Text

Inservice Insp Summary Rept for Northeast Utils Millstone Nuclear Power Station Unit 1 1989 Refueling Outage
	ML20248D570
Person / Time
Site:	Millstone
Issue date:	09/22/1989
From:	; NORTHEAST UTILITIES
To:	;
Shared Package
ML20248D566	List: B13356, Forwards Inservice Insp Summary Rept for Northeast Utils Millstone Nuclear Power Station Unit 1 1989 Refueling Outage, Per ASME Code Section XI & Tech Spec 6.9.2.a; ML20248D570;
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	NUDOCS 8910040317
	Download: ML20248D570 (251)
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INSERVICE INSPECTION

SUMMARY

REPORT FOR NORTHEAST UTILITIES-

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MILLSTONE NUCLEAR POWER STATION UNIT NO. 1 I

1989 REFUELING OUTAGE y .. '

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,_ TABLE OF CONTENTS SECTION PAGFS I OWNER'S DATA REPORT (FORM NIS-1) 4 11- INTRODUCTION AND ABBREVIATIONS 2 III

SUMMARY

CF CONDITIONS NOTED AND ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN 16 IV PROCEDURE, PERSONNEL QUALIFICATION, EQUIPMENT, AND MATERIAL LISTS 8 V ASME CLASS I EXAMINATION RESULTS 53 VI ASME CLASS 2 EXAMINATION RESULTS 10 VII ASME CLASS 3 EXAMINATION RESULTS 1 VIII SUBSECTION IWF EXAMINATION RESULTS 24 IX PRESSURE TEST

SUMMARY

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~y X SYSTEM AND COMPONENT IS0 METRICS 29 7

N XI OWNER'S DATA REPORT FOR RiPAIRS OR 81 REPLACEMENTS (FORM NIS-2)

'XII NON ASME SECTION XI ADDITIONAL INSPECTION WORK

SUMMARY

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- ' FORM NIS-1 OWNER'S' DATA REPORT FOR INSERVICE INSPECTION

( AS REQUIRED BY THE PROVISIONS OF THE ASME CODE SECTION XI

1. OWNER: Northeast Epelear Enerry Company M E_93 222 Hartford, Connecticut 06101

2. PLANT: Millstone Nuclear Power Station M E93 llE Waterford, Connecticut 06385

3. PLANT UNIT: 1

4. OWNER CERTIFICATE OF AUTHORIZATION: N/A

5. COMMERCIAL SERVICE DATE: December 21, 1222

6. NATIONAL BOARD NUMBER FOR REACTOR VESSEL: 20797

7. COMPONENTS INSPECTED:

System Description Manufacturer g-v Reactor Vessel Internals Combustion Engineering s Shell Welds Bolting Bushings Nozzles Safe Ends Reactor Vessel Nozzles Combustion Engineering Closure Head Safe Ends Core Spray 10" Sch 80 304SS Dravo /SWF Fabricating &

10" Sch 80 C.S./304SS Welding Recirculation 10" Sch 80 304SS Dravo /A.P. & E.

8" Sch 80 304SS 8" $ch 80 C.S./304SS Valve Bolting Valve Internals Isolation 16" Sch 80 304SS Dravo /A.P. & E.

Condenser 14" Sch 80 304SS 14" Sch 100 316SS 12" Sch 80 304SS i I

10" Sch 80 304SS 8" Sch 80 304SS Heat Exchanger Nozzle Struthers Wells to Shell Welds

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Shutdown Cooling 14" Sch 100 316SS Dravo /A.P. 6 E.

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14" Sch 80 C.S.

12"-Sch 80 C S.

10" Sch 80 C.S.

8" Sch 80 C.S.

6" Sch 80 C.S.

Integral Attachment Valve Bolting Heat Exchanger "A" Struthers Wells Nozzle to Shell Welds Low Pressure 18" Sch 80 304SS Dravo Coolant 16" Sch 80 304SS Inj ection Integral Attachments Main Steam 20" Sch 80 C.S. Dravo 6" Sch 80 C.S.

Integral Attachment Flange Bolting Feedwater 18" Sch 80 C.S. Dravo 14" Sch 80 C.S.

12" Sch 80 C.S.

8" Sch 80 C.S.

Valve Bolting (Q,/ Standby Liquid 2" Sch 80 304SS Dravo Control 1.5" Sch 80 304SS Flange Bolting Valve Bolting Integral Attachment Support Members Various and Components for Piping, Pumps, and Valves

8. EXAMINATION DATES: April L 1289_ to June E 1989

9. INSPECTION INTERVAL FROM: Dec. E 1980 to *Dec. E 1290

Extended to the end of the 1991 refueling outage per ASME Section XI, IVA-2400.

10. ABSTRACT OF EXAMINATIONS ARE IDENTIFIED IN SECTIONS 5-9 0F THIS REPORT. .

11. ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE MEASURES TAREN ARE (3 IDENTIFIED IN SECTION 3 0F THIS REPORT.

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.We certify that the statements made in this report are correct and-r the examinations and corrective measures taken conform to the rules of the

'ASME Code, section.XI, 1980 Edition, Winter 1980 Addenda.

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l' Station Superintendent Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit No. 1

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7 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the. State of Connecticut and employed by'the Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut, have inspected the components described in this Owner's Data Report during the period April 7,1989 to June 26, 1989, and state- that to the best of my knowledge and belief, the owner has performed examinations 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 warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, ,

neither the inspector nor his employer 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 11, ),, { j 9, jq f f lila N$ maissions AJA 932d 0~r- llA !1 Insp 'or ii S ~ ire '

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SECTION II INTRODUCTION AND ABBREVIATIONS

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1 INTRODUCTION This report contains the results of the Twelfth Inservice Inspection of the ,

Millstone Nuclear Power Station Unit No. 1. !

Inservice inspections were performed in accordance with the scheduling requirements for the third inspection period of *! e second ten-year interval.

The examinations were performed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition, including the Winter 1980 Addenda. Acceptance criteria for Subsection IWF examinations was in accordance with the ASME Code,Section XI, 1983 Edition. Electric Power Research Institute (EPRI) qualified ultrasonic examination procedures and personnel were used for the inspection of all stainless steel piping subject to intergranular stress corrosion cracking (IGSCC).

Augmented inspections were performed on stainless steel piping welds based on the Millstone Nuclear Power Station Unit 1 Inservice Inspection Program for IGSCC. This program was developed and implemented to meet the requirements of Nuclear Regulatory Commission Generic Letter 88-01, "NRC Position on ICSCC in BWR Austenitic Stainless Steel Piping," dated January 25, 1988.

All records, examination data sheets, personnel certifications, equipment certifications, and material certifications ~for the examinations performed are on file at Millstone Nuclear Power Station Unit No. 1.

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f~N1.. ABBREVIATIONS 5

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The.following abbreviations listed below are defined as used within the text of this report:

Abbreviation Definition U.T. Ultrasonic Test P.T. Penetrant Test M.T. Magnetic Particle Test R.T. Radiographic. Test MSIP Mechanical Stress Improvement Process V.T.-1,2,3,4 Visual Test Followed by Exam Type Number 1.D. Inside Diameter 0.D. Outside Diameter

.NUSCO . Northeast Utilities Service Company

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V NU Fortheast-Utilities NNECO Northeast Nuclear Energy Compcny EBASCO Electric Bond And Share Company

. CTS CTS Power Services, Inc.

C/S Carbon Steel S/S Stainless Steel GE General Electric Company SWRI Southwest Research Institute ITI Innovative Technologies, Inc.

QSD NU Quality Services Department

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SUMMARY

OF CONDITIONS NOTED AND ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN

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1. ASME SECTION XI INSERVICE INSPECTIONS

") Nondestructive examinations were performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1980 Edition, Winter 1980 Addenda. The extent of examinations completed were in accordance with scheduling requirements for the third period of the second ten year interval.

Manual nondestructive examinations were contracted from the Electric Bond and Share Company (EBASCO) and the General Electric Company.

Autouated ultrasonic examinations of the reactor presssure vessel were performed with personnel contracted from Innovative Technologies, Inc., an ASEA-ATOM, and Westinghouse Company, of Monroeville, Pennsylvania.

Personnel performing automated and manual ultrasonic examinations on ASME Category B-D Nozzle to Vessel Welds and Inner Radius Areas were contracted from Southwest Research Institute, of San Antonio, Texas.

Personnel performing remote. visual examinations of the reactor vessel internal components were contracted frco CTS Power Services Inc., of Liverpool, New York.

Northeast Utilities Service Company (NUSCO), Northeast Nuclear Ener67

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(QSD) personnel participated in various nondestructive examinations in support of all inservice inspections.

Radiography services were provided by Trutom Inspection and Testing Services of.Branford, Connecticut.

2. INSPECTIONS OF STAINLESS STEEL j In response to Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," NNECO provided plans for piping replacement, inspection, repair, and leakage detection related to the mitigation of ICSCC of austenitic stainless steel piping at Millstone Nuclear Power Station Unit No. 1 prior to this refueling outage.

Our original inspection plan listed 150 welds to be examined.

Ultrasonic inspections of IGSCC piping welds began on April 7,1989 ;

and ended on May 4, 1989. A total of 155 welds were examined and the results of these inspections are found summarized and categorized in Tablea I, II, and III. i The following conditions resulted in the additional examination of five welds which were not part of the original inspection plan.

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a. Weld CUAJ-5, an eight-inch ICSCC Category "D" weld located in f.

the reactor water cicanup s.upply system, was found to contain a ;

rejectable flaw. This weld received a standard (full j structural) weld overlay. Four additional Category "D" welds of j the same pipe size and located in the saca system were added to l l

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i ,) All four welds of the expanded sample were found to be acceptable.

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b. A NUSCO Level III examiner, performing evaluations of a previously reported flawed weld, RCAJ-1, identified some examination concerns with an adjacent veld, RCAJ-1A. This weld, I RCAJulA, was added to the inspection plan based on the examination concerns of the Level III examiner and was found to be acceptable.

All of the completed IGSCC ultrasonic examinations were performed manually by'EPRI-qualified IGSCC personnel from EBASCO and General Electric. Additionally, ultrasonic test technicians were given procedure training, written, and practical examinations as part of the Northeast Utilities on-site qualification program for IGSCC.

Samples containing actual IGSCC flaws were used for the practical portion of this on-site qualification. Any preliminary manual ultrasonic examination results, which contained suspected ICSCC indications or geometry, were provided to NUSCO personnel for further evaluation end confirmation of results. The NUSCO evaluations consisted of a four-step program:

1. Analysis of the reported data.

2. Review of radiographs for ID geometry.

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3. Comparison of data to previous examination results.

4. Weld reexamination using ID creeping waves and additional angle beams and frequency transducers.

The final disposition of all weld indications was made by the NUSCO Level III examiner's evaluation of additional information obtained during the evaluation process.

Table I summarizes the inspection results by pipe size and system.

Table II lists the details of IGSCC inspections by individual weld ID and IGSCC category. Table III provides the category descriptions and numbers of welds completed in each category.

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SUMMARY

OF IGSCC-INSPECTION RESULTS 1A ., . . .

. WELDS ' WEDS WELD R . SIZE AND PIPING SYSTEM ACCEPTED REJECTED REPAIRS

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28" Recirculation 15 0

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- 4. .O 16" Isolation' Condenser.

'6 0 14" Re' circulation 1 0 14" . Isolation Cotidenser 5 0 14" Shutdown Cooling- 2 0' i 12" Recirculation- 14 0 12" Isolation condenser- 6 0 LO. -10" Isolation Condenser 10 0

10" Core. Spray- 12 0

-9" RPV Head' Spray

.1 0 9" RFV Head Instrument 1 0 8"' Cleanup ,

.17 1 Overlay 8" Isolation Condenser 10 0 6" RPV Head Vent 1 0-6" Isolation Condenser 2 0 5" CRD Cap 1 0

.4" Recirculation 4 0 22"2 Recirculation Overlay- 1 0 116": Isolation Condenser 1 0 LOveriay.-

-f L12" Recirculation Overlay. 6 9 155 1

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. TABLE II LJ MP1 1989 DETAILS OF ICSCC INSPECTION RESULTS SYSTDi: Recirculation Lonos and Rinn Manifold Weld ID

_ Catecorv Pine Size Acceptable Reiectable RCAF-1 C1 28" X (MSIP Applied)

RCAJ -l '- E 28" X RCAJ-1A C 28" X RCAJ-5 C 28" X RCAJ-6 C 28" ~X RCAJ E 28" X RCAJ-8 -C 28" X RCAJ-PB1 D 4" X

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(j RCBF-1 D 28" X (MSIP Applied)

RCBJ-3 C 28" X RCBJ-4 C 28" X RCBJ-5 E 28" X RCBJ-6 C 28" X RCBJ-7 C 28" X RCBJ-8 C 28" X RCBJ-ICl D 14" X RCBJ-PB1 D 4" X RCBJ-PS2 D 4" X RMAJ-1 C 22" X RMBJ-1 E 22" X (Overlay) p, RMBJ-4 C 22" X

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Weld ID Category Pine Size Accentable Reiectable-

[ - RRAF G1 12"' X . (MSIP' Applied) i RRAJ-4a .

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RRBF-1 G1 12" X- -(MSIP Applied)~ i

. RRBJ-1~ E- 12" X-(Overlay) --

- RRBJ-2: E 12" X (Overlay)

- RRCF-1 D 12" X (MSIP Applied)

RRCJ-3 E 12" X- j

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' RREF D 12" X (MSIP Applied) :

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RRFF-1 .D- 12" X. (MSIP Applied)

RRFJ-l'. E 12" -X

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- RRGF-1 D 12" X -(MSIP Applied)

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. RRHF-1 G1 12" X (MSIP Applied)

RRHJ-2 C 12" X RRHJ-4 C 12" X e - RRJF-1 G1 12" X (MSIP Applied)

RRKF-1 G1 12" X (MSIP Applied)-

RRKJ-4 C 12" X

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' CCM -1 C 16" X CCM - 2 D 18" X CCM - 3 D .18" X p CCM -4 D 18" X CCM - 5 D 18" X.

CCM -6 D 18" X CCM -7 D 18" X j CCM - 8 D 18" X CCM - 9 D 18" X CCM -10 D 16" X CCM-11 D 16" X

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(,/ . CCM -12 D 18" X CCM -13 D 18" X CCM -14 D 18" X CCM -15 D. 18" X CCM-16 D 18" X CCM -17 D 18" X CCM -18 D 18" X CCM-19 D 18" X CCM -20 D 18" X CCM -21 D 18" X CCBJ-1 D 18" X CCBJ-2 D 18" X CCBJ-3 D 18" X i._) CCBJ-4 D 18" X CCBJ .D 16" X omixa m 3.6

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- CCBJU12 =D 18" X-CCBJ-13' 'D 18" X

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.CCBJ-16 ~D X-CCBJ-17 D 10" X CCBJ-18 D 18" X.

.. CCBJ -19 D 18 " X CCBJ_-20' D, 18" .X SYSTEM: Isolation condenser fream Sunolv Weld ID' Categorv~ Pine Size Acceptable Rejectable ICAF-1 , , G1 14" X (MSIP Applied)

ICBF-1 ~- D 14" X (MSIP Applied)

ICAJ-14' A' .14" .X-

.ICAJ-15 A 14" X ICAC-F-1 D 14" X ICAC-F-2. D 16" X w

'ICAC-F-3 E 16'" X s (Overlay) 0- ICAC-F-8 D 16" X

.-ICAC-F-9 D 16" X LICAC-F-10 D 16" X ICAC-F-11 D. 16" X ICAC-F-12 .D 12" X ICAC-F-12A -D 12" X ICAC-F-14 D 12" X mium . 3.7

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12"= X ICAC-F-16A 'A 12" ' X ICAC-F D" .16 " ' ' X.

ICAC-F-29 A- 6" X

ICAC-F A- 6" X

, SYSTEM: Iso 1'ation Condenser Condensa'te Re' turn Weld-ID Categorv. ' Pine Size" 'Accentable >Re_iectable

-ICBJ-1 ' D -- 10'" - 'X ICBJ-2 D- ,

10" X ICBJ - 3 :- D 10" X-(ICBJ-4 D 10" _X 4

ICBJ-5 D 10" X

ICBJ-6 10" D: X ICBJ-7 D 10". X r

ICBC-F-9 D. 10" X' ICBC-F-10 D'- 10"- Xi ICBC-F-11. 'A. 8" X ICBC-F-15 'D 8" X ICBC-F-16 D. 8" X ICBC-F-17 D 8" X

ICBC-F-18 D 8" X lICBC-F-19 D 8" X ICBC-F-20 D 8" X ICBC-F-21 .D 10" X ICBC-F-22 D. 8" X m ix m e 3.8

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ICBC-F-23 D 8" X SYSTEM: Core Sorav Weld ID Category Pine Size Mcentable Reiectable CSAF-1 G1 10" X (MISP Applied)

CSAF-2. G1 10" X (MSIP Applied)

CSAJ-2 A 10" X CSBF-1 G1 10" X (MSIP Applied)

CSBF-2 C1 10" X (MSIP Applied)

CSBJ-l A 10" X CSBJ-3 A 10" X CSBJ-13 D 10" X CSBJ-14 D 10" X l'r

,y CSBJ-15 D 10" X CSBJ-16 D 10* X CSBC-G-2 D 10" X SYSTEM: Reactor Water Cleanun Sunniv Weld ID Category Pine Size Accentable Reiectable CUAJ-l A 8" X CUAJ-2 A 8" X CUAJ-3 D 8" X CUAJ-4 D 8" X CUAJ-5 D 8" (Overlay Applied) X CUAJ-6 D 8" X CUAJ-7 D 8" X CUAJ-14 D 8" X p

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it- CUA-9 D 8" -X g .CUA-10 D 8" X SYSTEM: Reactor Water Cleanuo Return b Weld ID Catecory Pine Size Acceptable Reiectable I CUBF-2 D 8" 'X CUBJ-3 D 8" X

-CUBJ-4 D. 8" X CUBJ-5 D 8" .X CUBJ D .8" X' CUBJ-18 D 8" X' CUBJ-19 D 8" X

- SYSTEM: ; Shutdown Cooline Weld ID Catecorv Pine Size Acceptable Reiectable SCAJ-2 .A 14" X SCAJ-CU1 A 14" X SYSTDi: Control Rod Drive'Can Weld ID Catecorv Pine Size Acceptable -Reiectable CRDF-1. G1 5" X (MSIP Applied)

SYSiEM: RPV Head Sorav Weld ID Catecorv Pine Size Acceptable Reiectable HSAF-1 D 9" X (MSIP Applied)

SYSTEM: RPV Head Vent Weld ID Catecory- Ploe Size Acceptable Reiectable HIAF-1 G1 6" X (MSIP Applied)

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.HIBF-1 .D 9" X (MSIP Applied)

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MP1 1989 IGSCC INSPECTION CATEGORIES AND SCHEDULES FOR PIPING WELDMENTS IGSCC INSPECTION DESCRIPTION OF WELDMENTS NOTES CATEGORY EXTENT & SCHEDULE Resistant Materials A 25% every 10 years (at Total Welds - 117 least 12% in 6 years)

MP1 IGSCC Prorram 5% each refueline outage or 6 welds minimum.

Nonresistant Materials SI (1) B 50% every 10 years (at within 2 years of least 25% in 6 years) operation (1)

Total Welds - 0 MP1 IGSCC Procram not annlicable.

Nonresistant Materials (1) C All within the next 2 SI after 2 years of refueling cycles, then all operation every 10 years (at least Total Welds - 76 50% in 6 years)

MP1 IGSCC Program 20% each refueling outage or 16 welds minimum. These are ;

welds with Induction Heat S9ess Improvement (IHS) son 11ed. l

,f g V Nonresistant Materials (1) D All every 2 refueling No SI cycles Total Welds - 184 MP1 IGSCC Procram 50% each refueline outare or 92 welds minimum.

Cracked (1) (2) E 50% next refueling outage, !

Reinforced by weld overlay then all every 2 refueling or mitigated by SI cycles Total Welds - 12 ;

MP1 IGSCC Program all welds every 2 refueling cycles, varies according to '

annlication of weld overlav or identification of flaws -

Cracked (2) F All every refueling outage Inadequate or no repair Total Welds - 0 MP1 IGSCC Program not annlicable.

Nonresistant (3) G All next refueling outage 1 Not Inspected Total Welds - 21 MP1 IGSCC Program subcategorized as G1 accessible welds and G2 inaccessible

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welds. G1 welds: 13, 100% during the 1989 refueling outage. G2 welds: 8, I Inside drvwell penetrations that are continuous 1v monitored for leakare. ,

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Notes:

O (1) All welds in nonresistant material should be inspected after a stress improvement process as part of the process. Schedules shown should be followed after this initial inspection.

(2) See recommendations for acceptable weld overlay reinforcements and stress improvement mitigation. (see NRC Generic Letter 88-01).

(3) Welds that are not UT inspectable should be repaired, " sleeved," or ]l local leak detection applied. RT examination or visual inspection for leakage may also be considered. Local leak detection was applied to the Core Spray X-16B piping penetration.

1989 COMPLETED INSPECTIONS Caterory Total Welds Percentare Each Outage Completed A 117 5% (6 welds minimum) 13 B 0 N/A N/A C 76 20% (16 welds minimum) 17 D 184 50% (92 welds minimum) 101

() E 12 100% (In two refuel cycles) 11 F 0 N/A N/A G 21 G1 (All accessible welds) 13 Total - 410 155 O

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l! 3. -MECHANICAL STRESS IMPROVEMENT PROCESS y

l o- Of-the 155 IGSCC welds examined, 22 welds-received a mechanical l; stress improvement process.(MSIP). -These MSIP weldsw'ere l nozzle-to safe-end welds with Inconel.182 weld butter. A pre-MSIP j ultrasonic test inspection was performed on 16 of the 22 welds.

Pre-MSIP inspection was' performed on 13 welds that were not

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inspected previously to _the upgraded 1985 EPRI NDE Center Qualification Program.

2. Pre-MSIP inspection was performed en one weld, RRCF-1, due to increased stress levels associated with existing weld overlays now present on'this recirculation system 12-inch riser.

3. Pre-MSIP inspection was performed on 2' welds, RRDF-1 and RCBF-1, because these welds were noted to have acceptable indications per Table IWB-3514-3 during the 1987 refueling outage.

Post-MSIP ultrasonic test inspections were performed on all 22 welds with no unacceptable conditions or changes noted.

4. WELD OVERLAY OF WELD CUAJ-5 A rejectable flaw was detected during ultrasonic inspection of weld ff CUAJ-5. This is a pipe to valve weld in the reactor water cleanup supply system The flaw was on the pipe side and was sized to be 3.5" long x 0.2" deep.

A stress corrosion crack growth evaluation was performed using the ASME Code Section XI guidelines. The results of this evaluation

. predicted that the flaw would propagate beyond the ASME Code Section XI allowables prior to the end of cycle 13. A we}d overlay

, was thus designed to restore the margins of safety required by the ASME Code Section III.

The full structural weld overlay was designed to withstand the complete range of loads assuming the pipe would be severed (i.e., the pipe was assumed to carry no load). The weld overlay design dimensions were 0.3" thick x 3" long with tapered ends.

The overlay was applied with water backing in the pipe using the gas tungsten arc process (CTAW). Type 308L filler material having 8FN-17FN delta ferrite was used. Weld metal is deposited until a layer having a minimum of 8FN delta ferrite and an acceptable liquid penetrant inspection is obtained. This provides the base upon which the overlay is applied in accordance with the design parameters.

Thus, credit was taken only for veld metal having a minimum delta ferrite of 8FN. The final overlay surface was liquid penetrant and ultrasonically examined for thickness, bond, and flaw propagation.

. fc* - The overlay was performed utilizing acterials and procedures consistent with the guidelines in NUREG 0313, Revision 2, for mitigation of IGSCC.

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5.

LEAK DETECTION OF UNINSPECTABLE WELDE

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An acoustic leak detection system utilizing acoustic emission (AE) technology was installed en the Core Spray X-16B piping penetration on March 15, 1989. The AE system is currently operating to collect background noise data. The system will remain operational during Cycle 13 for evaluation purposes. No plans beyond Cycle 13 have yet been made regarding the future use of this technology. NNECO continues to maintain that the Millstone Unit No. 1 drywell sump monitoring system is adequate for leak detection of uninspectable welds located inside piping penetrations. NNECO will continue to evaluate the reliability of the installed AE system for. future applications.

6. REACTOR VESSEL EXAMINATIONS Ultrasonic ex nations were performed on portions of the Millstone Unit No. 1 ret .or pressure vessel (RPV). The two contractors who provided inspo cion support for these examinations vere 1) Southwest Research Institute (SWRI) and 2) Innovative Technologies Inc. (ITI).

SWRI provided automated and manual ultrasonic test (UT) techniques for ten nozzle-to-shell welds and nozzle inner radius areas. Manual UT techniques were utilized on two of the scheduled RPV closure head r- nozzles and the control rod drive nozzle due to compound curvatures

(_)g and small nozzle sizes. Automated UT techniques utilizing automatic

( scanners and data recording devices were used on all other nozzles examined by SWRI. Areas containing ultrasonic indications were additionally evaluated with manual UT techniques to provide for j

additional flaw sizing and characterization information. The nozzle inner radius areas of the closure head nozzles were supplemented with surface examinations (PT and MT) to aid in ultrasonic signal identification. Indications found on these nozzles were dispositioned after grinding as acceptable and specific indication details can be found in Section V of this report.

Other examinations performed by SWRI identified several indications in nozzle weld and inner radius areas that were all characterized and evaluated as acceptable to ASME Section XI criteria.

l ITI provided inspection support for a "first-time" automated I

ultrasonic examination effort of selected welds and areas on the Millstone Unit No. 1 RPV.

These selected areas included the flange thread ligament areas, the I flange-to-shell weld, the upper vessel longitudinal welds, and the j upper vessel circumferential weld. This was the first time a BWR l vessel in this country has attempted portions of these examinations l from the inside diameter (I.D.) of the RPV. Unfortunately, equipment I malfunctions and scheduling concerns did not allow enough data to be collected to justify takit 4 credit for any of the examinations g

(m

')g performed. It was demonstrated that the Millstone Unit No. 1 RPV can be ultrasonically examined from the vessel I.D. with automated eqttipment . The data that was collected showed good ultrasonic l l

j e7xixa. ore 3.15

[1

("

i results and has provided much needed experience for future examinations to be conducted in this area.

7. EXAMINATIONS OF CONTROL' ROD DRIVE BOLTING Bolting for thirty control rod drives (CRDs) was visually VT-1 examined under' Category B-G-2 after disassembly. Examinations were performed by Northeast Utilities Quality Services Department (QSD) personnel. Each drive contained eight bolts and no detrimental indications were recorded on any of the bolts examined.

During disassembly and examination of CRD 22-23 (location identifier), one bolt was dropped and inadvertently not examined upon reinstallation. Since none of the other bolts examined were found to contain any detrimental indications, NNECO will reexamine this CRD's bolting in place at the next refueling outage.

8. INVESSEL INSPECTION Remote visual examination of the reactor vessel core spray spargers was performed by CTS Power Services of Liverpool, New York. The spargers and invessel supply piping were inspected to the criteria of I&E Bulletin 80-13 and GE SIL 289 and were found acceptable. The steam dryer drain channels were also visually inspected to CE SIL 474 and were found to be of a different design. EBASCO and NUSCO Reliability visual inspectors performed all visual examinations with

(>(

\- CTS personnel handling the TV cameras and inspection fixtures.

9. HYDROSTATIC PRESSURE TESTS Hydrostatic pressure testing was performed for Section XI 10-Year Code credit or for repair / replacement work on the following systems:

Shutdown Cooling Class 2 Isolation Condenser Class 2 Core Spray A & B Class 2 Reactor Building Closed Cooling Water Class 3 Service Water Class 3 Reactor Water Cleanup Class 1 Low Pressure Coolant Injection A & B Class 2

10. COMPONENT SUPPORT EXAMINATIONS Originally, 344 IWF component supports were scheduled and examined in accordance with the inspection plan. Rejectable conditions identified in Section VIII of this report required an additional 129 supports to be examined. All 25 rejectable supports were corrected in accordance with an ASME Section XI repair and replacement procedure and are documented by NIS-2 forms where required in Section XI of this report.

O 97K1X2 079 3.1b L_____________

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' 't,f SECTION IV.

PROCEDURE, PERSONNEL QUALIFICATION, EQUIPMENT, A'O MATERIAL LISTS i

[ :-

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m' 7, PROCEDURE LIST

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Procedure No. Revision Changes Title NU-VT-1: 8 Tech. Sheet Procedure for Inservice

.NU-VT-1-1 Visual Examination (NU)

NU-LP-1 8 Tech. Sheet Procedure for Liquid NU-LP-1-1 Penetrant Examination (NU)

NU-MP-1 7 Tech. Sheet Procedure for Magnetic NU-MP-i-1 Particle Examination (NU)

NU-UT-1 7 N/A Ultrasonic Examination Procedure for General Requirements (NU)

NU-UT-2 6 N/A Ultrasonic Examination Procedure for Austenitic ,

Piping Welds (IGSCC) (NU)

NU-UT-3 5 Tech. Sheet Ultrasonic Examination NU-UT-3-1 Procedure for Ferritic and Dissimilar Metal Piping Welds (NU)

O

(_) NU-UT-4 3 N/A Procedure for Weld Marking i Datum Points and Identifi-cation (NU)

NU-UT-5' 4 N/A Ultrasonic Examination Procedure for Thickness Measurements (NU)

NU-UT-7 3 Tech. Sheet Ultrasonic Examination NU-UT-7-1 Procedure for Vessel Welds (NU)

~

NU-UT-10 1 N/A Ultrasonic Examination Procedure for Weld Overlay Repairs (NU)

, NU-UT-ll 1 Tech. Sheet Ultrasonic Examination for L-Wave Butt Weld

~

NU-UT-ll-1, l

NU-UT-ll-2 Examination (NU)

{ NU-UT-27 1 Tech. Sheet Ultrasonic Examination NU-UT-27-1 Procedure for Reactor l Pressure Vessel Studs l

l Millstone Unit 1 and 3 (NU) l

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emuare 4.1

t h:

r~T NU-RT-1 3 Tech. Sheet Procedure for Radiographic

(_s' NU-RT-1-1 Examination of Welds (NU)

NU-RT-1-2 APPENDIX A 3 N/A Calibration Blocks (NU)

APPENDIX B 2 N/A Issuance and Approval of Technique Sheets, and Temporary Procedure Changes (NU)

APPENDIX C 1 N/A Ceneric Procedure for Sizing of ICSCC (NU)

APPENDIX E 2 N/A Flaw Sizing (NU)

APPENDIX F 1 N/A Numbering System for NDE Data rackages ACP-QA-9.09 2 0 Management of Inservice NEO 2.07 Inspection Programs (NU)

ACP-QA-9.06A 2 0 Inservice Inspection NEO 3.13 Ur. resolved Indication Reporting (NU) o

(_) ACP-QA-2.18 1 0 ASME Section XI Repair /

Replacment frogram (NNECO)

SP 681 8 0 Operational Leak Test of Reactor Vessel (NNECO)

SP 1060A 1 1 Remote Visual Inspection of the Spray Spargers, Core Spray In Vessel.

