IR 05000416/1978023
| ML19263C657 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/12/1979 |
| From: | Conlon T, Crowley B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263C656 | List: |
| References | |
| 50-416-78-23, 50-417-78-23, NUDOCS 7902280448 | |
| Download: ML19263C657 (7) | |
Text
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UNITED ST ATES
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NUCLEAR REGULATORY COMMISSION REGION il p
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Report Nos.: 50-416/78-23 and 50-417/78-23 Docket Nos..
50-416 and 50-417 License Nos.:
CPPR-118 and CPPR-119 Categories: A2 and A2 Licensee: Mississippi Power and Light Company P. O. Box 1640 Jackson, Mississippi 39205 Facility Name:
Grand Gulf Nuclear Station, Units 1 and 2 Inspection at:
Grand Gulf, Mississippi Inspection conducted: December 27-29, 1978
/ L'!7 9 Inspector: /,E
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B. R. Crowley, Metallurgi@ l Engineer Date l
/ // : /b Approvedby:h.(,1/
,.,. fe Date T. E. Conlcrn, Chief [ RCESB, ESS-2 Inspection Summary Inspection on December 27-29, 1978 (Report Nos. 50-416/78-23 and 50-417/78-2 Areas Inspected: Routine, unannounced inspection on reactor coolant pressur boundary pipe welding activities and records (Unit 1); safety related pipe welding activities (Unit 1); containment welding records (Unit 2); and housekeeping. The inspection involved 23 inspector hours onsite by one hTC inspector.
Results:
No items of noncompliance or deviations were identified.
79D228 d
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-1-1.
Persons Contacted a.
Licensee Employees Mississippi Power and Light Company (MP&L)
G. E. Osborne, Nuclear Construction Supervisor
- S. F. Tanner, QA Representative
- J. C. Fuller, QA Representative b.
Other Organizations Bechtel Power Corporation (Bechtel)
- R. L. Scott, Project Quality Assurance Manager
- W. B. Phillips, Lead Welding Quality Control Engineer R. J. Alexander, Lead Field Welding Engineer J. M. Kelly, Assistant Lead Welding Quality Control Engineer D. L. Langan, Welding Quality Control Engineer
- T. W. Habermas, Project Field Engineer
M. N. Williams, Construction QA Auditor A. W. Hardy, Welding QA Supervisor In addition to the above, other Bechtel inspection and craft personnel were interviewed.
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (416/417/78-15-03):
Procedures for control of hydrostatic test water.
Bechtel specification 9645-M-204.0 has been revised (Rev. 18) to specify sampling of water used on stainless steel pipe prior to filling the system.
In addition, instructions have been issued to standardize the " test medium" description recorded on the hydrostatic test forms. The inspector has no further questions at this time.
(Closed) Inspector Follow-Up Item (416/417/78-15-01):
Control proce-dures for temporary attachments.
Work Plan procedure WP/P-W-101 has been revised (Rev. 0) to include the requirements of Bechtel Informatio Bulletin W-26.
The inspector has no further questions at this time.
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-2-3.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. An unresolved item identified during this inspection is discussed in paragraph 8.
4.
Exit Interview The inspection scope and findings were summarized on December 29, 1978, with those persons indicated by an asterisk in paragraph 1.
The unre-solved item of paragraph 8 was discussed and the licensee's contractor stated that this problem had been previously identified and that the welding procedures in question were under review and revision to correct the problem.
5.
Independent Inspectipn Effort The following areas of interest were reviewed by the inspector:
a.
Walk-Through Inspection A general walk-through inspection of Units 1 and 2 (reactor buildi and auxiliary building) was made.
Site housekeeping and general construction activities were observed and compared with the requir ments of Work Plan / Procedure WP/P-3, "lfousekeeping for Nuclear Power Plants" and Quality Control Procedure QAP-9.2, " Housekeeping'
b.
Containment (Structural Steel Welding) - Review of Quality Records (Unit 2)
The inspector reviewed the quality records described below relativ to containment liner welding to determine whether these records reflected work accomplishment consistent with NRC requirements and SAR commitments.
The applicable code for this welding is the ASMI Boiler and Pressure Vessel Code,Section III, Subsection NE, 1971 Edition with Addenda through the summer of 1973.
(1) The following completed weld records were reviewed in the areas of visual and dimensional inspections, weld history, preheat and interpass temperature, NDE, welder qualification and inspection qualification, as applicable to each veld:
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-3-Weld Number Dwg. Number Component B11/B12 R76, Rev. 2 Dome Plate 17-13 Girth R78, Rev. 1 Dome Dollar Plate B8/B9 R75, Rev. 1 Dome Plate (2) The following welding material records relative to receipt inspection, issue, and storage control were reviewed:
a)
" Welding Material Authorization And Release Report", //69, dated 11/2/78; and b)
" Daily Weld Material Distribution Log", dated 11/17/78, 11/20/78, 11/21/78, 11/22/78, and 11/27/78.
