IR 05000369/1978044
| ML19276E620 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/09/1979 |
| From: | Ang W, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19276E602 | List: |
| References | |
| 50-369-78-44, 50-370-78-18, NUDOCS 7903200069 | |
| Download: ML19276E620 (4) | |
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Report Nos.: 50-369/78-44 and 50-370/78-18 Docket Nos.: 50-369 and 50-370 License Nos.: CPPR-83 and CPPR-84 Category: A3/A2 Licensee: Duke Power Company P. O. box 2178 422 Church Street Charlotte, North Carolina 28242 Facility Name: McGuire Nuclear Station, Units 1 and 2 Inspectica at:
Lake Norman, North Carolina Inspection conducted-December 27-29, 1978 Inspector:
W. P. Ang
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Reviewed by b
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J. C. Bryant,' Chief
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1)a te Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on December 27-29, 1978 (Report Nos. 50-369/78-44 and 50-370/78-18)
Areas Inspected:
Safety-related pipe support and restraint systems (Units 1 and 2); reactor vessel internals records (Unit 1); radio-graphic film reading (Unit 2); housekeeping and general work practices (Units 1 and 2).
The inspection involved 16 inspector hours on site by one NRC inspector.
Results: Of the six areas inspected, no apparent items of noncompliance were identified in five areas; one apparent item of noncompliance was found in one area (Infraction - Failure to follow procedure for coated electrode weld rod control).
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RII Rpt. Nos. 50-369/78-44
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and 50-370/78-18 I-l DETAILS I Prepared by:
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W P. Ang, MecIlasical Engid ?er
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Engineering Support SectiorI No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection: December 27-29, 1978 Reviewedby:hkf,_
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'!7!77 J. C.~ B'rjanCf Chief g
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Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
Duke Power Company (DPC)
- G.
Grier, Construction Project Engineer
- W. Henry, Construction QA Manager
- E.
Miller, Construction Project Senior QA Engineer
- H. Wallace, Construction Mechanical Engineer
- H. Burriss, Construction General Superintendent
- G. Robinson, Construction Mechanical QA Engineer b.
Westinghouse (W)
- J. Elmendorf, Site Manager
- Denotes those present at the exit interview.
2.
Licensee Actions on Previous Inspection Findings Licensee actions on previous inspection findings were not reviewed during this inspection.
3.
Unresolved Items No unresolved items were identified during this inspection.
4.
Independent Inspection Effort (Units 1 and 2)
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A walk-through inspection of the reactor buildings and auxiliary building was performed. General work activities and housekeeping were observed.
In the Unit 2 reactor building the inspector found three
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s RII Rpt. Nos. 50-369/78-44 and 50-370/78-18 I-2 E7018 coated weld rods on an "I" beam. The inspector observed several more in trash cans. A welding foreman indicated that E7018 weld rods should not be left laying around.
He implied however that it was acceptable to throw them into the trash can. DPC QAP H-3 Rev. 9 and QAM Section H-3 Paragraph 5.7.1 states in part that ".
If all the
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welding material is not used in the time alloted in Table 1, the remaining material and corresponding H-3B forms shall be returned to the issue station." Table 1 requires E7018 to be returned to the issue station after 41/2 hours maximum exposure. This appears to be in noncompliance with 10 CFR 50 Appendix B Criterion V as implemented by DPC Topical Report Duke 1-A, Section 17, Paragraph 17.1.5.
This item is therefore identified as an infraction -Failure to follow procedure (50-370/78-18-01).
Radiographic film reading for Unit 2 reactor bottom mounted instrumentation tube welds was observed. DPC QA NDE program procedure NDE-10 Rev. I and Technique Number 9-3-A Rev. 2 were reviewed to determine compliance of work with the procedure and to determine compliance with W specification 82127JM. DPC construction Procedure 161 Rev. 6 was also reviewed.
Current qualifications of the non-destructive examiner was also reviewed. Within the area inspected, no items of noncompliance or deviations were identified.
5.
Safety-Related Pipe Support and Restraint Systems - Units 1 and 2 This is a follow-on inspection of that reported in RII Report Nos. 50-369/78-40 and 50-370/78-17.
The status of the open nonconformance item report number 6273 was reviewed and corrective action being taken by the licensee was inspected.
The licensee indicated that new procedures were to be prepared for the installation and inspection of hydraulic snubbers.
Site engineers, however, are still consulting with vendors and studying various alternatives to assure proper installation and inspection of the hydraulic snubbers.
No items of noncompliance or deviations were identified.
6.
Reactor Vessel Internals - Review of Quality Records - Unit I t
Pertinent quality records relevant to handling, installation and post installation protection of the reactor vessel internals were reviewed to confirm that the installation and inspection was in accordance with
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h RII Rpt. Nos. 50-369/78-44 and 50-370/78-18 I-3 specifications and procedures.
The following specifications and records were reviewed:
A.
y specification 616A407 Sub 6 - Reactor Internals Assembly B.
y specification status list (Follower) F37336 for McGuire 1 C.
E Drawing 1098E21 - (DAP) Vibration Check-Out Functional Test Inspection Data D.
DPC QA Surveillance Form 300B's for April 12, 1977 to August 26, 1977, July 5, 6,
7 and 8, 1978 and July 12 and 13, 1978 -
Regarding Reactor Vessel Internals Assembly and Installation E.
Form P-3A - Inside Reactor Building Storage and Maintenance Inspection from March 3,1976 to July 15, 1978 F.
DPC Form L72A - Housekeeping Zone Designating Sheets, Serial Nos.
007,19, 22, 23 and 25 G.
DPC Form M2BA Housekeeping Zone Inspection Report Serial Nos.
007,19, 22, 23 and 25 H.
DPC Form L-72B's - Personnel and Materials Log Sheets - Serial Nos.19 and 22 The reactor vessel internals and head had been assembled and installed for hot functional tests at the time of the inspection. No items of noncompliance or deviations were identified.
7.
Exit Interview A meeting with the licensee representatives denoted in Paragraph I was held at the end of the inspection to discuss the results of the inspection.
Items discussed included the Unit I reactor vessel internals records, Units 1 and 2 safety-related pipe support and restraint systems, radiographic film reading of Unit 2 reactor vessel bottom mounted instrumentation tube welds, and the observation of housekeeping and general work practices in Units 1 and 2.
The weld rod control inf raction for failure to follow procedure was also discussed.
The licensee acknowledged these findings.
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