Piping, and Sparger Hold Clamp (NNECO)

SP 1060F 2 0 Remote Visual Inspection of the Steam Dryer and Hofsture Separator (NNECO)

SP 1097 1 1 Manual Operation of Relief valves When Reactor is at Low Pressure (FNECO)

EN 6.09 0 N/A Balance of Plant Inservice Inspection Prograin (NNECO) 89-T-1040 1 N/A Examination Plan for Millstone Unit 1 (ITI)

(')

\_/

Westinghouse sminse 4.2

SWRI-NDT- 47 N/A Manual Ultrasonic O 600-11 tx 1 tie er ve et-re-Nozzle Inner Radius Sections (SWRI)

SWRI-NDT- 75 N/A Manual Ultrasonic Examina-600-15 tion of Ferritic Reactor Pressure Vessel Welds (SWRI)

SWRI-NDT- 33 N/A Mechanical Ultrasonic 700 6 Outside Surface Examina-tion of Ferritic Vessels Greater than 2.0" in thickness (SVRI)

O O

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, PERSONNEL QUALIFICATION LIST - 1 f

, METHOD EIRI,OUALS (ICSCC) h EBASCO LL. LL. LL. m E Detection Sizine overlav

' 1.. "J. Bagley 111-1234.

2. .' A; '. Bullock II

.3.- .T. Burnett 11 X 4 .- .J._ Busby? II 'II II-1234

. W. Chabotte' I II J6. -S. Crothers' I 'II I

e 7. D. DuFrene I- I

.8. T. Fish' I I I 9; .M.:Grell II II X X

10. V. Gruno II II- X- X X 111'. B. Kutt IT IT

12. .D. ~ Langston' .

II.

13. D..McCausland+ II II II

14. J. O'Neil- II II II-134 X X X

'15. G..Pattillo III III III II-1234 X X X

16. T. Pedersen- III. II II-1234 X X

'17. 'O. Saulter' II II II 11-134 X

18. 'S. Spindler 11-1234

19. K.-Sumrall II II II

0. !R.'Zieber .III III III-1234 NNECO

1. J. Heyworth 11-34'

2. J. Leason 11-1234 NUSCO 1; T. Davis II II II II-134 X X X-

~2. P. Durand II II II II 11-134 X X

'3. R. Fuller- III III III II-134 X X X

4. J. Pinto II- II II II II-134 X

5. S. Sikorski III III III III II-1 X X X TRUTOM

1. B. Allen III-

2. E. Sullivan II' 3, D. Waitkas II

'.n SRI 1, M.'Ehnstrom II

2. E. Feige III

3. P. Gains 'II

,14. R. Miller I enoxa.ove 4.4

l l

PERSONNEL QUALIFICATION LIST

'AME METHOD EPRI OUALS (IGSQQ1 FI ILL. E M . T . E V2 Detection Sizing Qverlay l'. S. Alger II II X X

2. G. Cook I II II X X

3. A. Giansanti I II II-1234

4. J.-Gillespie II II X

5. R. House II II II X

6. T. Rockwood I I

7. R. Parr II II X X

8. M. Trusskey I II

-111

1. Z. Dargaty II

2. M. Engstrom II

3. J. Funyak II

4. J. Messinger I

5. S. Sabo II Q.ED

, 1. S. Chieak 11-1 I '! . N. Grillo 11-1

~' 3 . J. Hayden II-l

4. L. Johnson 11-1

5. B. Keroack II-1

6. E. Palmieri 11-1

7. W. Wilson 11-1

,- m 97K1X2.079 4.5

\

- EOUIPMENT LIST 0,s MANUFACTURER MODFL SERIAL NO.

Ultrasonic Test Eouinment

1. Kraut Krammer-Branson USL-48 212525

2. Kraut Krammer-Branson USL-38 213051

3. Kraut Krammer-Branson USL-38 210895 4 Kraut Krammer-Branson USL-38 180453

5. Kraut Krammer-Branson USL-38 0180454

6. Kraut Krammer-Branson USL-48 213479

7. Kraut Krammer-Branson USL-48 213478

8. Kraut Krammer-Branson USL-38 211259

9. Kraut Krammer-Branson USL-48 213222

10. Kraut Krammer-Branson USL-48 212712

11. Kraut Krammer-Branson USL-38 211178

12. Kraut Krammer-Branson USK-7S 31459-525

13. Kraut Krammer Branson USL-37 211649

14. Kraut Krammer-Branson USL-38 210761

15. Kraut Krammer-Branson USL-37 211286

16. Panametrics EPOCH-2002 20BP/1153

17. Panametrics EPOCH-2002 362

18. Panametrics EPOCH-2002 382

19. Panametrics EPOCH-2002 363 h, 20. Brush Recorder 260 04981

21. Brush Recorder 260 13793

22. Sonic WA Mark III 13451

23. Sonic WA Mark III 13452

24. Sonic WA Mark III 13453

25. Sonic FTS Mark I 760811

26. Sonic FTS Mark I 774714

27. Sonic FTS Mark I 774224

28. Sonic FTS Mark I 01103E

29. Textronix Oscilloscope 2335 B012611

30. Textronix Oscilloscope 465B B065732

31. Kraut Krammer-Branson USIP-12 29321-496

32. Kraut Krammer-Branson USIP-12 29321-1083

33. Kraut Krammer-Branson USIP-12 29321-1165

34. Kraut Krammer-Branson USIP-12 29321-1273

35. Kraut Krammer-Branson USIP-12 29321-1275 0

97K1X2.079 k.b

l MANUFACTURER MODEL SERIAL NO. !

Macnetic Particle Test Ecuipment l

l 1. Parker Probe DA200 3164 l 2. Parker Probe DA200 8950-l 3. Parker Probe DA200 8697-

4. Parker Probe DA200 6751

5. Parker Probe DA200 8879

! 6. Parker Probe B-300 1627 l 7. Parker Probe DA200 6385 l l 8. Parker Probe DA200 8698 l 9 Detek Field Indicator D250 70 l 10. Detek Field Indicator D250 71

11. Detek Field Indicator D250 72

12. Detek Field Indicator D250 94

13. Detek Field Indicator D250 108

14. Detek Field Indicator D250 115

15. Detek Field Indicator D250 116 O

l 1

l .

I 1

l s7mn.o7e 4.7

I l'

l-

} e- MATERIAL LIST N ]s MATERIAL BATCH / LOT NO.

1. Ultragel II Couplant 8661

2. Ultragel II couplant '8868

3. Ultragel II Couplant 8872

4. Sanford Marking Pens 112

5. Mark-Tex Corporation Pens 179

6. Spotcheck Zyglo Developer SKD-NF/ZP-9B 87M020

7. Spotcheck Cleaner / Remover SKC-NF/ZC-7B 88A004

8. Spotcheck Cleaner / Remover SKC-NF/ZC-7B 88A045

9. Spotcheck Cleaner / Remover SKC-NF 89B01S

10. Spotcheck Penetrant SKL-HF/S 87F083 1

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o' 1 SECTION V ,

ASME CIASS 1 EXAMINATION RESULTS 3

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!- t ASME CLASS ~1 EXAMINATION RESULTS CATEGORY B-A EXAMINATION AREA: ' Pressure Retaining Welds (11) in Reactor Vessel' EXAMINATION METHOD: Volumetric (U.T.)

a-V- ' EXAMINATION ITEM EXAMS RESULTS REMARKS.

p, i Bottom Head Circumferential Weld (1) 1.2 BHCB-l' U.T[(0*, -Acceptable No indications scan from 45*, & 60*) skirt side only.

g.

Bottom Head Meridional Welds (8)

., 1 BHAB-l' U.T. (0", _ Acceptable No indications scanned 56"'

l 45*, & 60') -of accessible weld length.

l

2. :BHAB-2, EU.T. (0*,- Acceptable No' indications ~ scanned 56" 45*, & 60*) of accessible weld length.

~

3. Acceptable No indications scanned 56"

'ff

~ BHAB-3 U.T. (0*,

45*, & 60') of accessible. weld length.

p 4. BHAB-4 U.T. (0*, Acceptable No indications scanned 56" l

45*,'6'60')- of' accessible weld length.,

i;

. 5. EHAB-5; U.T. (0*, Acceptable-' No indications scanned 56" 45*, & 60*) of accessible weld length.

6. BHAB-6 U.T. (0*, Acceptable No indications scanned 56" 45*, & 60*) of accessible weld length.

7. BHAB-7 U.T. (0*, Acceptable No indications scanned 56" 45*, & 60') of accessible weld length.

8. BHAB-8 U.T. (0*, Acceptable No indications scanned 56" 45*, & 60*) of accessible weld length.

Shell to F1ance Weld (1)

1. VFAC -U.T. (Auto- Acceptable No code credit taken.

, mated 0*, Examined oniv nortion of 45*, 60*, & Egid. Recordable 70*) indications in base material. Acceptable per NUSCO calculation number 88-014-1094GP, Revision O.

emmm . 5.1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ ________________________________________________a

(..

EXICTINATION-ITEM EXAMS RESULTS REMARKS i: ,r q (f Shell Circumferential Weld (1)

'1. 'VCAB-1 U.T. (Auto- Acceptable No code credit taken.

mated 0*, Examined only nortion of

, 45', & 60', ylld. Recordable indica-

& 70*) tions in base material.

Acceptable per NUSCO calculation number 88-014-1094GP, Revision 0.

q N.)

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s7Ktx2.07e 5.2 ,

l u-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ . _ _ _ _ _ _ _ _ _

ASME CLASS'l EXAMINATION RESULTS

'- CATEGORY B-D EXAMINATION AREA: Reactor Vessel Nozzle to Vessel (10) Welds and (11) Inside Radius Sections EXAMINATION METHOD: Volumetric (U.T.)

EXAMINATION ITEM EXAMS RESULTS REMARKS Core Sorav "B" Nozzle 10" (1)

1. CSBD-1 U.T. (Auto- Acceptable Nozzle weld and inner mated 0*, radius section. Multiple 45*, & 60') recordable indications located in outer 75% of vessel wall. All indica-tions evaluated to have no through wall dimension.

Indications dispositioned as acceptable in accor-dance with Table IVE-3512-1.

()

CSBD-1-1R U.T. (Auto-mated 20' &

No recordable indications on inner radius 28') examination.

Control Rod Drive Return Canned Nozzle 5" (1)

2. CRDD-1 U.T. (0', Acceptable Nozzle weld and inner 45*, & 60') radius section. No recordable indications.

CRDD-1-1R U.T. (13* & ,

16*)

Head Sprav Nozzle 9" (1) i

3. HSAD-1 U.T. (0*, Rej ectable Nozzle weld and inner 45*, & 60') radius section.

Inside Ultrasonic indications at Diameter 20% of DAC recorded.

P.T. & M.T. Evaluation showed possible I.D. surface penetrating HSAD-1-IR U.T. (18', flaws. Liquid penetrant 21', 24', & and magnetic particle 30'), Inside examinations were Diameter performed on these areas P.T. & M.T. and revealed numerous

() linear indications.

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EXAMINATIONS' ,

V,j~ . ITEM EXAMS RESULTS- REMARKS sc _

f.t _: .- Retest.

sU.T.'(45* &' Acceptable Liquid penetrant examinas.

P, 4 m-( (Afteri 60*),.P.T.7 tion after grinding-Repair,by: revealed scattered linear.

, Grinding)~ indications:less than .2" 1 inclength. . Evaluation ~of thest~ indications showed they are typical of. base .

, : metal to clan interface indicationstand are acceptable in accordance with Table IWB-3510-l'.

Ultrasonic indications

were still present, but were-evaluated not to be surface penetrating flews

and were dispositioned as acceptable in accordance with Table'IWB-3512-1, my; .(See Section XI~.)

Fead Instrument Nozzle 9" (10)

4 '. HIBD-1 U.T. ( 0 * ', ' Rej ectable Nozzle weld and inner

~45*, &~60'), radius section.

Inside. Recordable ultrasonic Diameter indications. Evaluation-P.T. & M.T. showed 45* indications to be-located at.the closure LHIBD-1-IR .U.T.. (18*, head I.D. Liquid 4 21*, 24*, penetrant and magnetic and 30*),1 particle ~ examinations were.

, 'Inside performed on the weld I.D; Diameter and inner radius surfaces.

P..T. & M.T. Numerous. linear indica : '

-'- tions were revealed.

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~ EXAMINATION f ITEM' FXAMS RESULTE REMARKS l

. I t- 1 t

. ;., . 1

) Retest U.T. (45' & Acceptable Liquid penetrant examina-(After 60') P.T. tion after grinding showed Repair by scattered linear Grinding) indications less than .2" in length. Evaluation of these indications showed they are typical of base l

metal to clad interface indications and are acceptable in accordance with Table IVB-3510-1.

Ultrasonic indications were still present, but were evaluated not to be-surface penetrating flaws and were dispositioned as acceptable in accordance with Table IWB-3512-1.

(See Section XI.)

Head Vent Nozzle 6" (1)

5. HIAD-1-IR M.T. & P.T. Acceptable Due to indications observed on the Head Spray.

and Head Instrument Nozzle

( ). I.D.s. this nozzle inner radius was examined. Both liquid penetrant and magnetic particle examinations showed no indications.

Recirculation Outlet "B" Nozzle 28" (1)

6. RCBD-1 U.T. (Auto- Acceptable Nozzle weld and inner mated 0", radius section.

45*, & 60*) Recordable indication located in outer 75% of RCBD-1-IR U.T. (Auto- vessel wall at 348' nozzle mated 28' & azimuth. Indication 34*) evaluated as subsurface and dispositioned acceptable in accordance with Table IWB-3512-1.

07K1X2.079 5.5 i

. - _ . - _ . .___ _ __ ___ __ ______-_ _________-_-_______-__-__m

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1, p .u EXAMINATION 1.

ITEM' EXAMS RESULTS- REMARKS Entfreulation Inlet "D" Nozzle 12"-(l)-

7. -RRDD-l'-- U.T. (Auto- Acceptable Nozzle weld and inner.

f '

mated 0*, radius'section. Partial

, !45*, 60')L examination coverage due

!o to permanent reactor.

RRDD-1-IR fU.T. (Auto-- vessel isolation at mated 28* & approximately 300' to 60' 34') top of nozzle. .No recordable inc.ications.

i Recirculation Inlet E"

~

Fu Nozzle 12" (1)

H '

8. RRED-1 U.T. (Auto ' Acceptable Nozzle weld and inner mated O*, radius.section. Partial 45', & 60') examination coverage due L . .

to permanent reactor

,RRED-1-IR U.T. (Auto- vessel insulation at

' mated 28* &-

.approximately 300* to 60' 34*) top of nozzle. No recordable indications. ,

Recirculation Inlet "C" Nozzle 12" (1)

9. -RRGD-1 U.T.~(Auto-- Acceptable- Nozzle weld and inner

.t mated 0', radius section. Partial ,

45*, & 60*)- examination coverage due'.

to permanent reactor:

RRGD-1-IR U.T. (Auto- vessel insulation at mated 28* & approximately 300* to 60*

34*) top of. nozzle. No recordable' indications.

Recirculation Inlet "J" Nozzle 12" (1)

-10.

. RRJD-1 U.T. (Auto- Acceptable Nozzle weld and inner mated O*, radius section. Partial 45', & 60') examination coverage due to permanent reactor RRJD-1-1R U.T. (Auto- vessel insulation at mated 28* & approximately 300* to 60' 34*) top of nozzle. No recordable indications.

.O 97K1X2.079 5.6

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Y EXAMINATION

, ITEM EXAMS RESULTS REMARKS

.(D

~

\_,/ -

Recirculation Inlet "K" Nozzle 12" (1)

11. RRK2-1 U.T. (Auto- Acceptable Nozzle weld and inner mated 0*, radius section. Partial

'45*, & 60*) examination coverage.due

to permanent reactor RRDK-1-IR U.T. (Auto- vessel insulation at mated 28" & approximately 300* to 60*

34*) top of nozzle. Recordable indication located in outer 75% of vessel wall at 199* nozzle azimuth.

Indication evaluated as subsurface and disposi-tioned acceptable in accordance with Table

'IWB-3512-1.

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O B7K1X2.07e 5.7

' 4 k

ASME CLASS 1 EXAMINATION RESULTS CATEGORY B-F EXAMINATION AREA: . Pressure Retaining Dissimilar (9) Metal Welds in Piping.

EXAMINATION METHOD: Volumetric (U.T.) and Surface (P.T.)

EXAMINATION ITEM EKAMS RESULTS REMARKS Cleanun Return Elbow to Pine Weld 8" (1)

1. CUBF-2-E-SS U.T. (60*) Acceptable S/S elbow side of weld.

.(IGSCC Indications from I.D. ;

Cat D) . geometry were observed by NUSCO evaluator, but were not recorded by CE examiner. UT responses were similar to previous results from 1982, 1984, and 1987. Past indica-tions were evaluated as root reflectors from hand ground counterbore and

() beam angle shift.

CUBF-2-P-CS U.T. (60*) Acceptable C/S pipe side of weld.

(IGSCC Indications from I.D.

Cat. D) geometry were observed by NUSCO evaluator, but were not recorded by CE examiner. UT responses were similar to previous results. Past indications were evaluated as root reflectors due to sound beam angle shift caused by dissimilar metal weld interface.

Core Sprav "A" Nozzle to Safe End Weld 10" (1)

2. CSAF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45'L, indications.

Cat. G1) profile 0*)

Post-MSIP Acceptable Same as above.

U.T. (45'L, 60*)

m snix m e 5.8

__________________-__m

L EXAMINATION ITEM EXAMS RESULTS REMARKS CSAF-1-SE Pre-MSIP Acceptable Safe'end side of weld. No

['~D

'(IGSCC , U.T. (45'L, indications.

Cat. G1) profile O')

Post-MSIP Acceptable Same as above.

U.T. (45'L, 60')

Core Sorav "A" Safe End to Pine Weld 10" (1)

3. CSAF-2-SE Pre-MSIP N/A Safe end side of weld, (IGSCC U.T. (45'L, Incomplete scan due to Cat. Gl) profile O*) 0.D. configuration. No indications.

Post-MSIP N/A No scan due to 0.D. con-figuration.

CSAF-2-P Pre-MSIP Acceptable Pipe side of weld. No (IGSCC U.T. (45'L, indications.

Cat. Gl) profile O')

Post-MSIP Acceptable Indication from I.D.

U.T. (45'L, geometry evaluated as a 7_ 45') root reflector.

. Core Snrav "B" Nozzle to Safe End Weld 10" (1)

4. CSBF-1-NZ Pre-MSIP Acceptable Nozzle side of weld.

(ICSCC U.T. (45'L, Indications from I.D.

Cat. Gl) profile O') geometry evaluated as root reflectors 360* intermit-tent.

Post-MSIP Acceptable Indications from I.D.

U.T. (45*L, geometry evaluated as root 45*), P.T. reflectors. Noted inconel interface clad roll 360' intermittent.

CSBF-1-SE Pre-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (45'L, Indications from I.D.

Cat. G1) proffle 0*) geometry evaluated as root reflectors. Indications in weld area evaluated as multiple inclusions and pores identified in original radiograph.

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l EXAMINATION 1 ITEM EXAMS RESULTS' B1 MARKS

[^T- Post-MSIP Acceptable Same as above. i I, \l U.T. (45*L, 45*, 60', & z WSY 70'), '

P.T.

Core Sorav "B" Safe End to Pine Veld 10" (1)-

5. CSBF-2-SE Pre-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (45'L, Incomplete scan due to Cat. G1) profile O*) 0.D. configuration.

Indications-from I.D.

geometry evaluated as root reflectors.

Post-MSIP Acceptable No scan due to 0.D. con-

-P.T. figuration. No indica-tions.

CSEF-2-P Pre-MSIP Acceptable Pipe side of weld.

(IGSCC U.T. (45'L, Indication from 1.D.

Cat. Gl) profile O*) geometry evaluated as root reflector.

Post-MSIP Acceptable Indications from I.D.

U.T. (45*, geometry evaluated as root 45'L, 60', & reflectors and dendrities WSY 70'), in weld. Indications at P.T. 10" to 21" clockwise from top-dead-center of weld evaluated as possible lack of fusion or lack of penetration. Review of original radiograph shoved these indications to be acceptable.

CSBF-2-PL Pre-MSIP Acceptable Pipe longitudinal weld, U.T. (45'L, Indications from I.D.

profile O') geometry evaluated as root reflectors.

Post-MSIP Acceptable No indications.

U.T. (60*),

P.T.

Control Rod Drive Nozzle to Can Weld 5" (1)

6. CRDF-1-CAP Pre-MSIP Acceptable Cap side of weld. No (ICSCC U.T. (45'L, indications.

Cat. Gl) profile O')

exuape 5.10

~

EXAMINATION )

ITEM EXAMS RESULTS REMARKS (O

' Post-MSIP Acceptable Indication from I.D.

U.T. (45*L, geometry evaluated as root !

60*L, & WSY and counterbore 70*), P.T. reflectors. -

.CRDF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (ICSCC U.T. (4 5 ' L~, indications.

Cat. G1) profile 0*)

Post-ESIP Acceptable No indications.

U.T. (45'L),

P.T.

Reactor Vessel Head Sorav Nozzle to Safe End Weld 9" (1)

7. HSAF-1-NZ Post-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (axial indications.

Cat. D) scan 45'L,

'45', cire, scan 35',

profile 0*)

HSAF-1-SE Post-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (axial Indications from weld and Cat. D) scan 45'L, I.D. geometry evaluated as

( 45*, cire. inconel veld metal inter-scan 35*, face reflectors.

profile 0*)

Reactor Vessel Head Instrument Nozzle to Safe End Weld 9" (1)

8. HIBF-1-NZ Post-MSIP Acceptable Nozzle side of weld.

(ICSCC U.T. (axial Indications from weld and Cat. D) scan 45'L, I.D. geometry evaluated as 45*, cire, inconel veld metal inter-scan 35", face reflectors.

profile 0*)

l l HIBF-1-SE Post-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (axial Indications from weld and Cat. D) scan 45'L, I.D. geometry evaluated as 45*, cire. inconel weld uetal inter-scan 35*, face reflectors.

profile 0*)

O emx2 on 5.11

EXAMINATION

-ITEM EXAMS RESULTS REHARKS

-(s- Reactor Vessel Head Vent Nozele to Safe End Weld 6" (1)

\_)

9. HIAF-1-NZ Pre-MSIP -Acceptable Nozzle side of weld. Two (ICSCC U.T. (45'L, . indications evaluated and Cat. G1) profile O*) sized as spot indications from inconel weld metal interface reflectors.

p Indications less than

.0325" in diameter acceptable per Table L IWB-3514-3.

Post-MSIP Acceptable Same as above.

U.T. (axial scan 45'L, 45'L, cire, scan 35')

HIAF-1-SE Pre-MSIP- Acceptable Safe end side of weld. No (IGSCC 'U.T. (45'L, indications.

Cat. G1) profile O')

Post-MSIP Acceptable No indications.

U.T. (axial scan 45*L, 45*, cire.

[]--

\

scan 35')

Isolation Condenser Nozzle to Safe End Weld 14" (1)

10. ICAF-1-NZ Pre-MSIP Acceptable Nozzle side of weld.

(ICSCC U.T. (45'L, Indications from I.D.

Cat. G1) 45*, profile geometry evaluated as root 0*) reflectors.

Post-MSIP Acceptable No indications.

U.T. (45'L, 45')

ICAF-1-SE Pre-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (45'L, Indications from I.D.

Cat. GI) 45*, profile geometry evaluated as root 0*) reflectors.

Post-MSIP Acceptable Same as above.

U.T. (45'L, I

45*)

Isolation Condenaar Snare Nozzle to Safe End Weld 14" (1)

11. ICBF-1-NZ Pre-MSIP Acceptable Nozzle side of weld.

() (IGSCC Cat. D)

U.T.

(profile 0*)

s7xix2.o7s 5.12

EXAMINATION ITEM L2L/QiS, RESULTS REMARKS 7

() Post-MSIP U.T. (45*L, Acceptable No indications.

45*)

ICBF-1-SE Pre-MSIP Acceptable Safe end side of weld.

(IGSCC U.T.

Cat. D) -(profile 0*)

Post-MSIP Acceptable Indications from I.D.

U.T. (45*L, geometry evaluated as 45*) inconel weld metal inter-face reflectors.

Recirculation Outlet "A" Nozzle to Safe End Nozzle 28" (1)

12. RCAF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45*L, indications.

Cat. G1) profile 0*)

Post-MSIP Acceptable Indications from I.D.

U.T. (45'L, geometry evaluated as root 60*L, 45') reflectors.

RCAF-1-SE Pre-MSIP Acceptable Safe end side of weld. No (IGSCC U.T. (45'L, indications.

() Cat. G1) profile 0*)

Post-MSIP Acceptable Indications from I.D.

U.T. (45'L, geometry evaluated as root 60*L, 45*) reflectors.

Recirculation Outlet "B" Nozzle to Safe End Weld 28" (1)

13. RCBF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45'L) indications.

Cat. D)

Post-MSIP Acceptable Indications from weld and U.T. (45'L, I.D. geometry evaluated as 60* L, 45'L, root and inconel weld profile 0*) metal interface reflectors.

RCBF-1-SE Pre-MSIP Acceptable Safe end side of weld.

(IGSCC U.T. (45'L) Examined 20" to 28" clock-Cat. D) wise and counterclockwise from top-dead-center of weld to verify previous axial indication reported in 1987. No indications.

O enmme 5.13

EXAMINATION ITEM EXAMS RESULTS REMARKS

()

o Post-MSIP Acceptable Indications from weld and U.T. (45'L, I.D. geometry evaluated as 60'L, 45*, root and inconel weld profile 0*) metal irterface reflectors.

Recirculation Inlet "A" Nozzle to Safe End Weld 12" (1) 1

14. RRAF-1-NZ Pre-MSIP Acceptable Nozzle side of wold. No (IGSCC U.T. (45'L, indications. j Cat. G1) profile 0*)

i Post-MSIP Acceptable No indications.

U.T. (45'L, 45*)

RRAF-1-SE Pre MSIP Acceptable Safe end side of weld. No (IGSCC U.T. (45'L, indications.

Cat. Gl) profile O')

Post-MSIP Acceptable Indications from I.D.

U.T. (45'L, geometry seen 360*

45*) evaluated to be root reflectors from beam 7s redirection caused by

( ,) inconel to weld metal interface.

Recirculation Inlet "B" Nozzle to Safe End Weld 12" (1)

15. RRBF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (ICSCC U.T. (45'L, indications.

Cat. G1) profile O*)

Post-MSIP Acceptable No indications.

U.T. (45'L, 45')

RRBF-1-SE Pre-MSIP Acceptable Safe end side of weld. No U.T. (45'L, indications.

profile 0*)

Post-MSIP Acceptable Indications from I.D.

U.T. (45'L, geometry seen 360*

45*) evaluated to be root reflectors from beam redirection caused by inconel to weld metal interface.

(

97K1X2.079 5.14 I

_ _ _ _ _ _ _ _ _ _ _ . _ _ . ._____-_______O

' EXAMINATION ITEM' EXAMS RESULTS REMARKS I"h-

. Q.)

Recirculation Inlet "C" Nozzle to Safe End Weld 12" (1) 16 .- RRCF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45*L, indications.

Cat. D) profile 0*)

Post-MSIP Acceptable Spot indication located at U.T. (45'L, 30" clockwise from top-45*) dead-center of weld.

Indication sized to be approximately .0175" diameter. Acceptable per Table IWB-3514-3.

RRCF-1-SE Pre-MSIP Acceptable Safe end side of weld. No (IGSCC U.T. (45'L, indications.

Cat. D) profile 0*)

t Post-MSIP Acceptable Indications from I.D.

U.T. (45'L, geometry seen 360*

45*) evaluated to be root reflectors from beam red' ection etased by inconel to weld metal

(} tonat3b" cock e n weld from top-dead-center of weld. Indication sized to be approximately .0195" diameter. Acceptable per Table IWB-3514-3.

Recirculation Inlet "D" Nozzle to Safe End Weld 12" (1)

17. RRDF-1-NZ Pre-MSIP Acceptable Nozzle' side of weld. No (IGSCC U.T. (45'L, indications.

Cat. D) profile 0*)

Post-MSIP Acceptable No indications.

U.T. (45'L, 45*)

RRDF-1-SE Pre-MSIP Acceptable Safe end side of weld. No (IGSCC U.T. (45'L, indications.

Cat. D) profile 0*)

Post-MSIP Acceptable No indications.

U.T. (45'L, 45*)

O enum re 5.15 L _ _ _ ___ _-___ - _ - -____- _____ _ _ _ _ _ _ - _ - _ _ - _ - - - _ _ - - _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ - . . _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

n; ;,--

' .y .

7 ' EXAMINATION-ITEM JRWdl; RESULTS REMARKS n

Recirculation Inlet "E" Nozzle to Safe End Vold 12"'(1)1

}

18. 10REF-1-NZ Post-MSIP: - Acceptable: Nozzle side of weld. 1No (IGSCC_ 'U.T. (45'L, indications.

Cat 'D) 45*, profile 0*)

RREF 1-SE Post-MSIP JAcceptable- Safe end side of weld. No (IGSCC~ U.T.-(45'L,. indications.

Cat.~ D)_ _45*,' profile 0*)

Recirculation' Inlet "F" Nozzle to Safe End Weld 12" (1) 1'

'19. ~ RRFF-1-NZ Post-MSIP Acceptable Nozzle. side of weld. No

-(IGSCC U.T.;(45*L, indications.

Cat. D) 45*, profile 0*)

,, RRFF-1-SE ' Post-MSIP Acceptable Safe end side of weld.

j. , ;(IGSCC U.T. (45'L, Indications from I.D.

L Cat.'D) 45*, profile geometry seen 360*

0*) evaluated to be' root reflectors from beam redirection caused by inconel'to weld' metal

()[~

4 interface.

Recirculation Inlet *G" Nozzle to Safe End Weld 12" (1)

20. RRGF-1-NZ Post-MSIP Acceptable Nozzle side of weld. No l (IGSCC U.T. (45'L, indications.

Cat. D) 45*, profile o')

RRGF-1-SE Post-MSIP, Acceptable Safe end side of weld.

(ICSCC U.T. (45*L, Indications from I.D.

Cat. D) 45*, profile geometry seen 360*

0*) evaluated to be root reflectors from beam redirection caused by inconel to weld metal interface.

Recirculation Inlet "H" Nozzle to Safe End Veld 12" (1)

21. RRHF-1-NZ. Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45'L, indications.

Cat. Gl) ' profile 0*)

Post-MSIP Acceptable No indications.

U.T. (45'L,

?]/"' 45*), P.T.

oxumme 5.16

- - - - - - - - - - - - -- - - - --------.--.------------,_------,----.-------.--_-----.,-------a-- - - - - - - . - - - - , - - - - - - - - - _ ---

.. .L 3

I fy ' . I

?$ni '. s . . ,;r3a 3

O ]

e+ ,

-EXAMINATION.

