ML20138B914

Inservice Insp Rept for Northeast Utils Millstone Unit 1 1985 Refueling Outage on 851025-1223 of NDE Performed Per Section XI of ASME Boiler & Pressure Vessel Code,1980 Edition,Including Winter 1980 Addenda

ML20138B914
Person / Time
Site:	Millstone
Issue date:	02/24/1986
From:	Romberg W NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20138B903	List: B12018, Forwards Inservice Insp Rept for Northeast Utils Millstone Nuclear Power Station Unit 1 1985 Refueling Outage, Per Section XI of ASME Code & Tech Spec 6.9.2.a ML20138B914
References
NUDOCS 8603250219
Download: ML20138B914 (64)

Text

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i INSERVICE INSPECTION REPORT FOR NORTHEAST UTILITIES MILLSTONE NUCLEAR POWER STATION UNIT NO. I 1935 REFUELING OUTAGE O

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l TABLE OF CONTENTS t

'SECTION' f

I OWNER'S DATA REPORT (FORM NIS-1) i II INTRODUCTION AND ABBREVIATIONS III

SUMMARY

OF CONDITIONS NOTED AND ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN l

IV.

PROCEDURE, PERSONNEL, AND EQUIPMENT QUALIFICATIONS LISTS 1

V CLASS I EXAMINATION RESULTS j

VI CLASS II EXAMINATION RESULTS f

VII SUBSECTION IWF EXAMINATION

SUMMARY

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7 FORM NIS-1 OWNER's DATA REPORT FOR INSERVICE INSPECTIONS 1

AS REQUIRED BY THE PROVISIONS OF THE ASME B0ILER AND PRESSURE VESSEL CODE RULES 1.

0WNER:

Northeast Nuclear Energy Co., P.O. Box 270, Hartford, CT 06141-0270 2.

PLANT:

Millstone Unit No. 1, Waterford, CT 4.

CAPACITY: 2011 MWt 682 MWe 5.

COMMERCIAL SERVICE DATE: December 28, 1970 6.

NATIONAL BOARD NUMBER FOR REACTOR VESSEL:

20797 (No other board number or state numbers assigned to components.)

7.

COMP 0NENTS INSPECTED:

System Description Manufacturer Reactor Vessel Reactor Vessel Internals Combustion Engineering Recirculation 28" Sch 80 304 SS Dravo Piping 22" Sch 80 304 SS 9

12" Sch 80 304 SS 4" Sch 80 304 SS Isolation 16" Sch 80 304 SS Dravo /A.P.& E Condenser 14" Sch 80 304 SS (Combustion Engineering-Piping 12" Sch 80 304 SS ICBJ-CAP) 10" Sch 80 304 SS

.c LPCI Piping 18" Sch 80 304 SS Dravo /A.P.& E 16" Sch 80 304 SS 16" Sch 100 316 SS 12" Sch 80 304 SS Shutdown Cooling 14" Sch 100 316 SS Dravo /A.P.& E Piping 12" Sch 80 304 SS 12" Sch 80 C.S.

Clean-up Piping 8" Sch 80 304 SS Dravo /A.P.& E/

SWF Fabricating &-

Welding Core Spray 10" Sch 80 304 SS Dravo /SWF Fabricating &

Piping Welding n

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System Description Manufacturer p

Jet Pump 4" Sch 80 SB166 Ni-Cr-Fe General Electric /LAMC0 tj Instrumentation 5" Sch 80 SB166 Ni-Cr-Fe Nozzle Assembly 4" Sch 80 304 SS Welds 8" Sch 80 304 SS 12" Sch 80 304 SS Support Members Bergen-Patterson, and Components for Grinnel, Corner and Piping, Pumps, and Lada, and Pacific Valves Scientific.

LPC1 Valve 1-LP-11A Bolting Atwood & Morrill Valve 1-LP-11B Bolting Atwood & Morrill Valve 1-LP-12A Bolting Chapman Valve 1-LP-128 Bolting Chapman Valve 1-LP-10B Internals Chapman Core Spray Valve 1-CS-5A Internals Chapman Clean-up Valve 1-CU-3 Internals Chapman Valve 1-C0-28 Bolting Chapman 8.

EXAMINATION DATES:

October 25, 1985 to December 23, 1985 9.

INSPECTION INTERVAL: December 1980 to December 1990 4

10. ABSTRACT EXAMINATIONS:

3 Nondestructive examinations were performed in accordance with Section XI of the ASME Boiler and pressure vessel code, 1980 Edition including the Winter 1980 Addenda.

Augmented inspections were performed on stainless steel piping welds based on the guidance of NUREG-1J61, " Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Boiling Water Reactor Plants."

System pressure tests were conducted on Class 1 and Class 2 components during this refuel outage.

For Class 1 the Reactor Pressure Vessel and Class 1 piping and components were system leakage tested. For Class II components, a hydrostatic pressure test was conducted on the Isolation Condenser System and a system functional test was conducted on the Core Spray and Low Pressure Coolant Injection systems in accordance with IWA-5000 of the ASME Section XI Code.

11. Abstract of conditions noted and corrective measures taken are identified in Section III of this report.

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We certify that the statements made in this report-are correct and 4

examinations and corrective measures taken, conform to the rules of the ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition, Winter-1980 Addenda.

Date

.2 2 7 M By W.D. Romberg l

Station Superinten@ nt Northeast Nucle:.

iergy Co.

Millstone Nuclear Power Station-Unit 1 W

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'/7 CERTIFICATE OF INSERVICE INSPECTION V

I, the undersigned, holding a valid commission issued by the state of Connecticut and employed by the Hartford Steam Boiler Inspection and Insurance Company has inspected the components described in this Owner's Data Report during the period October 25, 1985 to December 23, 1985 and state 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 personnel injury or property damage or loss of any kind arising or connected with this inspection.

Date

?,0?-8d Commissions CT- /23 7 ANII M [ M I [ a Robert L. Bockus b-)

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INTRODUCTION s

This report contains the results of the Tenth Inservice Inspection of the Millstone Nuclear Power Station Unit 1.

Inservice inspections were performed in accordance with the scheduling requirements of the second inspection period of the 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.

Electric Power Research Institute (EPRI) qualified ultrasonic examination procedures were used for inspection of all stainless steel piping for the detection of intergranular stress corrosion cracking (IGSCC).

Augmented inspections were performed on stainless steel piping welds based on the guidance of NUREG-1061, " Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Boiling Water Reactor Plants."

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 1.

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

1 Abbreviation Definition U.T.

Ultrasonic Test P.T.

Penetrant Test M.T.

Magnetic Particle Test i

I R.T.

Radiographic Test l

VT-1,2,3,4 Visual Test i

'I.D.

Inside Diameter a

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Outside Diameter NUSCO Northeast Utilities

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Service Company i O

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SUMMARY

OF CONDITIONS NOTED AND V

ABSTRACT OF CORRECTIVE MEASURES RECOMMENDED AND TAKEN INSERVICE INSPECTION 1.

Inspections of Stainless Steel Piping A comprehensive program addressing Intergranular Stress Corrosion Cracking (IGSCC) was implemented this refuel outage. A total of 115 stainless steel welds were ultrasonically examined, based on the guidance of NUREG-1061. As shown in Table I of the 115 welds examined, six (6) welds were found to be rejectable by examination.

Table II contains a description of the flaws found in the six (6) welds and the dispositions of each.

In accordance with the NRC recommendations on the " Reinspection, Analyses and Repairs of the Reactor Coolant System Piping," the 4 inch recirculation system weldolets which were not examined in 1984 were examined this outage and all were found to be acceptable.

Ultrasonic examinations for IGSCC were performed by EBASCO, Trutom, Nuclear Energy Services (NES) and Northeast Utilities Service Company (NUSCO) personnel.

Level II and III ultrasonic test personnel were requalified for IGSCC detection at the EPRI NDE Center prior to performing ultrasonic examinations during the

(_)

refuel outage.

Additionally, ultrasonic examination technicians were given procedure training, master / slave system training, as v

well as written and practical examinations as part of the NU onsite qualification for IGSCC examination.

Samples containing actual IGSCC were used for the practical portion of the onsite qualification exercise.

Preliminary manual ultrasonic examination results which contained suspected IGSCC indications were provided to NUSCO for further evaluation and confirmation of results.

NUSCO evaluations consisted of a four step program consisting of:

1)

Analysis of the reported data.

2)

Review of radiographs for I.D. geometry.

3)

Comparison of data to previous examination results.

4)

Weld re-examination using alternative techniques, including:

I.D. creeping wave, Ultrasonic Data Recording and Processing System (UDRPS) and additional angle beam and frequency transducers.

If a disposition was not obtained via the use of the above-listed methods, radiography and I.D. penetrant examinations were performed.

Ten percent of the welds were examined using the master / slave system.

The system was also used for several re-examinations of suspect welds by NUSCO personnel.

