ML20235M517

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Insp Rept 50-285/89-08 on 890206-10.Violations Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings
ML20235M517
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/17/1989
From: Barnes I, Gilbert L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20235M500 List:
References
50-285-89-08, 50-285-89-8, NUDOCS 8902280287
Download: ML20235M517 (4)


See also: IR 05000285/1989008

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APPENDIX B

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. - U.S. NUCLEAR REGULATORY-COMMISSION

REGION IV

NRCInspeciion' Report:!'50-285/89-08 Operating License: DPR-40

Docket: 50-285

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Licensee:-.0maha Public Power District (0 PPD).

'FacilityName:'.FortCalhounStation(FCS)

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Inspection At: . FCS, Blair, Nebraska

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Inspection Conducted: February 6-10, 1989

Inspector: 8e 1[<  :://7/n

L. D. . Gilbert, Reactor Inspector,. Materials Date

and Quality Programs Section, Division of

Reactor Safety

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Approved:. be M'// Pet

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I. Barnes, chief, Materials and Quality . .

Programs Section, Division of Reactor Safety

Inspectiott, Summary

Inspection' Conducted February 6-10, 1989 (Report 50-785/89-08)

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~ Areas Inspected:. Routine, unannounced inspection of licensee's action on

previous inspection findings.

Theinspection'confirmedthatappropriatecorrectiveactions'(i.e.,

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Results:1 'l

reradiography) had been taken to resolve prior inspection findings concerning l

the~ radiographic examination of the emergency feedwater storage tank by j

Professional Services Inc. The inspection identified, however, that i

additional noncompliance with ASME Code requirements had been noted during

review'of other radiographs produced by.this contractor with respect-to welds

in safety-related modifications. No corrective actions had been taken in.

response to these nonconformances. The licensee had also previously informed a

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the NRC'that review of 1987 modifications had found that radiographs and

techniques used were of acceptable quality. Two violations were identified

.(paragraph 2) as-a result of the failure to take corrective action and the

providing of inaccurate information to the NRC. l

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DETAILS

1. Persons Contacted

OPPD

  • J.' H. MacKinnon, Acting Division Manager, Nuclear Operations

W. G. Gates, Plant Manager

  • T. J. McIver, Manager, Nuclear Projects
  • D. W. Dale, Supervisor, Quality Control (QC)
  • D. J. Matthews, Supervisor, Nuclear Licensing
  • R. Kellogg, Supervisor, Special Services
  • A. W. Richard, Manager, Quelity Assurance (QA)
  • R. L. Jaworski, Manager, Station Engineering

J. L. Dyer, Senior Quality Control Inspector

C. Bloyd, Lead, Special Services Engineer

Hartford Steam Boiler Inspection and Insurance Company

J. Tetreault. Authorized Nuclear Inspector

NRC

  • P. Harrell, Senior Resident Inspector
  • R. P. Mullikin, Project Engineer

The NRC inspector also interviewed other licensee employees during the

inspection.

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  • Denotes attendance at exit interview conducted on February 10, 1989.

2. Followup of Previously Identified Items

a. Unresolved Item (92701)-

(Closed)UnresolvedItem 285/88?9-01: Radio

the emergency feedwater storage tank is (EFWST)

considered graphic

an examination o

unresolved item pending acceptable radiographs and NRC review after

the EFWST has been repaired and reradiographed 100 percent. The NRC

inspector selected four welds from the EFWST for review following

repair and 100 percent reradiography of the EFWST welds by EBASCO.

The radiographs showed evidence of repair and were of acceptable

quality including radiographic technique. This item is resolved. 1

b. Deviations (92702)

(Closed)DeviationP85/8831-01: Failure to meet commitments to

provide an engineering guide for the preparation of welding

procedures. An engineering guide for preparing welding procedure

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. specifications has been prepared which was issued on

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October 26, 1988, as Civil Engineering Instruction'(CEI) 6..

