IR 05000529/1985032

Insp Repts 50-529/85-32 & 50-530/85-24 on 850916-19 & 0930-1004.No Violations or Deviations Noted.Major Areas Inspected:Nde of Piping,Structural Steel & Supports & Review of RCPB Piping Records

ML20138M701
Person / Time
Site:	Palo Verde
Issue date:	10/11/1985
From:	Wagner W, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20138M684	List: IR 05000529/1985032 ML20138M680
References
50-529-85-32, 50-530-85-24, NUDOCS 8511040219
Download: ML20138M701 (8)

Text

U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Repcrt No /85-32 and 50-530/85-24 Docket No and 50-530 Construction Permit No CPPR-142 and 143 Licensee: Arizona Nuclear Power Project P. O. Box 52034 Phoenix, Arizona 85072-2034 Pacility Nace: Palo Verde Nuclear Cencrating Station - Units 2 and 3 Inspection at: Palo Verde Site, Wintersburg, Arizona Inspection conducted: September 16-19 a- September 30 - October 4, 1985 Inspector: -

E7J. Wagner, React r Inspe r

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[M to / Date Signed

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Approved Ey: -

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T7 Young, Jr., Chie Engine in Section Date Signed Su==ary:

Inspection on September 16-19 and September 30 - October 4, 1985 (Report Nos. 50-529/85-32 and 50-530/85-24)

Areas Inspected: Routine unannounced inspection by a regional based inspector of activities associated with nondestructive examination of piping, structural steel and supports, and review of reactor coolant pressure boundary piping records. The inspection involved 62 inspector-hours by one NRC inspecto During this inspection, Inspection Procedures 49055, 55061, 55063, 55064, 55065, 55066, 55073, 55083 and 55085 were covere Results: No violations of NRC requirements or deviations were identifie PDR ADOCK 05000529 G PDR

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f DETAILS Persons Contacted Arizona Nuclear Power Project (ANPP)

• E. Ide, Director, Corporate QA/QC

• C. N. Russo, Manager, Quality Audits and Monitoring i

• S. G. Penick, Quality Monitoring Supervisor

• J. F. Ortiz, Nuclear Construction Engineer S. Mehta, QA Engineer D. LeBoeuf, QA Engineer Bechtel Power Corporation (Bechtel)

*D. R. Hawkinson, Project QA Manager

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• S. Nickell, Project Superintendent

• R. Butler, Assistant Project Field Engineer

• Stubblefield, QA Supervisor

• G. Getinas,~QC Engineer R. E. Vote, Assistant QA Manager

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H. A. Mears, Assistant Project QC Engineer i L. Bowles, Lead Welding QC Engineer

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J. Rachel, Assistant Lead Welding QC Engineer i

' J. J. Jagodic, Lead Field Welding Engineer R. R. Butler, Codes Lead Field Engineer

G. R. Griffith, Lead Civil QC Engineer

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C. C. Collup, Assistant Lead Civil QC Engineer D. J. Freeland, Supervisor, Plant Design Engineering

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Safety-Related Structures - Welding Quality Assurance Procedures - Units 2/3 i

The inspectors' review of the QA implementing procedures revealed that the Bechtel Project Quality Program Manusl Procedure No. 9,

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" Control of Special Processes" Revision 2 of January 7, 1980 describes the requirements to assure that NDE activities comply with requirements of Regulatory Agencies, and applicable Codes and Standards. The manual also contains provisions to assure that NDE

techniques conform to these requirements and have been qualifie The procedure that requires NDE personnel be qualified to applicable

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standards, such as SNT-TC-1A, is Nondestructive Examination Standard NEPQ-2, " Level I and Il Personnel Qualification and Certification Standard" Revision 0 of April 1, 198 In addition, the inspector reviewed the Bechtel Construction and Quality Control Manual, Procedure No. 102.0, " Nondestructive Examination Control" Revision 11 of May 31, 1985. This procedure

, contains provisions to assure that the following NDE activities are in compliance with applicable code requirements:

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Evaluation of weld quality by the use of specified NDE procedure Evaluation of the quality of radiograph I * Evaluation of weld quality by visual examination.