(j{

4 j , ITEM EXAMS - v RESULTS: REMARKS ,

l RRHF-1-SE. Pre-MSIP'. Accep table .- ' Safe end side of weld. -

-(IGSCC' U.T. (45'L, -Spot. indication see post-

-Cat; C1) profile O')- MSIP remarks.

Post-MSIP Acceptable' Indications.from I.D.

p

.U.T. (45'L, geometry seen 360*

.45'), P.T. evaluated to be root-reflectors from beam redirection caused by-inconel to weld metal r . interft.ce ; ' Spot-indica-

tion at 9.5" counter -

clockwise from top-dead-l center of weld. ' Indica--

tion sized to be approxi '

mately .0178" diameter.

Acceptable _per Table IWB-3514-3.

' Recirculation Inlet' "J" Nozzle to Safe End Weld 12"_ (1) 22.t RRJF-1-NZ - Pre-MSIP. ' Acceptable ' Nozzle side of weld. No (IGSCC U.T. (45'L, indications.

Cat. G1)" profile 0')

O~ rest-MS1P ^ccePtabte Ne ineicatiens.

U.T. (45*L,-

45'),.P.T.

RRJF-1-SE Pre-MSIP Acceptable. Safe end side of weld. No-

-(IGSCC U.T. (45'L,. indications.

Cat. G1)~ . profile 0*)

Post-MSIP Acceptable Indications from I.D.

U.T. (45*L, geometry'seen 360*

45*), P.T. evaluated to be root

^

reflectors from beam redirection caused by inconel to weld metal interface.

-Recirculation Inlet "K" Nozzle to Safe End Weld 12" (1)

23. RRKF-1-NZ Pre-MSIP Acceptable Nozzle side of weld. No (IGSCC U.T. (45'L, indications.

Cat. G1) profile O*)

Post-MSIP Acceptable No indications.

U.T. (45'L, 45'), P.T.

O 97K1X2.07a ' 5.17

.y ,,. - - - - - - - - -

i:

EXAMINATION ITEM EXAMS RESULTS REMARKS Acceptable Safe end side of weld. No

.b /]- RRKF-l-SE (IGSCC Pre-MSIP U.T. (45'L, indications.

Cat. Gl) profile O')

Acceptable

~

Post-MSIP Indications from I.D.

U.T. (45'L, geometry seen 360*

45'), P.T. evaluated to be root reflectors from beam redirection caused by

[ inconel to weld metal interface, p.

s k

w

)

O i 07K1X2.079 5.18 j

ASME CLASS 1 EXAMINATION RESULTS I l

'((~~)

- ' . CATEGORY B-G-1 EXAMINATION AREA: Pressure Retaining Bolting, Greater Than 2" in Diameter (56) Bushings, (6G) Studs EXAMINATION METHOD: Bushings Visual (V.T.-1)

Studs Volumetric (U.T.) and turface (M.T.)

EXAMINATION ITEM EXAMS RESULTS REMARKS Reactor Pressure vessel Bushings (56)

1. PR(D)G-01 V.T.-1 Acceptable All bushings examined in thru place with studs removed.

PR(D)G-56 No indications.

Reactor Pressure Vessel New Studs (60) Baseline Examinations (See Section XI) s

1. PR(A)G-01 U.T. (70'), Acceptable No relevant indications.

M.T.

2. PR(A)G-02 U.T. (70*), Acceptable No relevant indications.

.Il M.T.

. RJ

3. PR(A)G-03 U.T. (70'), Acceptable No relevant indications.

M.T.

4. PR(A)G-04 U.T. (70*), Acceptable First thread on top of M.T., V.T.-1 stud is dented for a ,

distance of 3/8". !

Evaluated not to effect function of stud. Subj ect thread is for tensioner and does not engage nut or RPV bushing.

5. PR(A)G-05 U.T. (70*), Acceptable No relevant indications.

M.T.

6. PR(A)G-06 U.T. (70'), Acceptable No relevant indications.

M.T.

7. PR(A)G-07 U.T. (70*), Acceptable No relevant indications.

M.T.

8. PR(A)G-08 U.T. (70'), Acceptable No relevant indications.

M.T.

()' 9. PR(A)G-09 U.T. (70'),

M.T.

Acceptable No relevant indications.

97K1X2 07e 5.19 j i

EXAMINATION ITEM MQ RESULTS REMARKS i

r'3 10.- PR(A)G-10 U.T. (70'), Acceptable No relevant-indications.

V M.T.

11. PR(A)G -U.T. (70'), Acceptable No relevant indications.

M.T.

12. .PR(A)G-12 U.T. (70'),' Acceptable No relevant indications.

M.T.

13. PR(A)G-13 U.T. (70*). Acceptable No relevant indications.

M . T .'

14. PR(A)G-14 U.T. (70'), Acceptable No relevant indications.

M.T.

15. PR(A)G-15 U.T. (70*), Acceptable No relevant indications.

M.T.

16. PR(A)G-16 U.T. (70'), Acceptable No relevant indications.

M.T.

l~

l 17. PR(A)G-17 U.T. (70'), Acceptable No relevant indications.

1 .M.T.

18. PR(A)G-18 U.T. (70'), Acceptable No relevant indications.

M.T.

19. PR(A)G U.T. (70'). Acceptable No relevant indications.

M.T.

20. -PR(A)G-20 U.T. (70'). Acceptable No relevant indications.

M.T.

21. PR(A)G-21 U.T. (70'), Acceptable No relevant indications.

M.T.

22. PR(A)G-22 U.T. (70'), Acceptable No relevant indications.

M.T.

23. Pa(A)G-23 U.T. (70'), Acceptable No relevant indications.

M.T.

24. PR(A)G-24 U.T. (70'), Acceptable No relevant indications.

M.T.

25. PR(A)G-25 U.T. (70'). Acceptable No relevant indications.

M.T.

26. PR(A)G-26 U.T. (70'), Acceptable No relevant indications.

M.T.

O

(>

97K1X2.079 5.20

W EXAMINATION ITEM EXAMS RESULTS- REHARKS

27. PR(A)G-27' U.T. (70'). Acceptable No relevant indications.

( }~ M.T.

1

28. :PR(A)G-28 U.T. (70'), Acceptable No relevant indications.

M.T.

29. PR(A)G-29 U . T.. (70'). Acceptable No relevant indications.

M.T.

l-l 30. PR(A)G-30 U.T. (70*), Acceptable No relevant indications.

M.T.

31. PR(A)C-31 U.T. (70*), Acceptable No relevant indications.

M.T.

32. PR(A)C-32 U.T. ( 70 * ) ., Acceptable No relevant indications.

M.T.

33. PR(A)G-33 U.T. (70'). Acceptable No relevant indications.

M.T.

34. PR(A)G-34 U.T. (70*), Acceptable No relevant indications.

M.T.

35. PR(A)G-35 U.T. (70'), Acceptable No relevant indications.

(} M.T.

36. PR(A)G-36 U.T. (70*), Acceptable No relevant indications.

M.T.

37. PR(A)C-37 U.T. (70*), Acceptable No relevant indications.

M.T.

38. PR(A)G-38 U.T. (70*), Acceptable No relevant indications.

M.T.

39. PR(A)G-39 U.T. (70*), Acceptable No relevant indications.

M.T.

40. PR(A)G-40 U.T. (70'), Acceptable No relevant indications.

M.T.

41. PR(A)G-41 U.T. (70'), Acceptable No relevant indications.

M.T.

42. PR(A)C-42 U.T. (70'), Acceptable No relevant indications.

M.T.

43. PR(A)G-43 U.T. (70*), Acceptable No relevant indications.

M.T.

97K1K2.07. 5,21

i EXAMINATION ITEM D2fd RESULTS RE%RKS

44. PR(A)G-44 U.T. (70*), Acceptable No relevant indications.

' A-.l~} M.T.

45. PR(A)G-45 U.T. (70*), Acceptable No relevant indications.

M.T.

46. PR(A)G-46 U.T. (70*), Acceptable No relevant indications.

M.T.

47. PR(A)G-47 U.T. (70*), Acceptable No relevant indications.

M.T.

48. PR(A)G-48 U.T. (70*), Acceptable Magnetic particlo M.T. indication 1/8" long axial at 23 1/4" from top of stud. Evaluated to be base metal inclusion and acceptable per IWB-3515.1.

49. PR(A)G-49 U.T. (7D*), Acceptable No relevant indications.

M.T.

50. PR(A)G-50 U.T. (70*), Acceptable No relevant indications.

M.T.

(~'N 51. PR(A)C-51 U.T. (70*), Acceptable No relevant indications.

\- M.T.

52. PR(A)G-52 U.T. (70*), Acceptable No relevant indications.

M.T.

53. PR(A)G-53 U.T. (70*), Acceptable No relevant indications.

H.T.

54. PR(A)G-54 U.T. (70*), Acceptable No relevant indications.

M.T.

55. PR(A)G-55 U.T. (70*), Acceptable Magnetic particle M.T. indication 3/4" long axial at 4 3/4" from bottom of stud. Evaluated to be base metal inclusion and acceptable per IWB-3515.1.

56. PR(A)G-56 U.T. (70*), Acceptable No relevant indications.

M.T.

57. PR(A)G-57 U.T. (70*), Acceptable No relevant indications.

(Spare M.T.

Stud)

O e7cc om 5.22 j

F .,, ..,.

EXAMINATION ITEM EXAMS REE E REMARKS

('"j .' 58. PR(A)G U.T. (70*), Acceptable No relevant indications.

(Spare M.T.

Stud)

59. PR(A)G-59 U.T. (70*), Acceptable No relevant indications.

(Spare M.T.

Stud)

60. PR(A)G-60 U.T. (70*), Acceptabib Magnetic particle (Spare M.T. indication 1/4" long axial.

Stud) at 17 1/2" from top of stud. Evaluated to be ba:e metal inclusion'and acceptable per IWB-3515.1.

O n

RJ 97K1,*2.Cro 5.23

ym, = ; .

l- i ( .,

L

- ASME CLASS 1 EXAMINATION RESULTS h 'i" 'I CATEGORY B-G-2 EXAMINATION AREA: Pressure Retaining Bolting 2" and Smaller in L Diameter (45)

EXAMINATION METHOD: Visual (V.T.-1)

EXAMINATION ITEM EXAtiS RESULTS REMARKS Reactor Vater Cleanun Suvolv System Valve Boltine (1)

1. 1-CU-1 V.T..-1 Acceptable Bolting examined in place-under tension.

Reactor Vater Cleanup Return System Valve Bolting (2)

1. 1-CU-29 V.T.-l Acceptable Bolting examined in place under tension.

2. 1-CU-30 V.T.-l Acceptable Bolting examined in place under tension.

p.- Feedwater System Valve Bolting (2) 1 5') 1. 1-FW-llA V.T.-1 Acceptable Bolting examined in place under tension and light rust noted.

2. 1-FW-llB V.T.-l Acceptable Bolting examined in place under tension and light rust noted.

Main Steam System Flante Bolting (2)

1. MSBG-RV-2 V.T.-1 Acceptable Bolting examined in place under tension and light rust noted.

2. MSDG-RV-2 V.T.-l Acceptable Bolting examined in place under tension and light rust noted.

Main Steam System Valve Boltir,r (1)

1. 1-MS-2D V.T.-1 Acceptable Bolting examined in place under tension and light rust and oxidation noted on all bolting threads.

.J

$7K1X2.07e 5.24

r' ,

es !

-- 1 EXAMINATION

' ITEM EXAMS RESULTS REMARKS h.

7

. Recirculation System Flance Boltine (2)

(

1. RCG-11A- V.T.-1 Acceptable Bolting examined in place under tension and light rust noted.

2. RCG-11B V.T.-1 Acceptable Bolting examined.in place

'under tension and light rust noted.

Recirculation System Valve Boltine.(1) 1.- l'-RR-1B ' V.T.-1 Acceptable Bolting examined while (Baseline) disassembled. New replacement studs and nuts for this valve. (See Section XI.)

Shutdown Cooline System ValypinglQng (1)~

1. 1-SD-5L V.T.-1 Acceptable Bolting examined in place

< under tension.

Standbv Liould Control System F1ance Boltine (2)

' ()' 1. SLF-1 V.T.-1 Acceptable Bolting examined in place

.under tension.

2. SLF-2 V.T.-1 Acceptable Bolting examined in place under tension and minor corrosion noted on studs.

Standby Liould Control System Valve Boltine (1)

1. 1-SL-7 V.T.-1 Acceptable Bolting examined in place under tension and minor corrosion noted on studs.

Control Rod Drive Boltine Identified by Location Number (30)

1. 06-31 V.T.-l Acceptable Bolting disassembled.

' 2 .. 10-39 V.T.-l' Acceptable Bolting disassembled and four bolts noted with rounded hex heads.

3. 10-47 V..T.-1 Acceptable Bolting disassembled cnd one bolt noted to have hex head damage. Hex head shows peening due to air tool use and corrosion on the hex head surface.

.( )

. e7xixr o7e 5.25

_ _ _ -2 _ _ _ _ - - . _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l

i EXAMINATION ITEM EXAMS RESULTS REMARKS

-[^',T 4. 14-35 V.T.-1 Acceptable Bolting disassembled.

x /

5. 14-39 V.T.-1 Acceptable- Bolting disassembled.

6. 18-31 V.T.-l Acceptable Bolting disassembled and five bolts noted with rounded hex heads.

7. 18-11 V.T.-1 Acceptable Bolting disassembled.

8. 14-19 V.T.-l Acceptable Bolting disassembled and one bolt noted with rounded hex head.

9. 22-07 V.T.-l Acceptable Bolting disassembled.

10. 22-15 V.T.-l Acceptable Bolting disassembled.

11. 22-19 V.T.-1 Acceptable Bolting disassembled and one bolt noted with rounded hex head.

12. 22-23 V.T.-1 Acceptable During disassembly and (7 Bolts) examination, one bolt was dropped and inadvertently not examined upon rein-(]

' stallation. No indica-tions are noted on the seven bolts examined. The bolting of this CRD will be examined in place under tension at the next refueling outage in accor-dance with Table IWB-2500-1, Category B-G-2, Item No. B7.80 as allowed by Note (1) under the extent and frequency of examination require-ments.

13, 22-27 V.T.-l Acceptable Bolting disassembled.

14, 22-31 V.T.-l Acceptable Bolting disassembled.

15. 22-35 V.T.-l Acceptable Bolting disassembled.

16. 26-03 V.T.-l Acceptable Bolting disassembled.

17. 26-11 V.T.-l Acceptable Bolting disassembled and all bolts noted to have slightly rounded hex

_() heads.

smx2me 5.26

i

' EXAMINATION !

ITEM EXAMS RESULTS REMARKS

/~N 18. 26-19 V.T.-l Acceptable Bolting disassembled and

\~sI all bolts noted to have j slightly rounded hex heads.

19. 26-23 V.T.-l Acceptable Bolting disassembled.

20. 26-35 V.T.-l Acceptable Bolting disassembled and four bolts noted to have rounded hex heads.

21. 26-43 V.T.-1 Acceptable Bolting disassembled.

22. 30-19 V.T.-l Acceptable Balting disassembled.

23. 30-37 V.T.-l Acceptable Bolting disassembled and all bolts noted to have rounded hex heads.

24. 30-39 V.T.-l Acceptable Bolting disassembled.

25. 34-07 V.T.-l Acceptable Bolting disassembled.

26. 38-15 V.T.-l Acceptable Bolting disassembled and all bolts noted to have f slightly rounded hex heads.

27. 38-27 V.T.-1 Acceptable Bolting disassembled.

28. 42-35 V.T.-l Acceptable Bolting disassembled.

29. 42-47 V.T.-l Acceptable Bolting disassembled. -

30. 50-35 V.T.-l Acceptable Bolting disassembled and all bolts noted to have slightly rounded hex heads.

h 97K1X2.079 5.27 rl _ _. _ _ _ _ _ - _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _

ASME CIASS 1 EXAMINATION RESULTS

['N .

\,. / CATEGORY B-J EXAMINATION AREA: Pressure Retaining Welds in Piping (148)

EXAMINATION METHOD: Nominal Pipe Size >4 in. - Surface and Volumetric Nominal Pipe Size $4 in. - Surface EXAMINATION ITEM EXAMS RESULTS REMARKS Reactor Water Cleanup Sunniv System 8" Stainless Steel (8)

1. CUAJ-l U.T. (0*, Acceptable No scan weldolet side of (IGSCC 45', & 60') weld. Ultrasonic indica-Cat. A) P.T. tions from I.D. geometry and weld porosity.

Verified by radiograph review.

CUAJ-1-PL U.T. (45') Acceptable Examined pipe long, weld P.T. 12" back from circumferen-tial weld. Indications from I.D. geometry evaluated as root reflectors.

}

2. CUAJ-2 U.T. (45* 6 Acceptable No scan valve side of (IGSCC 60') P.T. weld. No indications.

Cat. A)

CUAJ-2-PL U.T. (45*) Acceptable Examined pipe long weld P.T. 12" back from circumfer-ential weld. Indications from I.D. geometry evaluated as root reflectors.

3. CUAJ-3 U.T. (60') Acceptable No scan valve side of (IGSCC weld. Indications from Cat. D) I.D. geometry evaluated as root reflectors.

4. CUAJ-4 U.T. (60', Acceptable Indications from I.D.

(IGSCC 60*L, & WS4 geometry evaluated as root Cat. D) 70') and counterbore reflectors.

iJ 97K1X2.07e 5.28

EXAMINATION L ITEM EXAMS RESULTS REHARKS

$(} 5. CUAJ-5 U.T. (60') Rej ectable No scan valve side of K' (IGSCC weld. Indications from Cat. D) I.D. geometry evaluated as root reflectors. Flaw indication at 1" counter-clockwise to 2.5" clock-vise with axial mid-length. Flaw sized to be 3.5" long x .2". deep.

Zero inches is top dead center of weld.

Rejectable per 'IWB-3640.

Overlay repaired.

Overlay Acceptable Indications identified in-(baseline) weld overlay repair.

U.T. (O' Indication area 1) 1/2" bond, O' clockwise to 2" clockwise.

profile, Indication sized to be 60*L, 70*L, 1 1/2" long x .55" deep 0.D. from overlay 0.D. and Creeper) .1875" wide. Indication P.T. area 2) same clockwise location. Indication sized to be 1 1/2" long x

.42" deep from overlay

(~}

\~ 0.D. Indications evaluated as flaws typical of lack of bond and from original flaw repair.

Sufficient weld overlay thickness of 2 8FN weld metal exist and overlay is acceptable per NUSCO calculation f/88-014-1086GP. (See Section XI.)

6. CUAJ-6 U.T. (60') Acceptable No scan valve side of (IGSCC weld. Indications from Cat. D) I.D. geometry evaluated as root reflectors.

O 97K1X2 079 5.29

,33 Yi[ : EXAMINATION- '

l ITEM EXAMS 'EgSULTS .

REMARKS i

" ~C -7. CUAJ-7 U.T. (60') Acceptable Previously noted limited O[i(_):; (IGSCC scan 1 1/2" to 16". circum-Cat. D)' ferential limitation due to welded restraint pipe.

g. side of weld. Examiner.

~ noted same limitation to b be 4"'circumferential

- versus 4 1/2" circumfer-ential. Indications from

^

I.D. geometry evaluated as root reflectors.

8. CUAJ-14 U.T. (60') Acceptable No scan'(X-14) penetration t

' (IGSCC side of weld. ~ No indica-Cat. D) tion:.

Reactor Water Cleanup Return System 8" Stainless' Steel (6)

1. CUBJ-3 U.T. (60') Acceptable No scan valve side of (ICSCC. weld. . Indications from Cat. D) I.D. geometry evaluated as-root reflectors.

t

2. CUBJ-4 U.T. (60') Acceptable No scan valve side of (ICSCC P.T. weld. Indications ~from I.D. geometry. observed by Cat. . D)

. . NUSCO evaluator, but not recorded by GE examiner.

UT responses were similar to previous results-from e 1987. Past indications were evaluated as root and' counterbore reflectors.

Beam spread and sound.

redirection along with 0.D. geometric reflectors had been noted.

3. CUBJ-5' U . T.. (60') Acceptable No scan valve side of (IGSCC weld. . Indications from-Cat. D) I.D. geometry observed by NUSCO evaluator, but not recorded by GE examiner.

UT responses were similar to previous results from 1987. Past indications were evaluated as root reflectors. Beam spread' and sound redirection along with O.D. geometric reflectors had been noted.

O e7KQ2.07e 5.30 L _ _ __ __.______________-________________________.______________m_m___ _ _ _ _ _ _ _ ___---

l EXAMINATION ITEM EXAMS RESULTS REMARKS

4. CUBJ - 6 U.T. (60') Acceptable No scan valve side of

'f~}'-

(IGSCC weld. Indications from Cat, D) I.D. geometry observed by NUSCO evaluator, but not recorded by GE examiner.

UT responses were similar to previous results from 1987. Past indications were evaluated as root reflectors. Beam redirec-tion along with 0.D.

geometric reflectors had -!

been noted.

5. CUBJ-18 U.T. (60' & Acceptable No scan penetration (X-15)

(IGSCC 70*) side of weld. 70* angle ;

Cat. D) used to cover root area due to large weld crown.

Not previously noted during past examinations.

Indications from I.D.

geometry evaluated as root reflectors based on radio-graph review,

6. CUBJ-19 U.T. (60') Acceptable No scan valve side of f)'-

(IGSCC- weld. Indication from i

Cat. D) I.D. geometry evaluated as ;

root reflector. Spot indication at 4.75" circum. Indication sized ;

to be .075" diameter with !

no apparent length.

- Acceptable per Table IWB-3514-3. ,

Core Sorav System 10" Stainless Steel (7)

l. CSAJ-2 U.T. (45'), Acceptable No indications.

(IGSCC P.T. j Cat. A) i CSAJ-2-ELD U.T. (45'), Acceptable Elbow longitudinal weld i P.T. downstream of circum.

weld. No indications. l CSAJ-2-ELU U.T. (45'), Acceptable Elbow longitudinal weld P.T. upstream of circum. weld.

No indications. i 1

i

(

(_))

I eniome 5.31

.j

? -

EXAMINATION

' ITEM' EXAMS RESULTS REMARKS

2. CdBJ-l U.T. (60* 6 Acceptable Limited scan pipe side of

> /~}

i-- (IGSCC SW4 70*), weld 3" length due to pipe Cat. A) P.T. branch connection at top dead center of weld.

Indications from I.D.

geometry evaluated as root reflectors.

CSBJ-1-EL U.T. (60'), Acceptable Elbow longitudinal weld.

P.T. No indications.

CSBJ-1-PL U.T. (60'). Acceptable Pipe longitudinal weld.

P.T. No indications.

3. CSBJ-3 U.T. (60', Acceptable No indications.

(IGSCC profile 0*),

Cat. A) P.T.

CSBJ-3-EL U.T. (60'), Acceptable Elbow longitudinal weld.

P.T. No indications.

CS BJ- 3-PL U.T. (60'), Acceptable Pipe longitudinal weld.

P.T. No indications.

4. CSBJ-13 U.T. (60*) Acceptable Indications from 1.D.

f'i (ICSCC geometry evaluated as root

- \J Cat. D) reflectors. Spot indica-tion at approximately 28" clockwise from top dead center of weld. Indica-tion evaluated as porosity l pore from original radio-graph review.

5. CSBJ-14 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root

! Cat. D) reficctors.

6. CSBJ-15 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

7. CSBJ-16 U.T. (60*) Acceptable No scan valve side of (IGSCC weld. Indications from Cat. D) 1.D. geometry evaluated as j root reflectors.

l' Feedwater System 8" 12" 14" and 18" Welds Carbon Steel (13)

1. FWAJ-7 U.T. (60*, Acceptable Indications from I.D.

profile O'), geometry evaluated as root M.T. reflectors.

.( )

1 97KtX2M9 5.32

EXAMINATION-ITEM EXAMS RESULTS REMARKS

/~N 2. FWAJ-8 U.T. (60', Acceptable Indications from I.D.

(_) profile O'), geometry evaluated as root M.T. reflectors.

3. FWAJ-8A U.T. (60', Acceptable Indications from I.D.

profile O'), geometry evaluated as root M.T. reflectors. Beam redirec-tion noted.

4. FWAJ-CU1 U.T. (45', Acceptable No scan tee side of weld l profile 0*), due to 0.D. configuration.

l M.T. No indications.

I

5. FWAJ-10B U.T. (60*, Acceptable Indications from I.D.

profile O'), geometry evaluated as root M.T. reflectors.

1 j 6. FWAJ-10C U.T. (60', Acceptable Indications from I.D.

profile O*), geometry evaluated as root M.T. reflectors.

7. FWBJ-8 U.T. (60', Acceptable Indications from I.D.

I profile O*), geometry evaluated as root M.T. reflectors.

T 8. FWBJ-9 U.T. (60', Acceptable Indications from I.D.

('J A- - profile 0*), geometry evaluated as root M.T. reflectors.

9. FWBJ-20 U.T. (60', Acceptable Indications from I.D.

l profile O*), geometry evaluated as root M.T. and counterbore reflectors.

10. FWBJ -21 U.T. (60*, Acceptable Indications from I.D.

I profile O*), geometry evaluated as root M.T. reflectors.

11. FWBJ-22 U.T. (60*, Acceptable Indications frca I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

12. FWBJ-23 U.T. (45', Acceptable No scan valve side of profile O*), weld. Indications from M.T. I.D. geometry evaluated as root reflectors.

97KtK2W9 5.33

_ _ _ _ _ _ . _ _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - O

EXAMINATION 1 ITEM EXAMS RESULTS REHARKS i

! (~T 13. FWBJ-24 U.T. (45', Acceptable No scan valve side of

\l profile 0*), weld. Limited scan pipe M.T. side of weld 1.5" CU to 1.5" CCW for 3" at 0*

azimuth apparently due to gamma plug. Indications from I.D. geometry evaluated as root L reflectors.

Isolation Condenser Sunniv System 14" Welds Stainless Steel (2)

1. ICAJ-14 U.T. (45*, Acceptable No scan penetration (X-(IGSCC profile 0*), 10A) side of weld. No Cat. A) P.T. indications.

ICAJ-14-PL U.T. (45*), Acceptable Pipe longitudinal weld.

P.T. No indications.

2. ICAJ-15 U.T. (45', Acceptable No scan valve side of (IGSCC profile 0*), weld. Indications from Cat. A) P.T. I.D. geometry evaluated as root reflectors.

ICAJ-15-PL U.T. (45*), Acceptable Pipe longitudinal weld.

() P.T. No indications.

Isolation Condenser Return System 10" Welds Stainless Steel (7)

1. ICBJ-1 U.T (60') Acceptable Indications from I.D.

(ICSCC geometry observed, but not Cat. D) recorded by GE examiner.

NUSCO evaluator reexamined weld and I.D. geometry was evaluated as root ,

reflectors consistent with past U.T. results en this weld.

2. ICBJ-2 U.T. (60*, Acceptable Indications from I.D.

(IGSCC 60'L, & WS4 geometry evaluated as root Cat. D) 70') reflectors.

3. ICBJ-3 U.T. (60') Acceptable Limited scan pipe side of (ICSCC weld from 15" to 19" Cat. D) circum. due to welded support lug. Indications from I.D. geometry evaluated as root reflectors from beam redirection.

O maws 5.34

EXAMINATION ITEM EXAMS RESULTS REMARKS

4. ICBJ -4 U.T. (60*) Acceptable No scan valve side of

(_,

r') (IGSCC weld. Limited scan pipe Cat. D). side of weld same restric-tion as ICBJ-3. Indica-tions from I.D. geometry evaluated as root reflectors.

5. ICBJ-5 U.T. (60*), Acceptable No scan valve side of (ICSCC P.T. weld. Limited scan elbow Cat. D) side of weld at 4" circum.

for 2" due to branch weld.

Indications from 1.D.

geometry evaluated as root reflectors.

6. ICBJ-6 U.T. (60*) Acceptable Limited scan elbow side of (IGSCC weld at 4" circum. for 2" Cat. D) due to branch weld.

Indications from I.D.

geometry evaluated as root reflectors.

7. ICBJ-7 U.T. (60*) Acceptable Limited scan elbow side of (IGSCC weld at 8" circum. for 2" rT Cat. D) due to branch weld. Same

(_) restriction as ICBJ-6.

Indications from I.D.

geometry evaluated as root reflectors.

Low Pressure Coolant Iniection System 16" Welds Stainless Steel (4)

1. CCAJ-l U.T. (60*) Acceptable No scan tee side of weld.

(ICSCC Indications from I.D. and Cat. C) 0.D. geometry evaluated as weld configuration reflectors. Best effort UT examination.

2. CCAJ-10 U.T. (60*) Acceptable No scan valve side of (ICSCC weld. Indications from Cat. D) I.D. geometry evaluated as root reflectors.

O emxa on 5.35

r, )

l EXAMINATION ITEM EXAMS RESULTS REHARKS

('" i 3. CCAJ U.T. (60*) Acceptable No scan valve side of $

' weld. Limited scan j (IGSCC~

Cat. D) reducer side of weld at 49 1/2" to 2" circum. due to gamma plug. Indica-tions from I.D. geometry evaluated as root reflectors and beam redirection.

4. CCBJ-5 U.T. (60* & Acceptable- Limited scan valve side of (IGSCC WSY 70*) weld due to 0.D. configur-Cat. D) ation. Indications from I.D. geometry evaluated as root reflectors.

Low Pressure Coolant Injection System 18" Welds Stainless Steel (33)

1. CCAJ-2 U.T. (60*) Acceptable Limited scan 1/2 vee pipe (ICSCC side of weld due to 1.25" Cat. D) approximate spool piece length. Indications from I.D. geometry pipe side of weld evaluated as root and counterbore reflectors.

()

7s Indications from I.D.

geometry elbow side of weld evaluated as root and counterbore reflectors with beam redirection.

2. CCAJ-3 U.T. (45*) Acceptable Limited scan 1/2 vee pipe (IGSCC side of weld due to 1.25" Cat. D) approximate spool piece length. Indications from I.D. geometry pipe side of I weld evaluated as counter-bore reflectors. Indica-l tions I.D. Eeometry elbow i side of weld evaluated as root and counterbore reflectors.

l l

e7cuwe 5.36 l

\ _ _ _ . - - - _ _ -

EXAMINATION ITEM EXAMS RESULTS REMARKS

'_) 3. CCAJ-4 U.T. (60') Acceptable Limited scan elbow side of (IGSCC weld at 39" to 51" circum.

Cat. D) due to welded support lug.

Indications from I.D.

geometry pipe side of weld evaluated as root and counterbore reflectors.

Indications from beam redirection elbow side of weld finger dampened on O.D.

4. CCAJ-5 U.T. (45*) Acceptable No scan valve side of (IGSCC weld. Indications from Cat. D) I.D. geometry evaluated as counterbore reflectors.

5. CCAJ-6 U.T. (60') Acceptable No scan valve side of (ICSCC weld. Indications Cat. D) resulting from beam redirection finger dampened on 0.D.

