IR 05000369/1986013
| ML20203B805 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/26/1986 |
| From: | Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20203B802 | List: |
| References | |
| 50-369-86-13, 50-370-86-13, IEB-79-13, IEB-82-02, IEB-82-2, NUDOCS 8607180295 | |
| Download: ML20203B805 (5) | |
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- j@ REcg UNITED STATES
. , 'o NUCLEAR REGULATORY COMMISSION " [ REGION 11 n $ j 101 MARIETTA STREET, N.W.
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's ATLANTA, GEORGI A 30323
o 9.....g Report Nos.: 50-369/86-13 and 50-370/86-13 , Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17 Facility Name: McGuire 1 and 2 i Inspection Conducted: May 27-30, 1986 [ Inspector: N.M hW ALrt, d
% ' N. Economo /
Date Signed l Approved by: f>h [[ J. J'. Blak(,' Faction Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine unannounced ins observing inservice inspection (ISI) pection was scheduled for the purpose of activities on safety-related components.
However, the presence of unexpectedly high airborne activity precluded the licensee from performing ISI work scheduled for this time.
Therefore, the inspector discussed the replacement of flow elements in the nuclear service water system, reviewed licensee actions on IE Bulletins, previous enforcement matters, and inspector identified items.
Results: No violations or deviations were identified.
a l 8607180295 860703 PDR ADOCK 05000369 O PDR ,
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REPORT DETAILS 1.
Persons Contacted
Licensee Employees
- T. McConnel, Station Manager, McGuire Nuclear Station (MNS)
- B. Travis, Operations Superintendent, MNS
- B. Hamilton, Superintendent, Technical Services
- N. McCraw, Compliance Engineer, MNS R. P. Ruth, Project Senior QA Engineer
- A. F. Batts, QA Engineer, MNS
- T. D. Troutman, ISI Coordinator C. B. Cheezem, QA Engineer, ISI
- N. Atherton, Compliance K. Ramsey, Mechnical Technician, Technical Support t
M. Clayton, Associate Engineer, MNS Other Organizations i Babcock and Wilcox, Special Products & Integrated Services (SPIF) R. Patterson, ISI Coordinator j.
NRC Resident Inspector I
- W. T. Orders, Senior Resident Inspector
- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on May 30, 1986, with those persons indicated in paragraph 1 above. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
! 3.
Licensee Action on Previous Enforcement Matters (92702)
a.
(Closed) Violation 369/80-18-02 Failure to Follow Welding Electrode Control Procedures.
The licensee's letter of response dated
September 5,1980, has been reviewed and determined acceptable by i . Region II.
The inspector held discussions'with the Technical Support ' Engineer and examined the corrective actions as stated in the letter of response. The inspector concluded that the licensee had determined the full extent of the subject noncompliance, performed the necessary ' followup actions to correct the present conditions, and developed the necessary corrective conditions. The corrective actions identified in i the letter of response have been implemented.
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' l b.
(Closed) Unresolved Item (URI) 370/83-38-01 Discrepancies-in Steam .l ! Generator Records.
This item was issued when a review of the steam ! Senerator modification packages No. NSM-MG-983 and NSM-MG-2-1167
disclosed 'that certain line items on Procedure GEN-25 had not been signed off as required.
In ' addition the inspector identified that the , control number of.certain liquid penetrant materials had been docu-l mented incorrectly on the vendor's NDE reports. On May 29, 1986, this inspector discussed the matter with the licensee's accountable engineer ! i for the modification who stated that he had reviewed the completed package and found the aforementioned discrepancies had been corrected.
Because it would have taken an undue amount of time to locate this i information on the microfilm the inspector decided to forgo verifica-tion and closed the item.
- i 4.
Unresolved Items Unresolved item were not identified during this inspection.
5.
InspectorFollowupItems(IFI)-(92701) (Closed) IFI 369/80-36-01 Disposition of PSI'Related Findings.
Reportable
indications identified by B&W during ISI. examinations are. dispositioned through the use of evaluation reports- (ERs).
The data is. reviewed,
evaluated and appropriate corrective action is prescribed.
These ERs are subsequently included in the licensee's ISI report for the applicable outage which is a permanent station record, subject to review by NRC. Because the '
l licensee is performing more of the required ISI examination, procedure ! QA-516 Evaluation of ISI Indications, is being issued to address more fully I this subject and assign specific responsibilities to designated personnel.
