IR 05000302/1990010

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Insp Rept 50-302/90-10 on 900326-29.Violations Noted,But Not Cited Re Procedure RT-002,Rev 5 Not Having Correct Penetrameter Table for ASME Components.Major Areas Inspected:Radiographic Film for safety-related Piping Welds
ML20034A960
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/18/1990
From: Blake J, Coley J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20034A959 List:
References
50-302-90-10, NUDOCS 9004250134
Download: ML20034A960 (4)


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NUCLEAR REGULATORY COMMISSION.

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REGION 11

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101 MARIETTA STREET, N.W.

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ATLANTA, GEORGI A 30323

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Report No.:

50-302/90-10

.l Licensee: Florida Power. Corporation l

3201'34th Street, South St. Petersburg, FL 33733.

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L Docket No.:

50-302 License No.:

DPR-72

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Facility Name:

Crystal River 3

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L Inspection Conducted: March 26-29, 1990 Inspector:

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Approved by: a S

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ake, Chief Date Signed

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ter als and Processes Section ngi eering Branch

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i Division of Reactor Safety SUMMARY.

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Scope:

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This-routine, unannounced inspection was conducted in the area of review of radiographic film for safety-related piping. welds.

Results:

t The primary objective of this inspection was to examine inservice -inspection

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(ISI) work activities.

However, due to'a walk-out of Health Physics personnel at the Crystal River Facility, no ISI work was. performed during this

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inspection. The inspector therefore, concentrated the inspection effort on.the-review of radiographic film for safety related piping welds.

This area.

appeared to be technically adequate.

~ 0ne= weakness was. identified in.

Radiographic Procedure. RT-002, Revision 5, in that, ASME Section III ' was referenced as one of the codes applicable to this procedure.

However, review of this procedure revealed that it did not have the correct:penetrameter Table.

for ASME,Section III, Classes 1 or 2 components.

Failure to have a technically adequate procedure is a ' violation of 10 CFR 50 Appendix B,

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Criterion V.

However, this violation was not cited because criteria specified in Section V.A of the NRC Enforcement Policy were satisfied (See. paragraph 2).

I In the area inspected, one non-cited violation was identified, no deviations were identified.

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

  • J. Alberdi, Manager, Nuclear Plant Technical Support
  • J. Cooper, Jr., Superintendent, Nuclear-Technical Support
  • R. Hathorn, Material Technology Specialist-
  • J. Hicks, Supervisor, Material Technology-
  • P. McKee, Director, Nuclear Plant Operations
  • S. Robinson, Supervisor, Chemistry and. Radiation Control
  • W. Rossfield, Manager, Nuclear Compliance
  • R. Widell, Director, Nuclear Operations Site Support Other licensee employees contacted during this inspection included craftsmen, engineers,-security force members, technicians, and administra-i tive personnel.

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l NRC Resident Inspectors

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  • P. Holmes-Ray, Senior Resident Inspector
  • B. Bradford, Resident Inspector

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  • Attended exit interview I

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Review of Radiographic Film (57090).

  • The inspector reviewed. radiographs, associated records, and radiographic procedures for all safety-related piping welds performed since the-

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beginning of the 1987 outage.

The radiographs were. reviewed to determine l

whether they were prepared, evaluated, and maintained in accordance with applicable licensee commitments and code requirements.

In addition, this review was conducted to determine the quality of welding.at the Crystal River facility. Welding skills appear.to have generically decrease in the i

nuclear industry because of the infrequent need to perform safety related

piping welding.

The applicable code for this review was ANSI B31.7, i

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" Nuclear Power Piping," 1969 Edition.

Radiographic film packages-for the welds listed below were reviewed:

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Mat'1 Technology Weld _ Number System / Component Lab. RPT.No.

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SW-287 Letdown Cooler Service Water MTL 87-046 MV-85-229 Letdown Cooler Make-up MTL 87-045

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MV-85-231 Letdown Cooler Make-up MTL 87-061 MV-85-228 Letdown Cooler Make-up MTL 87-068

MV-85-226 Letdown Cooler Make-up MTL 87-066 l

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Mat'1_ Technology

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Weld Number System / Component Lab. RPT.No.

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MV-85-225 Letdown Cooler Make-up MTL 87-067 i

SW-85-251 Service Water MTL 87-051

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MV-85-232 Letdown Cooler MTL 87-059 MV-85-280-Letdown Cooler Make-up MTL 87-065 i

SW-279 Letdown Cooler Service Water -

MTL 87-049 r

SW-316 Letdown, Cooler Service Water MTL 87-044 SW-275 Letdown Cooler Service Water MTL 87-049 SW-274 Letdown Cooler Service Water

'MTL 87-041-t SW-310 Letdown Cooler Service Water MTL 87-043 SW-339 Letdown Cooler Service Water MTL 87-050

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SW-308 Letdown Cooler Service Water MTL 87-042

SF-85-2 Spent Fuel MTL 87-060

SF-85-4 Spent Fuel MTL 87-037-l FW-85-73 Feedwater MTL 87-064

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RW-85-352 Raw Water MTL 87-052-

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FW-85-72 Feedwater MTL 87-057~

The inspector reviewed radiographs for the above welds to determine if the following parameters were satisfactory:

film quality, film density; proper identification, adequate geometrical sharpness, correct

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penetrameters used and that the evaluation and disposition of. the radiographic results were satisfactory.

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During the review of Florida Power Corporation (FPC) radiographic _

procedures, the inspector noted that Procedure No. RT-002 Revision 5 was applicable to ASME Section III (1983 Edition) work.

However, this procedure did not have the correct penetrameter tables for radiography of-ASME Classes 1 and 2 welds.

FPC's level III examiner was notified of the-

inadequate procedure; however, discussions with this individual revealed -

that the procedure had never been used for ASME-Section III work.

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' safety-related welds at Crystal River have been welded and radiographed in accordance with ANSI B31.7.

The level III examiner committed to revise the procedure to include the correct penetrameter table, since the procedure was available for use if needed.

Failure of procedures to be technically accurate is a violation of 10 CFR 50 Appendix B, Criterion V and will be identified as violation 50-302/90-01-01,- Failure of Radiographic Procedure RT-002 Rev. 5 to Invoke Adequate ASME Section III Requirements.

However,.this NRC identified violation is not being cited because criteria specified in Section V.A of the NRC Enforcement Policy were satisfied.

i Within the areas examined, only one non-cited violation was reported. No

l deviations were identifie.

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Exit Interview The inspectio' n scope and, results were summarized on March 29, 1990, with those persons indicated in paragraph 1.

The inspector described the areas inspected and discussed in detail the inspection results listed below. -

Proprietary information is not contained in this report.

Dissenting-comments were not received from the licensee.

(0 pen) Non-Cited. Violation, 50-302/90-10-01, Failure of Rediographic Procedure RT-002 Revision 5 to Invoke Adequate ASME Section 111 Requirements, paragraph 2.

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