' Observation of Work and Work Activities - Units 2/3 NDE activities associated with welding of safety-related structures and supports outside containment were completed prior to this inspection. However, the inspector reviewed a substantial number of NDE records of structural weldments as discussed in Section 2.c of this repor Review of NDE Records - Units 2/3 The American Welding Society (AWS) Structural Welding Code, AWS D1.1, requires that a visual examination be performed on all

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ccmpleted welds. Unless the engineer specifies additional NDE, such

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as liquid penetrant or magnetic particle inspection, inspection records will indicate that visual inspection was performed on all

! welds within a given location specified on the inspection recor The inspector reviewed the following CIP's related to welding activities associated with steel structures and supports at the following locations:

) (1) Control Building - Unit 2

{ (a) CIP dated January 7, 1982, location at 100' elevatio ,

The inspection signof f was for visual inspection of welded

connections on beams QM27 through QM33 and stiffeners.

i j (b) CIP dated August 29, 1979, location at 100' elevatio i l Visual inspection was performed on welded connections of all auxiliary hanger beams.

l (c) CIP dated June 1, 1979, location at 74'-100' elevatio Inspection signoff for visual inspection on welding of columns and baseplates including the balance of structural columns and beams from line JC to JA and line JL to J (d) CIP dated April 19, 1979, location at 74'-100' elevatio Visual inspection signof f for all W36x300-10H beams f rom line JC to JE and J2 to 8'6" North of line J4.

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(2) Equipment Hatch Shield Doors - Unit 2 l The NDE records reviewed included visual, magnetic particle and l radiographic inspections for the following welds:

! 2EH-35-4 to 2EH-2-4

2EH-35-1 to 2EH-2-4

2EH-30-4

2EH-30-1

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2EH-30-2 2EH-30-3 2EH-35-3 2EH-35-2

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2EH-2-5 to 2EH-1-2 2EH-2-4 to 2EH-2-5 2EH-2-5B to 1/4" wall 2EH-2-5A to 1/4" wall 2 Ell-2-4B to 1/4" wall 2EH-2-4A to 1/4" wall 2EH-2-3B to 2EH-2-4B

! 2EH-2-3B to 1/4" wall 2EH-2-3A to 2EH-2-4A

, 2EH-2-3A to 1/4" wall

, 2 Ell-2-2B to 2EH-2-3B

! 2EH-2-2B to 1/4" wall 2EH-2-2A to 2EH-2-3A j 2EH-2-2A to 1/4" plate 2EH-2-1 to 2EH-2-2

2EH-2-1 to 2EH-1-1

l (3) Fuel Building - Unit 3

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(a) CIP dated February 15, 1982, location at 118' elevation, j Visual inspection performed on all welded connections from

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column line F2 to F3 and from FC to F (b) CIP dated July 12, 1982, location at 140' elevatio j Visual inspection performed on welded connections on  ;

columns FA to FF and F1 to F .

l (c) CIP dated October 25, 1983, location at 204' elevatio i l Visual inspection performed on welded connections on  !

! missile shield (West).

i (d) CIP dated April 18, 1984, location at 185' elevatio Visual inspection of welded structural supports on line i

FA, FB to F1.8F2,

! l (4) Control Building - Unit 3 i

(a) CIP dated October 1, 1980, location at 100' elevation.

! Visual inspection performed on structural steel columns

and support steel.

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(b) CIP dated April 27, 1981, location at 100' elevation.