Selected engineering, QC and nuclear production personnel were

trained on the guidance. .The OPPD tracking ' system for action 1

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e tracking of commitments to the Commission was reviewed by the NRC

inspector. The tracking system action overdue dates were discussed

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with plant and corporate licensing personnel.to. assure that the

L commitments to NRC had been met. The licensing personnel confirmed

that the commitments to NRC had been completed and the system was

being used to track internal actions due OPPD Nuclear Licensing as a

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followup to the NRC commitment. This item is closed.

'(Closed) Deviation-785/8831-0$:.Failuretomeetcommitmentsto

reradiograph the repair welds made to the EFWST. The licensee

contracted EBASCO to review the radiographs produced by Professional

Services Incorporated (PSI) 'for all the safety related modifications

installed during the 1983, 1984, 1985 and'1987 outages.' The EBASCO

review identified problems with both acceptability'of radiographer

areas and compliance of radiographs to the Code. These problems

related to radiographic examination,of the repairs to the EFWST ' welds ,

as well as other radiographic examinations performed by PSI on the .l

pressurizer spray piping during the.1987 refueling outage. The

results of the EUASCO review was included in a Operations Support

o ' Analysis Report (0SAR) No. 88-53 which was an analysis to determine

-if the radiographic examination technique employed by PSI at the Fort

Calhoun Station.could create a substantial safety. hazard. The

engineering analysis concluded that the radiographic examinations

which did not meet Code requirements would not create a substantial.

safety hazard. The engineering ' analysis stated that reradiography of

the EFWST should be perfonned in order to. address the numerous

concerns identified with the tank. . The NRC inspector selected.four

welds from the EFWST for review following repair and'100 percent

reradiography. The welds selected-included a longitudinal ' seam weld,

a circumferential' seam weld, and two nozzle welds. The welds were

radiographer for 100 percent of the length by EBASCO and areas

repaired were reradiographed. Approximately.70 final radiographs

were reviewed and were consistent with the radiographic technique and

acceptance' criteria of ERASCO Procedure RT-2002 which incorporated

the radiographic examination requirements of ASME B&PV Code

Section III, Subsection ND5000, 1983' Edition through Summer 1984

Addenda. This item is closed.

However, the NRC inspector identified two concerns relating to the

generic review of radiography performed by PSI and the identification

of nonconforming radiographs of Code Class I welds in the pressurizer

spray piping system. i

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First, nonconforming conditions were identified by EBASCO in the

radiographic examination performed on the pressurizer spray piping as

stated in Operations Support Analysis Report (OSAR) No. 88-53 and

other radiography nonconforming conditions were identified by an l

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OPPD contract QC Level III engineer in a memorandum to Oc s'upervision

with copies to QA and Engineering. The engineering evaluation of the

nonconformances identified by ERASCO were determined to not be a

significant safety. hazard for continued operation with no'further

radiography required. However, the Code.of Federal Regulations j

requires that systems and components of pressurized water-cooled  !

nuclear power reactors must meet the requirements of the ASME-Boiler

and' Pressure Vessel. Code. The nonconforming conditions identified by

EBASCO and QC were not corrected to meet Code requirements or

documented in a nonconformance report as required by Standing Order

No..G-18. This is an apparent violation for failure to take

appropriate corrective action to correct nonconforming conditions.

(285/8908-01)

Second,.the licensee's response to NRC Inspection Report No. 88-31

'for Deviation 285/8831-02 stated that results of the review of

modifications installed in the 1987 outage showed that the radiographs

and techniques used were of acceptable' quality. However, as stated

above, the review by EBASCO and QC identified radiographs of welds in

the pressurizer spray piping that did not meet Code requirements for

technique and quality. This is an apparent violation for providing

the NRC with inaccurate information. (285/8908-02)

. 4. Exit Interview

An exit interview was conducted on February 10, 1989, with those personnel  !

denoted.in paragraph 1. At the exit interview, the NRC inspector informed '

the licensee that three previously identified inspection finding would be

closed, that the failure to provide appropriate corrective action and

nonconformance reports would be.an apparent violation, and that the

inaccurate information provided in a response to NRC would be discussed

further with NRC management. No'information was presented to the NRC

inspector that was identified by the licensee as proprietary.

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