ML19290C960

Inservice Insp Rept for 790822-0921 & 1011-1031,one-third of First Interval.Describes Ultrasonic,Liquid Penetrant, Magnetic Particle & Visual Examination in Specific Welds & Bolts

ML19290C960
Person / Time
Site:	Browns Ferry
Issue date:	02/11/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19290C957	List: ML19290C956 ML19290C960
References
NUDOCS 8002150256
Download: ML19290C960 (6)

Text

.- ....---. .

ENCLOSURE INSERVICE INSPECTION

SUMMARY

BROWNS FERRY NUCI. EAR PLANT UNIT 3 (DOCKET No. 50-296)

In accordance with paragraph IWA 6220 of Section XI of the ASME Boiler and Pressure Vessel Code (1974 Edition, Summer 1975 Addenda), the following information is provided:

c.1. Date: December 1979

, c.2. Name of owner and address of corporate offices:

Tennessee Valley Authority Chattanooga, Tennassee 37401 c.3. Name and address of nuclet generating plant in which the nuclear power unit is located:

Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35601 c.4. Name or nun.ber assigned to the nuclear power unit by the owner:

Browns Ferry Nuclear Plant unit 3 c.5. Commercial service date assigned to the nuclear power unit by the owner:

March 1,1977 d.1. The number assigned to the "bo ile r ," " pressure vessel," or component by the State, municipality, or province:

Does not apply.

d.2. National Board Number assigned by the manufacturer to the " boiler,"

" pressure vessel," or component:

Does not apply.

d.3. Names of the components or parts of the components for which this is a record, including such in fo rma tion regarding size, capacity, material, location, and drawings as. may aid accurate identification:

The components or parts examined as part of this inservice inspection are listed in the abstract.

d.4. Name of the manufacturer of the components or parts for which this is a record, including the manufacturer's component or part numbers and such information regarding the manufacturer's corporate office or manufacturing locations as may aid in gaining: access to the manuf ac tu re r's records regarding the components or parts that the n002150 E F6 ;

manufacturer is maintaining in accordance with requirements of section III:

The majortty of the components examined was supplied by:

General Electric Company Atomic Power Equipment Department San Jose, California TVA Contract 66C60-90744 d.5. Date of completion of the inservice inspection:

November 1979 d.6. Name or names of the inspector (s), when required:

The Tennessee Valley Authority acted as ite. cvn inspector.

d.7. Name and mailing address of the employer (s) or the inspector (s):

Tennessee Valley Authority 505 Edney Building Chattanooga, Tennessee 37401 d.8. Abstract of examinations performed, conditions observed, and corrective measures recommended and taken:

During the periods of August 22 through September 21, 1979, and October 11 through October 31, 1979, Lambert-MacGill-Thomas, Inc. (LMT), under contract to Tennessee Valley Authority (TVA) performed either ultrasonic, liquid penetrant, magnetic particle, and visual examination on the following welds and bolting on unit 3:

Main Steam - GMS-3-5, GMS-3-32*, GMS-3-20, CMS-3-17, GMS-3-15*, GMS-3-25, KMS-3-53. KMS-3-32, KMS 103, KMS-3-36. KMS-3-59, KMS-3-3, IC1S-3-70 Feedwater - GFW-3-6, KFW-3-23, GFW-3-14, KFW-3-39*,

GFW-3-12*, GFW-3-26*, KFW-3-36, KFW-3-3 Core Spray - DCS-3-17, DCS-3-16, DSCS-3-12*, USCS-3-114, DSCS-3-10, DCS-3-8, DCS-3-7, DSC-3-15, DSC-3-9, DCS-3-6 Core Saray (Baseline of Replacement Carbon Steel Pipe Welds) -

TCS3410, TCS-3-409, TCS-3-403, TCS-3-407, TCS-3-406, TCS-3-405, TSCS-3-404, TCS-3-403, TSCS-3-402, TCS-3-401, TCS-3-417, TSCS-3-413, TCS-3-419, TSCS-3-420, TCS-3-421, TCS-3-422, TCS-3-424, iCS-3-423, TSCS-3-425X, TCS-3-425 Residual Heat Removal - DSRHR-3-6*, DRHR-3-7, DS Td[R 10, TRHR-3-191, DHS-3-1, DSHS-3-9 9

Reactor Water Clean-up - DRWC-3-59, DSRWCU-3-3*, DRWC-3-1A Reactor Core Isolation Cooling - TRCIC-3-2 High Pressure Coolant Injection - THPCI-3-66, THPCI-3-70*

Recirculation - GR-3-60, GR-3-53, KR-3-46, KR-3-37, GR-3-11, GR-3-46, KR-3-22, KR-3-42 Recirculation Inlet Thermal Sleeves - N2B, N2D, N2F, N2H, N2K Valve Bolting - FCV-68-1, FCV-68-33, FCV-1-14, FCV-1-27, PCV-1-4, PCV-1-18, PCV-1-34, PCV-1-42, 1-537, HCV-3-67, 3-572, HCV-75-27, FCV-75-54 Vessel Seams - C-4-5(1 ft), C-3-4(1 ft), V-4-c(0.5 ft),

V-5-A(1.5 ft)

Vessel Head - RCH-3-10(0.5 ft), RCH-3-1V(1 ft),

RCH-3-2V (2 ft)

Vessel to Flange - (23 ft)

Head to Flange - (22 f t)

