IR 05000528/1980003
| ML17296A715 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/08/1980 |
| From: | Dodds R, Eckhardt J, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296A714 | List: |
| References | |
| 50-528-80-03, 50-528-80-3, 50-529-80-03, 50-529-80-3, 50-530-80-03, NUDOCS 8005220438 | |
| Download: ML17296A715 (14) | |
Text
U. S.
NUCLEAR REGULATORY COHHISSION OFFICE OF INSPECTION AND ENFORCEH:"'.iT 50-528/80-03 50-529/80-03 Report No.
50-530/80-03
REGION V
Docket No, 50-528>50-529>50-530License No.
CPPR 141s142e143 Safeguards Group Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Faci1 ity Na+e Palo Verde Units 1,
8
Palo Verde Site, Mintersburg, Arizona Approved By:
Inspection conducted March 10-14, 1980 J'.
H. Eckhardt, Reactor Inspector f
!(') 2 cc-Li
'r,'-.'ernandez Reactor Inspector
.5~
p.
p.
acerb t,
'actor nspector R. T. Dodds, Chief, Engineering Support Section Reactor Construction 'and Engineering Support Branch a
e Signed 488o Date Signed a e Signed a
Signed Summitry:
Ins ection on March 10-14 1980 Re ort Nos.
50-528 80-03 50-529/80-03 and 0-530/80-03 Areas Ins ected:
Routine, unannounced inspection by regional based inspectors o
construction activities involving previous inspection findings, pipe weld-ing, structural steel installation and welding, reactor vessel and steam gen-erator storage, containment electrical penetration installation, and concrete placement.
The inspection involved 96 inspector hours on-site by three llRC inspectors.
Results:
Of the areas inspected, no items of noncompliance or deviations were identified.
RV Forn 219 (2)
8005@ '30
DETAILS 1.
Persons Contacted a
~
b.
Arizona Public Service Com an APS)
- E. E.
Van Brunt, Jr., Vice President, Nuclear Projects
- J. A. Roedel, Hanager, guality Assurance
- W. E. Ide, Site gA Supervisor
- S. Kesler, Supervising Engineer G. Pankonin, gA Engineer
- L. W. Price, Site Construction Hanager R.
D. Forrester, gA Engineer
- D. E. Fowler, gA Engineer D. Fasnacht, Field Engineer Supervisor Bechtel Power Corporation Bechtel)
- W. J. Stubblefield, Field Construction Hanager
- D. R. Kawkinson, Project gA Supervisor
- C. E. Gaither, Assistant Project Field Engineer
- R. H. Grant, Project gC Engineer
"A. K. Priest, Project Field Engineer H. L. Claxton, Construction Specialist R. Casey, Field Engineer D. Hontgomery, Field Engineer C. Collup, qC Engineer B. Garrow, Field Welding Engineer H. White, gC Engineer V. E. Hatson, gC Engineer J. Greco, gC Engineer
- Denotes those attending exit interview.
2.
Licensee Action on Followu Items a.
(Closed)
Noncom liance 50-529/79-03):
Nonconformance observed urban concrete acement activities for the Unit No.
2 contro
~bui 1 din The corrective action identified in the licensee's response, dated August 16, 1979, was reviewed.
Discussions with Bechtel personnel and examination of Civil Information Hemo No. 89 verified that the correction action described in the response had been satisfactorily accomplished.
In addition, the insoectors observed concrete place-ment activities for the Unit 3 basemat and no items of noncompli-ance or deviations were noted.
This item is close t
!
I tI f
I
(Closed)
0 en Item 50-528/79-07
Lack of a re uirement to evaluate reviousl com leted heat treatments if the current e ui ment ca i ration is oun to e unsatis actor Subcontract Change Notice 0'6 to Western Stress Inc. dated February 14, 1980 included a requirement to evaluate the validity of previous weld joint heat treatment operations when equipment calibration records indicate an item was found outside its calibration accuracy limits.
This item is considered closed.
(Closed)
0 en Item 50-528/79-07/04):
Insufficient cleanliness contro durin the time between i in fitu cleanliness inspection and the c osin of the root pass.
The licensee has instituted a training program for pipefitter/welders to provide training in cleanliness requirements for piping systems.
The licensee had trained the active pipefitter/welders and committed to train pipefitter/welder new hires.
This item is considered closed.