6. CCAJ-7 U.T. (60') Acceptable Indications from I.D.

r-' (IGSCC geometry pipe side of weld

(_) Cat. D) evaluated as root and counterbore reflectors with beam redirection. No indications elbow side of weld.

7. CCAJ-8 U.T. (45*) Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

8. CCAJ-9 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) and counterbore reflectors.

9. CCAJ-12 U.T. (45') Acceptable Indications from 1.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

10. CCAJ-13 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

11. CCAJ-14 U.T. (60') Acceptable Indications from I.D.

(IGSCC P.T. geometry evaluated as root Cat. D) reflectors.

l-l l EXAMINATION ITEM EXAMS RESULIS REMARKS l

12. CCAJ-15 U.T. (60*) Acceptable Indications from I.D.

[} (IGSCC P.T. geometry _ evaluated as root Cat. D)' reflectors and beam redirection noted.

CCAJ-15-PL U.T. (60*) Acceptable Pipe longitudinal weld.

P.T. Indications from I D.

geometry evaluated as root reflectors.

13. CCAJ-16 U.T. (45*) Acceptable Indications from I.D.

(IGSCC P.T. geometry evaluated as root Cat. D) reflectors. Indication in weld root area evaluated as porosity pore verified by original radiograph.

0.D. geometry and beam redirection noted.

CCAJ-16-PLD U.T. (45*) Acceptable Pipe longitudinal weld P.T. downstream of circum, weld. Indication from I.D. geometry evaluated as root reflector.

CCAJ PLU U.T. (45*) Acceptable Pipe longitudinal weld

('])

P.T. upstream of circum. weld.

Limited scan counter clockwise side of weld from 3" to 7.5" due to welded penetration (X-43) fin. Only 7.5" of weld length scanned due to penetration. Indication from I.D. geometry 8

evaluated as root reflector.

14 CCAJ-17 U.T. (60*) Acceptable No scan penetration (X-43)

(ICSCC side of weld. Indications Cat. D) from I.D. geometry evaluated as root reflectors.

15. CCAJ-18 U.T. (53*, Acceptable Indications from I.D.

(IGSCC 60*, 5 WSY geometry evaluated as root Cat. D) 70*) and counterbore reflectors with beam redirection noted.

97K1X2.07e 5.38

p i

EXAMINATION.

ITEM EXAMS RESULTS REMAPJ(S 16 ', .CCAJ : U.T. (53', Acceptable Indications.from I.D.'

.p)s A'

i

-(ICSCC .60*, & WSY geonetry evaluated as root and counterbore reflectors

~

l Cat. D) 70*),

with beam redirection noted. _Previously noted' L: , scan limitation due to l . .. long, weld no longer l noted.

17 . < CCAJ-20 _U.T. (60*) Acceptable Indications from I.D.

(IGSCC geometry evaluated as root..

l! g . Cat. D) reflectors.

18. CCAJ-21 U.T. (53*, Acceptable Limited scan. pipe side of' (ICSCC 60*, & VSY weld due to welded support

, Cat. D) 70*): ' lugs at 13 1/4" to

1. " 14.1/4', 18 1/2" to-L 19 3/4", 46.1/2" to l 47 1/2" and at 21" to l~ 22 1/4" because of l; ,

longitudinal weld.

! ' Indications from I.D.

geometry evaluated-as root and counterbore reflectors.

19. CCBJ-1 U.T. (60*) Acceptable Indications from I.D.

(IGSCC geometry reducer side of Cat. D) weld evaluated as root reflectors.

20. CCBJ-2 U . T.. (60*) Acceptable No scan valve side of l

(IGSCC veld. Indication from Cat. D)- I.D. geometry evaluated as counterbore reflectors.

21. CCBJ-3 U.T. (60*) Acceptable No scan valve side of

.(IGSCC weld. Indication from Cat. D) 1.D. geometry evaluated as root reflector resulting

, from beam redirection.

22. CCBJ-4 U.T. (60*) Acceptable Indications from I.D.

-(IGSCC geometry evaluated as root Cat. D) reflectors.

23. CCBJ-10 U.T, (60*) Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

24. CCBJ-11 U.T. (45*, Acceptable Indications from I.D.

(IGSCC' 60*, & VSY geometry evaluated as root )

Cat. D) 70') reflectors, e m xa m 5.39

EXAMINATION j ITEM EXAMS RESULTS REMARKS i ts 25. CCBJ U.T. (45', Acceptable Indications from I.D.

(s-) (IGSCC 60', & WSY geometry evaluated as root Cat, D) 70') and counterbore reflectors.

26. CCBJ-13 U.T. (60') Rejectable Ultrasonic indications (IGSCC P.T. from 1.D. geometry Cat. D) evaluated as root reflectors resulting from beam redirection acceptable. Two liquid penetrant indications

1) 3/8" linear at 52" clockwise circum, and

2) 1 1/4" linear at 35" to 36 1/4" clockwise circum.

Rejectable in accordance with Table IWB-3514-3.

Retest P.T. Acceptable No indications. (See (After Section XI.)

Repair By Grinding)

CCBJ-13-PL U.T. (60') Acceptable Pipe longitudinal weld.

/^ P.T. No indications.

U

27. CCBJ-14 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors and beam redirection.

28. CCBJ-15 U.T. (60') Acceptable No scan penetration (X-45)

(ICSCC side of weld. No Cat. D) indications.

29. CCBJ-16 U.T. (60') Acceptable No scan penetration (X-45)

(IGSCC side of weld. Indications Cat. D) from I.D. geometry evaluated as root reflectors.

30. CCBJ-17 U.T. (60') Acceptable Indications from I.D.

(IGSCC P.T. geometry evaluated as root Cat. D) reflectors.

31. CCBJ-18 U.T. (60') Acceptable Indications from 1.D.

(IGSCC P.T. geometry evaluated as root Cat. D) reflectors.

emx2m 5.40

c.

V,,L

n N o 2 : EXAMINATION ITEM EXAMS RESULTS REMARKS j r

.U.T. (60*) Acceptable

32. CCBJ-19 Ultrasonic indications P - , -s '

(IGSCCL P.T. from I.D. geometry evaluated as root and

-Cat. D) '

counterbore reflectors.

. Liquid penetrant' indications from poor weld cleaning. Recleaned and ;

reexamined weld. No E

indications.

i CCBJ-19-PL-- .U.T. (60*) Acceptable Pipe. longitudinal weld.

P.T. No indications.

33. CCBJ-20 .U.T. (60')' Acceptable Indications from I.D.

(IGSCC P .T. - geometry evaluated as root Cat. D) reflectors.

Main Steam System 6" Welds Carbon Steel (5)

'1. RVBJ-3 U.T. (45*, Acceptable No scan weldolet side of-profile 0*), weld due to 0.D. configur-M.T. ation. No indications.

2. -KVBJ-3A U.T. (45', -

Acceptable No scan flange side of profile 0*), veld. No indications.

M.T.

3. RVCJ-3A~ U.T. (60*, Acceptable No scan flanSe side of profile 0*), weld. No indications.

M.T.

4. RVDJ-2 U.T. (60*, Acceptable No scan weldolet side of profile 0*), weld due to 0.D.

M.T. configuration. Magnetic particle indication noted from poor weld cleaning.

Recleaned and reexamined weld. No' indications.

5. RVDJ-2A U.T. (60*, Acceptable No scan' flange side of profile 0*), weld. Indications from M.T. I.D. geometry evaluated as root reflectors.

Main Steam System 20" Welds Carbon Steel (20)

1. MSAJ-6 U.T. (60*, Acceptable Indication from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

O enumwe 5.41

l

{'

EXAMINATION ITEM EXAMS RESULTS REMARKS I~N 2. MSAJ U.T. (60', Acceptable No scan valve side of

\- profile O'), weld. Indications from M.T. I.D. geometry evaluated as ;

root reflectors.

3. MSBJ-RV3 U.T. (45'), Acceptable No scan weldolet side of M.T. weld. No indications. !

4. MSBJ-ll U.T. (45', Acceptable Indications from I.D.

profile O'), geometry evaluated as root M.T. and counterbore reflectors.

5. MSBJ-12 U.T. (45', Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

6. MSBJ-13 U.T. (45*, Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M . T.. and counterbore reflectors.

MSBJ-13-EEL U.T. (45') Acceptable Elbow extrados longi-M.T. tudinal weld. No indications.

MSBJ-13-EIL 'J . T . (45') Acceptable Elbow intrados longi-M.T. tudinal weld. No indications.

7. MSBJ-14 U.T. (45', Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

MSBJ-14-EEL U.T. (45') Acceptable Elbow extrados longi-M.T. tudinal weld. No indications.

MSBJ-14-EIL U.T. (45') Acceptable Elbow intrados longi-M.T. tudinal weld. No indications.

8. MSCJ-11 U.T. (45*, Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

9. MSCJ-12 U.T. (45') Acceptable Indications from I.D.

M.T. geometry evaluated as root reflectors.

O enum e7e 5.42

I.

EXAMINATION ITEM EXAMS RESULTS REMARKS L

(~') 10. MSCJ-13 U.T. (45*, Acceptable Indications from I.D.

'w/ profile 0*), geometry evaluated as root M.T. reflectors. . Magnetic particle indication at 57" circum. 1/4" transverse linear indication at toe of weld. Acceptable in accordance with Table IVB-3514-2.

11. MSCJ-14 U.T. (45') Acceptable Indications from I.D.

M.T. geometry evaluated as root reflectors.

12. MSCJ-15 U.T. (45*) Acceptable Indications from I.D.

M.T. geometry evaluated as root reflectors.

13. MSCJ-21 U.T. (60*, Acceptable No scan valve side of profile 0*), weld. Indications from M.T. I.D. geometry evaluated as root reflectors.

14. MSDJ-7 U.S. (60*, Acceptable Indications from I.D.

profile 0*), geometry evaluated as root

(,,) M.T. reflectors.

15. MSDJ-RV2 U.T. (45*, Acceptable No scan weldolet side of profile 0*), weld. Magnetic particle M.T. indication noted from poor veld cleaning. Recleaned and reexamined weld. No indications.

16. MSDJ-11 U

'.T. (60*, Acceptable Indication from I.D.

profile 0), geometry evaluated as root M.T. reflector resulting from beam redirection.

17. MSDJ-12 U.T. (60*, Acceptable Indications from 1.D.

profile 0*), geometry evaluated as root M.T. reflectors.

18. MSDJ-13 U.T. (60*, Acceptable No scan valve side of profile 0*), weld. Indications from M.T. 1.D. geometry evaluated as root reflectors.

19. MSDJ-16 U.T. (60*, Acceptable No scan penetration (X-7D) profile 0*), side of weld. Indications M.T. from I.D. geometry O evaluated as root reflectors.

emx2m 5.43

EXAMINATION ITEM EK/tMS RES'ULTS REMARKS 1

1

(

(')

(./

20. MSDJ-17 U.T. (60*,

profile O*),

Acceptable No scan valve side of weld. Indications from M.T. I.D. geometry evaluated as root reflectors.

Recirculation Outlet System 3" Weld Stainless Steel (1) l 1 RCBJ-PB3 P.T. Acceptable Na indications.

l. (Branch l Weld) l Recirculation Outlet System 4" Welds Stainless Steel (4)

1. RCAJ-PB1 U.T. (45') Acceptable This is a branch weldolet (IGSCC to pipe weld. Best effort Cat. D) ultrasonic examination.

Indications noted from root geometry at 18db above reference level.

2. RCAJ-PB2 U.T. (45') Acceptable Same as above.

(IGSCC Cat. D)

3. RCBJ-PB1 U.T. (45') Acceptable Same as above.

(IGSCC

(~/T

\- Cat. D) 4 RCBJ-PB2 U.T. (45') Acceptable Same as above.

(IGSCC Cat. D)

Recirculation Outlet System 14" Weld Stainless Steel (1)

1. RCBJ-IC1 U.T. (60') Acceptable No scan tee side of weld.

(IGSCC P.T. Indications from I.D.

Cat. D) geometry evaluated as root reflectors resulting from beam redirection. 1.5" long indication at 26" clockwise circum. elevated as root undercut verified by original radiograph.

RCBJ-ICl-RL U.T. (45') Acceptable Reducer longitudinal weld.

P.T. No indications.

O exiume 5.44

EXAMINATION ITEM EXAMS RESULTS REMARKS

(-- Recirculation Outlet System 28" Welds Stainless Steel (12)

\ )g .

1. RCAJ-1 U.T..(45*, Accepted by Original sizes Flaw #1 (IGSCC 60*, & WSY Analysis in .090"' deep by 2 1/2" long Cat. E) 70*) 1984 at 0*. Flaw #2 .175" deep by 6 1/2" long at 23" counterclockwise. Note:

Flaws match previous l examination data. No i change.

2. RCAJ-1A U.T. (45* 6 Acceptable Indications from I.D.

(IGSCC 60*) geometry evaluated as root Cat. C) reflectors.

3. RCAJ-5 U.T. (45*, Acceptable Indications from I.D.

(IGSCC 60*, & WSY geometry evaluated as root Cat. C) 70*) P.T. and counterbore reflectors.

RCAJ-5-EEL U.T. (45*) Acceptable Elbow extrados longi-P.T. tudinal weld. No indications.

RCAJ-5-EIL U.T. (45*) Acceptable Elbow intrados longi-x P.T. tudinal weld. No k'~_ indications.

RCAJ-5-PL U.T. (45*) Acceptable Pipe longitudinal weld.

P.T. No indications.

4. RCAJ-6 U.T. (45*) Acceptable No scan valve side of (IGSCC P.T. weld. Indications from Cat. C) I.D. geometry evaluated as root reflectors.

RCAJ-6-EEL U.T. (45*) Acceptable Elbow extrados longi-P.T. tudinal weld. No indications.

RCAJ-6-EIL U.T. (45*) Acceptable Elbow intrados longi-P.T. tudinal weld. Limited examination from 4" to 7" due to welded support lug on weld. No indications.

/3 V

emxwe 5.45 w_-____-___ __ . _ _ _ _ _ _ _ _

EXAMINATION ITEM EXAMS RESULTS REHARKS L ( s., 5. RCAJ-7 U.T. (45', Acceptable No scan valve side of l

(_) (ICSCC 60', & WSY weld. Indications from

. Cat. E)' 70') 1.D. geometry evaluated as root reflectors. Four flaw indications identi-fled in 1987 and resized this outage showed no evidence of further flaw propagation. Original l~

flaw sizes #1 (5.5" to 6.625" CW/1.125" long x

.11" deep), #2 (10" to 13" CCW/3" long x .03" deep),

3 (4.625" to 5.5" CCW/

.875" long x .1" deep),

and #4 (18" to 19.125" CCW/1.125" long x .16" deep). Flaws acceptable per IWB-3640. Winter 1985 Addenda. (NUSCO Calcula-tion No. 86-041-889CP.)

6. RCAJ-8 U.T. (45') Acceptable Limited scan elbow side of (ICSCC weld cast S/S. No Cat. C) indications.

() 7. RCBJ-3 U.T. (45') Acceptable No scan tee side of weld.

(ICSCC No indications.

Cat. C)

8. RCBJ-4 U.T. (45') Acceptable No scan tee side of weld.

(IGSCC No indications.

Cat. C)

{

i 97K1X2.07e 5.46 i i

1

- - _ . _ _ _ _ _ - _ _ _ _ _ _ _ ._ - - _ _ - _ _ _ . - _ _ b

( ,

EXAMINATION y . ITEM- EX4MS RESULTS REMARKS

(~N 9. RCBJ-5 U.T. (45', Acceptable Indications from I.D.

\- (IGSCC 60', & WSY geometry evaluated as root Cat. E) 70') and counterbore reflectors. Four flaw indications identified in 1987 and resized this outage showed no evidence of further flaw propaga-tion. Original flaw sizes

1 (3.5" to 4" CCW/.5" long x .16" deep), #2 (34.5" to 36.5" CCW/2" long x .19" deep), #3 (27.75" CW/.375" long x

.12" deep), and #4 (19.5" to 20.75" CW/1.25" long x

.17" deep). Flaws acceptable per IWB-3640, Winter 1985 Addenda.

(NUSCO Calculation No. 86-041-888GP.)

10. RCBJ-6 U.T. (45') Acceptable No scan valve side of (IGSCC weld. Indications from Cat. C) 1.D. geometry evaluated as root and counterbore

(~}L reflectors.

11. RCBJ-7 U.T. (45', Acceptable Limited scan valve side of (ICSCC 60', & WSY weld due to 0.D. configur-Cat. C) 70*) P.T. ation. Indications from I.D. geometry evaluated as root reflectors. Liquid penetrant indication at 2 3/4" clockwise circum.

1/8" linear, 3/8" from toe-of weld on valve. side.

Indication acceptable in accordance with Table IWB-3514-3.

RCBJ-7-PL U.T. (45') Acceptable Pipe longitudinal weld.

P.T. No indications.

12. RCBJ-8 U.T. (45* , Acceptable Limited scan elbow side of (IGSCC 60', & WSY weld due to 0.D.

Cat. C) 70*) configuration cast S/S.

Indications from 1.D.

geometry evaluated as root reflectors .

.O.

mmm 5.47

EXAMINATION ITEM EXAMS RESULTS REMARKS l

f s- Recirculation Manifold System Ellipsoidal Flued Head Weld to Cross

~( l' 28" x 12" Stainless Steel (1)

1. RMBJ-RRH U.T. (45') Acceptable No indications.

(IGSCC P.T.

Cat. C) i Recirculation Manifold System 22" Welds Stainless Steel (3) l

1. RMAJ-1 U.T. (45') Acceptable Indications from 1.D.

(IGSCC geometry evaluated as root Cat. C) and counterbore l reflectors.

2. RMBJ-1 U.T. (60*L Acceptable Overlay repaired in 1987.

(IGSCC & 70*L) No flaw extension noted Cat. E) into overlay.

3. RMBJ-4 U.T. (45') Acceptable No scan cross side of (ICSCC P.T. weld. No indications.

Cat. C)

RMBJ-4-PL U.T. (45') Acceptable Pipe longitudinal weld.

P.T. No indications.

(I R' circulation Inlet' System 12" Riser Velds Stainless Steel (10)

1. RRAJ-4 U.T. (60'L Acceptable Overlay repaired in 1984 (ICSCC & 70'L) No flaw extension noted Cat. E) into overlay.

2. RRBJ-1 U.T. (60*L, Acceptable Overlay repaired in 1984.

(IGSCC 70*L, & 0.D. No flaw extension noted Cat. E) Creeper) into overlay.

3. RRBJ-2 U.T. (60*L, Acceptable Overlay repaired in 1984.

(ICSCC 70'L, & O.D. No flaw extension noted Cat. E) Creeper) into overlay.

4. RRCJ -3 U.T. (60*L, Acceptable Overlay repaired in 1984.

(IGSCC 70*L, & O.D. No flaw extension noted l Cat. E) Creeper) into overlay.

5. RREJ-1 U.T. (60') Acceptable Indications from I.D.

(IGSCC P.T. geometry noted as root Cat. C) reflectors 360'.

6. RREJ - 3 U.T. (60*L Acceptable Overlay repaired in 1984.

(ICSCC & 70'L) No flaw extension noted Cat. E) into overlay.

O.

exumas 5.48 i

i _ l

l EXAMINATION.

l' ITEM EXAMS' RESULTS REMARKS l 1

(~') 7. RRFJ-1 U.T. (60*L Acceptable Overlay repaired in 1984.

() (IGSCC & 70*L) Several lift off areas

Cat. E) noted due to 0.D. overlay contour. No flaw exten-sion noted into overlay.

8. RRHJ-2 U . T.. (60*) Acceptable Indications from I.D.

(ICSCC P.T. geometry evaluated as root Cat. C) reflectors.

RRHJ-2-EEL U.T. (60*) Acceptable Elbow extrados longi-P.T. tudinal weld. No

. indications.

RRHJ-2-EIL U.T. (60') Acceptable Elbow intrados longi-P.T. 'tudinal weld. No indications.

1

9. RRHJ-4 U.T. (60*) Acceptable No scan ellipsoidal flued (IGSCC P.T. head side of weld.

Cat. C) Indications from I.D.

geometry evaluated as root reflectors.

RRHJ-4-PL U.T. (60*) Acceptable Pipe longitudinal weld.

(} P.T. No indications.

10 RRKJ-4 U.T. (60*) Acceptable No scan sweepolet side of L (ICSCC weld. Indications from Cat. C) I.D. geometry evaluated as root reflectors.

Shutdown Cooline System 14" Welds Stainless Steel (2)

1. SCAJ-2 U.T. (45*) Acceptable Indications from I.D.

(IGSCC P.T. geometry evaluated as root Cat. A) and counterbore reflectors and beam redirection.

SCAJ-2-EEL U.T. (45*) Acceptable Elbow extrados longi-P.T. tudinal weld, Indications from I.D. geometry evaluated as root

! reflectors.

i SCAJ-2-EIL U.T. (45*) Acceptable Elbow intrados longi-P.T. tudinal weld. Indication from I.D. geometry evaluated as root <

reflector.

SCAJ-2-PL U.T. (45*) Acceptable No indications.

P.T.

enume 5.49

'(.

EXAMINATION ITM EXAfiS RESULTS R NARKS

(~') 2. SCAJ-CU1 U.T. (45*) Acceptable No scan veldolet side of

\_,/ (IGSCC P.T. weld. No indications.

Cat. A)

Shutdown Cooline System 146 Weld Carbon Steel (1)

1. SCAJ-12 U.T. (45*, Acceptable No scan penetration (X-12) profile 0*), side of weld. Indications M.T. from I.D. geometry evaluated as root reflectors.

Shutdown Cooline System 12" Welds carbon Steel (3)

1. SCBJ-12 U.T. (45*, Acceptable No scan tee side of weld.

profile 0*), Indications from I.D.

M.T. geometry evaluated as root reflectors.

2. SCBJ-13 U.T. (45*, Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

3. SCBJ-16 U.T. (45*, Acceptable Indications from I.D.

profile 0*), geometry evaluated as root M.T. reflectors.

)

Standbv Liould Control System 2" 6 1.5" Socket Velds Stainless Steel (5)

1. SLCJ - 8 P.T. Acceptable No indications.

2. SLCJ-9 P.T. Acceptable No indications.

I

3. SLCJ-27 P.T. Acceptable No indications.

4. SLCJ-28 P.T. Acceptable No indications.

5. SLCJ-29 P.T. Acceptable No indications.

l l

l O

l 1

sma cn 5.50

h L

I..

ASME CLASS l' EXAMINATION RESULTS

>^

t lk .

t -CATEGORY B-K-1 EXAMINATION AREA: Integral Attachments for Piping, Pumps, and Valves Whose Attachment Base Material Design Thickness is 5/8" and Greater (8)

EXAMINATION METHOD: Volumetric (U.T.) or Sukface (P.T.-or M.T.) As Applicable

' EXAMINATION ITEM EXMiS RESULTS REMARKS Low Pressure Coolant Iniection System Intecral Attachment' Welds.

Stainless Steel

1. (A)CC-H-66 P.T. . Acceptable No relevant indications.

2, (A)CC-H-67 P.T.' Visual Acceptable 2" linear-indication noted. Visual ~ examination showed slag in toe of weld. Weld area was reeleaned and reexamined with liquid penetrant. No relevant indications.

Main Steam System Intecral Attachment Veld Carbon Steel (1)

1. (D)MSR-H-14 M.T. Acceptable No relevant indications.

Recirculation System Intecral Attachment Welds Stainless Steel (4)

1. (A)RLP-H-10A P.T. Acceptable No relevant indications.

2. (A)RLP-H-14B P.T. . Acceptable 1/4" linear indication noted in. toe of weld.

Indication area was reeleaned and reexamined with liquid penetrant. No relevant indications. !

3. (B)RLP-SS-8B P.T. Acceptable 1/8" rounded indication in toe of weld. Indication is acceptable in accor-dance with Table IWB-3516-2.

4. RLP-SS-2A P.T. Acceptable No relevant indications.

Standby Liould Control System Intecral Attachment Veld Stainless

. Steel (1)

1. PENET.X42 P.T. Acceptable No relevant indications.

97K1X2.07e 5.51 J -- _ . _ _ _ _ _ . _ _ _ __ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

ASME CIASS 1 EXAMINATION RESULTS fy

\v' CATEGORY B-M-2 EXAMINATION AREA: Internal Pressure Boundary Surfaces of Valve Bodies (1)

EXAMINATION METHOD: Visual (V.T.-3)

EXAMINATION ITEM EXAMS EISULTS REMARKS-

1. Reactor V.T. Acceptable 3/4" wide x 1/50" deep Water grooves noted on both Cleanup sides of valve gate Supply guides. Subject grooves System are from valve operation Valve and do not adversely 1-CU-3 effect valve function.

r~s

'\,)

r .

07K1X2 079 5.52

~

' ~ ~

aai - +

q# .- ,

15: r' '

cf, ,

p: .)

' ASME CIASS 1 EXAMINATION RESULTS -

CATEGORY'B-N-1 Reactor Vessel Interior;(2)

~

s EXAMINATION AREA:

EXAMINATION METHOD: 'Visuall(V.T.-3) Accessible' Areas ~

~'

EXAMINATION L

ITEM EXAMS RESULTS BEHARKS f

g.

.1. Steam Dryer: V.T;-3 ' Acceptable None

.. . p .= .

rs . 2. : Core Spray > .V.T.-3 Acceptable .None

.Spargers-1

\ ,

t O

l.,

1 l^

1 l::

h LO;

t. . . minm ' 5.53 V

E L r_

w-a - - _ _ _ . _ _ .

t i

J-1 d .

s o <

r s

T SECTION VI ASME CLASS 2' EXAMINATION RESULTS O.

4 0

6.0 97K1X2 079

_ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ , _ _ _ _ _ _ _ _ _ _]

ASME CLASS 2 EXAMINATION RESULTS e,

k_,}. CATEGORY C-B EXAMINATION AREA: Pressure Retaining Welds in Vessels (4)

EXAMINATION METHOD: Volumetric (U.T.) and Surface (M.T. or P.T.)'

EXAMINATION ITEM EXAMS RESULTS REHARKS North End Isolation Condenser Supply System Nozzle to Heat Exchancer Veld 12" Carbon Steel Cladded

1. ICAC-B-1 U.T. Acceptable Best effort U.T. examina-(60*L) tion from nozzle side of M.T. weld. No indications.

North End Isolation condenser Return System Nozzle to Heat Exchanger Veld 8" Carbon Steel Cladded

1. ICBC-B-3 U.T. Acceptable Best effort U.T. examina-(60*L) tion from nozzle side of M.T. weld. No indications.

Shutdown Cooline System Discharre Nozzle to Hx 10" Carbon Steel Veld

1. SDBC-B-1 U.T. Rej ectable Limited scan for approxi-(60*L, mately 2" circum. due to profile 1" pipe and plugs located 0*), M.T. at 0*, 90*, and 270*. No ultrasonic indications.

Magnetic particle indication 5 1/2" long at toe of weld rejectable.

Retest M.T. Acceptable No relevant indications.

(After (See Section XI.)

Repair by Grinding)

Shutdown Cooling System Inlet Nozzle to Hx 10" Carbon Steel Veld

1. SDAC-B-1 U.T. Acceptable Same limited scan as (60*L, SDBC-B-1 above. No profile relevant indications.

0*), M.T.

O 6.1 87K1X2 079

ASME CLASS 2 EXAMINATION RESULTS' f-)

V' CATEGORY C-C EXAMINATION AREA: Integral Attachments for Vessels, Piping, Pumps, and Valves with Base Material Design Thickness 2 3/4" EXAMINATION METHOD': Surface (M.T. or P.T.)

EXAMINATION ITEM EXAMS RESULTS REMARKS Shutdown Cooline System Integral Attachment Weld Carbon Steel (1)

1. (R) CC-H-16 M.T. Acceptable No relevant indications, na O

6.2 G7K1X2.079

ASME CLASS 2 EXAMINATION RESULTS n

k-}

% CATEGORY C-F EXAMINATION AREA: Pressure Retaining Welds in Piping (58)

EXAMINATION METHOD: Nominal Wall Thickness 5 1/2 in. - Surface (M.T.

or P.T.)

Nominal Wall Thickness > 1/2 in. - Surface (M.T.

or P.T.) and Volumetric (U.T.)

EXAMINATION ITEM EXAMS RESULTS REMARKS Core Sorav System 10" Stainless Steel to Carbon Steel Weld (1)

1. CSBC-G-2 U.T. (60*) Acceptable Scanned stainless steel S/S (ICSCC pipe side of weld only.

Cat. D) Indications from I.D.

geometry evaluated as root reflectors.

CSBC-G-2 U.T. (60') Acceptable Scanned carbon steel pipe C/S (ICSCC side of weld only.

Cat. D) Indications from I.D.

geometry evaluated as root reflectors.

[}

Core Sprav System 10" Carbon Steel Welds (4)

1. CSAC-G-37A R.T. Acceptable Examined for flange (baseline) P.T. R0 10-2A replacement.

(See Section XI.)

2. CSAC-G-38A R.T. Acceptable Examined for flange (baseline) P.T. R0 10-2A replacement.

(See Section XI.)

3. CSBC-G-31A R.T. Acceptable Examined for flange (baseline) P.T. RO 10-2B replacement.

(See Section XI.)

4 CSBC-G-32A R.T. Acceptable Examined for flange (baseline) P.T. RO 10-2B replacement.

(See Section XI.)

Isolation Condenser Suoply Steam 6" Stainless Steel Welds (2)

1. ICAC-F-29 U.T. (45*) Acceptable No scan weldolet side of L (IGSCC P.T. weld. Indications from l

Cat. A) 1.D. geometry evaluated as root reflectors.

6.3 97K1X2 079 t -. - - - - - - - - - - - - - _ - - - - - - _ _ -

EXAMINATION ITEM EXAMS RESULTS REHARKS

<~g 2. ICAC-F-31 U.T. (45*, Acceptable No indications

.I profile 0*),

ss i (ICSCC Cat. A) P.T.

Isolation Condenser Supolv System 12" Stainless Steel Velds (6)

1. ICAC-F-12 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root Cat. D) reflectors.

2. ICAC-F-12A U.T. (45' & Acceptable Indications from I.D.

(IGSCC 60') geometry evaluated as root Cat. D) reflectors.

3. ICAC-F-14 U.T. (45* & Acceptable Indications from I.D.

(IGSCC 60*) P.T. geometry evaluated as root Cat. D) reflectors.

ICAC-F-14-EL U.T. (45*) Acceptable Elbow longitudinal weld.

P.T. No indications.

4. ICAC-F-15 U.T. (60') Acceptable Indications from I.D. and (IGSCC P.T. O.D. geometry evaluated as Cat. D) root, counterbore and weld crown reflectors.

,y

(-) 5. ICAC-F-16 U.T. (60') Acceptable Indications from I.D. and (IGSCC P.T. O.D. geometry evaluated as Cat. D) root and weld crown reflectors.

6. ICAC-F-16A U.T. (60', Acceptable Indications from I.D. and (ICSCC profile O*), O.D. geometry evaluated as Cat. A) P.T. root and weld crown reflectors with noted beam redirection.