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A A careful evaluation of the LPCI system welds was performed due to V

the number of suspect indications identified by preliminary ultrasonic examination. The evaluation consisted of:

radiograpy on select welds with high amplitude indications, UDRPS of two welds, reexamina-tion of eleven welds using 1.5 MHz transducers, reexamination of three welds using 4 MHz 52.5* shear wave and 55 and 70* I.D.

creeping wave transducers, along with an I.D. water-washable remote flourescent liquid penetrant examination of three welds.

The welds selected for the I.D. liquid penetrant exams contained ultrasonic reflectors typical of all LPCI welds.

The liquid penetrant procedure was qualified on a mock-up representative of the actual piping configuration using actual IGSCC test blocks.

The I.D. penetrant exam revealed no flaws. The acceptable penetrant examination results, along with a review of the ultrasonic examination results as given above reveals that the high number of suspect ultrasonic reflectors is due to beam redirection and I.D. geometry.

It was found that a 60* probe exhibited a 10 downward shif t which when used for plotting would make 90 percent of the indications counterbore geometry.

To keep the data consistent throughout the examination, no plots were made showing this angle shift. The remaining 10 percent of the suspect indications are attributed to redirection due to weld material and I.D. geometry.

The LPCI system welds evaluated as acceptable per letter PSE-85-1095 in the examina-tion results of this report is based upon the information given above.

The final disposition of all weld indications was made by qualified NUSCO NDE personnel based on the additional information obtained during the evaluation program and the initial results provided by the qualified examination technicians.

The 1985 IGSCC program exceads the provisions of the ASME Boiler and Pressure Vessel Code Section XI and the guidelines of NUREG-1061.

The percentages of welds, per pipe size inspected, meet or exceed NUREG-1061 guidelines. The thorough inspection program, using recently requalified inspection personnel and equipment, (including ultrasonic imaging and " master / slave" scanning) give a high degree 1

of confidence that the welds inspected do not contain IGSCC. Where IGSCC has been mitigated by weld overlays, the design implementation and inspection procedures result in a safe weld joint.

The flawed weld accepted by analysis (RCAJ-1, 28" A recirc loop suction pipe to safe-end weld) and treated by Induction Heating i

Stress Improvement (IHSI) in 1984, showed no evidence of crack growth. This result serves to assure that the validity of the conclusions in the original analysis, provides justification for operation for another refuel cycle.

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Table I l

Millstone Unit 1 Summary of IGSCC Inspection Results Piping Systems Inspected Rejected Repair Recirculation 18 0

Shutdown 4

0 LPCI 51 0

Reactor Water Clean-up 8

0 Core Spray 4

0 Isolation Condenser 13 1

Weld Overlay Weld Overlays 7

0 Jet Nozzle Instrumentation 10 5

Weld Overlay Nozzle Assembly Total 115 6

6 Weld Overlays O

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O Table II Flaw Description and Disposition of Welds Rejected by Examination System Weld Flaws Disposition Isolation ICAC-F-13

1. 1).22" deep x 2.5" long at Weld Overlay 37"-39.5" clockwise.

1. 2 and #3 of lesser depth.

All flaws located in 8" length at 36"-3 7/8" Clockwise thru the 0 reference point at Top Dead Center of pipe.

Jet Pump JPAF-2-SE

1. 1).042" deep x.5" long at 5.5"-6" Weld Overlay Instrument Clockwise.

Note:

Conservatively Nozzle"A" treated as a flaw.

Examination was from Safe End side of weld only due to outside diameter geometric config-uration.

JPAJ-2

1. 1 and #2 both flaws combined are.1" Weld Overlay deep x 4.66" long at 39"-3.22" Clockwise thru the 0 reference point at Top Dead Center of the JPI nozzle.

Jet Pump JPBF-2-SE

1. 1).09" deep x.5" long at 2.75"-3.25" Weld Overlay Instrument Clockwise.

Recorded by examiner at Nozzle "B" center point 3" Clockwise 1/2" long.

1. 2).06" deep x.625" long at 13.68"-

14.31" Clockwise.

Recorded by examiner at center point 14" Clockwise 5/8" long.

Note:

Conservatively treated as two flaws.

Examination was from Safe End side of weld only due to outside diameter geometric configuration.

3.4 CMB601221/A i

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4 Table II Flaw Description and Disposition of Welds Rejected by Examination 4

4 System Weld Flaws Disposition Jet Pump JPBJ-2

1. 1).172" deep x 360* intermittent.

Weld Overlay Instrument Recorded by examiner as 25% deep of Nozzle "B"

.688" nominal wall thickness.

JPBJ-3

1. 1).344" maximum depth x 360* intermit-Weld Overlay 4

tent.

Recorded by examiner as 50% maximum depth of.688" nominal wall thickness.

Recirculation RCAJ-1

1. 1).090" deep x 2 1/2" long at 0.

Accepted by

1. 2).175" deep x 6 1/2" long at 23" Analaysis in 1984 Counter Clockwise.

i Note:

Flaws match previous i

examination data from the

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1964 outage.

No change or new indications have been identified.

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Table III Miilstone Unit No. 1 ISI/NDE STATUS REPORT Welds Welds Welds System Scheduled Acceptable Rejectable 28" RECIRC 3

3 0

j 22" RECIRC 1

1 0

18" LPCI 46 46 0

16" LPCI 5

5 0

150 COND 1

1 0

S.D. CLG 1

1 0

.i 14" 5.D. CLG 1

1 0

i ISO CAP 1

1 0

12" RECIRC 4

4 0

150 COND 7

6 1

S.D. CLG 2

2 0

. O 1o" coat sea ^v 4

4 o

ISO COND 4

4 0

8" CLEAN-UP 8

8 0

WELD OVERLAYS 13 13 0 **

4" RECIRC BYP 5

5 0

JET PUMP INSTR 10 5

5 RECIRC 4

SAFE ENDS 4

4 0

RCAJ-1 (UDRPS) 1 1

0 TOTAL 121 115 6

The examination scope was increased by four welds from the original inspection plan due to the rejection of weld ICAC-F-13.

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The examination scope was increased by six weld overlays from the original inspection plan due to the addition of welds ICAC-F-13,

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JPAF-2, JPAJ-2, JPBF-2, JP8J-2, and JPBJ-3, which were found to be rejectable during the 1985 inspection.

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Weld Categories per NUREG-1061 V

Category "A":

Resistant material welds and welds of nonresistant to resistant material that were corrosion resistant clad welded (CRC).

Requirement:

5% by pipe size inspected each outage.

Category "B":

Nonresistant material welds with IHSI applied and welds of nonresistant to resistant material that were heat sink welded (HSW).

Requirement:

10% by pipe size each outage.

I Category "C":

Nonresistant material.

l Requirement:

25% by pipe size each outage and all welds that were not inspected to IEB 82-03 and 83-02 inspection requirements this outage.

Category "S":

Supplemental inspections required by NUSCO.

Category "AA": Additional Category "A" LPCI System welds, inspected beyond the minimum requirements of NUREG-1061.

Category "AC": Additional Category "C" LPCI system welds inspected beyond the minimum requirements of NUREG-1061.

Note:

100% of the LPCI system category "A" and "C" welds were inspected this outage. This includes 18 LPCI welds that were previously inspected to IEB 82-03 and 83-02 and 14 LPCI welds that were designated as category "S."

These 14 LPCI welds are located in the portion of the LPCI system that is less than 200*F system temperature.

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SYSTEM:

LPCI "A" Header Weld Designation Category Pipe Diameter Acceptable Rejectable CCAJ-17 C

18" X

CCAJ-18 C

18" X

CCAJ-19 C

18" X

CCAJ-20 C

18" X

CCAJ-21 C

18" X

CCAJ-23 5

18" X

CCAJ-24 S

18" X

CCAJ-25 S

18" X

CCAJ-26 S

18" X

SYSTEM:

LPCI "B" Header Weld Designation Category Pipe Diameter Acceptable Rejectable CCBJ-16 C

18" X

CCBJ-17 C

18" X

CCBJ-18 C

18" X

CCBJ-19 C

18" X

CCBJ-20 C

18" X

CCBJ-21 S

18" X

CCBJ-22 S

18" X

CCBJ-22A S

18" X

O CCBJ-228 5

18" X

U CCBJ-23 5

18" X

CCBJ-24 5

18" X

CCBJ-25 S

18" X

CCBJ-26 5

18" X

CCBJ-27 5

18" X

CCBJ-SC-1 5

12" X

SYSTEM:

LPCI "A" Header Weld Designation Category Pipe Diameter Acceptable Rejectable CCAJ-3 C

18" X

CCAJ-4 C

18" X

CCAJ-5 C

18" X

CCAJ-6 C

18" X

CCAJ-7 C

18" X

CCAJ-8 C

18" X

CCAJ-9 C

18" X

CCAJ-10 C

16" X

CCAJ-11 C

16" X

i CCAJ-12 C

18" X

CCAJ-13 C

18" X

i CCAJ-14 C

18" X

CCAJ-15 C

18" X

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CCAJ-16 C

18" X

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CCAJ-2 AC 18" X

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SYSTEM:

LPCI "B" Header Weld Designation Category Pipe Diameter Acceptable Rejectable CCBJ-5 AC 16" X

CCBJ-6 A

16" X

CCBJ-9 AA 16" X

CCBJ-1 AC 18" X

CCBJ-2 AC 18" X

CCBJ-3 AC 18" X

CCBJ-4 AC 18" X

CCBJ-10 C

18" X

CCBJ-11 C

18" X

CCBJ-12 C

18" X

CCBJ-13 C

18" X

CCBJ-14 AC 18" X

CCBJ-15 AC 18" X

SYSTEM:

Clean Up Supply Header Weld Designation Category Pipe Diameter Acceptable Rejectable CUAJ-2 A

8" X

CUAJ-4 C

8" X

CUAJ-5 C

8" X

CUAJ-6 C

8" X

CUAJ-7 C

8" X

Os CUAJ-7A B

8" X

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SYSTEM: Shutdown Cooling Header Weld Designation Category Pipe Diameter Acceptable Rejectable SCCF-1 S

12" X

SYSTEM:

Shutdown Cooling Header "A" Weld Designation Category Pipe Diameter Acceptable Rejectable SCAJ-1 A

14" X

SYSTEM:

Recirc Bypass Weldolet and Cap Weld Designation Category Pipe Diameter Acceptable Rejectable RCAJ-PB-1 S

4" weldolet X

RCAJ-PB-2 S

4" weldolet X

RCBJ-PB-1 S

4" weldolet X

RCBJ-PB-2 S

4" weldolet X

RCAJ-30 A

4" cap X

SYSTEM:

Core Spray Header "B" Weld Designation Category Pipe Diameter Acceptable Rejectable CSBJ-13A B

10" X

CSBJ-14 C

10" X

CSBJ-15 C

10" X

CSBJ-16 C

10" X

4' SYSTEM: Clean Up Return Header Weld Designation Category Pipe Diameter Acceptable Rejectable CUBJ-18 C

8" X

CUBJ-19 C

8" X

SYSTEM:

Isolation Condenser Piping Weld Designation Category Pipe Diameter Acceptable Rejectable ICAC-F-13 C

12" X

ICAC-F-14 C

12" X

ICAC-F-16A A

12" X

ICAC-F-8 C

16" X

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• ICAC-F-15 C

12" X

• ICAC-F-16 C

12" X

• ICAC-F-12 C

12" X

• ICAC-F-12A C

12" X

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• Additional welds required to be inspected due to rejectable indication in

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i SYSTEM:

Isolation Condenser Return Header Weld Designation Category Pipe Diameter Acceptable Rejectable ICBJ-5 C

10" X

ICBJ-6 C

10" X

ICBJ-7 C

10" X

ICBJ-8 A

10" X

SYSTEM:

Recirc Risers Weld Designation Category Pipe Diameter Acceptable Rejectable RRCJ-1 B

12" X

RRCJ-2 B

12" X

RRCJ-4 8

12" X

RRFJ-3 B

12" X

SYSTEM:

Recric System Discharge Header "A" Weld Designation Cate1ory Pipe Diameter Acceptable Rejectable r

RMAJ-4 8

22" X

RMAJ-RRC B

28" X

SYSTEM:

Recirc System Weld Designation Category Pipe Diameter Acceptable Rejectable RCAJ-1 C

28" X

RCAJ-SC-1 B

16" X

RCAJ-1A B

28" X

RCAJ-2 8

28" X

SYSTEM: Jet Pump Instrumentation Nozzle "A" and "B" Weld Designation Category Pipe Diameter Acceptable Rejectable JPAF-1 S

5" X

JPAF-2 S

4" X

JPAJ-1 S

8" X

JPAJ-2 S

12" X

JPAJ-3 S

12" X

JPBF-1 S

5" X

JPBF-2 S

4" X

JPBJ-1 S

8" X

JPBJ-2 S

12" X

JPBJ-3 S

12" X

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SYSTEM:

Recire Riser Safe Ends Weld Designation Category Pipe Diameter ' Acceptable Rejectable 4

RRCF-1 S

12" X

RREF-1 S

12" X

RRFF-1 S

12" X

RRGF-1 S

12" X

SYSTEM:

Recirc System Weld Overlays a

Weld Designation Category PipeDi$seter Acceptable Rejectable i

RRAJ-4 5

12"\\

X RRBJ-1 S

12":

X RRBJ-2 S

12" X

2 j

RRCJ-3 S

12" X

RREJ-3 S

12" X

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RRFJ-1 S

12" X

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Isolation Condenser Supply Header SYSTEM:

Veld Designation Category Pi d Diameter Acceptable Rejectable IC8J-CAP AC 14"'

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Weld Designation Category Pipe Diameter Acceptable Rejectable ICAC-F-3 S

16" X

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• ICAC-F-13 S

12" X

SYSTEM: Jet Pump Instrumentation Nozzles A&B Weld Overlays y t

Weld Designation Category Pipe Diameter Acceptable Rejectable

• J?AF-2 S

4" X

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• JPAJ-2 S

12" X

• JPBF-2 S

4" X

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• JPBJ-2 S

12" X

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• JP8J-3 S

12" J

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• 0verlays applied during 1985 refuel outage.

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Pipe Crack Repairs Weld Overlays During ultrasonic testing of service sensitive piping systeu welds, a total of six (6) welds were evaluated to have unacceptable crack indications.

Weld overlays were applied to one (1) on the Isolation Condenser Piping System and five (5) on the Jet Pump Instrumentation Nozzle Assemblies.

The design of the wsld overlays during this outage was accomplished using the computer program PC-CRACK, developed by Structural Integrity Associates. All weld overlays designed were full structural weld overlays, which are based on an assumed 100 percent through wall, 360 flaw.

The weld overlays were applied by GAPCO.

Initial overlay layers that did not pass liquid penetrant examination and did not exhibit a delta ferrite measurement greater than 8FN were not included in the final design overlay thickness.

All overlays were deposited using the automatic GTAW process using ER303L/ERNiCr-3 weld wire depending on the base metal to be overlayed.

All weld overlays were subjected to a construction liquid penetrant inspection of the first layer that exhibited a delta ferrite level greater than 8FN and the final layer.

Baseline angle beam longitudinal wave techniques were used for detection and sizing of flaws in the overlay and required base material.

Baseline zero O

degree longitudinal wave examinations were performed on new overlays to detect lack of bonding or clustered small flaws in the overlay and at the base material interface. All examinations were performed manually by EPRI qualified individuals using EPRI suggested techniques.

These examinations were not a part of the ASME Code Section XI program.

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" i" ste eiae seaaert aea ir-Damage to two pipe supports (MS-R-515 and MS-R-519) on the Main Steam System was discovered during a routine plant housekeeping tour by NNEC0 personnel on December 14, 1985. The damage consisted of three (3) fully severed Hilti-Kwik-Bolts on the floor mounted base plates.

As a result of this damage, a comprehensive inspection was conducted.

Ultrasonic testing of the remaining Hilti Bolts revealed a total of seven (7) of the twenty-four bolts, on a total of four (4) base plates for two (2) supports had failed.

A complete visual inspection of all supports from the steam tunnel Main Steam Isolation Valves to the Turbine Stop and Bypass Valves was performed to ASME Section XI rules with qualified inspectors.

The visual results revealed no damage which would impact the function or operability of the supports. A surface examination (magnetic particle) was performed on the welded attachments to the two main steam line supports which sustaincd damage. This surface examination revealed no indications.

Two Main Steam Line pipe welds which were evaluated to be the highest stress welds in the area of the damaged supports were surface (magnetic particle) examined and were found to be free of service induced flaws.

It is believed that the Main Steam System has been subjected to o

transient loadings which damaged the supports and caused excessive Q

piping movement.

The design calculation for the damaged supports was reviewed and found to fully comply with the requirements of AISC and IE Bulletin 79-02. A review of the piping and support analysis indicates that normal operating conditions could not generate a load to cause the observed damage.

The bol s which failed have been tested and found to demonstrate the anticipated c

properties of the AISI 1144 material.

It is concluded that the bolts did not have any material deficiencies which contributed to this failure.

The damaged seismic restraints have been redesigned and instrumented along with the existing support on the adjacent Main Steam Lines.

This strain gage instrumentation will allow verification of normal operat.ing loads and identify any operating transient load cases.

In summary, the bolt failure is believed to be the result of an operating '.ransient which caused the supports to be overloaded.

The support redesign will carry a transient load capable of causing the observed damage and intrumented to give insight into the actual load they experience.

3.14

4.

Remote Visual Inspection of Reactor Pressure Vessel Components C.T.S. Power Services, Inc., was contracted to assist in performing the remote visual inspection of scheduled reactor pre:sure.yessel components. All inspections were performed to NNEC0 procedures and were videotaped for permanent retention.

NUSCO NDE/ISI and NNECO Level II VT-1 and VT-3 visual inspectors performed the component surface inspections. The following summarizes the remote visual inspection activity.