Main Steam Nozzle N3B (Nozzle to Vessel, Inner Radius, and Safe End)

Core Spray Nozzle N5A (Nozzle to Vessel, Inner Radius, and Safe End)

Feedwater Nozzle N4C (Nozzle to Vessel, Inner Radius, and Safe End)

Feedwater Nozzle N4B (Nozzle to Vessel, Inner Radius, and Safe End)

Recirculation Nozzle NIA (Nozzle to Vessel, Inner Radius, and Safe End)

Recirculation Nozzle N2B (Nozzle to Vessel, Inner Radius, and Safe End)

Recirculation Nozzle N2D (Nozzle to Vessel, Inner Radius, and Safe End)

Recirculation Nozzle N2F (Nozzle to Vessel, Inner Fadius, and Safe End)

Jet Pump Instrumentation Nozzle N8A (Nozzle to Vessel, Inner Radius , and Safe End)

~

Vessel Head Nozzles - N6A, N6Al Vessel Stud Numbers 26, 63-71 Vessel Nut Numbers 30 Vessel Washer Numbers 30 Vessel Bushing Numbers 71 Vessel Ligament Numbers 30 ,

Skirt to Vessel Weld - 1 f t Clad Patches - 2 Recirculation Pipe and Valve Hangers - KR-3-S4, R-3-R1, R-3-H1, R-3-H2, R-3-SS1, R-3-SS3, R-3-R1, R-3-H12, R-3-89 Recirculation Pump Hangers - R-3B-H3, R-3A-H2 Main Steam Pipe and Valve Hangers - MS-3-HA1, MS-3-HC4, MS-3-SSA12, MS-3-HA4, MS-3-RD3, MS-3-GD-1, MS-3-SSB4, MS-3-SSB5, MS-3-HC1, MS-3-SSC2, MS-3-HC4 Feedwater Pipe and Valve Hangers - FW-3-H6, FW-3-H7, fW-3-H5, FW-3-3, FW-3-G1, FW-3-H10, FW-3-SSB1, FW-3-SSB3, FW-3-SSB7, FW-3-H7 Core Spray Pipe and Valve Hangers - CS-3-H6, CS-3-HS, CS-3-H1 Residual Heat Removal Pipe and Valve Hangers - HS-3-H15, RHR-3-H6, RHR-3-H3, RHR-3-H9, RHR-3-H2, HS-3-11, HS-3-H15, HS-3-R75 Reactor Water Clean-up Pipe and Valve Hangers - RWC-3-H1 High Pressure Coolant Injection Pipe and Valve Hangers -

HPCI-3-H1 Recirculation Pump Bolting - 10

. . . . _ .. . _ . _ . _ . . .._. . . m. .

Recirculation Pump Nuts - 10 Resideal Heat Removal Heat Exchanger Circumferential welds RHRG-10-A (3 f t), RHRG-11-A (0.5 f t)

Bolts - 12 on B Nuts - 112/ flange on B Main Steam (Class 2) - DMS-3-9, DMS-3-16, DMS-3-17, DMS-3-29, DSAS-3, DSAS-15 Residual Heat Removal (Class 2) - TRHR-3-281, TRHR-3-67, TRHR-3-39A, TRHR-3-197, TRHR-3-204, TRHR-3-239, TRHR-3-183C, TRHR-3-374, TRHR-3-320, TRHR-3-104, TRHR-3-253, TRHR-3-404, TRHR-3-448, TRHR-3-118C Residual Heat Removal Pipe Flange Bolts - A Pump Discharge (24)

Residual r eat! Removal Pipe Flange Nuts - A Pump Discharge (48)

Residual Hes' Removal Pump Bolts - A Pump (24)

Residual Heat Removal Pump Nuts - A Pump (24)

Main Steam Supports and Hangers - RG-1-ST, RG-1-MSR, MSH-3-12, MSH-3-7, MSH-3-10, MSH-3-13, MSGEH-1, MSH-3-17, HPASH-1, HPASH-3, HPASH-8, HPASH-10, RPASH-18 Residual Heat Removal Supports and Hangers - H-158, R-50, H-122, H-62, H-14, H-4, H-23, H-158, R-36, H-82, H-84, H-SS, R-35, H-73, R-35C, H-98, R-50, H-63, H-55, H-122, H-56, H-65, H-121, R-54, H-67, H-o2, R-o4, H-124, H-125, H-4, H-14, H-16, H-10, H-8, H-26, H-19, H-21, H-23, H-29, H-146, R-70, H-160, H-145B

• These welds are included in the plant technical. speci'fications as an augmented inspection to protect against damage caused by pipe whip. The remainder of the program is listed in "The

Preservice Baseline Inspection and Inservice Inspection Program for the Tennessee Valley Authority - Browns Ferry Nuclear Plant,"

which is Surveillance Instruction 4.6.g.

Most examinations performed by LMT and TVA showed nothing but geometric indications caused by mismatch or weld crown. A rejectable linear indication was found on weld DCS-3-18; however, this 10-inch stainless steel core spray weld was already scheduled to be replaced with carbon steel. Another indication was located on weld TilPCI-3-66, a 10-inch carbon steel seam weld. Further evaluation which included radiographic examination was performed. It was determined that this weld was acceptable but would be examined again during the next inservice inspection of this unit.

Records which give detailed information on this inspection will be filed at Browns Ferry Nuclear Plant.

1 I