IR 05000338/1988030
| ML20155J454 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/07/1988 |
| From: | Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20155J446 | List: |
| References | |
| 50-338-88-30, 50-339-88-30, IEB-87-002, IEB-87-2, NUDOCS 8810260144 | |
| Download: ML20155J454 (6) | |
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.j NUCLEAR REGULATORY COMMISSION
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REGION 11
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ATLANTA. GEORGIA 30323 101 MARIETTA ST, N.W.
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Reports Nos.:
50-338/88-30 and 50-339/88-30 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-338 and 50-339 License Nos.: NPF-4 and NPF-7 Facility Name: North Anna l'and'2 Inspedtion Co a:
September 12-16,-1988
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Inspecto :
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os Date signed Approv d By:
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J. J/Blake, Chief Date Signed
M ty' rials Processes Section ngineering Branch Division of Reactor Safety Scope:
This routine, announced inspection was in the areas of requested
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actions on NRC bulletins, Temporary Instruction 2500/26, licensee action on previous enforcement matters and Inspector Followup Items (IFIs).
Results:
The licensee's response to the above mentioned items was indicative
of a concerted effort by management and plant supervision to resolve issues of a technical nature which could have impacted safety if lef t uncorrected No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees:
- M. L. Brownling, Jr., Assistant St> tion Manager L. Carter, Quality Specialist
- R. F. Droscoll, Manager Quality Assurance D. Fortin, Supervisor of Inservice Inspection (ISI), Programs R. Hurd, Lead Procurement Engineer
- M. R. Kansler, Superintendent Maintenance
- J. Leberstein, Licensing Engineer
- D. Quarz, Licensirg Coordinator
- J. E. Wroniewicz, Supervisor, Site Engineer Of fice
- C, A. Zalesiak, Senior Engineer, Engineering Mechanics, (SE0)
Other licensee employees contacted included QC/QA inspectors, engineers, security force members, technicians.
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NRC Resident Inspectors J. Caldwell, Senior Resident Inspector
- L. King, Resident Inspector
- Attended Exit Interview 2.
Unresolved Items Unresolved items were not identified during this inspection.
3.
Licensee Action on Previous Enforcement Matter (92702)
(Closed) Violation 338,339/87-12-01: Failure to Maintain Control of Safety-Related Materials The licensee's letter of response dated August 26, 1987, has been reviewed and determined acceptable by the Region II staff.
The inspector held discussions with the cognizant Senior Engineer and examined the corrective actions as stated in the letters of response.
The inspector concluded that the licensee had determined the full extent of the subject i
noncompliance, performed the necessary followup actions to correct the present conditions and developed the necessary corrective actions to
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preclude conditions of this problem. The corrective actions identified in
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the letters of response have been implemented.
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4.
Inspector Followup Items (IFI) and Unresolved Items (UNR), (92701)
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(Closed) UNR 338,339/87-18-01:
Specification for System and/or Component Cleanliness Following Maintenance This item was identified when the inspector noted that the licensee had not issued a procedure specification to outline specific cleanliness requirements following system / component maintenance.
On August 18, 1988, the licensee issued Maintenance Department Administration procedure, ADM 6.0 which addresses the area of concern.
b.
(Closed) IFI 338,339/85-37-01:
Review of Computer Aided Draf ting Program (CAD)
This item was identified because at the time of the inspection, documented in report 85-37, the inspector determined that isometric drawings used to develop the station's inservice inspection plan, did not necessarily reflect existing as-built plant conditions.
To correct the problem, the licensee contracted NUTECH to investigate the problem and develop a program for updating the ISI drawings as necessary.
Discussions with cognizant personnel disclosed the program was operational and drawings to support the upcoming Unit 2 refueling outage would be issued for use during the outage.
c.
(Closed) IFI 338/87-12-02:
Apparent Base Metal Indication, Hanger Weld Number SHP-R-305 This item was identified when a field inspection of Line 3"-SHP-531-601-02 found an apparent weld deposit on a pipe near Support 1-SHP-R-305.
The weld measured approximately 1/32"x3.'3"x3/4".
The licensee's report indicated tha+ the deposit had been ground almost flush to match the contour of the pipe, but could not state the specific reason for it (weld deposit) being there. The inspector
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reviewed Action Report, AR-N-87-256 and related engineering eva';uation/ documents issued to address this item and Feld discussions with the cogni.'. ant engineer, in charge of the investigation.
Following
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this work effort the inspector concluded that the action taken and
the results achieved were sufficient to close the item.
d.
(Closed) IFI 338,339/87-07-01:
Field Changes and Revision to DC 84-31 This item was identified to allow for a review of revisions to field
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drawings generated during the installations o
,he new service water spray array support system and to assure that field changes were included in the as-built control drawings By memorandum from J. E. Wroniewicz and M. L. Browling dated July 2,1987, the licensee
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pro /ided a status of the on going work effort and the target dates for completion of the revisions. Completed drawings were selected at random and reviewed to verify that subject field changes and revisions had been incorporated as appropriate.
