IR 05000354/1985028

From kanterella
Jump to navigation Jump to search
Insp Rept 50-354/85-28 on 850610-14.No Violation Noted. Major Areas Inspected:Preservice Insp Activities,Including Demonstration of Ability to Detect Cracks in Corrosion Resistant Cladding Matl
ML20133G728
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/01/1985
From: Mcbrearty R, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20133G723 List:
References
50-354-85-28, NUDOCS 8508090053
Download: ML20133G728 (5)
v • d • e


Text

Y

.

.

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

50-354/85-28 Docket No.

50-354 License No.

CPPR-120 Priority --

Category B Licensee:

Public Service Electric & Gas Company 80 Park Plaza - 17C Newark, New Jersey 07101 Facility Name:

Hope Creek Generating Station, Unit 1 Inspection At:

Hancocks Bridge, New Jersey Inspection Conducted: June 10-14, 1985 Inspectors:

/, /97[

'

R. A. McBrearty, Reacto/ Engineer date/

'

^

Approved by:

MS A21[/NS

-

J/.JT.%"iggins(gfief 96Ae (/ 7 Katerials & P McessesSection V

Inspection Summary:

Inspection on June 10-14,1985 (Report No. 50-354/85-28)

Areas Inspected:

Routine, unannounced inspection of licensee action on previous inspection findings; PSI activities including observations of work in progress, demonstration of ability to detect cracks in corrosion resistant cladding material, review of procedures, and review of PSI data.

The inspec-tion involved 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> onsite by one regional based inspector.

Results: No violations were identified.

hhk

DO G

f

.

.

DETAILS 1.

Persons Contacted Public Service Electric and Gas Company

  • A. Barnabei, Principal Quality Assurance (QA) Engineer
  • R. F. Brandt, Nuclear Plant Servic:a engineer
  • R. B. Donges, QA Enginear
  • G. L. Duncan, PSI Senior Supervisor
  • A. E. Giardino, Manager QA - Engineering and Construction
  • R. T. Griffith Sr., Principal QA Engineer
  • A.S. Kao, Site Engineer
  • L. Lake, ISI Engineer Southwest Research Institute (SWRI)

H. Diaz, NDE Level III

  • E. Feige, Inspection Engineer

C. Brinson, QC Supervisor - San Jose U.S. Nuclear Regulatory Commission

  • L. Briggs, Lead Reactor Engineer
  • J. J. Lyash, Resident Inspector

2.

Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (85-01-02):

Resolution of rusted Reactor Pressure Vessel upper flange stud holes.

The inspector reviewed FDDR No.

KT 1-34! Revision 0 through 3 inclusive, which documented the actions taken by the GE Co. to determine the extent of damage to the stud holes, and the disposition based on their findings.

Molds were made of the most severely cceroded stud holes and based on the molds, all holes except hole number 67 were accepted as is.

KT1-341 Revision 2 required that molds be c.ade of the threads in hole number 67 before and after system hydrostatic test.

The molds were sent to G.E. in San Jose, California for evalur. tion and final disposition.

Revision 3 of the FDDR accepted hole number 67 as is based on the determination that the reported damage is within tne design margin, and the replications dis-closed no visible sign of damage caused by tensioning.

-

.

- -

-

I

.

Based on the above this item is considered closed.

(Open) Unresolved Item (83-11-04): Ultrasonic examination of welds with corrosion resistant cladding (CRC). The CRC is associated with 12" diameter, 22" diameter and 28" diameter piping at Hope Creek.

During the course of this inspection the licensee demonstrated his ability to detect cracks in 12" diameter samples containing CRC. (See paragraph 4 of this report).

Sections of 22" diameter material and 28" diameter material are being prepared for a similar demonstration by the licensee.

This item will remain open pending the performance of a successful demonstration of technique on the larger diameter samples.

3.

Procedure Review The following ultrasonic examination procedure was reviewed by the inspector with regard to ASME Code and regulatory requirements, and, in addition, to technical adequacy regarding parameters which were demonstrated at the EPRI NDE Center at Charlotte, North Carolina to be capable of detecting cracks in CRC piping weld samples:

SWRI-NDT-800-100 Revision 1, " Manual Ultrasonic Examination of

Corrosion - Resistant Clad Piping Welds at Hope Creek";

The inspector's review indicated that applicable code and regulatory requirements were met.

The inspector stated that technical adequacy would be based on a practical demonstration of the procedure on CRC piping samples which contained cracks.

See paragraph 4 of this repcrt.

No violations were identified,.

l 4.

Observations The inspector observed NDE in progress to ascertain that applicable ASME Code and regulatory requirements were met and that the examinations were performed by qualified personnel in accordance with approved procedures.

Ultrasonic examination of the following recirculation system welds were included in the inspector's observations:

1-BB-12VCA-014C-3, loop "B", 12" diameter pipe to elbow weld - no CRC

1-BB-12VCA-014C-4, loop "B", 12" diameter elbow to pipe weld no CRC

1-BB-12VCA-013G-5, loop "A", 12" diameter pipe to safe end weld -

ID/0D CRC The examinations were done by qualified technicians using approved procedure f

.

.

In addition to the above the inspector requested that the technical adequacy of procedure SWRI - NDT-800-100 Revision 1 be demonstrated on samples of CRC piping welds which contained cracks.

The licensee had two 12" diameter weld samples available, one of which contained two cracks and the second contained one crack and five notches. At the inspector's request the demonstration was performed in his presence by the SWRI Level II technician who was responsible for performing the CRC examinations in the plant.

The demonstration was performed using the same equipment, including transducer, which was used for production examinations.

Prior to scanning the cracked samples, the examination system was calibrated on the welded calibration block which is used for production examinations.

All cracks were successfully identified in the two samples.

Subsequent to the demonstration described above portions of loop "A",12" diameter pipe to pipe weld 1-BB-12 VCA-013F-2 were scanned to compare the ultrasonic noise level of the production weld with the noise level of the samples. A similar comparison was made of weld 013G-5 with the samples.

At the calibrated examination sensitivity, noise level amplitude from each weld and from the samples were found to be similar.

Based on the demonstrated abil'

' detect cracks, and the observed similarities of acoustic noise in the samples and production welds, the inspector stated that the prucc.ure was acceptable for the examination of 12" diameter CRC piping welds.

The licensee stated that 22" diameter and 28" diameter samples, representing the remaining pipe sizes containing CRC at Hope Creek, were being prepared for a similar demonstration and NRC Region I would be notified when the samples were available.

No violations were identified.

5.

Data Review The inspector reviewed data associated with the following 12" diameter recirculation system welds:

Ultrasonic Examination 1-BB-12VCA-013F-2,

=

1-BB-12VCA-013H-2, a

,

l 1-BB-12VCA-013H-2LU,

=

1-BB-12VCA-014D-4LD.

=

1-BB-12VCA-013H-2LU

=

1-BB-12VCA-013J-4

1-BB-12VCA-013F-1LD

=

1-BB-12VCA-0140-4LD

=

pr

.

.

.

The review was done to ascertain that findings were properly recorded and evaluated, and that ASME Code and regulatory requirements were met.

.

The inspector found that the records were complete and that indications were properly recorded and dispositioned.

No violations were identified.

6.

Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on June 14, 1985.

The inspector summarized the purpose and the scope of the inspection and the findings.

At no time during this inspection was written material provided by the inspector to the licensee.

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000354/1985028&oldid=4239597"