ICAC-F-16A-PL U.T. (60*) Acceptable Pipe longitudinal weld.

P.T. No indications.

Isolation Condenser Sunniv System 14" Stainless Steel Veld (1)

1. ICAC-F-1 U.T. (45') Acceptable No scan valve side of (IGSCC weld. Indications from Cat. D) I.D. geometry evaluated as root reflectors.

Isolation Condenser Sunniv System 16" Stainless Steel Velds (7)

1. ICAC-F-2 U.T. (60') Acceptable Indications from I.D.

(IGSCC geometry evaluated as root

/'] Cat. D) reflectors.

kJ 6.4 97K1X2.079

___________________________________o

q 3: , y

, -+

. EXAMINATION-ITEM EXAMS RESULTS- REMARKS l -2. ICAC-F-3 U.T. (60*L & Acceptable Veld overlay repaired:in' E 4 s (IGSCC- 70*L). .1984. Indications noted FU ' ' Cat'. E) due to lift-off caused by overlay surface. Presence; of original flaw could not be detected. No.sf3nals of flaw propagation into .

the overlay could be seen.

3. .ICAC-F-8 -U.T. (45') Acceptable No indications.

(IGSCC t

Cat. D)

4. ICAC-F 'U.T. (45' & Acceptable Indications from I.D.

(IGSCC 60*) geometry evaluated as root Cat. D) reflectors.

5. ICAC-F-10 U.T. (45' & Acceptable ' Indications from I.D.

(IGSCC 60*) P.T. geometry evaluated as root Cat. D) reflectors.

6. -ICAC-F-11 U.T. (45* & Acceptable' Indications from I.D.

(IGSCC 60') P.T. geometry evaluated as root Cat. D) and counterbore reflectors.

\s - 7. ICAC-F-20 U.T..(45' & Acceptable Indications from I.D.

(IGSCC 60') geometry evaluated as root Cat. D) reflectors.

Isolation Condenser Return System 8" Stainless Steel Welds'(10)

1. ICBC-F-11' U.T. (45*, Acceptable Indications from 1.D.

(ICSCC. profile O*), geometry evaluated as I.D.

Cat. A) P.T. weld transition reflectors-from original radiograph.

2. ICBC-F-15 U.T. (45' & Acceptable Indications from I.D. and (IGSCC 60*) 0.D. geometry evaluated as Cat. D) root and weld crown reflectors.

3. ICBC-F-16 U.T. (45' & Acceptable Indications from I.D. and (IGSCC 60*) P.T. O.D. geometry evaluated as

. Cat. D) root, counterbore and weld.

crown reflectors with noted beam redirection.

[.

sO 6.5

. 97K1X2.079 L _ ._ - _ _ - - _. _ _ _ _ _ - . - _ - - _ _ _ _ _ - - _ - _ _ _ _ _ - - _ _ _ _ - - _ _ -

EXAMINATION ITEM EXAMS RESULTS REMARKS 1

gg 4. ICBC-F-17 U.T. (45' & Acceptable Indications from I.D.

(_) (IGSCC 60*) geometry evaluated as root Cat. D) reflectors and beam <

redirection noted off counterbore.

5. ICBC-F-18 U.T. (45* & Acceptable Indications from I.D.

(IGSCC 60') geometry evaluated as root Cat. D) reflectors.

6. ICBC-F-19 U.T. (45* & Acceptable No scan safe end side of (IGSCC 60') P.T. weld due to 0.D. con-Cat. D) figuration. Indications from I.D. geometry evaluated as root reflectors.

7. ICBC-F-20 U.T. (60*L) Acceptable No ultrasonic indications.

(ICSCC P.T. Magnetic particle Cat. D) indication noted while examining adjacent. weld ICBC-B-3. Indication caused by dissimilar metal interface and verified nonrelevant by liquid penetrant examination.

(~)

%.)

8. ICBC-F-22 U.T. (45*, Acceptable Indications from I.D. and (IGSCC 60', & base 0.D. geometry evaluated as Cat. D) metal 0*) root and weld crown R.T. reflectors. Various spot indications found in base metal on pipe spool piece between this weld and ICBC-F-22A. Base metal indications were evaluated as inclusions dispersed throughout the microstruc-ture of the base metal and were characterized and assessed by radiography.

These inclusions are not considered deleterious to the function of the pipe material and are not uncommon in cold drawn piping of this ASTM A-312 material specification.

Reference disposition letter PSE-CE-89-262.

6.6 07K1X2.079

1 EXAMINATION l

' ITEM EXAMS RESULTS REMARKS l

.fs 9. ICBC-F-22A U.T. (45*, Acceptable Same as ICBC-F-22 above.

ts ,) (IGSCC 60*, & base Cat. D) metal 0*)

R.T.

10. ICBC-F-23 U.T. (45' & Acceptable Indications from I.D. and (IGSCC 60*) 0.D. geometry evaluated as Cat. D) root and weld crown reflectors.

Isolation Condenser Return System 10" Stainless Steel Weld (3)

1. ICBC-F-9 U.T. (60*) Acceptable Limited scan noted in (IGSCC curvature areas of tee.

Cat. D) Indications from I.D.

geometry evaluated as root reflectors.

2. ICBC-F-10 U.T. (60') Acceptable Limited scan noted in (IGSCC P.T. curvature areas of tee.

Cat. D.) Indication from 0.D.

geometry noted and evaluated as weld crown reflector.

g3 3. I CBC- F--21 U.T. (60*) Acceptable Limited scan noted in

( (IGSCC curvature areas of tee.

Cat. D) Indications from I.D. and 0.D. geometry evaluated as root and weld crown reflectors .

Low Pressure Coolant Injection System 10" Carbon Steel Velds (2)

1. CCBC-G-17A R.T. Acceptable Examined for valve 1-LP-(baseline) P.T. 15B rotation. (See Section XI.)

2. CCBC-G-18A R.T. Acceptable Examined for valve 1-LP-(baseline) P.T. ISB rotation. (See Section XI.)

Shutdown Coolinc System 6" Carbon Steel Welds (4)

1. SDAC-F-1C P.T. Acceptable No relevant indications.

2. SDAC-F-10 R.T. Acceptable Examined for valve 1-SD-34 (baseline) P.T. installation. (See Section XI.)

1 6.7 97KtX2.070

L l

. EXAMINATION s -ITEM- EXAMS RESULTS REMARKS E

T('< ' t 3. SDAC-F-1E_. 'R.T. Acceptable LExamined for valve 1-SD , (baseline) P.T. installation. (See Section XI.)

4. -SDBC-F-1E R.T. Acceptable. Examined for valve 1-SD L (baseline) P.T. installation (See~

Section XI.)-

Shutdown Cooline System 8" Carbon Steel Veld (1) 1.- SDAC-F-39 M.T. Acceptable No relevant indications-.

Shutdown Cooline System 10" Carbon Steel Velds (14)

'l. SDAC-F-29 U.T. (45*, Acceptable Indications from I.D.

60*, & geometry evaluated as root' profile 0*), reflectors.

M.T.

2. SDAC-F-30 U.T. (45*, Acceptable Indications from I.D.

60*, & geometry evaluated as root profile 0*),

re flectors .

M.T.

3. SDAC-F-31 U.T. (45*, Acceptable Indications from I.D.

geometry evaluated as root 60*, &

profile 0*), reflectors.

M.T.

4. SDAC-F-40 U.T. (60*, Acceptable Limited scan from 7.5" to profile 0*), 10.5" circum, on elbow M.T. side of weld due to welded support lug. Indications from I.D. geometry evaluated as root reflectors.

5, SDBC-F-1D P.T. Acceptable Examined for valve 1-SD-34 (baseline) installation. (See Section XI.)

6.8 mum E_.___________________________________.____ _ . _ _ . _ _ _ . _ . _ _ . _ _ _ _

l EXAMINATION f- ITEM EXAMS RESULTS REMARKS I

<~5 6. SDBC-F-2A U.T. (60*, Acceptable Examined for valve 1-SD-34

(._) (baseline) profile 0*), installation. Limited R.T., P.T. sean at 9 1/2" to 17" circum, due to weldolet veld SDBC-F-lD. Limited scans due to vent lines upstream side of weld 28 1/2" to 31" circum. and downstream side of weld 20" to 22" circum.

Indications from I.D.

geometry evaluated as root reflectors with beam redirection. (See Section XI.)

7. SDBC-F-2B U.T. (60', Acceptable Examined for valve 1-SD-4A (baseline) profile O*), replacement. No scan R.T., P.T. valve side of weld.

Limited scan 9 1/2" to 17" circum, due to weldolet veld SDBC-F-lD.

Indications from I.D.

geometry evaluated as root reflectors with beam r~% redirection. (See

.(_) Section XI )

8. SDBC-F-3A U.T. (60', Acceptable Examined for valve 1-SD-4A (baseline) profile 0*), replacement. No scan R.T., P.T. valve side of weld. No ultrasonic indications.

(See Section XI.)

9. SDBC-F-4A U.T. (53', Rejectable Examined for valve 1-SD-4A (baseline) 60', 70*L, & replacement. Ultrasonic profile 0*), spot indication evaluated R.T., P.T. as rejectable porosity located at 8 1/2" circum.

in weld crown area.

Retest (After U.T. (60') Acceptable No indications. (See Weld Repair) P.T. Section XI.)

10. SDBC-F-6 U.T. (45', Acceptable Indications from I.D.

60*, & geometry evaluated as root profile 0*), reflectors.

M.T.

6.9 97K1K2.079

EXAMINATION ITEM EE6M1 RESULTS REHARKS

.rs 11. SDBC-F-9A U.T. (60*, Acceptable Examined for valve 1-SD-4B

(_) (baseline) profile O*), replacement. No scan R.T . P.T. valve side of weld.

Indications from 1.D.

geometry evaluated as root reflectors. (See Section XI.)

12. SDBC-F-10A U.T. (60', Acceptable Examined for valve 1-SD-4B (baseline) profile 0*), replacement. No R.T., P.T. ultrasonic indications.

(See Section XI.)

13. SDBC-F-11A U.T. (60", Acceptable Examined for valve 1-SD-4B (baseline) profile O*), replacement. Indications R.T., P.T. from I.D. and 0.D.

geometry evaluated as root and weld crown reflectors.

(See Section XI.)

14. SDBC-F-14 U.T. (45' & Acceptable No scan tee side of weld.

60*) M.T. Indication from I.D.

geometry evaluated as root reflector.

rS Shutdown Cooline System 12" Carbon Steel Welds (3)

(_/

1. SDAC-F-1B M.T. Acceptable No indications.

2. SDAC-F-37 U.T. (60', Acceptable Ultrasonic indications profile O*), from I.D. geometry M.T. evaluated as root and counterbore reflectors.

Magnetic particle indication noted due to poor veld cleaning.

Indication area was reeleaned and reexamined by magnetic particle examination. No relevant indications. 1

3. SDBC-F-7 U.T. (45*, Acceptable No scan tee side of weld 60*, & due to O.D. configuration, profile O*), Indications from I.D.

M.T. geometry evaluated as root reflectors.

l' '

(.

6.10 97K1X2.079

_ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ - - . _ _ _ _ _ - - _ _ - 2

i.i .s 51 LOL SECTIO'N VII-ASME CLASS 3 EXAMINATION RESULTS O!

q.

h O:

7.0 97K1X2 079

ASME CLASS 3 EXAMINATION RESULTS

,-s.

.i h,

-V CATEGORY D-A EXAMINATION AREA: Integral Attachments of Supports for Systems in Support of Reactor Shutdown Function EXAMINATION METHOD: Visual (V.T.-3) l

. EXAMINATION l ITEM EXAMS RESULTS REMARKS l

l Main Steam Relief Lines to Torus System Integral Attachments (2)

1. (A) MSR-HSS-1 V.T.-3 Acceptable Snubber attachment.

2. (F) MSR-A-4 V.T.-3 Acceptable Examination was performed in conjunction with IWF portion of support.

O)

R.

)

l

)

i 7.1 j 97K1X2 079

_ _ _ __ _a

O SECTION VIII SUBSECTION IWF EXAMINATION RESULTS O

i 1 O 8.0

. 97K1X2 079 i l

L - _ . _ . _ - . _ _ _. . . _ . .

SUMMARY

TABLE IVF

-[

\

COMPONENT SUPPORT EXAMINATIONS wi NUMBER CATEGORY IWF.CL1 OF SUPPORTS Reactor Water Cleanup Return System 2 L Core Spray System 4 l Feedwater System 9 l Isolation Condenser System 1

( Low-Pressure Coolant Injection System 11 l Main Steam System 6 Recirculation System 11 Standby Liquid Control System __1 TOTAL - 45 NUMBER CATEGORY IWF.CL2' OF SUPPORTS Core Spray System -15 Feedwater Coolant Injection System 163 Isolation Condenser System' 7 Low-Pressure Coolant Injection System 33 Low-Pressure Coolant Injection Suction Ring Header System 10 Low-Pressure Coolant Injection Cross-Tie System S Main Steam System 32

() Scram Discharge System Shutdown Cooling System 14

_19 TOTAL - 289 NUMBER CATEGORY IWF.CL2 OF SUPPORTS Emergency Service Water System 9 Fuel Pool Cooling System 15 Isolation Condenser System 1 Main Steam Relief Lines to Torus System 7 Reactor Building Closed Cooling Water System 63 Service Water System 8 Standby Gas Treatment and Atmosphere Control System 17 Turbine Building Secondary Closed Cooling Water System _12 TOTAL - 139 GRAND TOTAL - 473 I

O 8.1 97KlX2.079 l L____. _:____________--____-____________-_____

ASME CLASS 1 IUF EXAMINATION RESULTS

/T b' CATEGORY IVF.CL1 EXAMINATION AREA: Component Supports (45)

EXAMINATION METHOD: Visual (V.T.-3 or V.T.-3 and V.T.-4)

EXAMINATION-ITEM EXAMS RESULTS REMARKS Reactor Water Cleanun Return System (2)

1. (B) CUW-H-1 V.T.-3-4 Acceptable None

2. (B) PENET.X15 V.T.-3 Acceptable None Core Surav System (4)

1. (A) CS-H-28 V.T.-3 Acceptable None

2. (B) CS-H-3 V.T.-3-4 Acceptable None

3. (B) CS-H-4 v.T.-3-4 Acceptable None

4. (B) CS-H-56 V.T.-3 Rej ectable Base plate nuts are O loose and the base plate is separated from the ceiling.

Retest V.T.-3 Acceptable None Feedwater System (9)

1. (A) W-R-005 V.T.-3 Acceptable None

2. (A) WR-H-1 V.T.-3-4 Acceptable None

3. (A) WR-H-5 V.T 4 Acceptable None

4. (A) WR-H-17 V.T.-3 Acceptable None

5. (A) WR-H-51 V.T.-3 Acceptable None

6. (B) W-R-008 V.T.-3 Acceptable None l.

7. (B) WR-H-15 V.T -3 Acceptable None -

8. (B) WR-H-18 V.T.-3 Acceptable None I

9. (B) WR-H-50 V.T.-3 Acceptable None i l

(~~)

l 's.)

8.2 97K1X2.07P

w , y--- - . ,

EXAMINATION'

_ 1 ITDI EXAMS RESULTS REMARKS T

Isolation condenser System (1)~

1. PENET.X11B V.T.-3~ Acceptable None Iow Pressure Coolant Iniection System (11)

1. (A)~CC-H-64 V.T.'- 3 -4 ~ Acceptable None L- - 2. (A) CC-H-65 V .T. 4 Acceptable 'None l

L 3 ." (A) CC-H-66. V.T.-3 Acceptable None l; 4. (A)'CC-H-101 .V.T.-3-4 Acceptable Light rust noted.

5. (B) CC-H-14 V.T. 3-4 Acceptable None

6. (B) CC-H-15 V.T.-3-4 Acceptable -None

7. (B) CC-H-103 .V.T.-3-4 Acceptable None

8. -(B) CC-H-104 V.T.-3-4 Rej ectable -Loose jam nut bottom of pipe attachment.

Retest V.T.-3-4 Acceptable None

: 9.- (B) CC-H-105 V.T.-3-4 Acceptable None

10. (B) CC-R-002 V.T.-3 Acceptable None

~

l11. (B) PENET X45 V.T.-3 Acceptable .None Main Steam System (6)

1. (A) MS-R-581 V.T.-3 Acceptable None

2. (B) MSR-H-7 V.T.-3-4 Acceptable None

,3.- (B) MSR-H-21 V.T.-3 Acceptable None 4 (C) MS-R-579 V.T.-3 Acceptable None

5. (D) MSR-H-14 V.T.-3-4 Acceptable None

6. (E) MD-H-37 v.T.-3 Acceptable None Recirculation System (11)

1. (A) RLP-H-9A V.T.-3-4 Acceptable None

.2. (A) RLP-H-10A V.T.-3-4 Acceptable None j

3. (A) RLP-SB-6A V.T.-3-4 Acceptable None 8.3 97K1X2.079

.-. _ _______________D

7 ' l+

'& 3

-EXAMINATION:

> ITEM' EXAMS RESULTS REMARKS

.'- f 4 ' .,. (A).RLP-SB i6C V.T.-3-4 ! ' Acceptable' ' None p Si -(A) RLP-SB-7C .

V.T.-3-4' Acceptable. Rear bracket load bolt E '

exhibi_ted gap between-g '

nut-and rear bracket ear. Nut has incom-L plete thread engage-

'4 -

ment and is painted in this position.

Support has been retired in place'under I::. ,

the I&E Bulletin 79-14 project and serves no active support func-tion'. Support will be removed from the ISI-program.

.6. (B) RLP H-10B V T.-3-4 A'eceptable - -None

'7. _( B) RLP-H-14B V.T.-3-4 Acceptable 'None

8. '(B)' RLP-Sb-7B - 'V.T.-3-4 Acceptable None 9 .' .: (B) RLP-SB-7D ;V.T. 3-4 Acceptable None 0; ' 10 '.

RLP-H-1A ;V.T.-3-4 ' Acceptable None

11. RLP-H-2A' V.T.-3-4 Acceptable None J.gandby Liould Control System (1)

1. SLC-RH-2 'V.T.-3-4 Acceptable None iOI 8.4 87K1X2.079 U-_-_--_:-____---__-____-._ --- ._ -- -

6SfE CLASS 2 IVF EXAMINATION RESULTS

, 7].

(,/ CATEGORY IVF.CL2 1

EXAMINATION AREA: Component Supports (289)

EXAMINATION METHOD: Visual-(V.T.-3 or V.T.-3 and V.T.-4)

EXAMINATION ITEM EXAMS RESULTS REMARKS Core Sorav System (15)

1. (A) CS-A-504 V.T.-3 Acceptable None l 2. (A) CS-H-16 V.T.-3-4 Acceptable None

3. (A) CS H-20 V.T.-3-4 Acceptable None

4. .(A) CS-H-21 V.T.-3-4 Acceptable None

5. (A) CS-H-22 V.T.-3 Acceptable None

6. (A) CS-H-25 V.T.-3-4 Acceptable None

7. (B) CS-A-503 V.T.-3 Acceptable None

-~s

- 8. (B) CS H-48 V.T.-3-4 Acceptable None

9. (B) CS H-49 V.T.-3-4 Acceptable None

10. (B) CS-H-51 V.T.-3 Acceptable None

11. (B) CS-H 52 V.T.-3 Acceptable Channel steel and rod slightly bent.

12. (B) CS-H-53 V.T.-3-4 Acceptable None

13. (B) CS-H-54 V.T.-3 Acceptable None

14. (B) CS-H-55 V.T.-3-4 Rej ectable Loose nuts on middle pipe clamp bolt and improper spacer loca-tion. Incomplete thread engagement on two anchor bolt nuts.

Retest V.T.-3-4 Acceptable None

15. (B) CS-R-001 V.T.-3 Acceptable None Feedwater Coolant Iniection System (163)

1. C-H-27 V.T.-3-4 Acceptable None 8.5 C7K1X2.070 u__._...__.____._._

-EXAMINATION ITEM EXAMS 'RESULTS REMARKS

2. C-H 28 V.T.-3-4 Acceptable Anchor bolt and nut missing on southwest corner of floor plate.

3. C-H-29 V.T.-3-4 Acceptable None

4. C-H-30 V.T.-3-4 Acceptable None

5. C-H 31 V.T.-3-4 Acceptable All four anchor bolts noted to be one to two threads below nut sur-face on floor base plate.

6. C-H-32 V.T.-3-4 Acceptable None

7. C-H-38 V.T.-3 Acceptable None

8. C-H-50 V.T.-3 Acceptable None

9. C-H-51 V.T.-3-4 Acceptable None

10. C-H-52 V.T.-3 Acceptable None

11. C-H-53 V.T.-3-4 Acceptable None

12. C-H-54 V.T.-3 Acceptable None

13. C-H-55 V.T.-3-4 Acceptable Two nuts missing from base plate of variable spring base support.

Evaluated as not needed for support function.

14. C-H-57 V.T.-3-4 Acceptable None

15. C-H-67 v.T.-3 Acceptable None

16. C-H-75 V.T.-3 Acceptable None

17. C-H-76 V.T.-3 Acceptable None

18. C-H-81 V.T.-3 Acceptable None

19. C-H-82 V.T.-3-4 Acceptable None

20. C-H-84 V.T.-3-4 Acceptable None

21. C-H 85 V.T.-3 Acceptable None

22. C-H-86 V.T.-3-4 Acceptable None 8.6 87K1X2.079

A EXAMINATION ITEM EXAMS RESULTS REMARKS

(~T, 23. C-H-87 V.T.-3 Acceptable None 1 \.J l 24. C-H-88 V.T.-3-4 Acceptable None

25. C-H-89. V.T.-3 Acceptable None

26. C-H-90 V.T.-3 Acceptable None

27. C-H-91 V.T.-3 Acceptable None

28. C-H-92 V.T.-3 Rej ectable Load bolt is missing nut.

Retest V.T.-3 Acceptable (See Section XI)

29. C H-140 V.T.-3 Acceptable None

30. C-H-145 V.T.-3 Acceptable None l

l 31. C-H-147 V.T.-3 Acceptable None l

32. C-H-150 V.T.-3 Acceptable None

33. C-H-153 V.T. 3 Acceptable None

( 34. C-H-163 V.T.-3 Acceptable None v

35. C-H-165 V.T.-3 Acceptable None l 36. C-H-185 V.T.-3-4 Acceptable None 1

37. C-H-186 V.T.-3 Acceptable None l

l

38. C-H-187 V.T.-3 Acceptable None

39. C-H-188 V.T.-3 Acceptable None

40. C-H-189 V.T.-3 Acceptable None

41. C-H-190 V.T.-3 Acceptable None

42. C-H-191 V.T.-3 Acceptable None

43. C-H-193 V.T.-3-4 Acceptable None l 44. C-H-194 V.T.-3-4 Acceptable None

45. C-H-195 V.T. 3-4 Acceptable None

46. C-H-196 V.T.-3-4 Acceptable None

47. C-H-197 V.T.-3 Acceptable None

(')s u

8.7 97KtX2_079

_ =. - - - _-__ . -

,p: *

' U s ,

EXAMINATION ITEM' EXAMS RESULTS REMARKS

48. C-H-198 V.T.-3-4. Acceptable None V.T.-3 Acceptable-

~

?' 49.,,C-H-199 None L '

i 50. C-H-200 V.T.-3-4 Acceptable None

51. C-H-2000- V.T. Acceptable , None

52. C-H-2001 - V.T.-3 Acceptable None

53. C-H-2004- V.T.-3 Rej ectable Loose jam nut on rod.

Retest _- V.T.-3 ' Acceptable None 54 C-H-2005 ' V.T.-3 Acceptable None

55. C-H-201A- V.T.-3-4 Acceptable- None 56 C-H-201B V.T.-3 -Acceptable None

57. C-H-202 V.T.-3-4 Acceptable None

58. C-H-203 V.T.-3 Acceptable None

59. C-H-204. V.T.-3-4 Acceptable None U 60. _C-H-205 V.T.-3-4 Acceptable None

61. C-H-206 V.T.-3-4 Acceptable None

62. C-H-207 v.T.-3 Acceptable None

63. C-H-208 V.T.-3-4 Rej ectable Loose pipe clamp bolt.

Retest V.T.-3-4 Acceptable None

64. C-H-209 V.T.-3 Acceptable None

65. -C-H-210 V.T.-3 Acceptable None

66. .C-H-211 V.T.-3-4 Acceptable None

'67. C-H-214 V.T.-3 Rej ectable Loose bolt.

Retest V.T.-3 Acceptable (See Section XI)

68. C-H-216 V.T.-3-4 Acceptable None

~69. C-H-217 V.T.-3 Acceptable None

70. C-H-218 V.T.-3 Acceptable None

71. C-H-219 V.T.-3-4 Acceptable None 8.8 emxwo 7

.______m___.._..._____. _ _ _ _ _ _ _ . . . _ . _ _ _ ___.___._.._m _

[

EXAMINATION ITEM EXAMS RESULTS REMARKS

,m.

72. C-H-221 V.T.-3-4 Acceptable Examiner noted spring hanger had no freedom of movement. Evalua-tion showed that piping displacement will unload the spring.

73. C-H-222 V.T.-3-4 Acceptable None

74. C-H-223 V.T.-3 Acceptable None 1

! 75. C-H-224 V.T.-3 Acceptable None l

l 76. C-H-225 V.T.-3-4 Acceptable None

77. C-H-227 V.T.-3-4 Acceptable None

78. C H-562 V.T.-3 Acceptable None

79. C-H-563 V.T.-3 Acceptable None

80. C-H-564 V.T.-3 Acceptable None

81. C-R-532 V.T.-3 Acceptable None

82. C-R-533 V.T.-3 Acceptable None

83. C-R-535 V.T.-3 Acceptable None 84 C-R-568 V.T.-3 Acceptable None

85. C-R-602 V.T.-3 Acceptable None l 86. CC-A-540 V.T.-3 Acceptable None j 87. CC-H-95 V.T.-3-4 Acceptable None l

l 88. CC-H-110 V.T. 3-4 Acceptable None 1

89. CC-H-128 V.T.-3 Acceptable None

90. CC-H-130 V.T.-3 Acceptable None

91. CC-H-131 V.T.-3 Acceptable None l' 92. CC-H-132 V.T.-3 Acceptable None 1

93. CC-H-133 V.T.-3 Acceptable None

( 94. CC-H-134 V.T.-3 Acceptable None 8.9 97K1X2D79 im__________._____ _ _ . _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ . . _ . _ _ _ _ _ . . _ _ _ _ _

EXAMINATION ITEM EXAMS RESULTS REHAREE

95. CC-H-135 V.T.-3 Acceptable None

- .}

l 96. CC-H-136 V.T.-3 Acceptable None L 97. CC-H-138 V.T.-3 Acceptable None

98. CC-H-543 V.T.-3 Acceptable None p 99. CC-R-542 V.T.-3 Acceptable None l

100. CD H-77 V.T.-3 Acceptable None 101. CD-H-85 V.T.-3 Acceptable None 102. CD-H-110 V.T.-3 Acceptable None l

103. CS-H-5 V.T.-3-4 Acceptable None j 104. CS-H-8 V.T.-3 Acceptable None 105. CST-H-3 V.T.-3 Acceptable None l

l 106. CST-H-74 V.T.-3 Acceptable None 107. CST-R-13 V.T.-3 Acceptable Examiner noted four nuts missing on two t]

"U" bolts. Design change number 1599 was in process of being completed. All nuts were reinstalled per the design change and a baseline examination was performed.

108. CST-R-14 V.T.-3 Acceptable Examiner noted four nuts missing on two "U" bolts. Design change number 1600 was in process of being completed. All nuts were reinstalled per the design change and a baseline examination was performed.

109. CST-R-15 V.T.-3 Acceptable None 110. CST-R-16 V.T.-3 Acceptable None 111. FDU-H-3 V.T.-3-4 Acceptable None 112. FDW-H-31 V.T.-3 Acceptable None 8.10 97K1X2.079 uw----_-___-__-___ ____ __ -

EXAMINATION ITEM EXAMS RESULTS REMARKS

113. FDW-H-33 v.T.-3-4 Acceptable None 114. FDW-H-34 v.T.-3-4 Acceptable None 115. FDW-H-35 V.T.-3-4 Acceptable None 116. FDW-H-36 V.T.-3-4 Acceptable None ,

117. FDW-H-37 1 V.T.-3-4 Acceptable None 118. FDW-H-38 ,

V.T.-3-4 Acceptable None 119. FDW-H-39 V.T.-3-4 Acceptable None 120. FDW-H-40 V.T.-3-4 Acceptable None 121. FDW-H-42 V.T. 3 Rej ectable Loose anchor bolts and nuts.

Retest V.T.-3 Acceptable None 122. FDU-H-43 V.T.-3-4 Acceptable None 123. FDW-H-44A V.T.-3-4 Acceptable None

['

124. FDW-H-44B V.T.-3-4 Acceptable None 125. FDW-H-44C V.T.-3-4 Acceptable None 126. FDW-H-45A V.T.-3-4 Acceptable None 127. FDW-H-45B V.T.-3-4 Acceptable None 128. FDW-H-45C V.T.-3-4 Acceptable None 1

129.-FDW-H-46A V.T.-3-4 Acceptable None 130. 'FDW-H-46B V.T.-3-4 Acceptable None 131. FDW-H-46C V.T.-3-4 Acceptable None 132. FDU-H 47A V.T.-3-4 Acceptable None 133. FDW-H-47B V.T.-3-4 Acceptable None 134. TDW-H-47C V.T.-3-4 Acceptable None 135. FDW.H-48 V.T.-3-4 Acceptable None 136. FDW-H-50 V.T.-3-4 Acceptable None 0 137. FDW-H-51 V.T.-3-4 Acceptable None 8.11 mmm

l, EXAMINATION-b ITEM- EXAMS RESULTS REMARKS

-?

.138. FDW-H-53 V.T.-3-4 Acceptable None 139. FDW-H-54' V.T.-3-4 Acceptable' None 140. FDW-H-55 V.T.-3-4 Acceptable None 141. FDW-H-56 v.T.-3-4 Acceptable None

'142. FDW-H-57 V.T.-3-4 Acceptable None

, 143. FDW-H-58. V.T.-3-4 Rejectable. Loose clamp bolt.

L h

Re te s t. ' V.T.-3-4 Acceptable None 144. FDW-H-59 V.T.-3-4 Acceptable None 145. FDW-H-60 V.T.-3. Acceptable None L -146. FDW-R-500 V.T.-3. Rejectable Leose clamp bolt.

Retest V.T.-3 Acceptable None 147. W-A-004 V.T.-3 Acceptable None

.148. W-A-007 V.T. 3 Acceptab'.e None

.149. FWR-N-21 V.T.-3. Rej ectable Three loose anchor belts and nuts.

Retest- V.T.-3 Acceptable None 150. FWR-H-22A V.T.-3 Acceptable None 151. WR-H-22B V.T.-3 Acceptable Nono 152. WR-H-22C V.T.-3 Acceptable Nae 153. FWR-H-23A V.T.-3' Acceptable None 154. nT-H-23B V.T.-3 Acceptable None

-155. WR-H-23C V.T.-3 Acceptable None 3 56. WR-H-25 V.T.-3 Rej ectable Loose pipe clamp.

