IR 05000530/1985016
| ML20127P716 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/10/1985 |
| From: | Miller L, Wagner W, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20127P701 | List: |
| References | |
| 50-530-85-16, NUDOCS 8507020494 | |
| Download: ML20127P716 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
-50-530/85-16 Docket No.
50-530 Construction Permit No.
CPPR-143 Licensee:
Arizona Nuclear Power Project P. O. Box 52034 Phoenix, Arizona 85072-2034 Facility Name:
Palo Verde Nuclear Generating Station - Unit 3 Inspection at:
Palo Verde Site, Wintersburg, Arizona Inspection conducted:
May 13-17 and 28-30, 1985 Inspector:
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d6 -d-8g W.
agner, Re clor Inspector Date Signed ~
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Approved By:
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Date Signed
. Young, Jr., Ch lf Engi eering Secti l
l0 f L.(/F. Mill
~Jr., Chief Date Signed Reactor P cts Section 2 Summary:
Inspection on May-13-17 and 28-30, 1985 (Report No. 50-530/85-16)
Areas Inspected: Routine unannounced inspection by a regional based inspector of activities associated with steel structures and supports, reactor coolant loop piping, other safety-related piping, and reactor vessel and internals documentation. The inspection involved 58 inspector-hours by one NRC inspector. During this inspection, Inspection Procedures 55154, 55156, 55158, 55173, 55175, 55177, 55178, 55183, 55185, 55186 and 50055 were covered.
Results: No violations of NRC requirements or deviations were identified.
8507020494 850610
$DR ADOCK 05000530 PDR
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Persons Contacted
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, s, Arizona Nuclear Power Pmject (Ah' P) (
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- D. B. Karner, Assistant Vice President, Nuclear Production
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- L. A. Souza, Assistant Corporatd Qi/QC Manager
-#*C. N. Russo, Manager, Quality Audids and Monitoring!
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- S. G. Penick, Quali.ty Ponitoring;Sthirvisor
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- J. C. Matteson, Transition QA/QC' Engineer
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- G. J. Pilicy, Nuclear' Engineer
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- J. L. Gross, Nuclear Construction Engineer
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- J. D. Bayless, Quality Assurance Engineer
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K. Daly, Qualit) Assurance Engineer
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.Bechtel Power Corporation (Bechtel)
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9*D. R. Hawkinson, Project QA Manager
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- T. L. Horst, Project Field Engineer
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- M. A. Rosen, QC Engineer ii
- J. L. Black, Resident Engine'er, 3 A.
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H. Mears, Assistant Project QC Engineer s D. T. Scribner, Resident Engind e, Civi,1/ Structural G. Stam, Lead Field Welding Eng? nee'e
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- Denotes those attending the exit int 2rview on May'17, 1985.
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- Denotes those attending the exitsinterview on May 30,l1985.
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2.
Steel Structures and Supports
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a.
Weld Heat Treatment
Preheating, when required by a weMing procedde, is performed to the requirements specified in General Welding Standard, GWS-FM, Revision 5 of August 19, 1977. This welddig standard specifies the acceptable preheating methods, the minimum preheat temperatures to be maintained during all welding, and reqv.iAments for verification of preheat temperatures. Postweld deat tceatment (PWHT), an operation frequently required >for tempering or stress relieving a welded assembly, is not requitdd for the type of structural steels utilized in fabrication of structures and, supports for Unit 3.
The Structural Welding Code, AWS' DL1 does not require PWHT unless the design drawings or specifications demand it.
b.
Special Welding Applications i
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A review of the Welding Nonconformance Report (NCR) Log revealed the following two NCRs as requiring-weld repairs. The reason for the e
low number of weld repairs is that potential', problems are identified and corrected (reworked) while the work is in process thus mitigating the chances for weld rejection aufsubsequent repairs.