J l 6.
IE Bulletins (IEB) (92703B).
a.
(Closed) 79-BU-13 Cracking in Feedwater System Piping.
Radiographic examinations of the feedwater nozzle and pipe welds following hot
j functional testing required by IEB 19-13 were performed and the results - -j documented in IE Report 50-369/79-40.
As 'a followup to that work effort, the ' inspector reviewed radiographs of the below listed welds-i which were taken during the 1984 outage for Unit I and the 1985 outage " for Unit 2.
The inspector noted that the ' records contained a memo to file dated April 19, 1984, which referenced a memo from W. O. Parker to
j J. P. O'Reilly dated October 19, 1979. The memo stated that because of
nozzle geometry 1.e. section thickness changes and weld reinforcement, ' area coverage would be limited to 11" minimum on the elbow side of the
weld and 3/4" minimum on the nozzle side of the weld. The welds were- ' radiographed in accordance with procedure NDE-12A, Rev. 3.
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Unit - 1 Unit - 2 CAIF - 540 SG"A"-2CA2FW, 52-21 CA1F - 575 SG"B"-2CA2FW, 50-19 CA1F - 679 SG"C"- CAIF - 699 SG"D"-2CA2FW, 53-29 Although Unit 2 was not covered by IEB 79-13 these welds were examined by the licensee as a precautionary measure.
The inspector noted that the weld for SG "C" of Unit 2 had been magnetic particle inspected but not radiographed at this time.
This matter was discussed with the station's ISI coordinator who indicated that he was aware of it and that the weld would be radiographed in the near future.
b.
(Closed) 82-80-02 Degradation of Threaded Reactor Coolant Pressure Boundary of PWR Plants.
The work effort on this bulletin was documented in Report 369, 370/84-06.
The licensee's responses of August 2, 1982 and July 19, 1984, completed the reporting requirements as stated in the Bulletin.
As a final action on this Bulletin, the Inspector reviewed selected procedures issued by the licensee, to control the handling of threaded fasteners in safety related components, to inspect their condition and, monitor the service-life of-these items. Procedures and records reviewed were as follows: Procedures: MP/0/A/7150/59 - Disassembly, Inspection & Reassembly of Reactor Coolant Pump MP/0/A/7650/96 - Cleaning, Testing and Serializing of Threaded Fasteners MP/0/A/7150/39 - Reactor Coolant Pump Seal Removal and Replacement QCL-13 Rev. 3 - ISI Visual Examination VT-1 Records: Valve 2NC-1 Intake Flange Studs 1-3/8d VT-1 2NV275-FL-1 Nuts & Bolts VT-1 2NV14 Nuts & Bolts VT-1 This IEB is close _ . ..
7.
Nuclear Service Water Pumps - Installation Of New Flow Elements, Units 1 & 2 (62703) At the time of this inspection, fabrication of the replacement nuclear service water (RN) pump flow-element assemblies was complete. The licensee had installed those in lines / trains A and B of Unit 2 and the assembly on line A of Unit 1.
The replacement assemblies including the flow elements and ball valves for isolation, were fabricated from stainless steel material to minimize corrosion problems and improve service life.
Discussions with the accountable engineer disclosed the assemblies were calibrated prior to installation in order to assure accuracy in pump flow measurements.
The modification was performed under the following modification numbers.
MG - 1-1841 Rev. 0 Unit-1 Train "A" MG - 1-1841 Rev. 1 Unit-1 Train "B" MG-2-0636 Rev. 0 Unit-2 Train "A" MG-2-0636 Rev. 1 Unit-2 Train "B" A review of the licensee's safety evaluation report on Form 160.2 Rev. 3 dated Feburary 5,1986, stated that no unreviewed safety questions were involved or created by this modification.
Fabrication and inspection requirements i.e.
welding and nondestructive examinations (NDE) were governed by ANSI-831.7 Power Piping Code.
Line classification was designated as class C, QA condition 1.
Within these areas, the inspector observed subsections 1RN-751land 1RN-752 fabricated for modification MG-1-1841 Rev.1 under work request #951069.
Areas of specific interest included weld condition / appearance and identification of material, welder and weld number.
Also the inspector reviewed selected quality records including material _ certification, welder qualifications and fabrication control documents.
Within the areas inspected no violation or deviations we,re identified.
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