5.
Followup on IE Bulletins (92703) (Units 1 and 2)
a.
(Closed) Temporary Instruction (TI) 2500/26, Inspection Requirements for NRC Compliance Bulletu 87-02, Fastener Testing Determine Conformance with Applicable Material Specifications.
prior to issue of NRC Bulletin 87-02, some NRC procurement inspections have included the collection and testing of a small sample of fasteners. This limited program was initiated in response to a concern by Industrial Fastener Institute over the potential use of inferior fasteners in military and industrial applications, including nuclear power plants. The results indicated that 11 out of 32 fasteners tested did not meet specification requirements for mechanical and/or chemical properties.
In a separate effort, one utility tested 1539 fasteners following discovery that commercial grade fasteners had been used in safety-related applications.
The test results indicated that 339 failed to meet specification requirements for mechanical and/or chemical properties.
Based on evaluations performed by the utility, the fasteners which did not meet specification would have fulfilled their safety function.
Based on the testing described above, the NRC issued NRC Bulletin 87-02 on November 6, 1987.
The Bulletin requested that licensees perform independent testing on a sample of fasteners and provide information to the NRC as follows:
Describe characteristic examined during Receipt Inspection (RI)
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of fasteners and controls of storage and issue.
Select ten safety-related and ten nonsafety-related fasteners
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from current stock and perform mechanical and chemical testing in accordance with specification requirements - the NRC is to
participate in selection of the fasteners for test.
Forward test results and supporting information to the NRC.
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For any fastener found out specification, provide an evaluation i
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of the safety significance.
Based on the results of the testing and review of current
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procedures, describe any further actions being taken to assure fasteners meet specification requirements.
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The licensee's letter of response is dated January 18, 1988.
Supplemental responses are dated February 29, and July 21, 1988.
In summary, the January 18, !988, submittal provided description of:
(a) characteristics currently examined during receipt inspection of fasteners; (b) internal controls utilized during storage and issuance of stock to assure the appropriate use of fasteners; (c) completed fastener testing data sheets, and (d) technical evaluations for the out-of-specification of fasteners requested by Item 6.
Juring the inspection, the inspector reviewed the licensee's procedures for control of fasteners and ccmpared the procedures with descriptions in the licensee's response; and reviewed the licensee's further action being taken as required by Paragraph 6 of the Bulletin.
Specifically, documents reviewed for this purpose included:
NAS-2094 Rev. O Specification for Pressure Boundary Threaded Fasteners ADM-8.0 Identification and Control of Materials, Parts, Components ADM-7.0 Control of Purchased Materials, Equipment and Service -
Receipt Place ADM-4.2 Repeating Purchase Requisitions ADM-13.0 Handlir.g Storage and Shipping SOP-8.12.8N Material Shipping / Receiving NDCM-4.1 Procurement
NASE 0-013 SE0 Review of Procurement Requisition Documents
- North Anna Power Station AR-N-38-5 Material Storage, Quality Control Activity Report In addition to the above, the inspector reviewed elements of the Sterekeeper Enhancement Training Program, discussed the procurement, receiving, storage and issu&nce program with the lead procurement engineer. A tour of the licensee's warehouse receiving, storage and plant storeroom facilities was conducted to accertain whether approved procedural requirements were being enforced.
Within the areas inspected, no violations or deviations were identifie.
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b.
(0 pen) 88-BU-02, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes On February 5, 1988, the Commission issued the subject bulletin requesting that licensees having Westinghouse designed nuclear power reacters with steam generators having carbon steel support plates implement certain specified actions to minimize the potential for a steam generator tube rupture event caused by a rapidly propagating crack such as that which occurred at North Anna Unit 1 on July 15, 1987.
The licensee's suomittal, dated March 24, 1988, referenced an earlier letter of the Commission on this subject, dated July 29, 1987.
The presen', submittal describes the current status of Unit 1 steam generator, and delineates those met.sures which have been taken to assure continued safe operation of the plant. With regards to the-
"Action Reque>ted" section of the subject bulletin, the licensee references applicable sections of Westinghouse publisaed WCAP-11601,
"North Anna Unit 1 Steam Generator Tube Rupture and Remedial Actions Technical Evaluation." With reference to Unit 2, the licensee's submittal states that steam generator tube fatigue evaluations have been performed and the results submitted to the Commission for review. The subject of "Tube Dentiiig" discussed in the bulletin and the actions requested are addressed in the licensee's report entitled
"North Anna 2 Steam Generator Evaluation and Remedial Actions Report" which has also been submitted for review.
6.
Exit Interview The inspection scope and results were summarized on September 16, 1988, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection results listed below.
Although reviewed during this inspection, proprietary information is not contained in this report.
Proprietary information is not contained in this report. Dissenting comments were not received from the licensee.
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