NRC IE Bulletin 80-13, " Cracking in Core Spray Spargers" inspection was completed for the fourth successive cutage with no evidence of cracks, abnormal movement, corrosion, or erosion. As an additional requirement based on the findings of the 1982 sparger inspection, the sparger hold clamp was inspected for structural integrity and also for any further crack propagation of the existing flaw.

No abnormalities were found.

G.E. SIL No. 409, "Incore Dry Tube Cracks," recommended visual irsoection of the upper two (2) feet of the dry tubes because of at BWR dry tube failures. All twelve (12) Source Range /

Intei 'diate Range Monitor dry tubes were inspected to a visual acuity of 1 mil from the top to approximately three (3) inches below the Spring Housing / Pressure Tube Weld.

Additionally, SRM dry tube 36.33 was inspected along it's entire accessible length. This inspection was completed for the second successive outage with no apparent defects observed.

Previous investigation revealed that the Millstone dry tubes are of a different design as compared to the type identified by the SIL.

The steam dryer was visually examined for structural integrity because of recent BWR dryer bank seam weld failures and also for any further crack propagation of the existing flaw identified during the previous outage.

No abnormalities were observed.

G.E. SIL No. 420, " Inspection of Jet Pump Sensing Lines,"

recommended visual inspection of the jet pump sensing lines and support brackets. This was performed concurrent with the jet pump and jet pump hold-down beam inspection.

No apparent defects were observed.

The center ligaments of the core top guide, top guide hold-downs, guide rods and brackets, baffle plate manway welds, and the shroud annulus were visually inspected in accordance with ASME Section XI.

No apparent defects were observed.

O 3.15

- A

i 1

NONDESTRUCTIVE EXAMINATION PROCEDURES PROCEDURE NO.

REVISION TECH. SHEET TITLE NU-VT-1 4

Special Procedure for NU-VT-1-4 Inservice Visual i

from Rev. 3 Examination (NU)

NU-LP-1 3

N/A Procedure for Liquid Penetrant Examination (NU)

NU-UT-1 4

NU-UT-1-1 Ultrasonic NU-UT-1-2 Examination Procedure General Requirements (NU)

NU-UT-3 2

N/A Ultrasonic Examinati6n Procedure for Ferritic and Dissimilar Metal Piping Welds-(NU)

O NU-UT-4 1

NU-UT-4-1 Procedure for Weld Marking Datum Points and Identification (NU)

NU-UT-5 1

N/A Ultrasonic Examination Procedure for Thickness Measurements (NU)

NU-UT-6 2

NU-UT-6-1 Ultrasonic Examination Procedure for Intergranular Stress Corrosion Cracking (IGSCC)

(NU)-

83A0331 2

Field Change Automated

1. 1 Ultrasonic Examination a

Procedure for Pipe Butt Welds Millstone Nuclear Station O

u it 1 caes) 4.1

NONDESTRUCTIVE EXAMINATION PROCEDURES (Cont.)

PROCEDURE NO.

REVISION TECH. SHEET TITLE ACP-QA-9.06A 0

N/A Nuclear Engineering and Operations Procedure NE0 3.13 Inservice Inspection Indication Reporting i

Spec. Proc. 84-1-17 0

N/A Ultrasonic Examination of Weld i

Overlay for Bond j

Integrity (NU)

Spec. Proc. 85-1-15 0

N/A Procedure for Manual L-Wave Ultrasonic Weld

,l Overlay Repair (WOR)

Examination (NU)

Spec. Proc. 85-1-18 0

N/A Procedure for Weld Overlay Repair Inspection (NU)

SF 581 4

N/A Operational Leak Test of Reactor Vessel SP 1060A 0

N/A Remote Visual Inspection of The Core Spray Spargers, Core Spray In-Vessel Piping and Sparger t

Hold Clamp j

SP 10608 0

N/A Remote Visual Examination of The Feedwater Spargers EN 1060C 0

N/A Installation Procedure for The In-Vessel TV Camera Fixture (NNECO).

SP 1060E 1

N/A Remote Visual Examination of The IRM/SRM Dry Tubes j

, 0 4.2 j

t 1

NONDESTRUCTIVE EXAMINATION PROCEDURES (Cont.)

+

4 PROCEDURE NO.

REVISION TECH. SHEET TITLE I

SP 1060F 1

N/A Remote Visual Inspection of The-Steam Dryer and 4

Hoisture Separator SP'1060J 0

N/A demote Visual Inspection of The Jet Pumps, Top Core l

Guide Radial Restraints, and Shroud Annulus Region NU-MP-1 3

N/A Procedure for i

Magnetic Particle Examination (NU) 1 J

O 5

I

{

4 i

h-i I

a b

s t

t 9

'O 1

l 4.3 1 -

.-,...--,-,,.,,.-nn,-_,

-n.,

.--.,_...-..-,.-n,-,.,n

PERSONNEL QUALIFICATION:

1 NAME METHOD EBASCO U.T.

P.T.

EPRI-REQUAL DATE

1. R. Bouck II II September 10, 1985

2. J. DeMailo I

II

3. M. Evich I

4. J. Filson IT

5. C. Latiolais II II

6. C. Martzloff IT

7. D. Nowakowski II II September 10, 1985

8. J. O'Neil I

II

9. M. Orihuela I

10. C. Pattillo II II September 17, 1985

11. T. Pedersen III II September 17, 1985

12. P. Peterson I

II

13. L. Valenzuela II II

14. C. Walraven II II Note:

T. Pedersen EPRI - weld overlay qualified.

Nuclear Energy Services U.T.

EPRI-REQUAL DATE

1. T. Beltz IT

2. B. Cesnik II

3. B. Fetz IT

4. D. Funk IT

5. R. Harp IT

6. E. Kozlowski IT

7. N. MacNamara II November 5, 1985 Trutom U. T.

EPRI-REQUAL DATE

1. R. Pfannenstiel II September 27, 1985

2. R. Soriano II September 24, 1985 Northeast Nuclear Energy Co. (NNECO)

V.T.-1,2,3,4

1. J. Heyworth II

2. J. Leason II

3. G. Mathers II

'O 4.4

- -.- - =

.i i

i I

i I

PERSONNEL QUALIFICATIONS (Cont.)

i.

Northeast Utilities l

Service Co. (NUSCO)

U.T.

P.T.

M.T.

V.T.-1,2,3,4 R.T.

1. 1. Baird II

2. T. Davis II II

-II

3. P. Durand II II II II

4. R. Fuller III III III II

5. J. Pinto II II II II II

6. S. Sikorski III III III II III

7. R. West II-II II EPRI-REQUAL DATE 1

1

1. P. Durand-October 11, 1985 j

2. S. Sikorski September 24, 1985 l

l 4

l I

l O i

1 i

l i

I i

1 i

b q

j

}

4.5

i EQUIPMENT INSTRUMENT LIST MANUFACTURER MODEL SERIAL NO.

Ultrasonic Test Equipment

1. Kraut Krammer-Branson USL-38 210228N

2. Kraut Krammer-Branson USL-38 210692

+

3. Kraut Krammer-Branson USL-38 210158

4. Kraut Krammer-Branson USL 38 210760

5. Kraut Krammer-Branson USL-38 210761

6. Kraut Krammer-Branson USL-38 210449-QA3030

7. Kraut Krammer-Branson USL-32 211854

8. Kraut Krammer-Branson USL-31 210064

9. Kraut Krammer-Branson USK-7 RF 27276-1068

10. Automation Industries M-90 55912

11. Panametrics EPOCH-2002 20BP/330

12. Panametrics EPOCH-2002 20BP/363

13. Panametrics EPOCH-2002 20BP/362 Magnetic Particle Test Equipment

1. Parker Probe B300 417

l e

d I

4.6

N.D.E. MATERIAL LIST MATERIAL BATCH / LOT N0.

Ultragel II Couplant 8551 Exosen #20 Couplant 0115812001 Sanford Marking Pens 112 Zyglo Penetrant ZL-S4 848010 Spotcheck Penetrant SKL-HF/S 84LO33 Spotcheck Penetrant SKL-HF/S 84C025 Spotcheck Penetrant SKL-HF/S 84H027 Spotcheck Penetrant SKL-HF/S 84J044 Spotcheck Cleaner / Remover SKC-NF/ZC-78 840054 Spotcheck Zyglo Developer SKD-NF/ZP-98 84D007 Zyglo Developer ZP-4B 85C050 b) v O

4.7

m INSERVICE INSPECTION EXAMINATION RESULTS i

ASME CLASS 1 l

CATEGORY B-E i

EXAMINATION AREA:

All Pressure Retaining Partial Penetration Welds j

in Vessels, Control Rod Drive Nozzles, and Instrumentation Nozzles.

