IR 05000528/1981023
| ML17297B164 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/18/1981 |
| From: | Bishop T, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17297B163 | List: |
| References | |
| 50-528-81-23, 50-529-81-16, 50-530-81-16, NUDOCS 8201130273 | |
| Download: ML17297B164 (12) | |
Text
U.S CLEAR REGULATORY COMMISSION OFFIC OF INSPECTION AND ENFORCEMENT 50-528/81-23 50-529/81-16 ort No.
REGION V
Docket No.
'0-530 Licensee:
License No.
Safeguards Group CPPR-142,CPPR-143 Faci,'l,ity Name:
Inspection at:
Inspection conducted:
C Inspectors:
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K. Uorderbrueggen Senior Resident Inspector Units 1, 2,
and
)2 /18/SI Date Signed Date Signed Aved By:
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W.. Bishop, Chief Reactor Projects Section
Summary:
Date Signed I< /is/8I Date Signed Ins ection on Se tember
October
1981 (Re ort Nos.
50-528/
81-23 50-529/81-16 and 50-530/81-16 Areas Ins ected:
Routine, unannounc'ed inspection by the resident inspector of construction activities associated with protection of installed reactor vessels-Units 1 and 2; reactor coolant pressure boundary and other safety related piping; containment liner welding; containment penetrations, main coolant pump supports; care and preservation of equipment; followup of licensee action on previous inspection findings; and general activities in progress at the plant site.
The inspection in-volved 52 inspector hours on-site by one NRC inspector.
a Results:
No items of noncompliance or deviations were identified.
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','"PDR ADOCK,QSQpQ'52B 8 " ', 'DR" RV Form 219 (2)
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I Persons Contacted I
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Arizona Public Service Com an APS)
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Van Brunt, Jr.,
Vice President, Nuclear Projects Management B. Fasnacht, Site Construction Manager E. Ide, Site QA Supervisor S.
Kaplan, Quality Systems Supervisor Pankonin, QA Engineer Forrester, QA Engineer b.
Bechtel Power Cor oration Bechtel S.
M. Nickell, Project Superintendent A. K. Priest, Project Field Engineer
- D. R. Hawkinson, Project QA Supervisor
- R. M. Grant, Project QC Engineer C. Stalnaker, Unit 2 General Superintendent 0. Ostereich, Welding Engineer Unit
Combustion En ineerin CE S.
Mager, Site Manager C. Farley, Unit 2 Internals Superintendent Other persons contacted during the inspection period included construction craftsmen, inspectors, and supervisory personnel.
<<Management Meeting attendees.
2.
Licensee Action on Previous Ins ection Findin s
(0 en Unresolved Item 50-529/81-12/01)
Possible Cold-Workin of Pi e
S ool Ends Durin Fitu This item was referred to Bechtel Engineering for resolution on Field Action Item Request No. 1205-P.
The response to the request was rejected by the licensee because it appeared to be opinionated and did not fully address the metallurgical aspects of the matter.
The inspector agreed with the licensee's con-clusion.
This item remains open.
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Protection of Installed Reactor Vessels (Units 1 and 2)
(I A security guard controls access to the reactor refueling pool areas.
-Entry of personnel, equipment, tools and materials are limited to only those that are authorized.
During this re-porting period the Unit 1 vessel was filled with demineralized water in preparation.'for the'preservice examination of the I
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vessel seams.
Preliminary interna1s'nstallation activities were started on the Unit 2 vessel, but when there is no work in progress, a plastic cover is ket in place over the vessel flange to prevent the entry of foreign objects and debris.
Housekeeping conditions in the pool areas appeared satisfactory.
The inspector verified that the procedures for protection of r
the installed reactor vessels were being implemented.
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No items of noncompliance or deviations, were identified.
Reactor Vessel Internals U'nits 1 and
Installation of the vibration monitoring components on the Unit 1 internals structure continued during this'eporting period.
The internals assembly is "parked" 'on i.,ts storage stand in the refueling cavity and clean room type procedures are followed when work is being performed.
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In Unit 2, the core support barrel was placed in the reactor vessel for measurement of the hot leg nozzle gaps and for initial installation work on the snubber lug shims.
The cylindrical flow baffle, which fastens to the reactor vessel lower head, was taken into the containment building and cleaned in preparation for installation.
The work is being performed by CE under subcontract to Bechtel, with workmen furnished by the Boilermaker craft.
The components are kept covered except when work is actually in progress.
It appeared to the inspector that the procedures for protection to the vessel internals were being followed.
No items of noncompliance or deviations were identified.
Reactor Coolant Pressure Boundar and Safet Related Pi in Installation a
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Pi in Com onent Installation Activities Various work activities associated with handling and installation of Unit 2 piping components were observed to ascertain compliance with the ASME Code, FSAR and specifica-tion requirements.
The systems involved were the safety injection piping from tank lA, and the underground essential spray piping serving the train A diesel generator cooling system.
Particular attention was directed to the handling and supporting of components, correctness of configuration, use of specified materials, control of weld filler metal, control of welding records in the work areas, absence of defects on component surfaces, and inspection performance
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by qualifie8 'personnel;i
'The saf'eely'injection piping was 14-inchiiline'-Sl-E-207's
'shown" oni<<sometric drawing 13-P-'SIF-103.
The diesel cooli'ng piping was 10-inch lines 2-SPA-080 (supply), spools 39 through 44 inch, and 2-SPA-065 (return'),'spools
through" 27, 'inclusive, all as shown on drawing13-,P'-'ZYA-928.
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No items of noncompliance'r deviations were identified.