NCR No. WY 1264 of March 4, 1985, identifiejd finear indications
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,(laminations) located on the inside of flange pipe support number 13NC-092-H013. Disposition called for removal of laminations by grinding, liquid penetrant examination and adding weld filler material utilizing weld procedure WPS No.-PI-A-Lh_(structural). NCR No. WG 1115 of" August 21, 1984, identified gouges on a base plate of a pipe support located.in the Diesel Generator Building. Repair called for blending the gauged area into the surrounding surface with a minimum taper of 3 to 1, QC inspection of blended area, followed by. welding to build-up the ground sections using WPS No. PI-A-Lh (structural). The welding' procedures used for these
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weld repairs were qualified in accordance with the AWS D1.1 Structural. Welding Code. The repair procedure included all the special requirements pertaining to pre-heat, base metal conditioning, welding with low hydrogen electrodes and observing applicable code requirements.
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Observation of Welding Activities Outside Containment Welding on steel structures and supports outside the containment building was completed prior to this inspection. No welding activities were in process during this-inspection nor were any scheduled. However, welding was observed and reported in NRC Report No. 50-530/82-08.
No violations' of NRC requirements or deviations were identified.
3.
Reactor Coolant Loop Piping; a.
Observation of Welding Activities
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Welding activities associated with the reactor coolant loop piping were completed prior to this. inspection.
Welding during installation was observed and. reported in NRC Report No.
50-530/82-15. However, the inspector visually examined ten of these welds and the welder's qualifications as discussed in Sections 3.c and 3.d of.this report.,
b.
Special' Welding Applications-
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Special welding applications such as weld repairs were not required to be performed on the reactor coolant loop piping since the weld quality was determined acceptable.
c.
Visual Examination of Welds The. inspector selected ten reactor coolant loop pipe welds for visual. examination. Drawing Number 13-P-ZCG-103, Revision 7,
" Containment Building Reactor Coolant Loops" was utilized to verify proper identification of the weld joints.
Although the weld face reinforcements had been ground smooth, in preparation for preservice and inservice inspections, the inspector was able to verify by visual examination that the following characteristics conformed to the applicable ASME Code and welding procedure requirements:
location, surface finish from grinding, absence of wall thinning,
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and presence of any surface defects that might be exposed resulting from the. grinding operation. The following is a description of the welds examined:
Line No.
Weld No.
WeldDiameter Weld Type RC-031 W-002 30" Pipe to Reactor Vessel Nozzle RC-032 W-001 42" Pipe to Reactor Vessel Nozzle RC-034 W-002 30" Pipe to Reactor Vessel Nozzle RC-093 W-002 30" Pipe to Reactor Vessel Nozzle RC-033 W-003 30" Pipe to Elbow RC-032 W-002 42" Pipe to Steam Generator Nozzle RC-031 W-001 30" Pipe to Reac. Coolant Pump Nozzle RC-073 W-003 30" Pipe to Elbow RC-073 W-004 30" Elbow to Reae. Coolant Pump Nozz.
RC-084 W-003 30" Pipe to Elbow Information contained on the weld joints included the weld number, the radiographic symbol and the welders' symbol. The inspector reviewed the Field Welding Check Lists (WR-5 Form) associated with the welds selected for examination. The WR-5's reviewed indicated that the required quality verificationc were performed for preheat, cleanliness, fit-up, qualified welders, interpass temperature, and visual examination of completed weld.
The records reviewed reflect adequate weld quality.
d.
Welder Qualification The qt.alification records for six of the welders involved in welding the reactor coolant loop piping welds examined during this inspection were reviewed. This review revealed that the welders were properly qualified, at the time welding was in process, to weld under the respective welding procedures.
No violations of NRC requirements or deviations were identified.
4.
Other Safety-Related Piping a.
Visual Examination of Completed Welds Ten completed field welds in piping outside the reactor coolant pressure boundary were selected for visual examination. This was for verification that the following items conformed to the applicable ASME Code and welding procedure requirements:
location, surface finish from grinding in preparation for inservice inspection, absence of wall thinning, and presence of any surface defects that might have been exposed from the grinding operation.
The following welds were examined:
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Line No.. Weld No.
Weld Diameter Weld Type SI-240 W-005 16" Pipe to Flange SI-203 W-001 12"
. Pipe to Valve SG-048 W-014 6"
Pipe to Valve SG-011 W-003 8"
Pipe to Valve AF-006 W-013 6"
Stainless Steel Pipe to Carbon Steel Tee CH-258 W-00L 2"
Pipe to Valve DG-004 W-WOO 2"
Pipe to Elbow PC-114 W-001 10" Pipe to Valve PC-116 W-300 8"
Pipe to Elbow CH-149 W-021 20" Pipe to Pipe The inspector reviewed the quality records for the ten completed field welds to determine that the records reflect adequate weld quality.