Retest V.T.-3 Acceptable None 157. WR-H-26 V.T.-3 Acceptable None 158. FWP.-H-27 V.T.-3 Rej ectable Bent strut tube.

Retest V.T.-3 Acceptable (See Section XI) 8.12 97K1X2 079

.a... - - - - . . _ - _ - _ _ . _ . _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ -__ _-_ - _-_.______ - -..-- _ -__ _ -__ - _ -

. M , ah

EXAMINATION '

~ ITEM JQBlD. RESULTS REMARKS w

j 1159. WR-H-28 ' 'V.T.-3. Acceptable .None-

+ %{ ay ' '

160.'FWR-H 'V.T.-3 ; Rej ectable Missing clamp' bolt.

Retest- V.T.-3 ,

Acceptable -(See Section XI)

-161. Pump.(M2-28). .V.T.-3 Acceptable None-O.

162.-Pump (M2-7A) V.T.-3 Acceptable. None 163. Tank'(M2-BA)

V.T.-3 Acceptable None s

' Isolation Condenser System (7)

'1. .-IC-H-3 .V.T.-3-4 Acceptable .None

~2. IC-H-8 V.T.-3-4 Acceptable None

~

3. IC-H-9 '.V.T.-3-4 Acceptable None

. 4. ; IC-H-11 V.T.-3 Acceptable -None g '5. IC-R- 907 .'- 1

V.T.-3 Acceptable- None d . .. , .. . 6, IC-R'-909. V.T.-L Acceptable- None M') ... 7. IC-R-912. V.T.-3 Acceptable None-y' '

Low-Pressure CooJant Iniection System (33)

.1 1(A) CC-B-52 V.T.-3 Acceptable None

2. (A) . CC H V.T. -4' Acceptable None 3.. (A) CC-H-57 V.T.-3-4 Acceptable Spring can noted to be out of alignment and appears to be binding does not impair support function.

4. -(A) CC-H-58B

. .V.T. Rej ectable . Two loose anchor bolts and nuts.

Retest V.T.-3 Acceptable None

5. "(A) CC-H-59 V.T.-3-4 Acceptable None e

'6. (A) CC-H-62 VT-3 Acceptable None

7. -(A) CC-H-76 ~V.T.-3 Acceptable None 1

C. (A) CC-H-79 V.T.-3-4 Acceptable None 8.13

, 97K1k2.079

(,, .

f E ~' . a .

r; EXAMINATION L ITEM EXAMS RESULTS BJMARKS

9. (A) CC-H-98 V.T.-3-4 Acceptable None

['

10. .(A) CCA-C-C-3 V.T.-3 Acceptable None

11. (B) CC-A-517 V.T.-3 Acceptable Ncne

12. (B) CC-A-518 V.T.-3 Acceptable None

13. (B)-CC-H-1 V.T.-3-4 Acceptable None

14. (B) CC-H-2 V.T. 3 Acceptable None

15. (B) CC-H-10 V.T.-3-4 Acceptable None

16. (B) CC-H-11 V.T.-3 Acceptable None

17. (B) CC-H-17 V.T.-3-4 Acceptable None

18. (B) CC-H-18 V.T.-3-4 Acceptable None

19. (B) CC-H-22 V.T.-3 Acceptable Broken grout at base plate.

20. (B) CC-H-23 V.T.-3-4 Acceptab le None

[3 21, (B) CC-H-27 V.T -3 Accept 4.ble None v'

22. (B) CC-H-28 V.T.-3-4 Acceptable Nona

23. (B) CC-E-29 V.T.-3 Acceptable None

24. (B) CC-H-30 V.T.-3 Acceptable None

25. (B) CC-H-32 V.T.-3-4 Acceptable None

26. (B) CC-H-42 V.T.-3 Acceptable None

27. (B) CC-H-43 V.T.-3-4 Acceptable None

28. (B) CC-H-44 V.T.-3-4 Acceptable None

29. (B) CC-H-lli V.T.-3-4 Acceptable None

30. (B) CC-R-003 7.T.-3 Aceeptable None

31. (B) CC-R-004 V.T.-3 Acceptable None 32 (B) CC-R-006 V.T.-3 Acceptable None

33. (B) CC-R-537 v.T.-3 Acceptable None O

V 8.14 97K1X2.079

3 i

i EXAMINATION ITEM- EXAMS RESULTS REMARKS

' ,(] ]pw Pressure Coolant Iniection Suction Rine Header System (10)

J 1.- CC-H-520B V.T.-3 Acceptable None

{

2. CC-H-520C V.T.-3 Acceptable None 1

3. CC-H-520D V.T.-3 Acceptable None

4. CC-H-520E V.T.-3 Acceptable None

5. CC-H-520F V.T.-3 Acceptable None

6. CC-H-520J V.T.-3 Acceptable None

7. CC-H-520K V.T.-3 Acceptable None

8. CC-H-520L V.T.-3 Acceptable None

9. CC-H-520M V.T.-3 Acceptable None

10. CC-H-520N V.T -3 Acceptable None L2d Plj JBIA..G2pJ ant Iniection Cross-Tie System (3)

1. CC-H-118 V.T,-3 Acceptable Nane 98

2. CC-H-120 V.T.-3 Acceptable None

3. CC-H-122 V,T. 3 Acceptable None

4. CC-H-124 V.T.-3 Acceptable Nane

).

S. CC-H-123 V.T.-3 Acceptable None Main Steam System (32)

1. (A) MS-H-3 V.T.-3-4 Acceptable None

2. (A) MS-H-5 V.T.-3 Rej ectable Missing bolt top of pipe clamp.

Retest V.T.-3 Acceptable (See Section X1)

3. (A) MS-H-6 V.T.-3 Rej ectable Locking nut noted not drawn tight. Bent rod evaluated as accept-able.

Retest V.T.-3 Acceptable None

4. (A) MS-H-7 V.T.-3 Rejectable Gap noted between 1/2" plate and building

's structure "I" beam.

8.15 97K1X2.079

('

EXAMINATION ITEM EXAMS RESULTS REMARKS

(}

\_/ Retest V.T.-3 Acceptable (See Section XI)

5. (A) MS-H-8 V.T.-3-4 Acceptable None

6. (A) MSH-A-1D V.T.-3 Acceptable None

7. (A) MSR-H-566 V.T.-3 Acceptable None

8. (A) SB-H-8 V.T.-3 Acceptable None

9. (B) MS-H-12 V.T.-3-4 Acceptable None

-10. (B) MS-H-14 V.T.-3 Acceptable None

11. (B) MS-H-15 V.T.-3 Acceptable None

12. (B) MS-H-16 V.T.-3 Rej ectable Gap noted between 1/2" plate and building.

structure "I" beam.

Retest V.T.-3 Acceptable (See Section XI)

23. (B) ES-H-17 V.T.-3-4 Acceptable None

(p ts 14 (B) MSH-A-lc V.T.-3 Acc.eptable None

15. (B) SB-H-2 V 'i.-3-4 Acceptable None

16. (B) SB-H-7 V.T.-3-4 Acceptable None

17. (C) MS-H-22 V.T.-3 Acceptable None

18. (C) MS-H-23 v.T.-3 Acceptable None

19. (C) MS-H-24 V.T.-3 Rej ectable Locking nut noted not drawn tight and rod is bent.

Retest V.T.-3 Acceptable None

20. (C) MS-H-25 V.T.-3 Acceptable None

21. (C) MS-H-26 V.T.-3-4 Acceptable Nonload bearing bolt spins freely in pipe clamp. Bent rod noted and both conditions do not impair the support function.

22. (C) MSH-A-1B V.T.-3 Acceptable None

23. (C) SB-H-6 V.T.-3 Acceptable None 8.16 97K1X2.079

EXAMINATION'-

-ITEM EXAMS RESULTS REMARKS

~t 3

24. (D)lMS-H-29 V.T.-3-4 -Acceptable None

'25.

(D).MS-H-31 V.T.-3 Acceptable. None

26. -(D) MS-N-32 V.T.-3 Rej ectable . Loose jam nut top of

. rod.

. Retest V.T.-3 Acceptable None

'27. (D) MS-H-33 V.T.-3-4 Acceptable None

,28. (D) MS-H-34 V.T.-3 Acceptable None

29. -(D) MS-H-35 V.T.-3 Acceptable None

30. (D);MSH-A-1A .V.T.-3 Acceptable- -None

31. (D).SB-H-4 V.T.-3-4 Acceptable None

32. (D) SB-H-5 V.T.-3 Acceptable None Scram Discharge System (14) i1. .(N) SDH-1B V.T.-3 Acceptable Nono

'2 . (S) CRD-R 003 V.I.-3 Acceptable None

3. I(S) CRD-R-LOO V.T.-3 Acceptable None

4. (S)'CRD-F 2501' V.T.-3 Acceptable None

.V.T.-3

5. (S)'SDH-3B Acceptable None

6. (S) SDB-4 V.T.-3 Acceptable None

7. (S) SDH-31 Y.T.-3 Acceptable None

.8. .(S) SDH 32 ~V.T.-3 Acceptable None

9. (S) SDH-35 V.T.-3 Acceptable None 10.- (S) SDH-36 V.T.-3 Acceptable None

11. (S) SDH-38 V.T.-3 Acceptable None

12. (S) SDH-39 V.T.-3 Acceptable None

13. (S) SDH-41 V.T.-3 Acceptable None

14. (S) CRD-H-504 V.T.-3 Acceptable None 8.17 97K1X2.079 '

[: _ _ _ . _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____

4

. EXAMINATION !

ITEM EXAMS RESULTS REMARKS !

Shutdown Cooline System (10) )

- [^') -

x.. / -

.1. (A') SHC-H ?1. V.T.-3-4 Acceptable None

2. (A) SHC-R-13 V.T.-3 Acceptable None.

3. (A) SHC-R-15 V.T.-3 Acceptable None

4. (B) SHC-H-23 V.T.-3-4 Acceptable None

5. (B) SHC-H-28 V.T.-3 Acceptable None

6. (B) SHC-R V.T.-3 Acceptable None

7. (R) CC-H-16 V.T.-3 Acceptable None

8. (R) SHC-H-40 .V.T.-3-4 Acceptable Load bolt and nut top of spring can is loose. Evaluation shows support only loads bolt in shear direction.

9. (R) SHC-E-41 V.T.-3-4 Rej ectable Loose locking nut, loose nut on "U" Folt, f') - misalignment of hanger V assembly and spring cans are not 1cve1.

Retest V.T.-3-4 Acceptable None

10. (R) SHC-H-42 V.T.-3-4 Acceptable Spring cans and "U" bolt a;sembly are uts~

aligned. Does not irtpai. support function,

?\

()

8.18 07K1X2 070

pg ,r

{

-9 m:

'ASME-CLASS 3 IWF EXAMINATION RESULTS CATEGORY IWF.CL3-il: EXAMINATION AREA: Component Supports (139)

EXAMINATION METHOD: Visual (V.T.-3 or V T.-3 and V.T.-4)

EXAMINATION "5, ' ITEM EXAMS 'RESULTS REMARKS l? Emergency Service Water-System (9)

, .l. CCS-H-1 V.T.-3-4 A'eceptable None l

2. CCS-H-3' . . V . T . 4 '. Acceptable None L 3. .CCS-H-8 V.T.-3 4 Acceptable None 4 CCS-H-9 -V.T.-3-4' Acceptable None

5. CCS-H-22 V.T.-3 Acceptable None

6. CCS-H-23 V..T.-3 Acceptable None

[ .

7. 'CCS H 24 V.T.-3 Acceptable None

. S' . CCS-N-25 V.T -3 Acceptsble None 7 ^

9. CCS-R-24 V.T. . Acceptable None Fuel Pool- Cooline System C;5;

1. FIC-li+12 v.T.-3 Acceptable. None ]

2. FPC-H-19 V.T.-3 Acceptable None

3. FPC-H-22 V.T.-3 Acceptable Examiner noted support carries no dead weight load of the piping.

.4 FPC-H-23 V.T.-3 Acceptable None

5. FPC-H-24 V.T.-3 . Acceptable None

6. FPC-H-26 V.T.-3-4 Acceptable None 7 .- FPC-H-29 V.T.-3-4 Acceptable None

8. FPC-H-30 V.T.-3-4 Acceptable None

9. FPC-H-35 V.T.-3-4 Acceptable None

~

10. FPC-H-37 V.T.-3 Acceptable None 8.19 97K1X2.079

L

- EXAMINATION ITEM EXAMS RESULTS REMARKS ap L[ 11. FPC-H-38 V.T.-3 Rej ectable . Pipe clevis is not-W supporting the pipe and' appears to be out-

'of adjustment.

Retest V.T.-3 Acceptable- None

.12. FPC-H-39' V.T.-3-4 Acceptable Rods on both spring cans are bent. Con-

~

dition does not impair

. support function.

.13. FPC-H-42 V'.T.-3 Acceptable None

14. ~FPC-H-116 V.T.-3 Acceptable None

=15. M4-18A -V.T.-3 Acceptable None.

Isolation Condenser System (1)

1. IC-H-14 V.T.-3-4 Acceptable None Main Steam System Relief Lines to Torus System (7)

,1. --(D) MSR-H-574 V.T.-3-4 Acceptable None

.g i T- .i i

2. (D) MSR-H-982 V.T.-3-4 Acceptable None .j

3. (D) MSR-ER-10 V.T.-3 Acceptable None 4 (E) MSR-RR-11 V.T.-3 Acceptable None

5. (F) MSR-A-4 V.T.-3 Acceptable None

6. (F) MSR-H-550 V.T.-3 4 Acceptable None

7. (F) MSR-RR-13 V.T.-3 Acceptable None Reactor Buildine Closed Cooline Water System (63)

1. M4-12A-(S)2 V.T.-3 Acceptable None

2. RCW-EH-14 V.T.-3 Acceptable None

3. RCW-H-22 V.T.-3 Acceptable None

4. RCW-H-23A V.T.-3 Acceptable None

5. RCW-H-23B V.T.-3 Acceptable None

6. RCW-H-26A V.T.-3 Acceptable None

-0 7. RCW-H-26B V.T.-3 Acceptable None 8.20 97K1X2.079

.p

'v9

.y:

EXAMINATION' '

<. . .. ITEM EXAMS -RESULTS REMARKS 8 .' RCW-H-28B Vl.T -3 . Acceptable None V.T.-3

9. RCW-H-29 Acceptable- None.

10. RCW-H-36A- -V T.-3. Acceptable- None'

.11. RCW H-36B V.T.-3' Rej ectable Nuts not drawn down-tight on cross member.

~

Bent rod evaluated as acceptable.

Retest . . V . T.. - 3 .. Acceptable' None-

12. RCW-H-38A V.T.-3 Acceptable. .None 13; RCW-H-39 LV.T'-3 Acceptable' None

14. RCW-H-42 V.T.-3 Acceptable ~None 151 'RCW-H-45A .V.T.-3 Acceptable None

16. .RCW-H-51A V.T.-3 Acceptable None

17. ~RCW-H-51B V.T.-3 . Acceptable None

< /7 -- '18. RCW-H-5$A V.T.-3 Rej ectable Loose nut on hanger.

V

. Retest V.T..-3 ' Acceptable None >

'19. RN-li SSB V.T.-3 Acceptable None V.T.-3. Acceptable

.20. .RCW-H46 None

21. R0W-H 57 V.T -3 Acceptable None s- s 22; .RCW-H-39B- V.T.-3 Accept.abh Nene

23. RCW-H-63A V.T.-3 Acceptable None

-24. 'RCW-H-63B V.T.-3 Acceptable None

25. RCW-H-64A- V.T.-3 Acceptable None

26. RCW-H-64B V.T.-3 Acceptable- None 27.' lRCW-H-65A- V.T.-3 Acceptable None

28. RCW-H-65C V.T.-3 Acceptable None l 29. RCW-H-65D V.T.-3 Acceptable None 30'. RCW H-69 V.T.-3 Acceptable None 8.21

. 97K1X2.079

_ :-- .- ..L. - - _ _ _ _ - . _ _ _ __ _ - _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ - _ _ - - . _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ . _ . , _ _ _ - _ _ _ - - - _ - _ _ _ - - -

EXAMINATION ITEM EXAMS RESULTS REHARKS g 31. RCW-H-72 V.T.-3-4 Acceptable None

32. RCW-H-74 V.T.-3 Acceptable None

33. RCW-H-75 V.T.-3 Acceptable None

34. RCW-H-76 V.T.-3 Acceptable None

35. RCW-H-77 V.T.-3 Acceptable None

36. RCW-H-80A V.T.-3 Acceptable None

37. RCW-H-80B V.T.-3 Acceptable None

38. RCW-H-81B V.T.-3 Acceptable None

39. RCW-H-84A V.T.-3 Acceptable None

40. RCW-H-84B V.T.-3 Acceptable None

41. RCW-H-86 V.T.-3 Acceptable None

42. RCW-H-99 V.T.-3 Acceptable None

43. RCW-H-105 V.T.-3 Acceptable None O 44. RCW-H-106 V.T.-3 Acceptable None

45. RCW-H-109A V.T.-3 Acceptable None

46. RCW-H-109B V.T.-3 Acceptable None

47. RCV-H-110 V . 'i . - 3 Acceptable None 4 8. . RCW-H-111 V.7,-3 Acceptable None

49. RCW-H-ll3 V.T.-3 Acceptable None

50. RCW-H-114 V.T.-3 Acceptable None

51. RCW-H-ll7 V.T.-3 Acceptable None

52. RCW-H-ll8 V.T.-3 Acceptable None

53. RCW-H-516 V.T.-3 Acceptable None 54 RCW-H-517 V.T.-3 Acceptable None

55. RCW-H-518 V.T.-3 Acceptable None

56. RCW-H-519 V.T.-3 Acceptable None O 57. RCW-H-520 V.T.-3 Acceptable None 8.22 97K1X2 079

y ,-g

l. 1

- a. ,,

j.

lM 4, 1 EXAMINATION '

ll -

ITEM EXAMS p RESULIE- REMARKS 4 lL:":"' :::: ^::::::: :::

60. 'RCW-H-540 V.T.-3 Acceptable -None I-

61. lRCW-H-542 V.T.-3 Acceptable- NoneL

62. RCW-H-543 V.T.-3 ' Acceptable, :None 63 .- RCW-R-004'- V.T.-3 Acceptable- None Service Water System (8)

L 1. SW-H-3< V.T.-3 Acceptable' None.

- 2. SW-H-9. V.T.'-3 Acceptable -None

. 3. SW-H-12 v.T -3 Acceptable None j ,.

, , 4. SW-H-30 V.T.-3 Acceptable Minor corrosion noted.

5. SW-H-FN-8 V;T.-3 Acceptable None

6. SW-H-FN-25 V.T.-3 Acceptable Noted misalignment

. {j '- does not impair a support function.

.7. SW-R-015' 'V.T.-3 Accept 3ble None

8. SW-R-583 'V.T.-3 Acceptable None

f,f,JfgLy Cat Treatmen1 and Atgpfohen Control System (17): 1. AC-A V.Y.-3 Acceptable None

    ,                          2.         - AC - A- 2I.          V.T.-3            Acceptable    None

3. AC-A-2B V.T.-3 Acceptable None

4. AC-A-5 V.T.-3 Acceptable None

                              , 5.         AC-H-2A_              V.T.-3            Acceptable    None

6. AC-H-8 V.T.-3 Acceptable None

7. AC-H-9 V.T.-3 Acceptable None

8. AC-H-14' V.T.-3 Acceptable None

9. AC-R-6 V.T.-3 Acceptable None

                -*              10.        AC-R-9                V.T.-3            Acceptable     None 8.23
                      ' 37K1X2.079
                =                                          -.            - --      _-_-_--____                                               _a

EXAMINATION ITEM EXAMS RESULTS REMARKS [)

\.)

11. AC-R-10 V.T.-3 Acceptable None

12. HVAC-H-2 V.T.-3-4 Acceptable None

13. HVAC-H-3 V.T.-3-4 Acceptable None

                        .14.      HVAC-H-4            V.T.-3-4          Acceptable       None

15. HVAC-H-5 V.T.-3-4 Acceptable None

16. HVAC-R-2 V.T.-3 Acceptable None

17. SGT-R-003 V.T.-3 Acceptable None Turbine Buildint Secondary Closed Cooline Water System (19)

1. CW-H-87 V.T.-3 Acceptable None

2. CW-H-89A V.T.-3 Acceptable None

3. 'CW-H-90 V.T.-3 Acceptable None

4. CW-H-137A V.T.-3 Acceptable None

5. CW-H-137B V.T.-3 Acceptable None

6. CW-H-139 V.T.-3 Acceptable None

7. CW-H-140 V.T.-3 Acceptable None

8. CW-H-150 V.T.-3 Acceptable None

9. CV-H-153 V.T;-3 Acceptable None

10. CV-H-154 V.T.-3 Acceptable None

11. CW-H-156A V.T.-3 Acceptable None

12. CW-H-157B V.T.-3 Acceptable None

13. CW-H-161 V.T.-3 Acceptable None

14. CW-H-162 V.T.-3 Acceptable None

15. CW-H-164 V.T.-3 Acceptable None

16. CW-R-11A V.T.-3 Acceptable None

17. CW-R-12 V.T.-3 Acceptable None

18. CW-R-13A V.T.-3 Acceptable None i

l h 19. SC-H-537 V.T.-3 Acceptable None 8.24 97KtX2.079

                                                               , n,--         - , ---- --- - - - - , - . - - - , . , , . - - - - - - - - , - - - - - - - - -                                 .

F b

  -kr. .
         ~

o ' a SECTION IX

                                                                                                                                        - PRESSURE TEST

SUMMARY

I OL d

          .O                                                                                                                                                                                                                      ,

em,xa ore 9D _ _ _ _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - ^ - ._ j

r ASME CLASS 1 PRESSURE TEST RESULTS 7~. . CATEGORY B-E EXAMINATION AREA: All Pressure Retaining Partial Penetration Welds in Vessels, Control Rod Drive Nozzles, and Instrumentation Nozzles EXAMINATION METHOD: Visual (V,T.-2 at RPV Nominal Operating Pressure) RESULTS: Acceptable REMARKS: The reactor pressure vessel and Class 1 piping and components were system leakage tested at nominal operating pressure and temperature in accordance with IWA-5000. O O O ennx2 o7e 9.1

A..SME CLASS 1 PRESSURE TEST RESULTS ! 7_ l t d CATEGORY B-0 and B-P EXAMINATION AREA: Pressure Retaining Welds in Control Rod Drive Housings, Reactor Pressure Vessel, and Class 1 Piping and Component Pressure Retaining Boundary EXAMINATION METHOD: Visual (V.T.-2 at RPV Nominal Operating Fressure and System Hydrostatic Pressure Tests) RESULTS: Acceptable REMARKS: The Reactor Water Cleanup Supply System in the area of the CUAJ-5 weld overlay repair was hydrostatically tested in accordance with IWA-5000. The reactor pressure vessel and remaining Class 1 piping and components were system leakage tested at nominal operating pressure and temperature in accordance with IWA-5000. vs\ i s7xix2 o7e 9.2

ASME CLASS 2 PRESSURE TEST RESULTS

.m.

CATEGORY C-H EXAMINATION AREA: All Pressure Retaining Components of the ASME Class 2 Systems EXAMINATION METHOD: Visual (V.T.-2 at System Hydrostatic Pressure Test) RESULTS: Acceptable REMARKS: The ASME Class 2 piping and components of the following systems were hydrostatically tested in accordance with IWA-5000: Shutdown Cooling System Isolation Condenser System Core Spray A & B System Low Pressure Coolant Injection A & B System - (Portions for valve work only) 0 07K1X2.079 9.3

l l. ASME CLASS 3 PRESSURE TEST RESULTS _,\ Y CATEGORY D-A EXAMINATION AREA: All Pressure Retaining Components for Main Steam Relief Valve Discharge Piping Lines to the Torus EXAMINATION METHOD: V.T.-2 (Operability Verification During System Functional Test) RESULTS: Acceptable REMARKS: System functional test performed in accordance with IWA-5000. c

         .t l

v exix m e 9.4 u________________-__________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . - - - - - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ ASME CLASS ? PRESSURE TEST RESULTS

        \' ,h CATEGORY D-B EXAMINATION AREA:      All Pressure Retaining Components for Systems in Support of Emergency Core Cooling, Containment. Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal EXAMINATION METHOD:    V.T.-2 (at System Hydrostatic Pressure Test)
                          -RESULTS:                Acceptable REHARKS:               The ASME Class 3 piping and components of the following systems were hydrostatically tested in accordance with IWA-5000:

Reactor Building Closed Cooling Water System Service Water System (t 97K1X2.079 9.5

c e

~N

,.L, 6 SECTION X

                                               ' SYSTEM AND COMPONENT IS0 METRICS O

1

ll l O 10.0 mmx2 on . z _ o

l' ElMMARY TABLE

i. ) DRAWINGS PAGES o Reactor Pressure Vessel Nozzles, Shell Welds, Head Welds, Studs, and Internals 2-6 o . Control Rod Drive Nozzle to Cap Weld 7 o Core Spray System 8-10 o Feedwater System 11 o Isolation Condenser System 12-14 o Low Pressure Coolant Injection System 15-17 o Main Steam System 18-19 o Reactor Water Cleanup System - 20 o Recirculation System 21-25 o Shutdown Cooling System 26-27 o Standby Liquid Cooling System 28 m

k, O_ 10.1 smxwo

m________________________.____ ___

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                                                                                               . SECTION XI OWNER'S DATA REPORT FOR REPAISS OR REPLACEMENTS -

(FORM NIS-2)

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I e min ore _ _ _ _ .1___ _ _ _ _ _ _ __ _ _ _ - - - _ _ _ . _ _ _ _ _ _

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SUMMARY

TABLE (FORM NIS-2)

.)

DESCRIPTION PAGES

1. ASME Class 1 (Replacement) " Reactor Pressure Vessel 4-5 Closure' Studs" Date Inspected 8/25/89

2. ASME Class 1-(Repair) " Reactor Pressure Vessel Head 6-7 Spray and Head Instrument Nozzle to Vessel Welds MSAD-1 and HIBD 1" Date Inspected 8/25/89

3. ASME Class 1 (Repair) " Reactor Water Cleanup Weld 8-9 CUAJ-5" Date Inspected 6/27/89

4. ASME Class 1 (Repair) " Low Pressure Coolant Injection 10-11 Weld CCBJ-13" Date Inspected 6/26/89

5. ASME Class 1 (Replacement) " Main Steam Safety Relief 12-13 Valve 1-MS-3B" Date Inspected.9/1/89

6. ASME Class 1 (Replacement) " Main Steam Safety Relief 14-15 Valve 1-MS-3C Seat Leakage" Date Inspected 8/21/89

7. ASME Class 1 (Replacement) " Main Steam Safety Relief 16-17 Valve 1-MS-3C Assembly Changeout" Date Inspected 9/1/89

8. ASME Class 1 (Repair) " Main Steem Safety Relief Valve 18-19 1-MS-3D" Date Inspected 3/9/89

9. ASME Class 1 (Repair) " Main Steam Safety Relief Valve 20-21 1-MS-3E Steam Cutting" Date Inspected 3/9/89

10. ASME Class 1 (Replacement)'" Main Steam Safety Relief 22-23 Valve 1-MS-3E Assembly Changeout" Date Inspected 9/1/89

11. ASME Class 1 (Replacement) " Main Steam Safety Relief 24-25 Valve 1-MS-3F Assembly Changeout" Date Inspected 9/1/89

12. ASME Class 1 (Replacement) " Reactor Recirculation 26-27 Valve 1-RR-1B Bolting" Date Inspected 9/14/89

13. ASME Class 2 (Replacement) " Reactor Shutdown Cooling 28-29 Hanger Lugs" Date Inspected 9/11/89

14. ASME Class 2 (Replacement) " Reactor Shutdown Cooling 30-31 Valves 1-SD-4A and 1-SD-4B" Dated Inspected 8/21/89

15. ASME Class 2 (Replacement) " Reactor Shutdown Cooling 32-33

     -O                                        Fabrication of Pipe Elbows to Valves 1-SD-4A and 1-SD-4B" Date Inspected 8/25/89 11.1 emixws -

I 1 34-35 ([) 16. ASME Class 2 (Replacement) " Reactor Shutdown Cooling Spool Piece for Valve 1-SD-4A Elbow Assembly" Date Inspected 8/21/89 4

17. ASME Class 2 (Repair) " Reactor Shutdown Cooling Weld 36-37 SDBC-F-4A" Date Inspected 8/25/89

18. ASME Class 2 (Replacement) " Reactor Shutdown Cooling 38-39 Thermowell on Shutdown Cooling Line 10-SHC-SA" Date Inspected 8/25/89

19. ASME Class 2 (Repair) " Reactor Shutdown Cooling Weld 40-41 SDBC-B-1" Date Inspected 6/26/89

20. ASME Class 2/3 (Replacement) " Reactor Shutdown Cooling 42-43 to Fuel Pool Cooling Spectacle Flange Ref: Valve 1-SD-35" Date Inspected 9/12/87 j

21. ASME Class 2/3 (Replacement) " Reactor Shutdown Cooling 44-45 to Fuel Pool Cooling Spectacle Flange Ref: Valve 1-SD-34" Date Inspected 4/18/89

22. ASME Class 2 (Replacement) " Low Pressure Coolant 46-47 Injection Valve 1-LP-15B Rotation" Date Inspected 8/25/89

23. ASME Class 2 (Replacement) " Low Pressure Coolant 48-49 Injection Support CC-H-52" Date Inspected 9/11/89

24. ASME Class 2 (Replacement) " Low Pressure Coolant 50-51 Injection A and B Flow Switches" Date Inspected 6/14/89

25. ASME Class 2 (Replacement) " Low Pressure Coolant 52-53 Injection B and D Flow Switches" Date Inspected 6/14/89

26. ASME Class 2 (Replacement) " Main Steam Hanger (A) 54-55 MS-H-5 Bolt" Date Inspected 6/14/89

27. ASME Class 2 (Replacement) " Main Steam Hangers (B) 56-57 MS-H-16 and (A) MS-H-7" Date Inspected 6/14/89

28. ASME Class 2 (Replacement) " Main Steam Valve 1-GS-1" 58-59 Date Inspected 5/9/89

29. ASME Class 2 (Replacement) " Isolation Condenser Pipe 60-61 Supports Various" Date Inspected 9/11/89

30. ASME Class 2 (Replacement) " Core Spray A Restricting 62-63 Orifice Flange R0 10-2A" Date Inspected 9/11/89 11.2 07K1X2,079

y -. _ 1 H q 31. .ASME Class.2 (Replacement) " Core Spray B Re'stricting 64-65 Q Orifice Flange RO 10-2B" Date Inspected 9/11/89

32. ASME Class 2 (Replacement)." Core Spray'A Bolting on '66-67

(< -Flange" Date Inspected 9/13/89

33. 'ASME Class 2.(Replacement) " Reactor Building Closed. 68 Cooling Water Valve Installations" Date Inspected 8/25/89

                       .- 34 . ' ASME Class 2. (Replacement) '"WCI Feedwater Valve              70                                  .1- W-14A" Date Inspected 9/8/89

35. ' ASME Class 2 '(Replacement) "WCI 'Feedwater ' Hanger - .

