IR 05000321/1980007
| ML19305E547 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/02/1980 |
| From: | Compton R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305E538 | List: |
| References | |
| 50-321-80-07, 50-321-80-7, 50-366-80-07, 50-366-80-7, NUDOCS 8005200041 | |
| Download: ML19305E547 (4) | |
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UNITED STATES o
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g NUCLEAR REGULATORY COMMISSION J
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o 101 MARIETTA ST., N.W., SUITE 3100 g
ATLANTA, G EORGIA 30303
APR 7 '8 80 Report Nos. 50-321/80-07 and 50-366/80-07 Licensee: Georgia Power Company
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270 Peachtree Street Atlanta, GA 30303 s
Facility Name: Hatch
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l Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at Hatch site near Baxley, Georgia
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Inspector L,,
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'Da'te Signed Approved by:
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[J A. R. Herdt, Section Chief, RCES Branch
' Date Signed SUMMARY Inspection on March 11-14, 1980 Areas Inspected This routine, announced inspection involved 26 inspector-hours on site in the areas of IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems" and licensee action on previous inspection findings.
Recults Of the two areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- M. Manry, Plant Manager
- C. R. Miles, Jr., QA Field Supervisor
- D. A. McCusker, QC Supervisor l
- W. R. Glisson, Lenior Plant Engineer
- W. Nettleton, Associate Engineer
- J. D. Peregox QA Field Representative
- J. T. Yaun, QC Specialist Other Organizations A. J. Ciccone, Plant Design Supervisor - Bechtel NRC Resident Inspector
- R. F. Rogers
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 14, 1980 with those persens indicated in Paragraph 1 above.
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Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item 321/79-07-01 and 366/79-08-01, Concrete removed from expansion anchor stress cones. Unit 1 pipe support E11-RHRH-306 was noted in NRC reports 50-321/79-31, 50-366/79-35 as an example where concrete had been removed from the stress cones of expansion anchors. Although this condition had not been documented on the concrete integrity inspection data sheet, an as-built sketch of the installation was prepared and forwarded to Bechtel Power Corporation for evaluation. A letter from Bechtel to GPC dated January 25, 1980 stated that analysis had shown the as-built condition of this support to be acceptable. During the course of this inspection two additional supports were noted to have similar conditions.
The removed concrete near these supports had been documented on the concrete integrity inspection data sheets.
A QA Department Surveillance in November 1979 identified two other penetrations / supports where removal of concrete had been properly documented.
This item remains open pending a review of the Bechtel analysis of the supports discussed above during a future inspection.
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-2-(Closed) Infraction 321/79-31-01, Failure to follow IEB 79-14 piping surveil-lance procedure.
GPC letter of response dated December 14, 1979 has been reviewed and determined to be acceptable by Region II.
The report of QA audit 79-SA-12, conducted October 24 - November 17, 1979, which confirmed that the initial surveillance was inadequate, was examined. Revised surveil-lance procedure HNP-1-10124, Revision 3, was reviewed for conformance to requirements and complete coverage of Bulletin 79-14 items.
The remainder of the resurveillance has been contracted to Bechtel Power Corporation which is using EDS Nuclear Corporation personnel for the inspec-tion teams. The qualifications of new team members, training memos and course outlines were examined and discussed with cognizant licensee personnel.
A surveillance team working in the field was observed to be taking detailed and accurate measurements.
The original and the latest surveillance markups and checklists for packages T46-101 and E11-114 were compared for completeness and the type and extent of differences. The inspector also reviewed seven QC Inspection and Test Reports dated between January 31 and February 18, 1980 documenting QC's random check of the resurveillance field work and documentation.
Based on the examination of the licensee's response, the revised site procedure, QA/QC records and observations of field activities, this item is considered closed.
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Unresolved Items Unresolved items were not identified during this inspection.
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(Open) IE Bulletin Number 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems," Units 1 & 2 As of March 6, 1980, 774 of 1367 accessible supports / restraints had been inspected and approved by the surveillance coordinator (57% of the accessibles, 36% of the total 2156 supports / restraints). Approximately one-half of these had been forwarded to Bechtel for analysis, but no analysis had been performed, i
The inspector selected the follosing four Unit 1 piping runs and compared the as-built piping and support configurations with the marked up drawings completed by the. esurveillance teams:
Isometric E11-110, Revision G.6" RHR Discharge to Torus Spray Header.
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Support location shown on Revision D.
Supports H48A, H85, H86, H87, H88, H89 and H249 b.
Isometric PS2-F-108, Revision 3.3" Instrument Air.S ;pports H192A, J192B, H227A and H227B Isometric P42-100, Revision C.4" Reactor Building Closed Cooling Water c.
Supply and Return in the Drywell. Supports H13, H14, HIS and H16
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Isometric T48-102, Revision C.18" Reactor Building Drywell and Torus Purge. Supports H14, HIS, H46, H5I, H52, H53 and H54 The inspector selected the following nine piping runs in Unit 2 for comparison of the as-built condition to the markups from the construction surveillance program performed in 1977 and 1978:
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Isometric 2E21-100, Revision F, 14" and 20" Core Spray-Pump Suction a.
from Torus and Condensate Storage Tank.
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Side "A" - From data point 5 to data point 135} Supports A26, H1, H2,
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H3, H4, R35, R36, R37, R38, R39, R40 and H108 Side "B" - From data point 5 to data point 135; Supports A78, H79,
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R80, R81, R82, HS3, R84, R85, H86, R87, H88, R109 and R110 b.
Isometric 2E11-105, Revision G.18" RHR Service Water Return from RHR Heat Exchanger Side "A" - Supports H1, R13, R14, RIS, R16 and R17 Side "B" - Supports H7, R21, R22, R23, R24, and R25 Isometric 2B21-108, Revision F.24" Hain Steam line "C".
Supports H3, c.
H9, R39, R41, R42, R43 and R44 d.
Isometric 2E51-100, Revision G.
Reactor Core Isolation Cooling 4"line from data point 238 (torus) to data point 115.
Supports H218, H220, and R311 4" and 6" line from data point 115 to data point 300.
Supports H209, HR210, A36, HR211, H212, R309, HR213, HR214, R310, H215, H216 and A61 6" line from data point 110 to data point 205.
Supports A21, HR20, HR19, HR18, H17 and HR16 f
Isometric 2P41-102, Revision C.8" Plant Service Water at Chiller-e.
Units.
From data point 265 to chiller units.
Supports HR266, HR267, R299, H268, R298, H269 and R300 From data point 5 to data point 85.
Supports HR264, H265 and R301 No siguificant discrepancies were identified other than support modifications resulting from IE Bulletin 79-02 (concrete expannion anchor modifications)
which were properly documented.
No deviations or items of noncompliance were identified.
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