IR 05000416/1979020
| ML19254E945 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/25/1979 |
| From: | Bryant J, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19254E939 | List: |
| References | |
| 50-416-79-20, 50-417-79-20, NUDOCS 7911050088 | |
| Download: ML19254E945 (4) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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E REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 o
g AILANTA, GEORGIA 3o3o3
Report Nos. 500-416/79-20 and 50-417/79-20 Licensee: Mississippi Power and Light Company Jackson, Mississippi Facility Namc: Grand Gulf Un: ts 1&2 Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Grand if sit ar Port Gibson, Mississippi f -M M Inspected
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Approved By:
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J. C. Bryant, Section. thief, RCES Branch D6(e Si/gned SUMMARY Inspection on September 12-13, 1979.
Areas Inspected This routine, unannounced inspection involved 14 inspector-hours onsite in the areas of construction progress, review of design and engineering effort status, procurement activities, craft work force review anti warehousing.
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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s DETAILS 1.
Persons Contacted Licensee Employees
- J. Fuller, Acting QA Field Supervisor
- D. Little, QA Representative
- W. Finch, Construction Representative
- B. Lee, QA Representative Other licensee employees contacted included construction craftsmen, and office personnel.
Other Organizations
- J. Yelverton, Bechtel QA Engineer
- P. Collins, Bechtel QA Engineer
- R. Valdez, Bechtel QA Engineer
- C. Torell, Bechtel Project Superintendent
- Attended exit intervie
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Exit Interview The inspection scope and findings were summarized on September 13, 1979 with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item No.416/417/79-13-04, Housekeeping.
The licensee's program to correct the trash and litter problem both inside and outside the containment continues to be effective. For the most part, trash cans are being utilized by the workers and a definite trend toward neater working areas was observed by the inspector.
In addition Bechtel has revised Job Bulletin No. 294, now identified as Job Bulletin No. 306.
This establishes the ESF Switchgear Building as zone IV cleanliness areas.
This action clarifies the requirements and resolves this item.
(Closed) Unresolved Item 416/417/79-13-02 H$ndlingofReactorVessel Internals The licensee has pursued this item with Bechtel and General Electric to assure that procedures and requirements for handling the internals are being followed. The inspector reviewed the licensee's findings concerning handling of stainless steel parts and subsequent cleaning of them. The inspector has no further questions regarding this matter.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Compliance with ASME Certification System Requirements The inspector verified that the licensee has established an organization for construction of the Grand Gulf nuclear plant that satisfies ASME Sec-tion III, Article NA-3000 requirements. The effective ASME Code at Grand Gulf is the 74 code, summer 74 edition. The licensee has provided for the Bechtel constructor organization to assume the responsibilities and duties of the certificate holders defined in Article NA 3000,Section III.
Bechtel's ASME Certificates, NA, N-881-5, effective until 11-18-80 and NPT, N-882-5 effective until 11-18-80 were examined by the inspector and found valid for the work activities being performed.
Since Bechtel does not perform any fabrication applications such as tailding vessels, tanks or other components on site, stamps other than NPT and NA are not required by NA-3000.
Bechtel, as a certificate holder, has been issued a site ex-tension from Grand Gulf via a survey conducted by the ASME survey team on August 16 - 18, 1976. No items of noncompliance or deviations were identified.
6.
Licensee Identified Items a.
(0 pen) 10 CFR 50.55(e) Item No. 416/417/79-20-01 Plastic disc holdcrs, ASCO valves. The licensee identified the subject item as a poten-tially reportable item on September 7, 1979. MP&L advised that ASCO supplied control solenoid valves with disc holders and/or other parts are fabricated from plastic. As discussed in IEB 79-01A these plastic parts have limited temperature and radiation applications.
The licensee is investigating and is to submit a written report by October 7, 1979.
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(0 pen) 10 CFR 50.55(e) Item NO. 416/417/79-20-02 NAMCO limit switch malfunction. This item was reported by MP&L on September 7, 1979.
NAMCO has identified that their Model EA 180 limit switch might malfunction at temperatures over 175*F. MP&L has determined that they have purchased this model switch both separately and as a part of Pcwell valve packages. MP&L is investigating and will submit a written report by Ocotober 7, 1979.
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(Closed) 10 CFR 50.55(e) Item No. 416/417/79-20-03 Tube Turns low carbon elbows. The licensee identified the subject item as poten-tially reportable on September 7, 1979. The MP&L report was based on a tube turns report to Bechtel which identified heat numbers W5558,
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W5559 and W5875 as possibly having an alloy grade of steel rather than material with the chemistry of ASTM A106, Grade B. However, MP&L has established that none of the questionable heat numberr have been supplied to the Grand Gulf Nuclear Plant. Therefore, a 50.55(e)
written report on this item is not required.
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(0 pen) 10 CFR 50.55(e), 416/417/79-20-04 Powell Valve Company computer code challenged. The licensee reported on September 4 and 5, 1979 that Bechtel is challenging the Powell Valves Company computer code which was used to determine seismic requirements adequacy. The licen-see is investigating the problem further and will submit.a written report by October 5,1979.
(0 pen) 10 CFR 50.55(e) 416/417/79-20-05 Rosemount trip units, inade-e.
quate power supply. The licensee advised the NRC on September 4 and 5, 1979 that the Rosemount Model 510 DW trip units are equipped with power packs that may not be adequate to operate the units. This item is being studied by the licensee and a written report is due October 5, 1979.
7.
Independent Inspection The inspector examined various areas of Units 1 and 2 to observe construc-tion work and related activities in progress, to inspect the general state of maintenance and to examine the inplace storage conditions of mechanical and electrical equipment.
No items of noncompliance or deviations were identified.
8.
IE Bulletins (Closed) IEB 79-11, Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems. The licensee reparted by a letter dated July 20, 1979 that the Grand Gulf Nuclear Station does not use the DB-75 and DB-50 type circuit breakers.
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