72-73 WR-H-27 Strut" Date . Inspected 6/14/89

36. ASME Class 2 (Replacement) "WCI Feedwater Support 74 75

                                . WR-H-29 Bolt" Date . Inspected 6/14/89

37. ASME Class 2 (Replacement) "WCI Condensate Hanger 76-77 C-H-92 Bolt" Date Inspected 6/29/89

38. ASME Class 2 (Replacement) "WCI Condensate Hanger 78-79 C-H-214 Bolt" Date Inspected 6/14/89

39. ASME Class 2 (Replacement) "WCI Condensate "A" 80-81

  . -c ' '                      ' Booster Pump Casing" Date Inspected 2/5/88
  .o-11.3
                $7K1X2.079

l f ) AI FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT ~

                                 -As-Required by the Provisions of the ASME Code Section XI

1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut. 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWO NO: M1-89-02319.

4. SYSTEM: Reactor Pressure Vessel Closure Studs, ASME Class 1

5. (a) APPLICABLE CONSTRUCTION CODE: ASME Code Section III, 1965 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Reactor Pressure Vessel Closure studs (56 total).

7. DESCRIPTION OF WORK PERFORMED: Replaced all 56 Reactor

        -\/)                         Pressure Vessel Closure Studs.                                                                                         .

8. TESTS CONDUCTED: Performed surface examination (Wet magnetic particle test) and volumetric examination (Ultrasonic test) on all 56 studs and 4 spare studs. Performed operational leak test of reactor vessel head flange.

9. REMARKS: Stud change out per PDCR 1-35-87 to adapt to quick disconnect Black stud tensioner.

L i l. l L

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Page 1 of 2 1 11.4 l' L -- _ _ _ - _ -- - - - _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

                      ~ - - _ . - _ - - _ _                             ._ __

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                                                                                                                                           -AWO NO: Mi-89-02319 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify.that the statements made'in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI.

YAN l S l G et- b k rr- $M 17 Da(e (/ df Signed Title CERTIFICATE OF INSPECTION

    ,6                              I, the undersigned, holding a valid commission issued by the

(/ National Board of Boiler and Pressure Vessel Inspectors and the State.of Connecticut, employed by the Hartford Steam Boiler

                             . Inspection and Insurance Company hav'e inspected the de/nur4                                            described in this report on                                       M> rM      'and state to the           best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of
                                .the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.

Furthermore, neither the Inspector nor his employer shall be-liable in any manner for personal injury or property damage or loss of any kind arising from er connected with this inspection. DateMarld ' NN(In~spector) b Commissions S M /9 Page 2 of 2 0 11.5 L_._ _._ -.____ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _____ _ _ _ _

h. FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI

1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O.-Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit i Engineering AWO NO: M1-89-04740

4. SYSTEM: Reactor Pressure Vessel Head, ASME Class 1

5. (a) APPLICABLE CONSTRUCTION CODE: ASME III, 1965 Class A (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition.

Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Reactor Pressure Vessel Head Spray and Head Instrument Nozzle to Vessel Welds HSAD-1 and HIBD-1.

O National Board No: CE 65202.

7. DESCRIPTION OF WORK PERFORMED: Inservice Inspection ultrasonic examination of Category B-D welds HSAD-1 and HIBD-1 identified indications on the ID clad surface. The areas of interest on the ID surface were liquid penetrant tested to confirm the ultrasonic test results. The surface indications on the cladding were reduced in size by grinding and measured for length. The indications were then evaluated to the acceptance criteria of Table IWB-3510-1 of Section XI of the ASME Code 1980 Edition, Winter 1980 Addenda. Due to their size and orientation, the indications are typical base metal to clad interface indications and are acceptable as in.

8. TESTS CONDUCTED: Performed liquid penetrant and ultrasonic baseline examinations on Head ID after grinding.

9. REMARKS: NCR 189-042. ISI UIR MP1-89-102, 102A and 102B.

inspection visual examinations. Page 1 of 2 11.6 L-____-____--__. _ - _ _ _ . _ _ _

sm AWO NO: M1-89-04740 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASMK Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI. Y0 /6 / Gesawme Title tluw Date

                                                                                   /s. t989 6/             (/ Signed CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the
      / $attb                                r-        (erlL9lA9 y'~
                                                                                                                                                                                             ~

g ' Signed Title D6te ' CERTIFICATE OF INSPECTION _.I, the undersigned, holdinc a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance described in this report on Company have inspected the4'd 'I3 ' and
/We <*n state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss'of any kind arising from or connected with this inspection. DatelJ 7 H b Y lm~ Commissions ' ] < ? (Id/pector) Pane 2 of 2 O 11.9 L __ _ _ - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
r j FORM HIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Engineering AWO NO: M1-89-04823

4. SYSTEM: Low Pressure Coolant Injection, Class 1.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 1980 Edition, (b) ASME SECTION XI REPAIR / REPLACEMENT CODE:
~~Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: LPCI Weld CCBJ-13.~~
~~() 7. DESCRIPTION OF WORK PERFORMED: surface indications by grinding. Removed unacceptable linear~~
8. TESTS CONDUCTED: Performed liquid penetrant test after removal of the indications.

9. REMARKS: Inservice Inspection liquid penetrant test revealed unacceptable linear indications 3/8" and 1/4" long (Ref:
NCR 189-044, UIR MP1-89-087). Page 1 of 2 11.10 t - - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
AWO NO: /77/ 8I-WM3 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statemente made in thic report are correct and thic repair or replacement conforme to the rulee of the ASME Code Section XI. Ye{ y (/ ' Signed
~~/5 / (%rchmk r Title &f/*bfR'9 Dafe /~~
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspec, tion and Insurance Company have inspected the sfefe
described in this report on ( J4-11 and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
~~Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DatW2t&f~~
~
~~kW(1stpector)~~
~~?" Commissions C7//4 O~~
II*II Page 2 of 2 L .
O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASHI Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWD NO: M1-87-11311.

4. SYSTEM: Main Steam Relief, ASME Class 1 5.
~
~~(a) APPLICABLE CONSTRUCTION CODE: ASME Section III, 1968. (b) ASME SECTION II REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Relief valve 1-MS-3B.~~
~~O(ms 7. DESCRIPTION OF WORK PERFORMED: Replaced Target Rock steam relief topworks with identical assembly. (e.g. refueling outage surveillance).~~
~~8. TESTS CONDUCTED: Performed IST valve operability test surveillance SP-1097 after replacement of assembly.~~
~~Performed operational leak test after installation.~~
~~9. REMARKS: Replacement is a normal refueling outage valve assembly changeout.~~
i 1 O Ly g Page 1 of 2 1 -- - - - _ _ - - _ _ _ _ _ _ _ _ _ - _ - _ - - - _ - -
f
)
O j AWO NO: M1-87-11311 1 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT l As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ME ode Section XI. kU Y $
~~/. Signet 1 . Title Dat6 /~~
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected rthe , ,*aw-ser uwste me.ne# described in this report on cMr / /N9 and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By eigning this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date s;rk UMP A M A_ Commissions 07//3'1 s ector)
)
l Page 2 of 2 0 11.13 , L _ _ _ ___ _ _ _ . _ _ - _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ ____ _
_ ,- - - -- -_7 - _-
'l
~~(~). FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT~~
~~As Required by the Provisions of the ASME Code Section XI ;~~
~~1. Owner: Northeast Nuclear Energy Co.~~
~~P.O. Box 270 Hartford Ct, 06101~~
2. Plant: Millstone Unit i P.O. Box 128 Waterford Ct, 06385

3. Work Performed by: Unit 1 Maintenance AWO No: M1 89 07390

4. System: Main Steam Relief Valve, ASME Clace 1

5. (a) Applicable Construction Code: ASME Section III Class A, 1968.
~~(b) ASME XI Repair / Replacement Code: 1980 Edition, W 80 Addenda~~
6. Component Identification: Main steam relief valve 1-MS-3C.

7. Description of Work: Removed existing valve assembly and topworks and installed spare valve assembly and topworke.
~~.(])~~
8. Teste Performed: Performed operational lhak test of bolted flanged assemblies and performed valve operability test to procedure SP-1097.

9. Remarks: Replaced valve due to valve seat leakage.
Page 1 of 2 0 11.14 L________-_________________
() AWO NO: H1-89-07390 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statemente made in thic report are correct anc this repair or replacement conforms to the rules of the ASME Code Section XI.
~~] $ --~ /4) 6dech*m rr Pb//E9'~~
(/ [/ ' Signed Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the O e~ '- - - deecribed in this report on "< H and state to the best of my knowledge and belief this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied,- concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DateJbher YWh (Inf6ector) Commissions C7M/$ Page 2 of 2 1 11.15 L ---- -- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
~~-l li O~~
FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI !. 1. OWNER: Northeast Nuclear Energy Company l P.O. Box 270 Hartford Connecticut, 06101
2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWO NO: Mi-87-11315.

4. SYSTEM: Main Steam Relief, ASME Class 1 5.- (a) APPLICABLE CONSTRUCTION CODE: ASME Section III, 1968.
~~(b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Relief valve 1-MS-30.~~
~~() 7.~~
~
~~DESCRIPTION OF WORK PERFORMED: Replaced Target Rock steam relief topworks with identical aceembly. (e.g. refueling outage surveillance).~~
~~8. TESTS CONDUCTED: Performed IST valve operability test surveillance SP-1097 after replacement of assembly.~~
~~Performed operational leak test after installation.~~
~~9. REMARKS: Replacement is a normal refueling outage valve assembly changeout.~~
~~0 Page 1 of 2 11.16~~
~~l. _. -_---------_---_--____-- _ - _ _ _ .~~
O v AWO NO: N1-87-11315 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Seotion XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the E Code Section XI. k Y Ss W h' 5 09 j/ Signfd Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the3e grpr4/#P described in this report on h d M"/ mad and state to the best of my knowledge and belief ,'this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither-the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date SE& f /ff) / A. 2A_ Commissions OTR27 ' ( etor) l Page 2 of 2 b 11.17 L
() FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
~~1. Owner: Northeast Nuclear Energy Co.~~
~~P.O. Box 270 Hartford Ct, 06101~~
2. Plant: Millstone Unit 1 P.O. Box 128 Waterford Ct, 06385

3. Work-Performed.by: Unit 1 Maintenance AWO No: M1 88 09104

4. System: Main Staem Relief

5. (a) Applicable Construction Code: ASME Section III. Class 1 1968 (b) ASME XI Repair / Replacement Code: 1980 Edition, W 80 Addenda

6. Component Identification: Main Steam Safety Relief Valve 1-MS.AB'3D j%& nlov/H

7. Description of Work: Removed safety relief valve, lapped lower.
~~b inner gasket seat. Installed rebuilt valve S/N 1038. Installed two'new gaskets, one 0-ring, torqued bolts and installed lock-wire.~~
8. Tests Conducted: Operational leak test of bolted flanged assemblies after installation. Operability test in accordance with SP-1097.

9. Reason for Repair / Replacement: Cause of failure is due to steam cutting through the seat / disk of pilot assembly.
~
Suitability of replacement: Replaced existing topworks with new topworks. Page 1 of 2 11.18 l L
O. Awo No ," < - re - o s o y FORM NIS-2 OWNER'S REPO'RT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or' replacement conforms to the rules of th ASM Code Section XI. W hW YV Sig6ed # Title' D6t6 CERTIFICATE OF INSPECTION I, the undersigned,_ holding a valid commission issued by the National Board of Boiler and Pressure Veccel Inspectors and r% the State of Connecticut, employed by the Hartford Steam (l Boy (erInspectionandInsuranceCompanyhaveinspgepp/ d the n AU'
described in this report on 1 j and ' state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection.
Date77 h /# Th Commissions (~ 7///9 ( F(icpector) O O Page 2 of 2 11.19
[]~' FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
~~1. Owner: Northeast Nuclear Energy Co.~~
~~P.O. Box 270 Hartford Ct. 06101~~
2. Plant: Millstone Unit 1 P.O. Box 128 Waterford Ct, 06385

3. Work Performed by: Unit 1 Maintenance AWO No: M1 88 09105

4. System: Main Staem Relief

5. (a) Applicable Construction Code: ASME Section III, Class 1.1968 (b) ASME XI Repair / Replacement Code: 1980 Edition, W 80 Addenda

6. Component Identification: Main Steam Safety Relief Valve 1-MS .kE 36 psnAVAltshi
$g' 7. Description of Work: Removed safety relief valve, lapped lower inner gasket seat. Installed rebuilt valve S/N 1071. Installed two new gaskets, one 0-ring, torqued bolts and installed lock-wire.
~~8. Tests Conducted: Operational leak test of bolted flanged assemblies after installation. Operability test in accordance with SP-1097.~~
~~.9. Reason for Repair / Replacement: Cause of failure is due to steam cutting through the seat / disk of pilot assembly.~~
Suitability of replacement: Replaced existing topworks with new . topworks. Page 1 of 2 {) L 11.20 N .__ -__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ - - - _ O
i
)p AWD NO: th I ff 09 f n r FORM NIS-2 OWNER'S REPO'RT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of t e ASME Code Section XI.
~~A && V u Ti{1e d/er Date Sp/gned' CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and~~
/~'i the State of Connecticut, employed by the Hartford Steam k/ Boiler Inspection and Insurance Company have inspected the s(E #e st described in this report on 2-7 f1 and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection.
~~Date 7 f/4 ~~~
~~//7^ Commissioner C7///f (Inspector)~~
O Page 2 of 2 11.21
1 FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millston'e Nuclear Station, Unit 1 P.O. Box 128 Waterford,' Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWO NO: M1-87-05710.

4. SYSTEM: Main Steam Relief, ASME Class 1

5. (a) APPLICABLE CONSTRUCTION CODE: ASME Section III, 1968.
(b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition. Winter 1980 Addenda. o 6. COMPONENT IDENTIFICATION: Relief valve 1-MS-3E.
7. DESCRIPTION OF WORK PERFORMED: Replaced Target Rock steam relief topworks with identical assembly. (e.g. refueling outage surveillance).

8. TESTS CONDUCTED: Performed IST valve operability test surveillance SP-1097 after replacement of assembly.
Performed operational leak test after installation. ,- 9. REMARKS: Replacement is a normal refueling outage valve assembly changeout. i l () 11.22 Page 1 of 2
~~' ^~~
~~p .. S.~~
O AWO NO: M1-87-05710 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE-We certify that the statements made in this report are correct and this-repair-or replacement conforms to the rules of the A Co e Section XI.
0b [ Signed" Title Dat'e CERTIFICATE OF INSPECTION lO I, the undersigned, ho1 ding a va11d commission issued by the National Board of Boiler end Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and I surance Company have inspected the he'" "/22' AmWM 'y'Aescribed in this report on Cr/ r. / /979 and state to the-best'of my knowledge and belief ,this re' pair or. replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor'his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date 367/./9/9 SAY Commissions 0r//37 ' a or) Page 2 of 2 0 11.23
L o-FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT ! As Required by the Provisions of the ASME Code Section'XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWO NO: M1-87-11316.

4. SYSTEM: Main Steam Relief, ASME Class 1

5. (a) APPLICABLE CONSTRUCTION CODE: ASME Section III, 1968.
~~(b) ASME~SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
6. COMPONENT IDENTIFICATION: Relief valve 1-MS-3F.

7. DESCRIPTION OF WORK PERFORMED: Replaced Target Rock steam
~~() relief topworks with identical assembly. (e.g. refueling outage surveillance).~~
~~8. TESTS CONDUCTED: Performed IST valve operability test surveillance SP-1097 after replacement of assembly.~~
~~Performed operational leak test after installation.~~
~~9. REMARKS: Replacement is a normal refueling outage valve assembly changeout.~~
Q Page 1 of 2 11.24
p O AWO NO: M1-87-11316 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT l As Required by the Provisions of-the ASME Code Section XI l 1 1 CERTIFICATE OF COMPLIANCE ' We certify that the statements made in this report are corre t and'this repair or replacement conforms to the rules of the ME Code Section XI. t icW $ 2S [ Signdd Title ' Date ' CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the O National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the& Ant:re%d G/t22 and /-Nr V* described in this report on XM 4 /9W and state to the best of my knowledge and belief this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date n)*r 1/989 /Ad Commisalons 07HTf (I ctor) u Page 2 of 2 0 11.25 m
i FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Millstone Unit 1 Maintenance AWO NO: M1-89-04382.

4. SYSTEM: Reactor Recirculation, ASME Code Class 1.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Valve 1-RR-1B body to bonnet bolting.
~~( 7. DESCRIPTION OF WORK PERFORMED: Replaced body to bonnet bolts and nuts. (Ref: MRIR 184-114.)~~
8. TESTS CONDUCTED: Performed visual examination (VT-1) on new j bolting prior to installation in valve body for preservice inspection.

9. REMARKS: Original bolt threads were galled during removal Process required during seal welding of body to bonnet.
~~i O l Page 1 of 2 I 11.26~~
.)
~~h 1 m 4 ll f} AWO NO: M1-89-04382 s FORM NIS-2 OWNER'S REPORT OF: REPAIR REPLACEMENT As Required.by the Provisions of the ASME Code Section XI o~~
~~-CERTIFICATE OF COMPLIANCE We' certify that the' statements made:in this report are correct anduthis repair'or replacement conforms to the rules'of the ASME Code Section.XI.~~
~~M:142- m nediJ< e/iv/ss D(te 7 (/ {/ Signed Title~~
~~~ -~~
CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National; Board of Boiler and Pressure Vessel Inspectors and the State.of Connecticut, employed by the Hartford Steam Boiler
. Inspection and Insurance Company have inspected ths /A-# described in this report on T-N'N and state to the best of my knowledge and belief ,this repair or replacement has'been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor:his employer makes any warranty, expreseed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date 9.u IP N (16dpector) fh Commissions CT ///f Page 2 of 2 LO 11.27
FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-09086.

4. SYSTEH: Shutdown Cooling, ASME Code Class: 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Fabricated and installed new hanger lugs on new 1-SD-4A and 4B valve-elbow assemblies designated as SHC-H-40.
~~(]).~~
7. DESCRIPTION OF WORK PERFORMED: Installed new welded attachments to Shutdown Cooling pipe elbow for hanger SHC-H-40.

8. TESTS CONDUCTED: Performed visual examination as a preservice examination on piping support and LP on pipe attachment.

9. REMARKS: All. work was performed under PA 79-162.
~
Page 1 of 2 11.28
=-, O AWO NO: M1-89-09086 FORM NIS-2 OWNER'S RIPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI. Y. =n IS/ Go r di Title
*Tbr /bT Date '
6/ (7 Signed CERTIFICATE OF INSPECTION ( I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected Jhe tub e .* M described in this report on V //'f9 and
'st' ate to the best of my knowledge and belief ,th'is repair or replacement has been constructed in accordance-with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date 9*// *H b$ (Inkpector) Commissions _C h//9 Page 2 of 2 0 11.29
'r
~~-r3 FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT iss LAs Required by the Provisions of the ASME Code Section XI-i~~
~~1. OWNER: -Northeast Nuclear Energy Company P.O. Box 270~~
~~' Hartford Connecticut, 06101~~
2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Engineering / Generation Construction. AWO NO: M1-88-08424,

4. SYSTEM: Reactor Shutdown Cooling, ASME Class 2

5. (a) APPLICABLE. CONSTRUCTION CODE: ASA B31.1 1967.
~~(b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
6. COMPONENT IDENTIFICATION: Shutdown Cooling Valves 1-SD-4A and 1-SD-4B.

7. DESCRIPTION OF WORK PERFORMED: Replaced Shutdown Cooling valves 1-SD-4A and 1-SD-4B and their associated outlet piping
~~.Q' elbows with new valves and elbows.~~
8. TESTS CONDUCTED: Performed visual, liquid penetrant and radiographic testing on new welds. Performed ultrasonic baseline examinations to ASME Section XI. Performed hydrostatic pressure test of 1563 psig for.4 hours to IWC-5000 criteria of Section XI of the ASME Code (i.e. 1.25 x 1250 psig design pressure). Performed IST valve operability test surveillance SP-623.20 on new valves after final installation.

9. REMARKS: All work was performed according to specification SP-ME-696, PA 86-112 and PDCR 1-001-88.
Page 1 of 2 O 11.30
/'i V AWO NO: M1-88-08424 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rulee of , the ASME Code Se tion XI. r . _ _ _ fuswre R 8-/7-69 Signed <Jk Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors-and the g- State of Connecticut, employed by the Hartford Steam Boiler (_) Inspection and Insurance Company have inspected the A<r/*o 3 described in this report on N- J /-I'/ and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DateP h M Yd Commissions 07N/9
~~$' Inspector)~~
Page 2 of 2 , O 11.31
f ()~ FORM NIS-2 OWNER'S REPORT'0F REPAIR.OR REPLACEMENT " As Required by the Provisions of the ASME Code Section XI
~~1. OWNER: Northeast Nuclear Energy Company~~
~~-P.O. Box 270 Hartford Connecticut, 06101~~
2. -PLANTi Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED ~BY: NDSCO Generation Construction AWO NO: M1-89-08086.

4. SYSTEM: Reactor Shutdown Cooling. ASME Code Class 2

5. .(a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 19671980 Edition, (b) ASME SECTION XI REPAIR / REPLACEMENT CODE:
~~Winter 1980 Addenda.~~
6. COMPONENT IDENTIFICATION:~ Fabrication of pipe elbows to Shutdown Cooling valves 1-SD-4A and 1-SD-4B.

7. DESCRIPTION OF WORK PERFORMED: Shutdown Cooling Heat Exchanger outlet isolation valves 1-SD-4A and 1-SD-4B were replaced including their attached pipe elbows.
B. TESTS CONDUCTED: Performed visual examination, surface examination (liquid penetrant test) and volumetric examination (Radiography) to construction Code requirements. Performed ISI baseline UT examination after completion of all welding. Performed hydrostatic pressure test of 1563 psi (1.25 x 1250 design pressure). Performed IST valve operability surveillance SP 623.20 on new valves.
~~9. REMARKS: .All work was performed under PDCR 1-1-88, PA 86-112 and Specification SP-ME-696.~~
Page 1 of 2 0 11.32
o : O AWO NO: M1-88-08086 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of t ASME Code Section XI.
~~] . N.r- N / Gonl<'au bir- PfM M~~
(/ ~ [/>igned - Title Ddte ' CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the
.(]) -State of Connecticut, employed by the Bartford Steam Boiler - Jnspection and Insurance Company described in this have inspected report on thef* Jr* / / and rden s T 7 tate to the best of my knowledge and belief this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with~this inspection. Date8 'df-M 8e Commissions CI///6 (IVspector) Page 2 of 2 0 11.33
FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: Unit 3 Engineering / Generation Construction. AWO NO: M1-88-10145

4. SYSTEM: Reactor Shutdown Cooling, ASME Class 2

5. (a) APPLICABLE CONSTRUCTION CODE: ASA B31.1 1967.
~~(b) ASME SECTION II REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Shutdown Cooling Spool Piece for use on valve 1-SD-4A elbow assembly.~~
() 7. DESCRIPTION OF WORK PERFORMED: Performed shop fabrication of spool piece for installation of valve assembly 1-SD-4A. B. TESTS CONDUCTED: Performed vicual, liquid penetrant and radiographic testing 'on new welds. Performed ultrasonic baseline examinations to ASME Section XI. Performed hydrostatic pressure test of 1563 psig for 4 hours to IWC-5000 criteria of Section XI of the ASME Code (i.e. 1.25 x 1250 psig design pressure).
~~9. REMARKS: All work and nondestructive examination was performed according to specification SP-ME-696, PA 86-112 and PDCR 1-001-8B (Ref: AWD M1-08424).~~
Page 1 of 2 O 11.34
i AWO NO: M1-88-10145 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF DONPLIANCE We certify that the statements made in this report are correct and this' repair or replacement conforms to the rules of the ASME Code Section XI. i Enonc e a 6 e 9 SignhD Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the (]) d&rd "' ~ J- described in this report on V , /f and state to the best of my knowledge and belief .this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DateA V m ~ YO d Commissions 0 7#/4 gpInspector) Page 2 of 2 O 11.35
i
)
~~O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI i~~
~~1. OWNER: Northeast Nuclear Energy Company P.O. Box 27 0 '~~
~~Hartford Connecticut, 06101~~
2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-01570.

4. SYSTEM: Reactor Shutdown Cooling. ASME Code Class 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 1980 Edition, (b) ASME SECTION XI REPAIR / REPLACEMENT CODE:
~~Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Weld repair on Shutdown Cooling weli ID No. SDBC-F-4A.~~
lll 7. DESCRIPTION OF WORK PERFORMED: Preservice ultrasonic test baseline examination of weld SDBC-F-4A revealed an unac-ceptable spot indication rejectable to ASME Code Section XI Table IWB-3514.2 acceptance criteria. Indication was removed by grinding. Excavated area was surface examined (liquid Penetrant test) to verify removal of flaw. Weld repair was performed utilizing weld procedure WPS-001.
8. TESTS CONDUCTED: Performed surface examination (liquid penetrant test) and ISI baseline UT examination after completion of all welding.

9. REMARKS: A hydrostatic pressure test was not required since the repair excavation did not penetrate the pressure boundary.
O Page 1 of 2 11.36
O u AWO NO: M1-89-01570 FORM NIS-2 OWNER *S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforme to the rulee of the ASME Code Section XI. _ c_m /b/ Got t/r%e& 6*b YS1 (/ [phigned Title ~ Da'e t CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler I EspectionandInsuranceCompanyhaveinspectedthefr pA /t described in this report on
CM and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DateV*h* Y bV>~ Commissions Crn6 (16hpector) Page 2 of 2 O 11.37
(f FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeact Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWD NO: M1-89-00477.

4. SYSTEM: Reactor Shutdown Cooling. ASME Code Class 2

5. (a) APPLICABLE CONSTRUCTION CODE.: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Thermowell on Shutdown Cooling line 10"-SHC-5A.
~~r- 7. DESCRIPTION OF WORK PERFORMED: Installation of a valves l (_)3 1-SD-4A and 1-SD-4B required removal and re-installation of a thermowell.~~
8. TESTS CONDUCTED: Performed surface examination (liquid penetrant test) and visual exam to Construction Code requirements. Performed hydrostatic pressure test on system to Section XI Article IWC-5000 in accordance with procedure SP-89-13.
) 9. REMARKS: All work was performed in accordance with DCN 010-89. ( Page 1 of 2 l O 11.38
1 i
!O AWD NO: M1-89-00477 l FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME. Code Section XI. ,Yu $ .E_ m __ /Sl CwrthN S ib9 Da'te
~~(/ pdgned Title CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the~~
'O' st te or co=aecticut. en 1ovea dv the n rtrora ste m soiser Inspection and Insurance. Company have inspected the fu/*~ ~ T described in this report on Ih'49 and af. ate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate,-neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither-the Inspector nor his employer shall be liable in any manner for personal injury or property damage or l loss of any kind arising from or connected with this inspection. Datek3r#9 /N(Iddpector) b Commissions CI'/d Page 2 of 2 . O 11.39
l () FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI i
1. DWNER: Northeast Nuclear Energy Company P.O. Box 270 Bartford Connecticut. 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Engineering AMO NO: M1-89-05235

4. SYSTEM: Shutdown Cooling, Class 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Weld ID. No: SDBC-B-1.
~~(} k~~
7. DESCRIPTION OF WORK PERFORMED: Removed unacceptable linear surface indications by grinding.

8. TESTS CONDUCTED: Performed Magnetic particle examination after removal of the indications.

9. REMARKS: Inservice Inspection magnetic particle examination revealed unacceptable linear indications on the 10" sch 100 nozzle channel head to vessel weld ( Ref: NCR 189-0072).
~~Page 1 of 2 {) 11.40~~
.U .
AWO NO: M1-89-05235 FORM MIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF CONPLIANCE We certify that the statemente made in this report are correct and this repair or replacement conforms to the rules of
~~~ the ASME Code Section XI.~~
~~W W-m~~
~~/51foordufe ~Asw nsry '~~
f7 ~ V Signed Title Datef ' CERTIFICATE OF INSPECTION l I, the undersigned, holding a valid commission issued by-the O . National Board of Boiler and Pressure Vessel Inspectors and the j State of Connecticut, employed by the Hartford Steam Boiler ) Inspection and Insurance Company have inspected the : sfkesM' described in this report on ( 2/'If and l state to the best of my knowledge and belief ,this repair or i replacement has been constructed in accordance with Section XI of 4 the'ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, j concerning the repair er replacement described in this report. 1 Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Datel M M Af fr Commissions CT//d (Ih6pector) O Page 2 of 2 11.41 i
r~T (-) FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT
~~.As Required by the Provisions of the ASME Code Section XI~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone _ Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-00175.

4. SYSTEM: Reactor Shutdown Cooling system, ASME Code Class 2.
~~and Fuel Pool Cooling system ASME Code Class 3.~~
5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Removal of a spectacle flange and installation of 6" manual isolation valves between the
~~(~}~~
~~'- Shutdown Cooling and Fuel Fool Cooling system interface.~~
7. DESCRIPTION OF WORK PERFORMED: Removed spectacle flange and welded in new isolation valves at the Fuel Fool Cooling to Shutdown Cooling cross connection. Also replaced 6" Al Fuel Fool pipe with 6" CS pipe.

8. TESTS CONDUCTED: Performed visual, surface (magnetic particle or liquid penetrant) and volumetric (radiography) examinat-ions as applicable on new welded Shutdown Cooling pipe joints. Performed hydrostatic pressure test on Shutdown l Cooling side to 1.25 x Design Pressure (1563 psig).
~~Performed visual examination on Fuel Fool Cooling welds and hydrostatic pressure test to 1.1 x design (220 psig).~~
~~9. REMARKS: All work was performed in accordance with PDCR 1-19-88.~~
O Page 1 of 2 11.42 t .
I 1 I AWO NO: Mi-89-00175 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of,the ASME Code Section XI l CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code'Section XI.
-- /51 & i c- 9/H f8 9 ~
{/ (Kigned Title Date CERTIFICATE OF INSPECTION () I, the undersigned, holding a valid' commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler-Ipspection and Insurance Company have inspected M e A'eh<****7 described in this report on 7~/4'/f and
.st' ate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By' signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date7 M M M - Commissions C 7///9 (#"spector) n Page 2 of 2
,]
~~11.43~~
~~i. - - - _ _ _ _ _ - . _ - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ ____~~
~~.O.~~
~~FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI~~
~~1. Owner: Northeast Nuclear Energy Co.~~
~~P.O. Box 270 Hartford Ct, 06101~~
2. Plant: Millstone Unit 1 P.O. Box 128 Waterford Ct, 06385

3. Work Performed by: Unit 1 Maintenance AWO No: M1 88 08564

4. System: Reactor Shutdown Cooling

5. (a) Applicable Construction Code: ASA B31.1 1967 (b) ASME II Repair / Replacement Code: 1980 Edition, W 80 Addenda

6. Component Identification: Shutdown Cooling to Fuel Pool Cooling Spectacle Flange Replacement.

7. Description of Work: Removed the spectacle flange that cross-connected the Shutdown Cooling System to the Fuel Pool Cooling System and installed a new section of piping with a 6" 9008 valve in accordance with PDCR 1-19-88.

