reportable Indications UTM SIT-CF-52 No Reportable Indications Nor.e HSI-CF-1 No Reportable Indications None

NSI-CF-5 No Reportable Indications None HSI-CF-14 No Reportable Indications None HSI-CF-25 No Reportable Indications Nona.

4-HSI-CF-29 No: Reportable. Indications lNone N Complete with supplemental PT examination of the weld surface

. inside the pipe

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NUSCO CATECORY C-C Examination Area: Pressure Retaining Welds In Piping, Pumps,And Valves Which Circulate Other Than Reactor Coolant Examination Method: Volumetric (UT) l Examination Item Results Remarks FWB-C-G-13 No Reportable Indications None FWA-C-G-2 No Reportable Indications None MSA-CG-8 No Reportable Indications None MSB-CG-3 No Reportable Indications None l'

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PAGE 31 LO COMBUSTION ENGINEERING EXAMINATION DETAILS & RESULTS This section outlines the examination details and results by'11 sting the examination areas by zones. All examinations which were performed during this outage are included in these tables. Included in this listing are infornation only, examinations in excess of code requirements and examin ations which were performed in responce to USNRC Regulatory Guide 1.150.

i EXAMINATION TECHN7 QUES The nondestructive testing was performed using automated ultrasonic, automated addy current and visual techniques in accordance with written I procedures required by IWA-1400 of Section XI of the ASME Boiler and Pressure Vessel Code.

EXAMINATION.

SUMMARY

DEFINITIONS There are four columns under the general heading " Examination Results".

These columns are titled (1) No Indications, (2) Insignificant Indica-tions, (3) Significant Indications, Geometrical, and (4) Significant Indications, other.

For this listing, all Ut indications with amplitude equal to or greater than reporting response were recorded, evaluated and reported in the L

(O tables. The term-"No Indications" was used when the amplituad was less than the reporting response or when no indications were observed. All I recorded indications are concidered significant with those caused by componet geometry listed as " Geometrical" and true indications listed as "Other". The term " Insignificant Indications", was used for visual indica weld splatter,etc.

tions such as surface scratches, sling marks I.

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COMBUSTION ENGINEERING O'

NON-DESTRUCTIVE EXAMINATION SUMMRY

'" Examfpation Results Examination Examination Ama htW *[

e No insignificant Sinnificant Indications Remarks Mumber Indications indications Geometrical Other i

BHC-1 UT 001-13 X l

j- BHV-1 UT 001-13 X I BHV UT 001-13 X i

BHV-3 UT 001-13 ,

X BHV-4 UT 001-13 X i BHV-5 UT 001-13 X ,

001-14 X
BHV-6 UT 001-13 X 001-14 X HS-1 UT 001-13 X LSL-1 UT 001-5 X 1

001-11 X 001-12 X LSL-2 UT 001-6 X Clad Noise j 001-11 X Clad Noise j 001-12 X Clad Noise l LSL-3 UT 001-6 X 001-12 X

] ,

! MSL-1 UT 001-5 X

] 00.1-11 X 001-12 X 1

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0 O COMBUSTION ENGINEERING O'

NON-DESTRUCTITE' EXAMINATION SUN 14RY ,

Examination Examination Results Examination Examination Ama htW Data Sheet No insignificant Significant Indications Remads Number Indications Indications Geometrical Other ,

MSL-2 UT 001-6 X ,

001-11 X 001-12 X -

MSL-3 UT 001-6 X 001-11 X Sized Acceptable 001-12 .

X USL-1 UT 001-8 X USL-2 UT 001-9 X -

USL-3 UT 001-9 X .

. 001-18 X Sized Acceptable SC-1 UT 001-9 I SC-2 UT 001-6 X .

001-7 X 001-9 X UT 001-10 X X Sized Acceptable 001-17 X X Sized Acceptable

, FS-1 UT 001-14 X I 004-1 X NS-1 UT 001-3 X 001-16 X NS-2 UT 001-3 X 00.1-16 X l

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NON-DESTRUCTIVE EXAMINATION SIMMRY Examination Examination Results Examination Examination Area. Method Data Sheet No insignificant Significant Indications Remads Number Indications Indications Geometrical Other
NS-3 UT 001-3 X 001-15 X NS-4 UT 001-3. X 001-15 X .

NS-5 UT 001-13 X 001-15 X l

NS-6 UT 001-3 X 001-16 I IR-1 UT 001-4 X .

1 IR-2 UT 001-4 X IR-3 UT 001-4 X IR-4 UT 001-4 X -

IR-5 UT 001-4 X j IR-6 UT 001-4 X P-1-C-1A UT 001-2 X i'

P-3-C-1A- UT 001-2 X Sized Acceptable P-14-C-1A UT 001-2 X l P-10-C-IA UT 00.1-1 X P418-C-1A

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NON-DESTRUCTIVE EXAMINATION SLM MRY Examination Examination Results Examination Examination Ama htW Data Sheet No insignificant Significant Indications Remarks Number Indications Indications Geometrical Other P-5-C-1A UT 001-2 X L-37 UT 005-1 X thru L-54 CBCL-1 VT 065-8 X CBGL-2 VT 065-8 X CBGL-3 VT 056-8 X CBGL-4 VT 065-8 X .