I Visual inspection performed on columns and structural beam ;

(c) CIP dated November 30, 1981, location at 100' elevatio ;

Visual inspection performed on miscellaneous beams and stiffener plates,

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The above records indicated that all NDE activities were performed

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at the proper stage of fabrication. The records were identifiable j and easily retrieved which is consistent with established procedure i Safety-Related Piping - Welding i

, Observation of Work - Unit 2

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! NDE activities associated with welding of safety-related piping systems were completed prior to this inspection. However, the inspector reviewed the NDE records for several welds from selected

, systems as discussed in Section 3.b of this report.

i Review of NDE Records - Units 2/3 4 ,

The following NDE records were randomly selected by the inspector to  ;

assure that evaluation of weld quality was reflected on the work  :

j accomplished consistent with NRC requirements and SAR commitments:

Unit 2 System Field Weld N NDE Procedure CT 012 HCCA 3" W300 PT BPC 1 (1) I SI 030 HCBA 24" WOO 8 RT XG 2 (1)

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. SI B308 GCBC 24" W0ll RT XG 2 (3)

l SG E 033 DLBB 28" WOO 4 RT XG 2 (1)

i CH 065 HCBA 3" WOO 2 RT XG 2 (3)

} AF A 003 DCCA 6" WOOS PT BPC 1 (0)

EW A 023 HBCB 12" WOO 4 MT P1, 2 (2) f j  ;

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Unit 3 System Field Weld N NDE Procedure CH 842 HCCA 1" A00 VE BPC 1 (3)

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CT A002 HCCA 8" WO76 PT BPC 1 (1)

SG E 388 DABA 2" WOOA RT XG 2 (2)

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SI 033 GCBC 18" W300 RT XG 2 (2)

I SI B 033 GCBC 14" WOO 6 RT XG 2 (3)

EW B 057 HBCB 10" WOO 6 MT P1, 2 (1)

EW B 057 HBCB 12" WOO 4 MT YI, 2 (1)

l The inspector reviewed the above NDE procedures for compliance with requirements specified in the SAR. The precedures included the appropriate acceptance criteria for the specific welds examine The procedures also contained provisions requiring demonstration of the testing technique, and that personnel qualifications be in accordance with SNT-TC-1 t

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, Observation of Work - Unit 3 The inspector observed liquid penetrant examination being performed on weld number WOO 3 of the safety injection system, SI-173. The ,

resident inspector also observed the same NDE process performed on

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weld number W301 of System SI-12 In both instances, the l l operations were performed in accordance with the applicable liquid [

j penetrant procedure. Specific attention was paid to surface l

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preparation, penetrant application, dwell time, developer ,

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j application, and post cleaning.

J i No violations of NRC requirements or deviations were identified.

! 4. Reactor Coolant Pressure Boundary Piping - Unit 3

' Observation of RCPB Pipe Welding - Unit 3

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! Reactor Coolant Pressure Boundary (RCPB) pipe weldinr and NDE were i j completed prior to this inspection. Ilowever, the inspector reviewed the records associated with welding of two pipe sizes to ascertain j that the NDE performed was in accordance with applicable code f requirements. The records reviewed were for 16" pipe weld number .

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! WOO 2 system RC 051 BCAA, and 6" pipe weld number W001 system RC 001 BCAA. The records indicate that the radiography and liquid ,

penetrant testing were performed at the proper state of fabrication  !

using qualified NDE procedures. The records also show that the performance of the NDE activities were verified by a QC inspecto ]

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Review of RCP3 Piping Records l

j The reactor coolant pressure boundary piping records are prepared i i and reviewed for accuracy by the Bechtel Codes Group. This group  !

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also has the responsibility for assessing that the recorded l

information meets ASME Section III requirements. This is ,

accomplished in accordance with Bechtel Procedure WPP/QCI No. 26.4,  !

l " Preparation of the N5 Code Data Package", Revision 6 of April 2, l 1985.

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The inspector reviewed the piping drawings for two systems, the l Chemical and Volume Control and Safety Injection. The following

' components were selected from these systems for review of the j associated records relating to recei'ing inspection, material

certification and installation in.pections

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(1) Package 3Ci!07-4, Pipe Spcol No. 3Cl!!31S002 on drawing l i 13-P-ZYA-024 R13. Receipt inspection is documented on Material j Receiving Report (MRR) No. 125489 which confirms that the

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required material characteristics and specification

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) (2) Valve No. 3PCifNVS29, Dresser Serial No. II791 AAD on line 3Cil275.