8. Tests Conducted: Liquid Penetrant test and Radiography was performed on final welds. Shutdown Cooling weld joints were hydro'd to IWC-5000 and Fuel Fool Cooling Welds hydro'd to IWD-5000.

9. Reason for Repair / Replacement: An isolation valve was added to the system cross-tie piping to eliminate the spectacle flange.
Ref: PDCR 1-019-88. l Page 1 of 2 0 11.44
k rx O AWO NO: M1 88 08564 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are . correc and this repair or replacement conforms to the rules of t S de Section XI. V w ' Title 467h Da'te ' Sfgned CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and O- the State of Connecticut, employed by the Hartford Steam Bpiler In A'te/m'*pection
/ and Insurance described in Company this reporthave on inspected 9#O the and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection.
~~DateWrif ' he Commissions C7/h' (id/pector) l O Page 2 of 2 11.45~~
~~' 1 l~~
~~l C:)- FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT~~
~~. As Required by the Provisions of the ASME Code Section XI~~
~~-1. OWNER: Northeact Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101~~
2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-03539.

4. SYSTEM: Low Pressure Coolant Injection. ASME Code Class 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition.
~~Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Valve 1-LP-15B, "B" LPCI outboard Stop to Drywell-Spray isolation valve.~~
() 7. DESCRIPTION OF WORK PERFORMED: Installation of a new EEQ MOV actuator for valve 1-LP-15B required removal of the valve from the system, rotating the valve approximately 21 degrees then welding the valve back into place.
8. TESTS CONDUCTED: Performed surface examination (liquid penetrant test), visual exam and volumetric examination (Radiography) to Construction Code requirements. Performed Inservice Operability Test SP 622.7 (Stroke time testing) on valve. Performed hydrostatic pressure test on system to Section XI Article INC-5000 in accordance with procedure SP-89-13. Performed Appendix J type C local leak rate test to procedure Sp 623.14.

9. REMARKS: All work was performed in accordance with PDCR 1-32-88.
Page 1 of 2 11.46
1 i
~~,-s ,~~
(_f ' AWO NO: M1-89-03539 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statemente made in this report are correct and this repair or replacement conforms to the rules of ' the ASME Code Section XI, Y Q. 0- /si Ger ~elin r E BT (/ fS'igned Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the I () 7s State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the Jen ~T described in this report on l^2 r 41 and A's tate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or l loss of any kind arising from or connected with this inspection. l DatsV*2r99 ' lOA Commiesione C7/// 9 (Iq(pector) Page 2 of 2 (Z) 11.47
2 F? n h. FORM MIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT
~~-As Required by the Provisions of the ASME Code Section XI-l~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 -
~~Waterford, Connecticut, 06385~~
~~3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-00827.~~
i
4. SYSTEM: Low Pressure Coolant Injection, ASME Code Class: 2 ;

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967-(b) ASME SECTION XI' REPAIR / REPLACEMENT CODE: 1980 Edition, I Winter 1980 Addenda. ]
COMPONENT IDENTIFICATION: Modification of pipe support 1 6. CC-H-52 pursuant to I&B 79-14, PA 79-162 " Seismic Analysis 1 of as-built safety related piping". (])
~~.7 . DESCRIPTION OF. WORK PERFORMED: Modified LPCI pipe support CC-H-52'in accordance with Project Accignment 79-162.~~
8. TESTS CONDUCTED: Performed visual examination as a preservice-examination on piping support and performed liquid penetrant' examination on welded attachments to the pressure retaining pipe surface.

9. REMARKS: All work was performed under PA 79-162.
)
l 1 Page 1 of 2 3 l O 11.48
l j I i O AWO NO: M1-89-00827 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE - We certify that'the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI. W $ h-w ~ ist Gonbnahr-Title Seo-Hl. tres Date (7 (7 Signed CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler f'-) Inspection _and Insurance Company have inspected the A', /. r --e-/ described in this report on 9 // d f and
'st' ate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
~~Furthermore, neither the Inspector nor his employer shall be~~
~~' liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection.~~
~~Date91/*E? k4 L Commissions C f//0 (Inspfbtor)~~
~
o Page 2 of 2 . O 11.49
O)
\-
~~FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Engineering AWO NO: M1-89-03260

4. SYSTEM: Low Pressure Coolant Injection, Class 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, ,
~~Winter 1980 Addenda.~~
6. COMPONENT IDENTIFICATION: LPCI pump A and B flow switches

7. DESCRIPTION OF WORK PERFORMED: Replaced LPCI pumps A and B Peeco flow switches with blank flanges, 2" Class 300#, P/N 66204956.

8. TESTS CONDUCTED: Performed visual examination (VT-2) leak test after installation of bolted blank flanges. Performed operational testing of valves 1-LP-26A.

9. REMARKS:
~~Reference:~~
PDCR 1-7-89. () Page 1 of 2 11.50
i j O. AWO NO: M1-89-03260 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required.by the Provisions of the ASME Code Section II I l CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and'this repair or replacement conforms to the rules of
.the ASME Code Section XI, l$l fa web %sb r e N/ff 7 fate ~ ~~ ~ - [/ ~ 6 Signed Title' CERTIFICATE OF INSPECTION I, the undersigned.. holding a valid commission issued by the
~~(]~ :~~
. National Board of Boiler and Pressure Vessel Inspectors:and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the Ec h ear.r described in this report on /- NU and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the~ Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Dated N M ' AW L Commissions C f!#7 (In66ector) l Page 2 of 2 LO 11.51
O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Engineering AWO NO: M1-89-03259

4. SYSTEM: Low Pressure Coolant Injection, Class 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: LPCI pump B and D flow switches
~~_({) 7. DESCRIPTION OF WORK PERFORMED: Replaced LPCI pumps B and D Peeco flow switches with blank flanges, 2" Clace 300#, P/N 66204956.~~
8. TESTS CONDUCTED: Performed visual examination (VT-2) leak test after installation of bolted blank flanges. Performed operational testing of valves 1-LP-26B.

9. REMARKS:
~~Reference:~~
PDCR 1-7-89. l Page 1 of 2 () , 11.52 ,
t 1 1 i I L l 1(3)
-I AWO NO: M1-89-03259 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT q As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforme to the rules of the ASME Code Section XI.
~~Y $Cf' Signed~~
$m /S/ Derch.n b r Tit'le elwu_ /V. ' ~~ /fAS
~~(/ Date CERTIFICATE OF INSPECTION~~
.( ) I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam' Boiler Inspection and Insurance Company have inspected the /y* w -T described in this report on /*/M and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date d- M*H AWk Cometsakons CF/NP (PWapector) Page 2 of 2 11.53
\
~~O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As. Required by the Provisions'of the ASME Code Section XI~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. ' PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05492

4. SYSTEM: Mian Steam, Class 2. ,

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Hanger (A)MS-H-5.
~~({) 7. DESCRIPTION OF WORK PERFORMED: Replaced missing bolt with bolt made from 1 3/4" threaded rod to ASME SA-193, GR B7 and Installed 4 ASME SA-194, GR 2H nuts.~~
8. TESTS CONDUCTED: Performed visual examination (VT-3) after replacing bolt and nuts on hanger.

9. REMARKS:' Inservice Inspection visual examinations identified a missing bolt on top of the pipe clamp.
l Page 3 of 2 O l 11.54
i H
~~.O.~~
4 AWo no: #1/M dSA9% FORM NIS-2 OWNER *S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statemente made in thic report are correct and this repair or replacement conforme to the rules of the ASME Code Section XI. Y Wh-m ~
/S/ f6ethttH9 fore m /5ffg7 0 (/S1gned Title fate CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the Ardeu + ~
described in this report on MH and st' ate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied,
~~.concerning the repair or replacement described in this report.~~
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date0 NH UM Commissions N N8
~~'TInspector) l t~~
O 11.55 Page 2 of 2
FORM NIS-2. OWNER'S REPORT OF. REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385 3.- WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05491

4. SYSTEM: Mian Steam, Class 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Hanger (B)MS-H-16 and (A)MS-H-7.

7. DESCRIPTION OF WORK PERFORMED:
~~((} Added additional fillet weld metal on hanger plate to building structure weld,~~
8. TESTS CONDUCTED: Performed visual examination (VT-3) after welding on hanger plate.

9. REMARKS: Inservice Inspection visual examinations identified a gap between the hanger plate and building structure 1-beam.
Upon review, the hanger attachment welds were undersized and needed additional weld metal. These hangers were installed during the 1987 outage as part of the 79-14 Hanger program. Weld material was added in accordance with DCN 1532 R2. This repair is not considered a service induced defect but is a possible design discrepancy. O Page 1 of 2 11.56
O AWD NO: M1-89-05491 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforme to the rules of the ASt:E Code Section XI. m h Sw lS/ berchna e /O./Sjf f higne'd~ Title [/Date O CERTIr1CATE Or 1NSrECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Prepsure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the
#94m a described in this report on 2 n49 and state to the best of my knowledge and belief this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Datd & M A di ? Commiesionr7mf (In6ector)
~~-J N~~
O 11.57
G V FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. - WORK PERFORMED BY: Millstone Unit 1 Maintenance AWO NO: Mi-89-04570.

4. SYSTEM: Main. Steam, ASME Code Class 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Gland Seal Steam Regulator Isolation Valve 1-GS-1.
L 7. DESCRIPTION OF WORK PERFORMED: Replaced' original isolation valve with new Alsthom Fluides valve during the 1987 refuel outage. Due to misinterpretation of the NUQUAP Report and ASME Code boundaries and requirements, the valve was installed as Non-QA and no ASME Section XI requirements were imposed. During the 1989 refuel outage, radiography and a liquid penetrant examination were performed on the welds as required by the construction code. The radiograph failed the acceptance criteria and required removal of the valve and rewelding. The welding performed was performed in accordance with ASME Section XI criteria and passed all required NDE. i
~~8. TESTS CONDUCTED: Performed visual, surface (liquid penetrant) and volumetric (radiography) examinations on new pipe welds.~~
In lieu of the hydrostatic pressure test requirements of Article IWA 5214, an operational leak test was performed. The hydro is deferred until the next scheduled refuel outage in 1991 at which time the end of 10-year hydro of the main steam system will be performed. (Ref: Code case N 416).
~~9. REMARKS: Ref: NCR 189-028. AWO M1-89-03053. HUSCO Memo GMB-87-R-526 dated 11/13/87.~~
O Page 1 of 2 11.58
h AWO NO: Mi-89-04570 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI.
~~-- h l 0 sn-ll>r 9/n l99~~
(/ Signed' Title Da'te ' CERTIFICATE OF INSPECTION I, the' undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler nswo, ection and Insurance Company have inspected pp
. r described in this report on JM49 and state to.the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or propert,y damage or loss of any kind arising from or connected with this inspection. Date O lA ' kd ]~ Commissions OI/A f
~~@spector)~~
Page 2 of 2 O l 11.59 a-_________-_____-_____--__________-_______
6 V FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construct $on AWO NO: M1-89-00812. ,
1
4. SYSTEM: Isolation Condenser, ASME Code Class: 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Modification / Replacement of pipe supports IC-H-500, IC-H-502, IC-H-503, IC-H-504, IC-H-506,
('- IC-H-509, IC-R-518, IC-R-519 IC-R-520, IC-R-539 IC-R-540, IC-R-541, IC-R-542, IC-R-543, IC-R-544, IC-R-545, IC-A-548, and IC-R-517 pursuant to I&B 79-14, PA 79-162 " Seismic Analysis of as-built safety related piping".
7. DESCRIPTION OF WORK PERFORMED: Modified / replaced Isolation Condenser pipe supports in accordance with Project Assignment 79-162.

8. TESTS CONDUCTED: Performed visual examination as a preservice examination on all of the above piping supports and performed liquid penetrant examination on welded attachments to the Pressure retaining pipe surface on supports IC-R-518 and IC-A-548.

9. REMARKS: All work was performed under PA 79-162.
~~l ) Page 1 of 2 l 11.60~~
~~-. . _ - _ _ _ _ _ - _ _ _ _ a~~
O
\/
AWO NO: M1-89-00812 FORM NIB-2 OWNIR'S REPORT OF REPAIR RIPLACIMENT As Required by the Provisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE We certify that'the statements made in this report are correct'and this repair or replacement conforms to the rules of the ASME Cod Section XI. __ /S/ Gr>rN r- k.Apf $ /689 (/ fsigned Title Date CERTIFICATE OF INSPECTION
~~'I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the~~
~~(~' State of Connecticut, employed by the Hartford Steam Boiler~~
\ I3 spection and Insurance Company have inspected the /b h % , # described in this report on 4 //'M and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date 9-///S Y$ Commissions 07/// ? (Instector) Page 2 of 2 , i l l 11.61 L - __ _ _.____ _ _________ ____ _ _ _
s FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05031.

4. SYSTEM: Core Spray Loop A. ASME Code Class: 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Replacement of Restricting Orfice
~~{) Flanges on Core Spray Loop 'A*.~~
~~7. DESCRIPTION OF WORK PERFORMED: Replaced 10" 150 lb flanges around restricting orifice R0 10-2A with 300 lb flanges.~~
~~Installed new studs and nuts.~~
~~8. TESTS CONDUCTED: Performed visual, surface examination (LP) and radiography on new welds. Performed hydrostatic' pressure test (468 +30,-0 psig) on new welds to Special Procedure 89-1-38.~~
B. REMARKS: Ref: NCR 189-062. Page 1 of 2 r~ 11.62
i 1 AWO NO: M1-89-05031. FORM 1115-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the P.rovisions of the ASME Code Section II CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI.
~~- /S / G>c etske Nr 9luI*S Date / ~~~
~~(/ {}TS'igned- Title~~
'\
CERTIFICATE OF INSPECTION I, the undersigned. holding a valid commission issued by the. National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the Jte4-- - 7 described in this report on 9-e/ -}f and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date%N-}f h tinspector) Em Commissions C7/ M 1 Page 2 of 2
-Q 11.63 u - - _ _ _ __ .- - - _ _ _ _ . _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - . - - - - - - - - - - - _ _ _ _ . - - _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _
~~FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05030. ,

4. SYSTEM: Core Spray Loop B. ASME Code Class: 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Replacement of Restricting Orfice Flanges on Core Spray Loop *B'.

7. DESCRIPTION OF WORK PERFORMED: Replaced 10" 150 lb flanges around restricting orifice RO 10-2B with 300 lb flanges.

8. TESTS CONDUCTED: Performed visual, surface examination (LP) and radiography on new welds. Performed hydrostatic pressure test (468 +30,-0 psig) on new welds to Special Procedure 89-1-38.

9. REMARKS: Ref: NCR 189-062.
Page 1 of 2 () I 11.64
I i
\
(^) s-J l AWO NO: M1-89-05030. FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the'ASME Code Section XI. Y$ /S / loOrt;ll r 1'b ' lM Dste ' ~ (/ [}Bigned Title () CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler I spection and Insurance Company have inspected the
/> < c- , 7 described in this report on 0 // ff and afate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date9 ti -H ' A'$'7- Commiestons r T/M 9 finspector) Page 2 of 2 11.65 4
'(D
~~FORM NIS-2 OWNER'S. REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI~~
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Millstone Unit 1 Maintenance AWO NO: M1-89-04813.

4. SYSTEM: Core Spray, ASME Code Class 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Bolting on flange down stream of check valve 1-CS-3A.
~~-(])- 7. DESCRIPTION OF WORK PERFORMED: Replaced original flange bolting with new ASTM A193-B7 bolts and ASTM A194-2H nuts.~~
8. TESTS CONDUCTED: Performed operational leak test after assembly of new bolting.

9. REMARKS: None.
Page 1 of 2 11.66 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ - . - - - - ----------_a
.k AWO NO: M1-89-04813 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI, , m /5/ A u-b n N r- 9l/3 AT
(/ gfSigned Title D/te CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the O- National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler
]ns ection and Insurance Company have inspected the A+e N ~T described in this report on 9,8 and s' tate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DatfMM ' N I* -- .- CommiesionsC T/N 9 l (Idfpector) Page 2 of 2 LO 11.67
O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford,. Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-03139.

4. SYSTEM: Reactor Building Closed Cooling Water system-drywell inlet and outlet containment isolation valves.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.
~~(') -(>~~
6. COMPONENT IDENTIFICATION: Installation of motor operated containment isolation 1-RC-202, 203, 206, 207 and manual valves 1-RC-201, 2fl4, 205, and 208.

7. DESCRIPTION OF WORK PERFORMED: Removed MOV valve 1-RC-15 and welded in new motor operated valves and associated manual valves to meet 10 CFR 50 Appendix J criteria.

8. TESTS CONDUCTED: Performed surface examination (magnetic particle test) visual exam and volumetric examination (Radiography) to Construction Code requirements. Performed Inservice Operability Test-(Stroke time testing) on motor operated valves for baseline. Performed hydrostatic pressure test on system to 1.10 x Design Pressure. Performed Appendix J type C local leak rate test.

9. REMARKS: All work was performed in accordance with Specification SP-ME-431 and Project Assignment 80-189.
0 Page 1 of 2 11.68
D
.!v AWO NO: M1-89-03139 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that.the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI.
[b YO #' K~4 mere t-2r a t Signed Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the Os National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected thp s4 h e , - . -r described in this report on #45341 and st' ate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. DateS brM brY k Commissions Y Ghl Cfnspector) Page 2 of 2 ([) 11.69
FORM NIS-2 ONNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Nor'theast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 J P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: Unit 1 Miantenance AWO NO: Mi-87-10451.

4. SYSTEM: Reactor Feedwater, ASME Class 2

5. (a). APPLICABLE CONSTRUCTION CODE: ASA B31.1 1967.
~~(b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Feed Pump Minimum Flow Reciro Valve 1-FW-14A.~~
~~() 7. DESCRIPTION OF WORK PERFORMED: Disassembled valve, cleaned all surfaces, replaced valve internals and machined valve seating surfaces.~~
8. TESTS CONDUCTED: Performed IST valve operability test surveillance SP-608.28 after repairs and performed operational leak test with normal system pressure applied.

9. REMARKS: Repair was required because of valve body seat errosion.
~~I Page 1 of 2 O 11.70~~
~~/~)~~
(> AWO NO: M1-87-10451 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the AS E Co e ection XI.
~~& S2 Signed. Title' Date' '~~
[ i CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the () State of Connecticut, employed by the Hartford Steam Boiler InspectionandInsuranceCompanyhaveinspectedgI//1 p j6sdoce <f described in this report on and s' tate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
~~'Furthermore, neither the Inspector nor his employer shall be -~~
liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Datd /6 ' e ?W Commissions 6//N ' (Iinsp)ctor) Page 2 of 2 o 11.71
FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05301

4. SYSTEM: Feedwater, Clase 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Feedwater Hanger FWR-H-27
~~-(]) 7. DESCRIPTION OF WORK PERFORMED: Replaced damaged strut with 2" Sch 40 rod.~~
8. TESTS CONDUCTED: Performed visual inspection (VT-3) after reworking hanger to original configuration. Performed info only magnetic inspection on welded pipe attachment.

9. REMARKS: Hanger strut was found bent during 1989 Inservice Inspection and required replacement of damaged component.
l i Page 1 of 2 i l 11.72
O AWO NO: M1-89-05301 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As. Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of
~~-the ASME Code Section XI.~~
~~0 $(/ keen U~~
~~$ 717 Akb Date YM f5,/9f'1 '~~
S$ned Title CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State'of Connecticut, employed by the Hartford Steam Boiler O I3 spection and Insurance Company have inspected the
~w *rm.7 described in this report on f /c'6'1 and sfate to the best of my knowledge and belief this repair or replacement has been constructed in accordance with Seccion XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date4 N'M ' II d - Commissions 7/#9 (I dpector) i e Q Page 2 of 2 11.73
O FORM'NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT L As Required by'the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box'270 Hartford: Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1-P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05493

4. SYSTEM: Feedwater, Clace~2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967-
~~'(b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.~~
6. COMPONENT IDENTIFICATION: Feedwater Support FWR-H-29

7. DESCRIPTION OF WORK PERFORMED: Replaced missing pipe clamp bolt with a 3/4" x 3" ASTM A325 bolt and 2 ASTM A194 GR.2H nuts.

8. TESTS CONDUCTED: Performed visual inspection (VT-3) ai'ter reworking hanger to original configuration.

9. . REMARKS: Pipe support was found missing a pipe clamp bolt and nut during the 19S9 Inservice Inspection and required replacement of missing components.
l l I' O Page 1 of 2 11.74 _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - . _ _ _ . _ . _ _a
1 0 1 l AWO NO: M /d @SY93 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI. M Ob 0 hw 9 Signed ~
~~/6/ foerel,%v Title r // Date~~
~~(%/Tc?f O CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the~~
. National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler >IspectionandInsuranceCompanyhaveinspectedthe re4v-- / described in this report on AvY /1 and afate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Dat$ / N df kW L Commissions CY!US (In6$ector) O 11.75 Page 2 of 2
O FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI 1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101
2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut, 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05217

4. SYSTEM: Condensate, Claes 2

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition,
~~' Winter 1980 Addenda.~~
~~6. COMPONENT IDENTIFICATION: Condensate Hanger C-H-92~~
~~([) 7. DESCRIPTION OF WORK PERFORMED: Replaced existing pipe clamp bolt with a longer bolt 1" x 5" lg ASTM A-325 and inctalled a ASME A-194 GR 2H n'ut and jamb nut.~~
8. TESTS CONDUCTED: Performed visual examination (VT-3) after assembly of hanger bolting.

9. REMARKS: Hanger was found missing a nut during inservice inspection visual examinations.
Page 1 of 2 0 11.76
I
]
O AMO NO: A?/ tf9 OOD FOCM-NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section II 1 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair or replacement conforms to the rules of the ASME Code Section XI. (/ W}M signed
/S/ Gsrobakr Title & /t/927 Date O CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Ail /~olr described Company in this have report inspected on t. 2the 4- # ar.d s' tate to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector .nor his employer makes any warranty, expressed or implied, 'concerning the repair or replacement described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Dated h N WYS Commissions C P' 8 (%spector) 0 11.77 Page 2 of 2
O FORM NIS-2 OWNER *S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI
1. OWNER: Northeast Nuclear Energy Company P.O. Box 270 Hartford Connecticut, 06101

2. PLANT: Millstone Nuclear Station, Unit 1 P.O. Box 128 Waterford, Connecticut. 06385

3. WORK PERFORMED BY: NUSCO Generation Construction AWO NO: M1-89-05218

4. SYSTEM: Condensate, Class 2.

5. (a) APPLICABLE CONSTRUCTION CODE: USAS B31.1 1967 (b) ASME SECTION XI REPAIR / REPLACEMENT CODE: 1980 Edition, Winter 1980 Addenda.

6. COMPONENT IDENTIFICATION: Hanger C-H-214
~~-( ) 7. DESCRIPTION OF WORK PERFORMED: Replaced bolt with 1" x 4 1/2" ASTM A-325 bolt and SA-194 GR 2H nute.~~
8. TESTS CONDUCTED: Performed visual examination (VT-3) after rework of hanger.

9. REMARKS: Inservice Inspection visual examinations identified loose bolting on hanger C-H-214. Replaced exiting loose bolt with a- longer bolt utilizing a jamb nut to retain fastener.
~~1 O Page 1 of 2 11.78 __ ______-_______-__- _ ___ - ____ _ __ Q~~
-O AWO NO: M1-89-05218 FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT As Required by the Provisions of the ASME Code Section XI CERTIFICATE OF COMPLIANCE We certify that the statemente made in this report are .
~~correct and this repair or replacement conforms to the rules of the ASME Code Section XI.~~
~~$ lS/ [ctrb f YM ll l$50 '~~
~~67 (higned Title Date l CERTIFICATE OF INSPECTION~~
)
I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam Boiler Inspection and Insurance Company have inspected the AL 4 e u mir described in this report on 4 /9'# and state to the best of my knowledge and belief ,this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be i liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Datd N>d M 1 Commissions C W#1 (InsFector) O Page 2 of 2 11.79 l
l j I p
~~-Q- .~~
~~}. FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions cf the ASME Code Section XI 1'. Owner: Northeast Nuclear Energ/ Co. P.O. Box 270 Hartford Ct, 06101~~
2. Plant: Millstone Unit 1 P.O. Box 128 Waterford Ct, 06365

3. Work Performed by: NNECO Unit *. Maintenance
~~.AWO No: M1 87 06895. .~~
~~4. System: Condensate, ASME Section XI Class 2.~~
~~-_ 5 . (a) Applicable' Construction Ccde: MPC-M1-M7. EBASCO Spec. 53-47.~~
(b) Applicable Section XI Repair / Replacement Code: 1980 Edition,. Winter 1980 Addenda. (' 6. Component Identification: "A~ Condensate Booster Pump A Casing,Ingersoll-Rand Model Nc. 10SH1AX1 / 10SH2AX1.
7. Description of Work: Replaced existing pump casing with new pump casing assembly.

8. Tests Conducted: Operational leak test performed at normal operating pressure and ter. pere.ure. ISI vibration and op-erability test performed Er hE!eline test.

9. Remarks: Pump casing var re;;E:ed due to erosion beyond ,
~~repair. Froper clearance! Of internal parts could net be maintained causing premature -hnart bearing and seal wear. 11.80 Page 1 of 2~~
\
~~l l 1~~
~~-FORM NIS-2 OWNER'S REPORT OF REPAIR REPLACEMENT lh-- As Required by the Provisions of the ASME Code Section XI i~~
~~CERTIFICATE OF COMPLIANCE We certify.that the statements made in this report are amcrect and this repair or replacement conforms to the rules of b(W ,- Section XI.~~
~~, /~~
bl-/ 4'A/7C J~M&stf 2/ 4' Title Dat6 ' S/1&ned CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Connecticut, employed by the Hartford Steam ect d the Boiler A c /n Inspection
~~...1 and Insurance described in Company have insp/r/5p' this report'on ' .~~
anil state to the best of my knowledge and belief ,this repair p or replacement has been constructed in accordance with V Section XI of the ASME Code. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for personal injury or property damage or loss of any kind arising from or connected with this inspection. Date % /19 N M~ Commissions C r/'/9 (Inspector) l h Page 2 of 2 11.81
i---.----------.--_-,,-.,--.-.- - - - , - - - f L U'E : SECTION XII NON-ASME SECTION XI ADDITIONAL INSPECTION WORK
~~SUMMARY~~
~~o h 10 12,0~~
~~. 97K1X2.070 '~~
~~c-NON-ASME SECTION XI ADDITIONAL INSPECTION WORK~~
~~SUMMARY~~
TABLE 7, IIf,5 NUMBER OF EXAMS o' Non-0A weld examination results 2 (Welds) Category "D".IGSCC. o' Visual" examination results
~~'3'(Pumps) 1 (Nozzle)- .24 (Lifting' Lugs)~~
~~< o Ultrasonic thickness"information 2 (Valves)~~
~~-results- 4 (Pipe Runs)'~~
~~1 (Heat Exchanger)- .~~
~~.o . Balance of plant erosion / corrosion = 13 (Locations)'~~
~~program results ~~~
~~.0; /~~
O 12.1 87K1X2.079
NON-OA WELD EXAMINATION RESULTS t' ( CATEGORY "D" IGSCC EXAMINATION AREA: Welds 2 4" in. Diameter with In-Service Temperatures > 200*F Containing Reactor Coolant (2) EXAMINATION METHOD: Volumetric (U.T.) for IGSCC EXAMINATION ITEM EXAMS RESULTS REHARKS Reactor Water Cleanup Supp1v System 8" Stainless Steel Welds (2)
1. CUA-9 (IGSCC U.T. Acceptable Poor search unit contact Cat. D) (60*, noted on inside radius of profile elbow side of weld. No 0*) indications.

2. CUA-10 U.T. Acceptable No scan valve side of (IGSCC '(60*, weld. Poor search unit Cat. D) profile contact noted on inside 0*) radius of elbow side of weld. No indications.
O V 12.2 07K1X2.070 s
VISUAL EXAMINATION RCSULTS (3 b CATEGORY ePECIAL EXAMS EXAMINATION AREA: Control Rod Drive System, Standby Liquid Control System and Feedwater Coolant Injection System Exempted Pump Mounting Bolts and Shell Supports. Drywell Spray Nozzle after disassembly. Lifting lugs for rigging of MSIP equipment on Recirculation System. EXAMINATION METHOD: Visual and Visual (V.T.-3) EXAMINATION ITEM EXAMS RESULTS REMARKS
1. CRD Pump V.T.-3 Acceptable None (302-3B)

2. SLCS Pump V.T.-3 Acceptable None (1102A)

3. FWCI Pump V.T.-3 Acceptable None (M2-17A)

4. Drywell Visual Acceptable None Spray Nozzle
[] U S. Lifting lugs Visual Acceptable None for MSIP equipment (24) O 12.3 97K1X2.079 J
ULTRASONIC THICKNESS INFORMATION RESULTS I T
'l CATEGORY SPECIAL EXAMS EXAMINATION AREA: Emergency Service _ Water piping and valves, Service Water piping, and Low Pressure Coolant Injection Heat Exchanger EXAMINATION METHOD: Volumetric (U.T.) Thickness EXAMINATION ITEM EXAMS RESULTS REMARKS
1. E.S. WTR U.T. Information Thickness readings taken Valve 1-LPC- (Thick- on areas of valve erosion 4A ness) for MP1 maintenance.

2. E.S. WTR U.T. Information Same as above.
~~Valve (Thick-1-LPC-4B ness)~~
~~3. E.S. WTR U.T. Information None Piping 20"- (Thick-CSS-9A "E" ness)~~
~~Bay t,~~) 4. E.S. WTR U.T. Information None Piping 20"- (Thick-CSS-9B *E" ness) Bay~~
5. Serv. WTR U.T. Information None Piping 34"- (Thick-SW-2 "B" Bay ness)

6. Serv. WTR U.T. Information None Piping 34"- (Thick-SW-2 "E" Bay ness)

7. LPCI Hx (MB- U.T. Information None 76A) Shell (Thick-ness)
~~() 12.4~~
~~. 97K1X2.079~~
I l BAIANCE OF PIANT EROSION / CORROSION PROGRAM RESULTS ' 7 O CATEGORY SPECIAL EXAMS EXAMINATION AREA: Piping System Potential Problem Areas Per Generation Engineering Wear Models (MIT or EPRI) EXAMINATION METHOD: Volumetric (U.T.) Thickness EXAMINATION ITEM EXAMS RESULTS REMARKS
~~'1. Feedwater U.T. Acceptable No areas of rejectable'-~~
Coolant (Thick- wall thinning noted. Inj ection ness) Piping System Potential Problern Areas / Locations (13) i O 12.5 97K1X2.079
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ML20248D570

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