CBMS VT 065-22 X ONP-1 VT 065-2 X ONP-2 VT 065-2 X CSB VT. 065-6 X TSP VT 065-9 X Thermal Shield removed under major repair program CBCW VT 065-14 X CSW VT 064-4 X

CSA VT 065-4 X j.

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l COMBUSTI0tf ENGINEERING NON-DSSTRUCTIVE.EXANINATION SIMMRY I

I Examination Examination Results

Examination Examination .

Area htW Data Sheet  ;;o insignificant Sient ficant Indications Remarks Number Indications Indications Geometrical Other i

j LCSP VT 065-1 X . Debris from thermal l

065-5 shield located on plat e SB-1 VT 065-15 X SB-2 VT 065-23 X SB-3 VT 065-23 X SB-4 VT 065-23 X

.SB-5 VT 065-23 X

) .

SB-6 VT 065-23 X UGHDR VT 065-16 X J

1 UGMS VT 065-3 X 065-16 X UGKW-1 VT ---

  • Unaccessible UGKW-2 VT 065-19 -

X UGKW-3 VT 065-19 X l

I UGKW-4 VT

  • Unaccessible UCFAP VT 065-18 X
  • 1 i

PCES VT 065-17 X KW-1 VT 065-13 X a

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O O NON-DESTR I StMtARY Examination Examination Results Examination Examination Ama htW Data Sheet No Insignificant Significant Indications Remarks Number Indications Indications Geometrical Other KW-2 VT 065-13 X KW-3 VT 065-13 X KW-4 VT 065-13 X ONB VT 065-10 X. . Indications were evalua-076-1 X ted and found acceptable by information ECT tech-niques

,ONB-2 VT 065-10 I Indications were evalua-076-1 X , ted and found acceptable by information ECT tech-niques SC-l' VT 065-11 X SC-2 VT 065-11 X SC-3 VT 065-11 X SC-4 VT 065-11 X SC-5 VT 065-11 X SC-6 VT 065-11 X CBAK-1 VT 065-7 X CBAK-2 VT 065-7 X

~CBAK-3 VT 065-7 X d ,

m. . ._

Ol O O NON-DESTR TI ION SUMMRY Examination Examination Results Examination Examination Area htW Data Sheet No insignificant Significant Indications Remarks Number Indications Indications Geometrical Other CBAK-4 VT 065-7 X IS-1 VT 065-12 X l IS-2 VT 065-12 X i

IS-3 VT 065-12 ,

X IS-4 VT 065-12 X i

IS-5 VT 065-12 X i' IS-6 VT 065-12 X .

CSL-1 VT 065-21 X l CSL-2 VT 065-21 X 1 CSL-3 VT 065-21 X l CSL-4 VT 065-21 X CSL-5 VT 065-21 X CSL-6 VT 065-21 X ii l CSL-7 VT 065-21 X CSL-8 VT 065-21 X CSL-9 VT 065-21 X F8S VT 065-20 X

o L OO COMBUSTION ENGINEERING O'

PON-DESTRUCTIVE EXAMINATION SIMMRY Examination Examination Results j Examination Examination

! Area htW Data Sheet No insignificant Stanificant Indications Remarks Number Indications Indications Geometrical Other Class 1 VT N/A X Leak Test i

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LDMBUST[0N ENGINEERING NON u

_tsTRUCTl VE EXAMINATION SUMMRY Examination Examination Results Examination Examination Area Method Data Sheet No insignificant Stanificant Indications Ren. arks Number Indications Indications Geometrical Other SG-2-TSS-2 UT 056-1 X SG-2-TSS-3 UT 056-1 X X Sized Acceptable SC-2-TSS-1 UT 056-1 X SG-2-SC-1 UT 056-2 X O

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O 6 C0!iBUSTI0rl ENGINEERING 6

NON-DESTRUCTIVE EXAMINATION SIM MRY Examination Examination Results Examination Examination Area AtW Data Sheet No insignificant Significant Indications Remarks Number Indications Indications Geometrical Other P-1-C-1 UT 001-2 X P-1-L-1 UT 001-2 X P-1-L-2 UT 001-2 X W

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O cP COMBUSTION ENGINEERING 6

NON-DESTRUCTIVE EXAMINATION SlMMRY Examination Examination Results Examination Examination Area Method Data Sheet No insignificant Significant indications Remarks Number indict.tlons Indications Geometrical Other P-10-C-1 UT 001-1 X Sized Acceptable P-10-L-1 UT 001-1 X P-10-L-2 UT 001-1 X 9

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General Offices e Seiden Street. Berlin Connecticut aesY es5s7Ecow= HARTFORD, CONNECTICUT 06141-0270

.avou enta mata cowa"'

(203) 666-6911 k L J C'0".Ffd%,'co~~

April 3, 1984 MP-5927 Docket No. 50-336 Dr. Thomas E. Murley Director, Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Reference:

1. Facility Operating License No. DPR-65
2. Docket 50-336
3. ASME Boiler and Pressure. Vessel Code 1974 Edition and Addenda through Summer 1975'

Dear Dr. Murley:

In accordance with Reference 3, the Millstone Unit 2 1983 Inservice Inspection Report is submitted for your information and use. Inspections covered in this report were performed between June 6, 1983 and January 3, 1984.

Yours truly, NORTHEAST NUCLEAR ENERGY COMPANY

/

$9+

E.J.Mroczka/'

Station Superintendent Millstone Nuclear Power Station EJM/TRB:ck tb 6

0+ 9 p+7

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