(Closed 0 en Item 50-528/79-07 08:
The maximum allowable rind-in e ression in ie e osite stain ess stee c
a din o
reactor coo ant i in is not s ecified for uality contro ins ection.
A special addendum Construction Inspection Plan (CIP) No. 350.0, Rev. 4, Addendum 3 was issued on March 11, 1980 which requires gC verification that the contour of the field deposited cladding be such that there are no dips or valleys between and the adjacent NSSS vendor cladding.- This item is closed.
Closed 0 en Item 50-528/79-08/01
The licensee committed to obtain the redicted clearances and the seismic and thermal movements for two observe i in to structure c earances.
The inspector examined the predicted piping to structure clearances compared to the clearances achieved in the field and found that they agreed within..the erection tolerances specified.
The seismic and thermal movements were accommodated by the achieved clearances.
The inspector had no further questions at this time.
Since this item will be inspected during the normal course of future in-spections, this item is considered closed.
(Closed 0 en Item (50-528/80-01/03
Removal of excess li uid ene-trant testin materia s
rom we s an ase meta o
oi in
.
On February 1, 1980, Peabody Testing personnel were reinstructed regarding liquid penetrant examination post cleaning requirements as documented by correspondence from Peabody Testing to Bechtel welding on February 21, 1980.
In addition, 12 welds in Unit 1 con-tainment and the motor and turbine driven auxiliary feedwater pump rooms that had recently been liquid penetrant tested were examined to verify that excessive liquid penetrant material was satisfactorily removed from the welds and base metal.
This item is considered close,
Closed Unresolved Item 50-528 80-01/04
Practices concernin 1nterpretation of nonre evant indications durin s
used enetrant examinatton of s
e we s.
Peabody Testing has committed to Bechtel to have all Level II qual-ified liquid penetrant personnel repeat the practical portion of the certification process with a Bechtel representative present in order to verify understanding of the ASME BEPV Code requirements for handling indications which are believed to be nonrelevant.
The licensee agreed with the code position concerning treating in-dications as relevant until proven otherwise.
This item is consid-ered closed.
(Closed 0 en Item 50-528 80-01
Pro ram for elimination re-air of arc strikes on i in
.
The licensee considers that present procedures sufficiently cover arc strikes in the areas of (1) protecting installed piping during subse-quent welding activities in the vicinity of the installed pipe, (2) in-specting for arc strikes during pipe welding examination, and (3) elim-ination of observed arc strikes via the nonconformance process.
The inspector agreed with this position.
Also, the licensee committed to include inspecting for arc strikes as an attribute for final pipe inspection prior to hydrostatic testing.
This item is consid-ered closed.
IE Bulletin 79-02, Rev. 2:
Pi e
Su ort Base Plate Desi ns Usin oncrete Ex ansion Anchor Bo ts.
The APS responses to Bulletin 79-02, dated July 6 and November 16, 1979 respectively, had a question regarding requirements for piping smaller than 2~ inches in diameter.
The inspector discussed the question with the cognizant licensee personnel.
The licensee personnel stated they consider the item resolved and no further clarification is required in regards to this matter.
3.
Reactor Coolant Pi in Weldin a ~
Review of Weldin Procedure S ecifications and ualit Assurance roce ures Welding Procedure Specifications (WPS), P1-clad-o Revision 3, and Pl(G2)-T-I-o (ITP) Revision 2 were reviewed for compliance with the requirements with Section III and IX of the ASt1E Code.
The supporting Procedure gualification Records (PgR) were examined to de-termine whether the PgR's listed the essential variables for the specific welding process, whether all mechanical tests required by the Code were performed, and whether the PgR's were properly cer-tified by the licensee or contractor.
No items of 'noncompliance or deviations were identifie b.
Observation of Meldin Activities Two inprocess reactor coolant loop piping welds were examined for compliance with welding procedures, specifications and the requirements of the ASME code.
The welds examined were:
~Sstem RC-051 RC-033 Meld'o.
M003 M003
~PI e Size 1 6 II
II No items of noncompliance or deviation were identified.
c.
Visual Examination of Helds Six completed field welds in the reactor coolant loop piping were visually examined for conformance with applicable codes, standards, construction specifications and licensee/contractor welding proce-dure requirements.
The following welds were examined:
~Sstem SI-E160 SI-E160 SI-E160 SI-E175 SI-E179 RC-051 Meld No.
M001 H002 H003 W002 M002 W004
~Pi e Size 14" 14" 14" 12"
] 4 II 16" No items of noncompliance or deviations were identified.
d.