EXAMINATION METHOD:

Visual (VT-2 at RPV nominal operating pressure)

RESULTS:

Acceptable

- 1 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-5211(a).

f 9

i o i

J s

j j

l l

6 Ps

O i

5.1 2

._--,_-__-_----..----,---.--._.,_...,_.._..,_...--_..-._...__....__-___-_.__m_.,

..._.,.-~.4

INSERVICE INSPECTION EXAMINATION RESULTS ASME CLASS 1 CATEGORY B-F EXAMINATION AREA:

Pressure Retaining Dissimilar Metal Welds in Piping.

EXAMINATION METHOD:

Volumetric (U.T.) and Surface (P.T.)

(SE indicates Safe End side of weld)

(NZ indicates Nozzle side of weld)

EXAMINATION ITEM EXAMS RESULTS REMARKS Jet Pump Instrument Nozzle "A" 1.

JPAF-1-SE U.T. (60*)

Acceptable' No scan nozzle side of weld due to 0.D. nozzle geometry.

Indi-cations from I.D.

geometry evaluated as root reflectors.

f]

2.

JPAF-2-SE U.T. (60 )

Rejectable No scan penetration seal side of weld due to eccentric reducer 0.D. geome-try.

Flaw.042" deep by.5" long at 5.5"-

6" clockwise.

Overlay (Baseline)

Acceptable No indications.

P.T. U.T.

(0 Bond & 55 L)

Jet Pump Instrument Nozzle "B" 1.

JPBF-1-SE U.T. (60 )

Acceptable No scan nozzle side of weld due to 0.D. nozzle geome-try.

Indications from I.D. geometry evaluated as root reflectors.

/'

(])

4 5.2 l

EXAMINATION ITEM EXAMS RESULTS REMARKS

^'

2.

JPBF-2-SE U.T. (60 )

Rejectable No scan penetra-

,d-tion seal side of weld due to eccentric reducer 0.D. geometry.

Flaw #1.09" deep by.5" long at 2.75"-3.25" clock-wise.

Recorded by examiner at center point 3" clockwise 1/2" long. Flaw #2.06" deep by.625" long at 13.68"-14.31" clockwise.

Re-corded by examiner at center point 14" clockwise 5/8" long.

Overlay (Baseline)

Acceptable No indications.

P.T. U.T.

(0 Bond & 55 L)

Recirculation Inlet 12" 1.

RRCF-1-NZ U.T. (UDRPS 45* & 51 ) Acceptable None a

P.T.

RRCF-1-SE U.T. (UDRPS 45 & 51 ) Acceptable None 4

)

P. T.

2.

RREF-1-NZ U.T. (UDRPS 45 & 51*) Acceptable None P.T.

RREF-1-SE U.T. (UDRPS 45 & 51 ) Acceptable None P.T.

3.

RRFF-1-NZ U.T. (UDRPS 45 & 51 ) Acceptable None P.T.

RRFF-1-SE U.T. (UDRPS 45 & 51 ) Acceptable None P.T.

4.

RRGF-1-NZ U.T. (UDRPS 45* & 51*) Acceptable None P.T.

i RRGF-1-SE U.T. (UDRPS 45 & 51*) Acceptable None P.T.

5.3

EXAMINATION ITEM EXAMS RESULTS REMARKS Shutdown Cooling 12" 1.

SCCF-1-P-CS U.T. (60 )

Acceptable Spot indications P.T.

evaluated as weld l

metal interfaces (P-CS indicates pipe carbon steel side of weld) between the carbon i

steel and stain-less steel materials.

1 SCCF-1-P-SS U.T. (60*)

Acceptable Same as above I,

P. T.

(P-SS indicates pipe stainless steel side of weld) 5 3

5 i O i

i i

.rO 1

54

INSERVICE INSPECTION EXAMINATION RESULTS ASME CLASS 1 CATEGORY B-G-2 EXAMINATION AREA:

Pressure Retaining Bolting, 2" and smaller in Diameter.

EXAMINATION METHOD:

Visual (VT-1)

EXAMINATION ITEM EXAMS RESULTS REMARKS Cleanup Valve 1.

1-CU-28 VT-1 Acceptable Packing gland bolting found loose.

Low Pressure Coolant Injection Valves 1.

1-LP-11A VT-1 Acceptable None 2.

1-LP-11B VT-1 Acceptable None 3.

1-LP-12A VT-1 Acceptable None 4.

1-LP-128 VT-1 Acceptable None p

O 95

fa INSERVICE INSPECTION

\\J EXAMINATION RESULTS ASME CLASS 1 CATEGORY B-J EXAMINATION AREA:

Pressure Retaining Welds in Piping.

EXAMINATION METHOD:

Nominal Pipe Size > 4 in. = Surface and Volumetric Nominal Pipe Size 7 4 in. = Surface EXAMINATION ITEM EXAMS RESULTS REMARKS Cleanup Supply 8" Stainless Steel 1.

CUAJ-2 U.T.(60 Master / Slave)

Acceptable No scan valve side of weld.

Indications from I.D. geometry evaluated as root reflectors.

2.

CUAJ-4 U.T.(60 Mater / Slave)

Acceptable No indications.

3.

CUAJ-5 U.T.(60 Master / Slave)

Acceptable No scan valve O

side of weld.

U Indications from I.D. geometry evaluated as root reflectors.

4.

CUAJ-6 U.T.(60 Master / Slave)

Acceptable No scan valve side of weld.

Indications from I.D. geometry evaluated as root reflectors.

5.

CUAJ-7 U.T.(60 Mater / Salve)

Acceptable Limited scan 11 "

to 16" circum.

limitation due to welded restraint pipe side of weld.

Indications from I.D.

geometry evaluated as root reflectors.

6.

CUAJ-7A U.T.(60 Master / Slave)

Acceptable Indications from I.D.

geometry evaluated as root reflectors.

5.6

EXAMINATION ITEM EXAMS RESULTS REMARKS Cleanup Return 8" Stainless Steel 1.

CUBJ-18 U.T.(60*)

Acceptable No scan penetra-2 tion (X-15) side of weld.

Indica-tions from I.D.

geometry and beam redirection evaluated as root 4

and counterbore reflectors.

2.

CUBJ-19 U.T.(60)

Acceptable No scan valve side of weld.

Indications from I.D. geometry and beam redirection evaluated as root i

and counterbore reflectors.

Core Spray 10" Stainless Steel 1.

CSBJ-13A U.T.(60 )

Acceptable Indications from I.D. geometry i

evaluated as root reflectors.

2.

CSBJ-14 U.T.(60)

Acceptable Indications from I.D. geometry evaluated as root reflectors.

3.

CSBJ-15 U.T.(60 )

Acceptable Indications from I.D. geometry evaluated as root reflectors.

4.

CSBJ-16 U.T.(60 )

Acceptable No scan valve side of weld.

Indication from I.D. geometry evaluated as root reflector.

Spot indication at weld metal interface to pipe.

O 5.7 5

..m..

-,.r,

,_,-w

,-, ~,.

l EXAMINATION ITEM EXAMS RESULTS REMARKS

~

- ()

Isolation Condenser 2- /

Spare Nozzle Cap to RPV 1.

ICBJ-CAP U.T.(45 )

Acceptable Indication from I.D. geometry evaluated as root i

reflector.

Isolation Condenser Return 10" Stainless Steel 1.

ICBJ-5 U.T.(60 )

Acceptable No scan valve side of weld.

Limited scan at 4" circum. due to branch weld.

Indications from I.D. geometry evaluated as root and counterbore reflectors.

2.

ICBJ-6 U.T.(60 )

Acceptable Limited scan at 4" circum. due to branch weld

()

and a 6" circum.

area inside the elbow intrados.

Indications from I.D. geometry evaluated as root and counterbore reflectors.

3.

ICBJ-7 U.T.(60 )

Acceptable Indications from I.D. geometry evaluated as root reflectors.

4.

ICBJ-8 U.T.(60 )

Acceptable Indications from P.T.

I.D. geometry evaluated as counterbore reflectors.

ICBJ-8-EEL U.T.(60*)

Acceptable Indication from P.T.

I.D. geometry evaluated as root reflector.

1 O

5.8

,--n 9

.i--m.>g 9,.

ym as--

--y

.-%^.,

y

-.g

-ir-

-!*-+ee>

- + - - ' ' - -

EXAMINATION ITEM EXAMS RESULTS REMARKS 77 s ICBJ-8-EIL U.T.(60 )

Acceptable Indication from 4,

P.T.

I.D. geometry evaluated as root reflector.

ICBJ-8-PL U.T.(60 )

Acceptable Indication from P. T.

I.D. geometry evaluated as root reflector.

Jet Pump Instrument Nozzle "A" 1.

JPAJ-1 U.T.(60 )

Acceptable No scan 6' by 12" eccentric reducer side of weld due to 0 D.

eccentric reducer geometry.

Indications from I.D. geometry evaluated as root and counterbore reflectors.

'~

2.

JPAJ-2 U.T. (UDRPS 45 & 51 ) Rejectable Flaw #1 and #2 combined are.1" deep by 4.66" long at 39"-3.22" clock-wise thru the zero reference point at top dead center of the JPI nozzle.

