IR 05000482/1982017
| ML20028C460 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/29/1982 |
| From: | Bess J, Hunnicutt D, Clay Johnson, Johnson W, Mullikan R, Mullikin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028C457 | List: |
| References | |
| 50-482-82-17, NUDOCS 8301100218 | |
| Download: ML20028C460 (21) | |
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APPENDIX 8 U. S. NUCLEAR REGULATORY COMISSION
REGION IV
NRC Inspection Report: STN 50-482/82-17 Docket: 50-482 Licensee:
Kansas Gas and Electric Company Category:
A2 Post Office 80x 208 Wichita, Kansas 67201
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Facility Name: Wolf Creek Generating Station, Unit No. 1 Inspection At:
Burlington, Coffee County, Kansas Inspection Conducted:
October 18-22, 1982
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Inspector :
R. P. Mu111 kin, Reactor Inspector, Da'te /
Engineering Section (pars. 1, 8, 9, 10, 11, and 14)
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////Waz D. M. Hunnicutt, Chief, Engineering Section Dat/e
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(pars. 1, 9, 12, 13, and 14)
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C. E. Johnson, Reactor Inspector, Date
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Engineering Section v
(pars. 1, 2, 3, 4, 5, 6, 7, and 14)
l ll l? $ h J. E. Be'ss, Reactor Inspector, Engineering Date
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Sectior. (pars. 1, 8, 9, 10, and 14)
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8301100218 821124 PDR ADOCK 05000482 o
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Approved:
/k D. M. Hunnicutt, Chief, Engineering Seciion-Dite '
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Reviewed:
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bf. D. Gdhnson, Chief, Reactor Project Date Section C
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Inspection Summary
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Inspection Conducted on October 18-22, 1982 (Report STN 50-482/82-17).
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Areas Inspected:
Routine, unannounced inspectio'n of quality assurance'
procedures for electrical instrumentation cable, terminations, and related equipment; observation and independent evaluation of work performance, work in progress, and completed work of electrical instrumentation ~ cable terminations; review of quality related records relative to electric cable nondestructive s
examination and QA audits; review of quality assurance procedure for safety-related structures (structural steel); observation of work activities related to pipe supports and structural steel; review of quality related records'.
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pertaining to structural steel framing; review of pertinent quality related work and inspection records (QC) for the pressurizer, pressurizerf support
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stand, the three safety valves, the relief valve, the blo~ck valves for the
relief valves, and the boron injection tank.
The inspection _ involved 1R4 hours
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onsite by four NRC inspectors.
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Results: Within the seven areas inspected, one violation was identified.
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' DETAILS
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Persons Contacted
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Principal Licensee Employees
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'*D. W. Prigel, QA Manager, Kansas Gas and Electric Co. (KG&E)
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~*C. E. Parry, QA Systems Supervisor, KG&E
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R. Bird, QA Engineer, KG&E
- 0, L. Thero, QA Surveillance Supervisor, KG&E L. Ho', QA Engineer, KG8E-C. Ha, QA Engineet, KG&E D. L. Donohoe, QA Technologist II, KG&E
- J. Fletcher, QC Engineer, KG&E
- J. L. Stokes,' Project Support Supervisor, KG&E Construction Daniel International Construction D. Gillespie, Civil Engineer
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- R. S. Calabro, Area Hanger Engineer
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B. Browning, Area Hanger Engineer
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Walker, QC Electrical Inspector
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MG. Mau_1 din,~ Project quality Engineer
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- J. - G. _Gr f_1,1,, PPE
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hs_tinghouse E_ lect.ric Corporation _ Nuclear Services Division
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- D. Kent., Lead: Site QA Engineer
- G. Martin./ Eagineer E
B. Pre, Enginaer
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Licensee Action on Previous Findings I
' (Ciosd)' Unresolved Item (STN 50-482/81-15):
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.STN S0-482/81-15 identified an unresolved item concerning WP-VII-208,
%vi sion ' S o which requires additional alteration and cut of support l
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, "inuerial to'snape and size by mechanical or thermal means without engineer-
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[i'ng" approval.y Procedure WP-VII-208, Revision 11, is approved and it
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[ 'coreccts(this problem.
This item is considered closed.
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Safety-Related Structures (Structural Steel)
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' a, Review of Procedures.
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l he NRC inspector-reviewed procedures concerning the installation /
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- erection of safety-related structural steel.
Procedures reviewed are j
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QCP-IV-111, Revision 0, " Erection of Structural Steel and Pipe Whip Restraints" WP-IV-III, Revision 7, " Structural Steel and Pipe Whip Restraint Erection" CWP-509, Revision 3, " Stud Welding" No violations or deviations were identified.
b.
Observation of Work Activities The NRC inspector observed the erection and installation of safety-related structural steel in progress in the auxiliary building.