I Receipt inspection is documented on MRR No. 30572. Valve -

I l material certifications selected for review were of the valve

body and yok l l I i

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l i-n--n,---,,,---<w,n,._.,.,m,.--,- ,--v-nn-~~~-mn.n~ne_n, n m ,w n m .~.,- nm.--,. - , ,

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(3) Twenty foot section of pipe selected from Safety Injection System 3SIO7. The receipt inspection for thi.s pipe, Heat

No. 3526, is documented on MRR No. 8109

(4) Valve No. 3PCHNVX88, Dresser Serial No. H876AFE on line 3SIO Receipt inspection is documented on MRR No. 36143.

} The inspector reviewed the material test reports received with the i above components. A comparison of the test report values for chemical analysis and mechanical properties with the values

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specified in ASME Sections II and III revealed that the applicable requirements were me The installation inspect. ion records reviewed confirmed that the

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selected components were installed as specified, and that the j required inspections were performed.

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! The inspector reviewed the licensee's system for reporting and

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dispositioning nonconforming materials, parts and components associated with reactor coolant pressure boundary piping. The

following NCR's were selected for review:

PA 2873 PA 7249

PA 4263 PA 9365 PA 8374 PA 9829 l PA 8969 PA 10955

i PA 5476 PA 11495 i

j The review revealed that the records adequately document current i status of problem; the records are legible and complete, and i

promptly reviewed by qualified people; records are processed through i established channels for resolution of the immediate problem as well j as generie implications; records are being properly identified and j stored, and can be retrieved in a reasonable time; and the NCR's ,

l include the status of corrective action or resolution and action to prevent recurrence.

l NCR No. PA5476 reported a weld joint mismatch. Disposition required grinding around the pipe followed by UT examination to determine i I wall thickness. The UT examination revealed a wall thickness below  !

) that specified. The NCR reported this to be acceptable based on Calculation No. ZZ-584 which showed that the undersized wall

thickness will not affect the integrity or function of the system, i The inspector reviewed the calculations which took into

) consideration the affects of temperature, pressure, corrosion and

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stress. The calculations were satisfactory in concluding that the l piping stresses were still within the allowabic designed stress

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range.

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The following QC inspection personnel qualification records were

! reviewed and found to be complete and current: QC inspectors 295, l 342, 375 and 419. The records established that these individuals j i vere adequately qualified for their assigned duties and i responsibilities. The licensee's program to verify the l

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qualifications and certifications of QA Engineers and QC Inspectors was previously reviewed and reported in NRC Report No. 50-528/84-56.

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The Bechtel QA Group performed a number of audits concerning the installation of reactor coolant pressure boundary piping. The

! following QA Audits were reviewed:

l Audit N Audit Dates Area Audited i

i 14-S-82-21 3/23-29/82 Piping Systems Installation 14-S-82-81 10/28-11/29/82 Piping Systems Installation

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14-S-83-15 2/28-3/3/*3 Piping Systems Installation 28-S-83-19 3/7-10/83 Field Piping Fabrication 14-S-83-50 8/22-9/7/83 Piping Systems Installation 28-S-83-57 9/7-9/83 Field Piping Fabrication

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28-S-84-16 5/2-4/84 Field Piping Fabrication

, 14-S-84-47 9/11-18/84 Piping Systems Installation J 28-S-85-19 5/7-14/85 Field Piping Fabrication 14-S-85-45 9/16-27/85 Piping Systems Installation The records reviewed indicate that the required audits were l performed in accordance with the schedule and functional areas in

the established audit plans. The findings were reported in l sufficient detail to permit a meaningful assessment by those

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responsible for corrective action, final disposition, and trendin Proper follow-up action was taken on those matter. in need of j correction and action to prevent recurrenc I l No violations of NRC requirements or deviations were identified, t

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! Exit Meeting j The inspector met with licensee management representatives denoted in

) paragraph I on October 3, 1985. The scope of the inspections and the

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inspector findings as noted in this report were discussed. l

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