Overlay (Baseline)

Acceptable No indications.

P.T. U.T.

(0 Bond & 55 L) 3.

JPAJ-3 U.T. (60 )

Acceptable Limited scan at U.T. (UDRPS 45* & 51 )

38.8" thru 0 reference point to 8" clockwise on i

vessel side of weld due to welded sup-port lug and com-ponent identification plate.

Indication

1. 1 evaluated as geome-try.

Indication #2 evaluatte as sub-surface spot indica-tion acceptable per IWB-3514.3.

5.9 4

i

EXAMINATION ITEM EXAMS RESULTS REMARKS Jet Pump Instrument Nozzle "B" 1.

JPBJ-1 U.T. (60 )

Acceptable No scan 8" by 12" eccentric reducer side of weld due to 0.D.

eccentric reducer geometry.

Indica-tions from I.D.

geometry evaluated as root and counterbor reflectors.

2.

JPBJ-2 U.T. (UDRPS 45* & 51 ) Rejectable Flaw #1.172" deep by 360" inter-mittent.

Recorded-by examiner as 25%

deep of.688" nominal wall thickness.

Overlay (Baseline)

Acceptable No indications.

P. T. U. T.

(0 Bond & 55 L)

(

3.

JPBJ-3 U.T. (UDRPS 45 & 51 ) Rejectable Limited scan at 36" thru 0 reference point to 9.5" clockwise on vessel side of weld due to welded support lug and component identification plate.

Flaw #1.344" maximum depth by 360 intermittent.

Recorded by examiner at 50% maximum depth i

of.688" nominal wall thickness.

Overlay (Baseline)

Acceptable No indications.

3 b 'B

& 55*L)

.~

O 5.10 r-,

~ ~ -,,. -, -,,

EXAMINATION ITEM EXAMS RESULTS REMARKS j

Low-Pressure Coolant Injection "A" 18" Stainless Steel 1.

CCAJ-2 U.T. (50 )

Acceptable Limited scan vee pipe side of weld due to 1.25" long spool piece.

Indications from pipe side of weld evaluated as beam redirection and I.D. geometry root reflectors.

Indica-tions from I.D.

geometry elbow side of weld evaluated as root and counter-bore reflectors.

L i

2.

CCAJ-3 U.T. (60 )

Acceptable Limited scan h i

vee pipe side of weld due to 1.25" long spool piece.

Indications from pipe side of weld O

evaluated as beam redirection and I.D. geometry root reflectors.

Indica-tions from elbow side of weld evalu-ated per letter PSE-85-1095.

3.

CCAJ-4 U.T. (60 )

Acceptable Indications from elbow and pipe sides of weld evalu-ated per letter-PSE-85-1095.

4.

CCAJ-5 U.T. (60 )

Accepta'le No scan valve side o

+

of weld.

Indica-tions pipe side of weld evaluated as

)

beam redirection.

5.

CCAJ-6 U.T. (60 )

Acceptable No scan valve side of weld.

Indica-tions elbow side of weld evaluated per letter PSE-85-1095.

5.11

'l EXAMINATION ITEM EXAM _S RESULTS REMARKS 6.

CCAJ-7 U.T. (60*)

Acceptable Indications from elbow and pipe sides of weld evalu-ated per letter PSE-85-1095.

7.

CCAJ-8 U.T. (45*)

Acceptable Indications from both sides of weld evaluated per letter PSE-85-1095.

8.

CCAJ-9 U.T. (60*)

Acceptable Indications from pipe side and re-ducer side of weld evaluated as I.D.

geometry root re-reflectors and weld metal inter-face reflectors.

Low-Pressure Coolant Injection "A" 16" Stainless Steel 9.

CCAJ-10 U.T. (60 )

Acceptable No scan valve side of weld.

Indica-O tiee fre 1 o-geometry evaulated as root reflectors.

T 4

l 4

1 l

r 5.12 l

EXAMINATION ITEM EXAMS RESULTS

-REMARKS

10. CCAJ-11 U.T. (60 )

Acceptable No scan valve (n) side of weld.

Indications from I.D. geometry evaluated as root reflectors.

Low-Pressure Coolant Injection "A" 18" Stainless Steel

11. CCAJ-12 U.T. (45 )

Acceptable Indications from pipe side and j

reducer side of weld evaluated per letter PSE-85-1095.

12. CCAJ-13 U.T. (60 )

Acceptable Indications from elbow side and pipe side of weld evaluated as beam redirection and I.D. geometry root reflectors.

p

13. CCAJ-14 U.T. (60 )

Acceptable Indications from v

both elbow sides of weld evaluated as I.D. geometry root and counter-bore reflectors.

14. CCAJ-15 U.T. (60 )

Acceptable Indications from pipe side of weld evaluated as weld metal interface reflectors.

Indica-tions from elbow side of weld evaluated per let-ter PSE-85-1095.

15. CCAJ-16 U.T. (45 & 60 )

Acceptable Indications from i

pipe side of weld evaluated as beam redirection.

Indications from penetration (X-43) side of weld evaluated per letter PSE-85-1095.

f 5.13

EXAMINATION ITEM EXAMS RESULTS REMARKS 16.

CCAJ-17 U.T. (60*)

Acceptable No scan penetration j-~)s

\\,_

(X-43) side of weld.

Indications from I.D. geometry evaluated as root reflectors verified by original weld radiograph.

17. CCAJ-18 U.T. (60 )

Acceptable Indications from pipe side and elbow side of weld evaluated per letter PSE-85-1095.

18. CCAJ-19 U.T.(60 Master / Slave)

Acceptable Limited scan pipe side of weld at 30'"

s to 31 " clockwise due to pipe longi-tudinal weld.

Indications pipe side of weld evalu-ated as I.D. geome-try root reflectors, couterbore reflectors, s

and weld metal inter-~

face reflectors.

Indication from elbow side of weld evaluated as beam redirection.

19.

CCAJ-20 U.T.(60 Master / Slave)

Acceptable Indications from elbow side of weld evaluated as I.D.

geometry root refelectors and beam redirection.

Indications from pipe side of weld evaluated per let-ter PSE-85-1095.

20. CCAJ-21 U.T. (60 )

Acceptable Indications pipe U.T.(45 &60 Master / Slave) side of weld evaluated per let-ter PSE-85-1095.

Indications elbow side of weld

O evaluated as I.D.

geometry root reflectors and beam redirection.

5.14

EXAMINATION ITEM EXAMS

'RESULTS REMARKS f~s

21. CCAJ-23 U.T.(45* Master / Slave)

Acceptable indications from V

U.T. (53 & 70 L) both pipe sides of weld evaluated as geometry.

22. CCAJ-24 U.T. (45* & 60*)

Acceptable Indications from Visual of weld 0.D.

elbow side of weld surface axial and circum.

evaluated as I.D.

geometry root reflectors.

Indica-tions from pipe side of weld evaluated per. letter j

PSE-85-1095.

j Original radiograph showed.6" long.

slag inclusion i

accepted per structural mechanics evaluation calcula-tion number 84-149-424GP.

23. CCAJ-25 U.T. (45 & 60*)

Acceptable Indications from elbow side of weld 4

axial and circum.

s evaluated as I.D.

geometry root re-

{

flectors.

Indica-i tions from pipe side of weld evalu-ated as I.D.

geometry root re-flectors, counter-bore reflectors, j

and beam redirection.

24. CCAJ-26 U.T. (45* & 60 )

Acceptable No scan valve side of weld.

Indica-a tions from pipe side

{

of weld evaluated j

as I.D. geometry root reflectors,

{

couterbore re-flectors, and beam redirection.

i

..m

! O i

j 5.15 L

EXAMINATION ITEM EXAMS RESULTS REMARKS 7

Low-Pressure Coolant T

Injection "B" 12" Stainless Steel 1.

CCBJ-SC1 U.T. (60 )

Acceptable Indications from P. T.

pipe side and tee side of weld evalu-ated per letter PSE-85-1095.

Low-Pressure Coolant Injection "B" 18" Stainless Steel 1.

CCBJ-1 U.T. (60 )

Acceptabic Indications from elbow side of weld evaluated as beam redirection.

In-d1 Cat. cons from reducer side of-weld evaluated i

per letter PSE-85-1095.

2.

CCBJ-2 U.T. (60 )

Acceptable No scan valve side of weld.

Indica-(

tions from elbow side of weld evaluated as beam redirection.

3.

CCBJ-3 U.T. (60 )

Acceptable No scan valve side of weld.

Indica-tions from elbow side of weld evaluated per letter PSE-85-1095.

4.

CCBJ-4 II.T. (45 )

Acceptable Indications from elbow side and re-ducer side of weld evaluated per letter PSE-85-1095.

O 5.16

EXAMINATION ITEM EXAMS RESULTS REMARKS

?m Low-Pressure Coolant Injection "B" 16" Stainless Steel 5.

CCBJ-5 U.T. (45 )

Acceptable No scan valve side of weld.

Indications from reducer side of weld evaluated as I.D. geometry root reflectors and weld metal interface reflectors.