In the areas inspected, no items of noncompliance or deviations were identified.
6.
Safety Related Piping (Welding) - Observation of Work and Work Activities (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.
Observation of field welding activities included, as applicable to the welds listed below, the following areas: weld identification and location, joint preparation and alignment, specified weld procedure, welder qualifi-cation, specified weld material, specified temperature controls, welding variable checks, evidence of QC verification, physical appearance of veld, surface suitable for NDE and specified NDE being performed.
a.
Joint Fitup Joint Number ISO /Dwg. Number System
M-1349A QIE22 b.
Root Pass Joint Number ISO /Dwg. Number System
M-1349A QIE22
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Fill Pass - Pipe to Fitting Welds Joint Number ISO /Dwg. Number System
FSK-199-2034 QIB21
M-1348B QIE12(RER)
M-1348H QIE12(RHR)
d.
Welding Complete and Preparing Surface for NDE Joint Number ISO /Dwg. Number System
M-1349A QIE22
M-1336B QIE22 The auxiliary building weld caterial issue station was inspected.
e.
Storage of materials including identification, segregation, clean-liness, and temperature control were examined. Welding areas were examined for the pressure of uncontrolled welding materials.
In the areas inspected, no items of noncompliance or deviations were identified.
7.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities TUnit 1)
The inspector observed field welding of reactor coolant pressure boundary pipe welding at various stages of weld completion.
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 field welding activities included, as applicable to the weld listed below, the following areas:
weld identification and location, specified weld procedure, welder qualification, specified weld material, and physical appearance of weld.
a.
Fill Pass Welding - Pipe to Valve Joint Number ISO /Dwg. Number System Size
M-1349B QIE22 14" b.
The auxiliary building weld material issue station was inspected.
Storage of materials including identification, segregation, clean-liness, and temperature control were examined. Welding areas were examined for the presence of uncontrolled weldi,ng material.
-5-In the areas inspected, no items of noncompliance or deviations were identified.
8.
Reactor Coolant Pressure Boundary Piping (Welding) - Review of Quality Records (Unit 1)
The inspector reviewed the quality records described below relative to reactor coolant pressure boundary pipe welding to determine whether these records reflected work accomplishment consistent with NRC require-ments and SAR commitments.
See paragraph 7 above for the applicable welding code.
The following completed weld records were reviewed in the areas of:
a.
visual and dimensional inspections, weld history, preheat and interpass temperature, NDE, weld repair, welder qualificatisu, and inspector qualification, as applicable to each weld:
Weld Number ISO /Dwg. Number Pipe Size IR3 M-1328J 24"
M-1348T 12"
M-1328K 24" During review of the " Field Welding Check List" form WR-5 for the above welds the inspector noted that the interpass temperature requirement column was marked N/R. The applicable welding procedure for the three welds was PI-AT-LH (CVN), Rev. 1.
Review of this proce dure, which covers welding of carbon steel with notch toughness requirements, revealed that the procedure did not specify an inter-pass temperature.
By the 1974 and later Editions of Section IX to the ASME Code, it is clearly a requirement that interpass tempera-ture be covered in a welding procedure to be used on notch toughness materials.
However, by earlier Editions to Section IX (the proce-dure in quesiton was qualified in 1968 and 1969), requirements for procedure content are not as clearly defined. Qualifications to earlier Editions are acceptable per the preamble to Section IX.
When this problem was brought to the attention of the licensee, Bechtel stated that this problem had been identified at another Bechtel site and the procedure in question and one other affected procedure at the Grand Gulf site were being revised to specify an interpass temperature.
In addition, MP&L has initiated a review by Bechtel of all ASME procedures to ensure that all essential variable are covered (see D&CR No. 1097, Supp. 1, dated 6/29/78). This is considered unresolved pending completion of evaluation by the licens and is identified as item 416/417/78-23-01.
b.
The following welding material records relative to receipt inspection, issue, and storage control were reviewed:
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-6-(1) WR-6 forms for the welds listed in a. above.
(2) " Material Receiving Instruction and Inspection Record",
" Material Receiving Report", and " Certified Material Test Report" for the welding materials used in the welds listed in a. above.
(3) " Calibration Record of Rod Ovens" for oven serial numbers 24, 25, 26, 27, 28, 29, 30, 31, 33, 34, 35, 37, 41, 42, and 43 covering the dates the welds listed in a. above were welded.
(4) " Calibration Record of Portable Rod Warmers" for can numbers 86, 121, 60, 55, 28, 100, 18, 91, 8, 9, 99, 74, 78, 16, 21, 58, 59, 70, 79, 19, 57, 54, and 64 covering the dates the welds listed in a. above were welded.
In the areas inspected, no items of noncompliance or deviations were identified.
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