Ni In-Process Weldin Activities Two welds in system inside Unit 2 containment building were examined to ascertain compliance wi.th the requirements of specification 13-PM-204, the ASME Code (Section III, 1974 edition)
and Bechtel installation/inspection procedures WPP/QCI 100.0, 101.0, and 202.0.
The welds were:
(1)
Weld W-002 joining spools S-001 and S-002 in 28-inch mainstream outlet line 2-SG-036 from steam generator No. 1.
(2)
Weld W-008 joining spool S-005 from check valve V-237 in 14-inch injection line 2-SIE-207 to reactor cold leg loop 1A.
For weld No.
1, the applicable drawing was 13-P-SGF-118 and the welding procedure specification was PL-AT-Lh(cvn).
The weld had been completed and the crown had been ground smooth for NDE purposes.
Workmanship appeared very good.
For weld No.
2, the applicable drawing was 13-P-SIF-103, and the welding procedure specification was P8-AT-Ag.
The inspector observed a portion of the final pass being applied.
'the weld displayed good workmanship.
The inspector also examined the partially completed overlay cladding on the interior of weld W-003 which joins spools S-002 and S-003 in the main coolant pump 1A suction line (2-RC-033-30").
The workmanship also appeared satisfactory.
For all three welds, a properly filled out Field Welding Check List (WR-5 Form)
was present at the work location.
Filler metal issue records (WR-6 Form) which also identified the welders, were also present.
The WR-5 Forms identified the weld number, the system, and the applicab1e drawing number.
Also specified were the welding procedures to be used, the material specification and filler metal to be used, preheat
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Wj ~ III,I Il II ~ ) gf S h (I P 'f /, li i '1 1 I I g f Ilk I( '-; 'y f g I I,I ,I Jf ! and interpass temperatures, and NDE requirements. The inspector verified that the MR-5 provisions were in accordance with the requirements of the ASME Code,Section III, 1974 edition. The qualification records of the welders involved were examined and found to be acceptable. The inspector observed that quality control inspection and supervisory surveillance were being performed. to an appropriate degree. No items of noncompliance or deviations were identified'nit 2 Containment Liner Weldin i On the north side of the containment building a large section of the liner plate had been removed to provide access into the building for the NSSS, v'essel During the replacement of this cutout segment, the.i'nspectox e'xamined approximately 20 lineal feet of the lower horizontal seam and fitup of the right lower vertical seam to verify conformance with the specification and procedural requirements. The wegd segments examined were by two different,welders and were re'presentative of the work in progress'.'- Good wox',,kmanqhip was i'n evidence and the welders records showed that 'they wer'e qu'alified for the specified welding proced'ure speoifica't'i'on.(P1-.,A'-'Lh). Several areas where fitup.attachnients. had, been cut" off-'and ground smooth also show'ed',"s5tisfactoryqworkman'ship"','"=The Field Welding check List and"'-the",,Fi'lier'~He'Gal.."Wit)'drawal'uthorization forms were found to be'xn or'de'r". The goydxning'ocuments were Specification 13-CM-370 'and WPP~/QCI'61;0.;")'"-- No items of 'noncompliance o'r 'deviations were identified. Containment Penetrations Unit 3"c The completed welds attaching the flue'd 'head fittings to the liner sleeves 'for" penetrations 29 and 50 were examined to ascertain compliance with,the requirements of Specification 13-PM-204, the ASME Code (Section III, 1974 edition) and Bechtel procedures WPP/QCI 100.0 and 101.0. Penetration will serve the 1-inch low pressure nitrogen supply to contain-ment and penetration 50 will serve the 4-inch refueling cavity drain line. Both welds had been very recently completed and the workmanship appeared to be very good. A properly filled out Field Welding Check List (WR-5 Form) was present at the work locations with hold points and NDE callouts specified. The quality control inspections required to this point in the work process were properly signed off. The weld identification and material specifications were in accordance with the specified tl I f' r I'I sfactory,.<,IDetails of".the".penetrations are tab-ulated on, D'rawings 13-,'P-'ZCG-107.,an'd';3,08. No items of noncbmpliance.,or,deviat'ions were identi.fied. Reactor Coolant Pum Lat'eral 'Su ort - Unit Work activities, in progr'ess,on the'.wall structure for pump 1A lateral, support (centerline elevation 115-feet 4 3/4-inch) at the south-west corner of the. pump bay,were examined by the inspector. The size, grade and s<pacing of the rei.nforcing steel was as specified and was free"of any surface materials that would adversely afg'ect concrete bonding. The bar ties appeared to be adequate. The anchor bolts with their attendant anchor plates, washers and jam nuts were securely fastened in position. The exposed bolt ends were appropriately covered to provide protection from thread damage. The bolts were 3-inch diameter, ASTM A540, Grade B-22, class 4 and it was verifi.ed that the Material Test Report certified their physical and chemical properties to be within the limits specified in the ASTM standard. The governing documents for the installation were specifications 13-CM-125 and -375, and drawings 13-C-ZCS-370 and -603. No items of noncompliance or deviations were identified. 9. Ins ection Tours of Plant Site At various times toured the plant conditions, care heavy components adequacy of caps presence of crib other components lying around the during this inspection period, the inspector site in order to observe general housekeeping and preservation of equipment, handling of tagging and identification of materials, over pipe openings not being worked on, and bing under stored pipe spools, valves, and No welding electrode stubs were observed various work areas. No items of noncompliance or deviations were identified. 10. Mana ement Meetin A meeting was held on October 30, 1981 with the proj ect representatives 'identified in paragraph 1. During the meeting, the inspector summarized the scope of the inspection activities and reviewed 'the inspection findings as described in this repor I II I W II / r l r' J