Welder uglification and Review of ualit Records The quality records associated with the above welds were reviewed for compliance with licensee and code requirements.
Records exam-ined included, welder qualification, welding checklists, NDE results, and nonconformance reports.
No items of noncompliance or deviations were identified.
4.
Safet Related Structural Steel - Unit
The inspector examined structural steel high strength bolting fon con-formance to the requirements of the "Installation Specification for Erec-tion of Structural and Miscellaneous Steel", Specification Number 13-CM-320, Rev.
5, Work Plan Procedure/guality Control Instruction HPP/qCI 58.0, Rev. 9, and AISC "American Institute of Steel Construction (Seventh Edition).
The areas inspected were the fuel building structural steel at the 140 foot elevation in the area of column lines FD and F3 and the fuel building roof trusses being assembled in an outside lay down area.
The inspector observed (1) proper bolt and nut material, (2) the absence of visually evident defects in the material, (3) proper application of the turn of the nut method of tightening, and (4) evidence of gC inspections on completed portions of the work.
The inspector reviewed the qualification records of the gC personnel involved.
No items of noncompliance or deviations were identified.
Containment Structural Steel Meldin
- Unit 2 The inspector examined structural steel welding in the containment for conformance to the requirements of Specification Number 13-CM-20, Rev. 5,
"Installation Specification for Erection of Structural and Miscellaneous Steel",
Mork Plan Procedure/guality Control Instruction MPP/gCI 58.0, Rev. 9, and AMS D1.1-72, Rev. 1-1973 "Structural Melding Code".
The areas examined were the inprocess welding of cord beam gussets to the polar crane ring girder (Drawing 13C-2CS-520(7)
and miscellaneous beam clip welding at the 120 foot elevation of the containment (Draw-ing 13C-2CS 533(6)).
The inspector examined the use of the proper weld procedure, proper ma-terial, specified nondestructive examination, weld rod issue and control, gC personnel qualifications, and resultant weld quality.
Several of the beam clip welds did not meet AMS standards but they had not been accepted by the Field Melding Engineer and were to be reworked prior to inspection by the gC engineer.
No items of noncompliance or deviations were identified.
Reactor Vessel and Steam Generator Stora e - Unit 2 The Unit 2 reactor vessel (2t1-RCE-X01) and one steam generator (2H-RCE-E01A)
stored in an outside laydown area were examined to ascertain compliance with MPP/gCI-355.0, Rev. 3, "Reactor Vessel Storage, Handling, and In-stallation", MPP/gCI-370. 0, Rev. 2,
"SG Storage, Handling, and Installation",
and ANSI N45.2.2-1972.
Specific items observed were (1) limited access to the storage area via the area being roped and flagged off with signs des-ignating only authorized personnel admitted, (2) all covers and seals for the components in place, (3) exterior spraylat coating in good condition, (4) humidity indicator in reactor vessel, (5) nitrogen blanket on both primary and secondary sides of steam generator, and (6) adequate support for both components.
In addition, the maintenance program, including the maintenance records, for both units was reviewed and found to agree with the requirements of MPP/gCI 12.0 and 28.0.
No deviations or items of noncompliance were identifie t
7.
Installation of Electrical Penetrations
- Unit 1 Containment Two Unit 1 containment electrical penetrations manufactured by Conax were examined to ascertain compliance with MPP/gCI 258.2, Rev. 0, "Penetra-tion Assemblies Installation".
Penetration No. 88 was installed and pressurized.
Its interior box was installed but the bolts had not yet been torqued.
Penetration No. 90 was installed and pressurized.
Its interior and exterior boxes were installed but the bolts had not yet been torqued.
The installation and testing to date appeared to conform to the installation procedure and the assemblies were protected from other work in the area.
gC inspection coverage appeared adequate based on installation inspection records review.
No deviations or items of noncompliance were identified.
8.
Concrete Placement - Unit 3 Containment Base Mat Concrete placement activities for the Unit 3 base mat (placement Nos
.
3C012 and 3C013) were examined for conformance with licensee procedures and specifications.
The activities inspected included, aggregate and cement storage, batch plant operation, placement preparation, delivery and placement, and gC inspection.
guality records pertaining to concrete production and placement activ-ities were also examined.
No items of noncompliance or deviations were identified.
9.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on March 14, 1980 and summar ized the scope and findings of the inspection as stated in this repor i