IR 05000416/1979028
| ML19211D341 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/28/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19211D340 | List: |
| References | |
| 50-416-79-28, 50-417-79-27, NUDOCS 8001170578 | |
| Download: ML19211D341 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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-:E REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 (/
ATLANTA, GEORGIA 30303 o
F10V 2 91979 Report Nos. 50-416/79-23 and 50-417/79-27 Licensee: Mississippi Power and Light Company Jackson, Mississippi Facility Fame: Grand Gulf Nuclear Station Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Grand Gulf Site near Port Gibson, Mississippi
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Inspector:
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K, Lrowley Date bigned Approved by:
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7 /f A. M. Merdt, bection Chiel, MLtb Branch Da'te Sighed SUMMARY Inspection on October 31 - November 2, 1979 Areas Inspected This routine, unannounced inspection involved 21 inspector-hours onsite in the areas of reactor coolant piping and safety-related piping.
Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- C. K. McCoy, Site Manager
- T. E. Reeves, Jr., Manager of QA
- D. F. Mahoney, Acting QA Field Supervisor
- H. D. Morgan, Construction Supervisor
- S. F. Tanner, QA depresentative
- D. D. Little, QA Representative Other licensee employees contacted included construction craftsmen, technicians, security force members, and office personnel.
Other Organizations Bechtel Power Corporation (Bechtel)
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R. E. Dennis, Lead Piping Mechanica_ QC Engineer
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- Attended exit interview 2.
Exit interview The inspector met with licensee representatives noted in paragraph I at the conclusion of the inspection on November 2, 1979 and summarized the scope and findings of the inspection of reactor coolant pressure boundary piping and safety-related piping.
3.
Licensee Action on Previous Inspection Findings
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Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort (Unit 1)
The following areas of interest were examined by the inspector, a.
Walk-through Inspection A general walk-through inspection of Unit 1 (reactor building and auxiliary building) was made. Site housekeeping and general con-struction activities were observed and compared with the requirements 1764 033
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-2-of work plan / procedure WP/P-3, " Housekeeping for Nuclear Power Plants" and Quality Control Procedure QAP-9.2, " Housekeeping". During this inspection, garbage (sandwiches, candy wrappers, coke cans, fruit peelings, etc.) was observed on the floor in several areas in the auxiliary building.
These areas were pointed out to the licensee who immediately had the areas cleaned up.
b.
Safety-related pipe welding (Unit 1)
The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various stages of weld comple-tion. The applicable code for safety-related pipe welding is the ASME Boiler and Pressure Vessel Code,Section III, Subsections NC and ND, 1974 Edition with Addenda through the Summer of 1974. The following welds were observed in the stages indicated:
Weld Number ISO /Dwy. Number System Stage
M-1348B RHR Fill Passes
M-1350A LPCS Fitup
M-1350A LPCS Capping Weld identification and location, joint preparation and alignment, use of specified weld procedure, use of specified weld material, control of temperature, evidence of QC verification, physical appearance of weld and welder qualification, as applicable to the particular stage of each weld, were examined.
Within the areas inspected, no items of nonec=pliance or deviation were identified.
6.
Reactor Coolant Pressure Boundary Piping (Welding)-Observation of Work and Work Activities (Unit 1)
The inspector observed field welding of reactor coolant pressure boundary pipe as indicated below. The applicable code for this welding is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NB, 1974 Edition with Addenda through the Summer of 1974.
Observation of welding activities included weld identification / location, use of applicable weld procedure, evidence of welder qualification, tem-perature controls, use of specified weld material, use of specified purge, weld appearance, and evidence of welding variable checks.
a.
Fill - Pass Welding Weld Number ISO /Dwy. Number System Size
FSK-P-195-M001.0-C Recirc.
12"
FSK-P-195-M001.0-C Recircu.
12" l764 034
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b.
Filler Material Control During the inspection, welding areas were inspected for presence of uncontrolled filler material.
Within the areas inspected, no items of noncompliance or deviation were identified.
7.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Units 1 and 2)
The inspector observed non-welding work activities as indicated below for reactor coolant pressure boundary piping.
See paragraph 6 above for the applicable code for this work.
Observation of specific work activities were conducted to detecmine con-formance, where applicable, with inspection and/or work procedures, record keeping requirements, construction / installation specification requirements, use of specific materials, performance of prescribed NDE, and utilization of qualified inspection personnel.
The following activities were observed:
Activity Spool Number System Unit Handling and Protection During Installation G001-76;2977-G011 Recire.
Cutting Pipe For Fitup Q1E21-G002-8-11 LPCS
Storage Q1B21-G021-30-11 Nuclear Boiler 1 Storage Q1C11-G003-4-11 CDR Hydraulic 1 In-Process Fitup Q1E21-G002-8-11 LPCS
PT of Prep Q1E21-G002-8-11 LPCS
Storage Q2B21-G026-2-23 Nuclear Boiler 2 Storage Q2B21-G026-11-23 Nuclear Boiler 2 Storage Q2E21-G002-6-23 LPCS
Within the areas inspected, no items of noncompliance or deviation were identified.
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8.
. Reactor Coolant Pressure Boundary Piping - Review of Quality Records (Units 1 and 2)
The inspector reviewed non-welding work activity records for reactor coolant pressure boundary piping as indicated below.
See paragraoh 6 above for the applicable code.
a.
Records for the pipe spools listed below were reviewed in the areas of: material test reports including chemical analysis, physical characteristics, and nondestructive examination; vendor manufacturing records; NSSS Quality release forms; receiving inspection reports relative to physical damage and conformance to requirements; and nonconformance reports, as applicable to each spool.
Spool Number System Unit Q1B21-G026-2-11 Nuclear Boiler
Q1C11-G003-4-11 CRD Hydraulic
Q1B21-G021-30-11 Nuclear Boiler
Q1B33-G005-B-1 Recire.
Q2B21-G026-2-3 Nuclear Boiler
b.
Installation inspection records were reviewed for the following pipe spools:
Spool Number System Unit Q1B33-G008-A-1 Recire.
Q1B33-G009-B-1 Recirc.
The records reviewed included "Large Pipe Installation Card", "Large Pipe Inspection Record" and " Field Welding Check List" (reviewed to determine that welds were complete and signed off). During review of the "Large Pipe Inspection Record" for the above spools, the inspector noted that two items on the inspection checklist, " Surface Free of Injurious Defects" and " Cold Spring" were consistently marked N/A.
Review of the applicable procedures, QCI 9.1.5, " Piping Inspection Activities" and WP/P P-1, "Large Pipe and Small Pipe Work Plan and Inspection Records" revealed that requirements for performance and sign off of these two inspections, were not clearly defined. Dis-cussions with contractor personnel revealed that in practice (1) the N/A signoff for cold spring was being used to indicate that the par-ticular pipe being inspected was not fitup under cold sprung con-ditions and (2) the inspection for injurious defects was being per-formed on a surveillance basis during installation and not on every pipe. A 100% inspection would be performed after installation. At the time of the inspection, the contractor was in the process of 1764 036
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-S-revising QCI 9.1.5 and agreed to re-write requirements for the above two inspections to more clearly define the inspection and documentation requirements. The revised procedure will be reviewed on a subsequent inspection and this item will be identified as inspector followup item 416/79-28-01.
Within the areas inspected, no items of noncompliance or deviation were identified.
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