6.

CCBJ-6 U.T. (60 )

Acceptable No scan valve side of weld.

Indications from elbow side of weld evaluated per letter PSE-85-1095.

7.

CCBJ-9 U.T. (60 )

Acceptable Indications from reducer side of CCBJ-9-EIL U.T. (60 )

Acceptable weld evaluated as beam redirection.

fl CCBJ-9-EEL U.T. (60 )

Acceptable Indications from si elbow side of weld evaluated per letter PSE-85-1095.

Low-Pressure Coolant Injection "B" 18" Stainless Steel 8.

CCBJ-10 U.T. (45 )

Acceptable No indications.

9.

CCBJ-11 U.T. (45 & 606)

Acceptable Indications from pipe side of weld evaluated as I.D.

geometry root reflectors and beam redirection.

Indications from elbow side of weld evaluated per letter PSE-85-1095.

10. CCBJ-12 U.T. (45 )

Acceptable Indications from elbow side and pipe side of weld evalu-

/'

ated per letter PSE-85-1095.

I 5.17

EXAMINATION ITEM EXAMS RESULTS REMARKS

%g

11. CCBJ-13 U.T. (60 )

Acceptable Indications from b

pipe side of weld evaluated per let-ter PSE-85-1095.

Indications from elbow side of weld evaluated as I.D.

geometry root reflectors and beam redirection.

12.

CCBJ-14 U.T. (60 )

Acceptable Indications from pipe side of weld evaluated per let-ter PSE-85-1095.

Indications from elbow side of weld evaluated as beam redirection.

la.

Lt'J-15 U.T. (45 )

Acceptable No scan penetration (X-45) side of weld.

Indications from I.D. geometry evaluated as root reflectors.

14.

CCBJ-16 U.T. (45 )

Acceptable No scan penetration (X-45) side of weld.

Indications from I.D. geometry evaluated as root and counterbore reflectors.

15.

CCBJ-17 U.T. (60 )

Acceptable Indications from pipe side of weld evaluated as I.D.

geometry root reflectors.

Indica-tions from elbow side of weld evalu-ated as beam redirection.

16. CCBJ-18 U.T. (60*)

Acceptable Indications from pipe R.T. (Elbow base side of weld evalu-material indication ated as I.D. geometry area only) root and counterbore reflectors.

Indica-tions from elbow side F

of weld and elbow base material evalu-ated per letter PSE-85-1095.

5.18

EXAMINATION ITEM EXAMS RESULTS REMARKS pm.

17. CCBJ-19 U.T. (60 )

Acceptable Indications from

.d pipe side and elbow side of weld evalu-ated per letter PSE-85-1095.

18.

CCBJ-20 U.T. (60 )

. Acceptable Indications from pipe side and elbow side of weld evaluated per letter PSE-85-1095.

19. CCBJ-21 U.T. (60 )

Acceptable Indications from pipe side and elbow side of weld evaluated per letter PSE-85-1095.

20. CCBJ-22 U.T. (60 )

Acceptable Indications from pipe side of weld evaluated as I.D.

geometry root reflectors, weld metal interface reflectors and beam redirection.

O, Indications from-elbow side of weld evaluated as I.D.'

geometry root reflectors and weld metal interface reflectors.

21. CCBJ-22A U.T.(60 Master / Slave)

Acceptable No stan tee side of weld.

Indications fror pipe side of veld evaluated per letter PSE-85-1095.

22.

CCBJ-228 U.T.'(45*)

Acceptable No scan tee side of weld.

Indica-tions from pipe side of weld evaluated as I.D.

geometry root reflectors.

.n O

5.19

EXAMINATION ITEM EXAMS F.ESULTS REMARKS

~

23. CCBJ-23 U.T. (60 )

Acceptable Indications from s

U.T.(60 Master / Slave) elbow side of weld evaluated as I.D. geometry root reflectors.

Indications from pipe side of weld evaluated as I.D. geometry root reflectors and spot indica-tion <.5" long.

Spot indication matches position of slag on original weld radiograph.

24. CCBJ-24 U.T. (60*)

Acceptable Indications from U.T.(60 Master / Slave) pipe side and elbow side of weld evaluated as I.D.

geometry root reflectors.

25. CCBJ-25 U.T.(45*,52.5,55 L.

Acceptable Indications from 60 & 70 L) elbow side of weld n

U.T. (UDRPS 51*)

evaluated as beam v

P.T. (I.D.)

redirection and I.D.

geometry root reflectors.

Indications from pipe side of weld 4

evaluated per letter PSE-85-1095.

26. CC8J-26 U.T.(52.5,55 L, Acceptable Indications from 60 & 70 L) cibow side of weld U.T.(45 Master / Slave) evaluated as 0.D.

P.T. (I.D.)

geometry weld crown reflector, I.D.

geometry root reflectors, and beam redirection.

Indications from 2 pipe side af weld evaluated per letter PSE-85-1095.

27.

CCBJ-27 U.T.(45*,52.5*,55 L, Acceptable No scan valve side 1

& 70 L) of weld.

Indica-U.T. (UDRPS 51*)

tions from pipe P.T. (I.D.)

side of weld evalu-C"-)

ated per letter PSE-85-1095.

5.20

EXAMINATION ITEM EXAMS RESULTS REMARKS Recirculation Outlet 28" Stainless Steel 1.

RCAJ-1 U.T. (UDRPS 51*)

Accepted by Flaw #1.090" i

Analysis in deep by 24" long 1984 at 0*.

Flaw #2 t

.175" deep by 6 "

i long at 23" counter i

clockwise.

Note:

{

Flaws match 4

I previous examina-tion data from the 1984 outage.

No change or new

{

indications have been identified.

2.

RCAJ-1A U.T. (45*)

Acceptable Indications from 1,

U.T.(60* Master / Slave)

I.D. geometry evaluated as root reflectors.

3.

RCAJ-2 U.T. (45*)

Acceptable

. Indications from U.T.(60 Master / Slave)

I.D. geometry-

)

evaluated as root and counterbore Recirculation Outlet i

16" Stainless Steel 4.

RCAJ-SC1 U.T. (60*)

-Acceptable Indications from t

U.T.(60* Master / Slave)

I.D. geometry j;

evaluated as root and counterbore reflectors.

Recirculation Outlet 4" Stainless Steel 5.

RCAJ-30 U.T. (45*)

Acceptable-No scan weldolet

-(Cap) side of weld.

No-indications.

6.

RCAJ-PB1 U.T. (45*)

Acceptable-Limited scan from I

(Weldolet) 4" cap side of' j

weld due to 0.D.

configuration.

No

}

indications.

t l

1' 1

7.

RCAJ-PB2 U.T. (45*)

Acceptable Same as above.

^

i (Weldolet) 1 5.21 1

I m

,......,_,. _ _.._.-_,..-_,_.--. ~., _

EXAMINATION ITEM EXAMS RESULTS REMARKS

'p 8.

RCBJ-PB1 U.T. (45 )

Acceptable Same as above.

(Weldolet) 9.

RCBJ-PB2 U.T. (45*)

Acceptable Same as above.

(Weldolet)

Recirculation Manifold 22" Stainless Steel 1.

RMAJ-4 U.T. (45 )

Acceptable No scan cross side of weld.

Indica-tions from I.D.

geometry evaluated as root reflectors.

Recirculation Manifold Ellipsoidal Flued Head Weld to Cross 28" x 12" Stainless Steel 2.

RMAJ-RRC U.T. (45 )

Acceptable No scan cross side of weld.

Indications from I.D. geometry evaluated as root reflectors and beam redirection.

Recirculation Inlet 12" Stainless Steel 1.

RRAJ-4 Overlay *L)

Acceptable Flaw area 10" long (0verlaid 1984)

U.T. (55 by.66" deep under overlay.

Structural integrity assured per IWB-3640 and calculation 84-149-420GP.

2.

RRBJ-1 Overlay Acceptable Flaw area 4.25" (0verlaid 1984)

U.T. (55 L) long by 1.06" deep from 0.l. weld overlay surface.

Structo al integrity assureo per IWB-3640 and calculation 84-149-422GP.

3.

RRBJ-2 Overlay

. Acceptable No indications.

(0verlaid 1984)

U.T. (60*L)

. O 5.22

EXAMINATION ITEM EXAMS RESULTS REMARKS 4.

RRCJ-1 U.T. (606)

Acceptable No scan safe end side of weld.

Indications from pipe side of weld evaluated I.D.

geometry root and counterbore reflectors.

5.

RRCJ-2 U.T. (60 )

Acceptable Indications from I.D. geometry evaluated as root reflectors.

6.

RRCJ-3 Overlay Acceptable No indications.

(Overlaid 1984)

U.T. (55 L) 7.

RRCJ-4 U.T. (60 )

Acceptable No scan from ellipsoidal flued head side of weld.

Indications from I.D. geometry evaluated as root reflectors.

r aid 1984) 5 L) 9.

RRFJ-1 Overlay Acceptable No indications.