In all cases the WR-5 Form indicated quality verification for preheat,. cleanliness, fit-up, qualified welders, interpass temperature and visual examination of completed weld.
b.
Observation of Welding Activities All in process welding activities were completed prior to this inspection. Previous observations of safety-related pipe welding were reported in NRC Report Nos.- 50-530/81-09 and 50-530/84-08.
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c.
Weld Heat Treatment The,only safe'ty-related pipe weld's requiring post weld heat treatment (P.WHT) are the four steam generator nozzle to pipe welds.
The system and line numbers are SG-E-033, SG-E-036, SG-E-042 and SG-E-045.
The pipe diameters are 31.5 inches with a nominal wall thickness of 1.75 inches. The records associated with these heat treatments. indicated verification.from Quality Control and the Authorized Nuclear Inspector for (a) location of thermocouples, (b)
review of strip chart per PWHT criteria, and (c) calibration of the strip chart recorder and thermocouples. The inspector examined the strip chart and verified that the following ASME Code requireraents were complied with: maximum heatup rate above 800 F of 200*F per hour; PWHT temperature of 1125 F-1200 F, and a holding time at PWHT
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temperature of two hours. The heatup and cooldown rates and the total time at temperature were consistent with ASME Code requirements.
No violations of NRC requirements or deviations were identified.
5.
Reactor Vessel and Internals Record Review The inspection reviewed ten nonconformance reports (NCRs) generated as a results of inspections performed during equipment storage and installation. The NCRs reviewed were identified as BC-086, BC-103, NC-098, NC-139, NC-658, NC-797, NC-808, NC-1174, NC-1187 and NC-1619.
The NCR's were reviewed by the Resident Engineer and Quality Assurance; disposition and concurrence, when required, was by the Project Field c
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Engineer, Quality Assurance, Project Field Engineer, Authorized Nuclear Inspector, Project Engineer, and the Nuclear Group. The NCR's were legible, complete, retrievable, and included the status or resolution of the corrective action.
The following QC inspection personnel qualification records were reviewed and found to be complete and current: QC inspectors 19, 57, 82, 174 and 206. The records established that these individuals were adequately qualified for their assigned duties and responsibilities.
The Bechtel QA Group performed a number of surveillances to assure that the reactor vessel and internals were stored and installed consistent with NRC and ASME Code requirements. The following QA Surveillance Reports, including the area or ites inspected, were reviewed:
a.
Installation and Inspection of NSSS Components, " Storage Control" May 6, 1982.
b.
Installation and Inspection of NSSS Components, " Containment Building" May 26, 1982.
c.
NSSS Welding, June 28, 1982.
d.
Installation and Inspection of the Reactor, July 19, 1982.
e.
Installation of the Core Support Barrel Stand, January 28, 1983.
f.
Reactor Vessel Internals Alignment, August 18, 1983.
g.
Core Shroud Flatness Inspection and Rework, November 9, 1983.
h.
Reactor Vessel Lower Support and Core Shroud (Observation of Leveling Operations), April 17, 1978.
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Reactor Lower Support and Core Shroud. Witnessed Operation 70 consisting of lifting the lower support structure / core shroad and placing it into the core support barrel, April 18, 1984.
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Core Shroud Flatness Inspection and Rework, November 9,1983.
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Surveillance of the Disassembled Reactor Vessel, November 30, 1983.
=In addition, the inspector reviewed the Bechtel " Project QA Audit of CE Construction Services PVNGS Site Facility for Reactor Vessel Internals."
The purpose of this audit was to verify the implementation of CE's QA Field Manual and Subcontract FSC-81 (Reactor Vessel Internals Installation) of February 22-24, 1982.
The records reviewed indicated'that the deficiencies identified during these audit /surveillances were corrected. The corrective actions were such that repetition of the deficiency would be precluded.
No violations of NRC requirements aor deviations were identified.
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Exit Meeting The inspector met with licensee management representatives denoted in
paragraph 1 on May 17 and 30, 1985. The scope of the inspections and the inspector findings as noted in this report were discussed.
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