(Overlaid 1984)

U.T. (55 L) 10 RRFJ-3 U.T. (52.5 & 60 )

Acceptable Indications from pipe side and elbow side of weld evaluated as I.D.

geometry root and counterbore reflectors.

Shutdown Cooling 14" Stainless Steel 1.

SCAJ-1 U.T. (60 )

Acceptable Indications from U.T.(60 Master / Slave) pipe side and reducer side of weld evaluated as I.D. geometry root and counter-bore reflectors.

,&.D a

5.23

INSERVICE INSPECTION i

EXAMINATION RESULTS ASME CLASS 1 CATEGORY B-M-2 EXAMINATION AREA:

Internal Pressure Boundary Surfaces of Valve Dodies.

}

EXAMINATION METHOD:

Visual (VT-3) i EXAMINATION ITEM EXAMS RESULTS REMARKS 1.

Cleanup VT-3 Acceptable None Valve 1-CU-3 2.

Core Spray VT-3 Acceptable None Valve 1-CS-5A 3.

Low-Pressure VT-3 Acceptable None Coolant Injection Valve 1-LP-10B

(-)

s i

)

J 4

1 g-s, 5.24 i

. _. _. _.,, - _ ~.. ~. _ _ _, _. -. _.... _.. _. -

i INSERVICE INSPECTION

-s EXAMINATION RESULTS i

ASME CLASS 1 CATEGORY B-N-1 EXAMINATION AREA:

Reactor Vessel Interior j

EXAMINATION METHOD:

Visual (VT-3) Accessible areas t

EXAMINATION ITEM EXAMS RESULTS REMARKS 1.

Core Spray VT-3 Acceptable None Spargers 2.

Guide Rods VT-3 Acceptable None 3.

Jet Pumps VT-3 Acceptable None 4.

Shroud Annulus VT-3 Acceptable None 5.

Steam Oryer VT-3 Acceptable None 6.

Top Guides VT-3 Acceptable None

)

e 1

3 i

s. 2, 5

T-INSERVICE INSPECTION EXAMINATION RESULTS ASME CLASS 1 CATEGORIES B-0 AND B-P 1

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 (VT-2 et 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 i

temperature in accordance with IWA-5211(a) and IWB-5221.

1 O

4

-l 4

1 5.26

i 1

i l

f INSERVICE INSPECTION EXAMINATION RESULTS i

ASME CLASS 2 CATEGORY C-C

- EXAMINATION AREA:

Integral Attachments for Vessels, y

Piping, Pumps, and Valves.

J l

EXAMINATION METHOD:

Surface _(P.T. or M.T.)

[XAMINATIONITEM EXAMS RESULTS REMARKS 1

Isolation Condenser Piping 4.

1.

IC-R-900 P.T.

Acceptable None 4

I Main Steam Piping 1.

(C) MS-R-515 M.T.

Acceptable None 2.

(D) MS-R-519 M.T.

Acceptable None j

I liO 4

I 4

I l

I i

1 4

i i

i 1

h r,

e' 6,1 4

b o

s

i b

Eg INSERVICE INSPECTION EXAMINATION RESULTS ASME CLASS 2 CATEGORY C-F EXAMINATION AREA:

Pressure Retaining Welds in Piping, i

EXAMINATION METHOD:

Nominal wall thickness <

in. = surface.

Nominal wall thickness I in. = surface j

and volumetric.

EXAMINATION ITEM EXAMS RESULTS REMARKS Isolation Condenser Supply 16" i

i Stainless Steel i

1.

ICAC-F-3 Overlay Acceptable Flaw #1 at over-i (Overlaid 1984)

U.T. (55*L & 60 L) lay to base metal 4

interface.38".from surface by.5" long.

1 Estimated size based on amplitude and beam spread compensation E.125" long by.090" high.

Flaw #2.at i

overlay to base metal interface.34"

)

from surface by

.25" long.

Esti-1 mated size based on amplitude and beam spread s.060" long x.047" high.

Indication from I.D. geometry i

i evaluated as root 1

reflector.

Flaw

1. 1 and #2 acceptable l

per IWB-3514.

2.

ICAC-F-8 U.T. (45* & 60*)

Acceptable Indications from pipe side and elbow side of weld evaluated as I.D. geometry j

root reflectors.

r-l O i

a 6.2 e

i...,-.

-,.,...m__,,_.,._s,.

EXAMINATION ITEM EXAMS RESULTS REMARKS Isolation Condenser Supply 12" Stainless Steel 3.

ICAC-f-12 U.T. (45 )

Acceptable Indications from pipe side and reducer side of weld evaluated i

as I.D. geometry counterbore re-flectors and beam redirection.

4.

ICAC-F-12A U.T. (45*)

Acceptable Indication from upstream pipe side of weld evaluated as I.D.

geometry counter-bore reflectors.

5.

ICAC-F-13 U.T. (60 )

Rejectable Limited scan due to welded pipe sup-port p' late at 17.5" ta 24 clockwise pipe side of weld.

Flaw #1.22" deep (3

by 2.5" long at V

37"-39.5" clock-wise.

Flaw #2 and #3 of lesser depth.

All flaws located in 8" length at 36" -

3-7/8*' clockwise tnru the 0 refer-ence point at top dead center of pipe.

Overlay (Baseline)

Acceptable No indications.

P. T. U. T.

(0 Bond & 60 L) 6.

ICAC-F-14 U.T. (45 & 60 )

' Acceptable Indications from pipe side and elbow side of i

weld evaluated as I.D. and 0.D.

geometry counter-bore, root, and weld crown i."

reflectors.

i 6.3 y

g-y<

y e

3-e

4 I

EXAMINATION ITEM EXAMS RESULTS

' REMARKS 2

7.

ICAC-F-15 U.T. (60*)

Acceptable Indications from j

~.

pipe side of weld I

evaluated as I.D.

geometry root 4

and counterbore reflectors, i

8.

ICAC-F-16 U.T. (60 )

Acceptable Indications from pipe side of weld i

evaluated as I.D i

and 0.D. geometry counterbore and weld crown reflectors.

9.

ICAC-F-16A U.T. (45*)

Acceptable Indications from both pipe sides 1

of weld evaluated as I.D. geometry i

clad role.

i Main Steam 20" Carbon Steel 1.

MSAC-F-6 M.T.

Acceptable No indications.

()

2.

MSDC-F-6 M.T.

Acceptable No indications.

i

}

4 I

r O

O 6.4

r~-

INSERVICE INSPECTION

O ex^"'aa'1oa suaaaav ASME CLASS 1 IWF COMPONENT SUPPORTS EXAMINATION AREA

Component Supports EXAMINATION METHOD:

Visual (VT-3 or VT-3 and VT-4).

EXAMINATION ITEM NUMBERS EXAMINED RESULTS j

1.

Low Pressure Coolant 2

Acceptable System i

2.

Cleanup System 4

Acceptable Total 6

J J

i a

O l

I i

i i

4 9

O i 'O 71 4

....--u.-.,.---..-.,

r-**-+

v

=~v

• -~re w - v *+, 's - e w e e+ - e w-e,

w~**,v-+=~-=*--ew-=*-e-e-=~--w==*ere-,-=wr-----~,*w--y

-= - - - = - - *

---+-=ve-a--+

v e==--

1

'p) -

INSERVICE INSPECTION s

EXAMINATION

SUMMARY

ASME CLASS 2 IWF COMPONENT SUPPORTS i

MAMINATIONAREA:

Component Supports EXAMINATION METHOD:

Visual (VT-3 or VT-3 and VT-4).

EXAMINATION ITEM NUMBERS EXAMINED RESULTS l

1.

Low Pressure Coolant 26 Acceptable InjectionSystem 2.

Core Spray System 1

Acceptable 3.

Main Steam System 50 Acceptable (Two Repaired see Section III.)

4.

Shutdown Cooling System 12 Acceptable 5.

Scram Discharge System

~4 Acceptable 6.

Isolation Condenser System 2

Acceptable 7.

Standby Gas and 15 Acceptable 4

i Atmospheric Control System 8.

Feedwater Coolant 250 Acceptable Injection System Total 360 l

i i

e j

i i

i 7.2

~

INSERVICE INSPECTION

\\

EXAMINATION SUMMARV ASME CLASS 3 i

IWF COMPONENT SUPPORTS EXAMINATION AREA:

Component Supports EXAMINATION METHOD:

Visual (VT-3 or VT-3 and VT-4).

EXAMINATION ITEM NUMBERS EXAMINED RESULTS 1.

Main Steam System 2

Acceptable 1,

Isolation Condenser System 3'

Acceptable 2.

l 3.

Fuel Pool Cooling System 11 Acceptable 4.

Emergency Service 8

Acceptable i

Water System 5.

Reactor Building Closed 65 Acceptable Cooling Water System I

6.

Turbine Building Secondary 29 Acceptable Closed Cooling Water System 7.

Service Water System 5

Acceptable Total 123 i

i i

r%

O 7.3

.-