During the observation, the NRC inspector observed one discrepancy which involved some damage to approximately six shear anchors or studs attached to one of the structural beams.
These studs were bent in excess of the 15 angle permitted by procedure.
The NRC inspector informed the licensee of the discrepancy. The problem was immediately corrected by visual examination and subsequent replacement of studs that showed cracks in the welds.
Overall installation and erection appear to comply with procedures.
No violations or deviations were identified.
c.
Review of Records The NRC inspector reviewed USS American Bridge drawings of structural steel fi.
5eing erected in the auxiliary building.
The area is
.3 located between A7 and A14 line and on EL. 2026'-0", EL. 2047'-6",
and EL. 2073'-2" of the auxiliary building.
There were no records at this time generated by QC because of the early stages of the work in progress.
The craft notifies QC upon completion of work.
Drawings reviewed by the NRC inspector are listed below.
Drawing #
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10466-C-121-0617-03 10466-C-121-0627-05 10466-C-121-0629-05 10466-C-121-1634-01 10466-C-121-1700-02 10466-C-121-1929-01 10466-C-121-0982-01 No violations or deviations were identified.
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4.
Safety-Related Pipe Supports and Restraints Review of Procedures The NRC inspector reviewed several procedures during the course of the inspection.
Some of the procedures had been revised to incorporate more information to the craft and quality control inspectors.
Technical adequacy and acceptance criteria have been established in these procedures.
Procedures reviewed are listed below.
WP-VII-208, Revision ll, " Installation of Component Supports" WP-IV-111, Revision 7. " Structural Steel and Pipe Whip Restraint Erection" No violations or deviations were identified.
5.
Review of Records The NRC inspector reviewed approximateloy 15 pipe support travelers of various safety-related systems inside the containment.
Some of the travelers were not complete and were still in process.
The completed traveler packages contained all required documentation as required by procedure.
Travelers reviewed are listed below, by system.
High Pressure Safety Injection (EM)
Feedwater (AE)
EM05-R005/213 AE04-H001/242 EM05-H503/231 AE04-H002/241 EM05-H502/231 AE04-R007/241 EM05-H003/231 AE05-R001/242 EM05-C502/231 Reactor Coolant (BB)
Main Stream (AB)
BB02-H006/261 AB01-R001/251 BB01-H002/231 BB02-R018/261 BB02-R019/261 BB02-R020/261 No violations or deviations were identified.
6.
Observation of Work The hRC inspector visually inspected 11 pipe supports that were reviewed
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The pipe support travelers not examined were l
inaccessible.
During this visual examination, the NRC inspector found one l
deviation.
Pipe support AE04-H001/242 had been signed off as completed according to the records contained in the traveler.
All required docu-I mentation indicated that this support was completely installed and final I
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inspection had been performed by QC.
However, the pipe support in the field had been disassembled and not completed as the traveler indicated.
The DIC hanger engineer assisting in the inspection stated that the craft probably disassembled the pipe support to perform work in that area.
The NRC inspector ask the hanger engineer what method was used to control the disassembly and reassembly of quality cccepted pipe supports.
After some investigation of this matter by the hanger engineer, he found that there was no method of controlling hanger disassembly et the present time; however, the licensee will add an Interim Change to Procedure (ICP)
WP-VII-208 to correct this problem.
This is a violation against Criterion V of 10 CFR Part 50, Appendix B.
7.
Observation of QC Inspectors The NRC inspector observed quality control inspectors performing inspec-tion on safety-related pipe supports on the heating / ventilating / air conditioning (HVAC) system and other safety-related supports in the auxiliary building.
QC performed an adequate inspection of the supports and included all inspection requirements and acceptance criteria.
No violations or deviations were identified.
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Review of Records (Cable Nondestructive Examination [NDE])
The NRC inspectors examined the licensee's QC records dealing with cable nondestructive examinations. The records reviewed showed that continuity and megger tests were performed as required and that the results met requirements.
The QC cable termination checklists were examined for the following power and control cables:
Power Control 1ALY01AA 1ABK03AD 1 BGG 11BA 1ABK03AE IBGY01AA 1ECY08AA 1ABK03KB 1 EGG 04AA 1ABK03MA 1 EGG 04BA 1ABK23AG 1 EGG 05CA 1ACI38JC 1 EGG 05AA IBGK27AA 1 EGG 07AA No violations or deviations were found in this portion of the inspectio.
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9.
Observation of Electrical Cable Termination Work (Instrumentation and Control)
The NRC inspectors witnessed the termination of several instrumentation cables at two electrical penetration assemblies.
The use of specified materials and installation procedures were examined for conformity to NRC requirements.
The NRC inspectors verified that the QC termination cards issued to the DIC installer corresponded to the card issued to the DIC QC inspector.
Also verified was that the completed work matched the QC termination cards.
The electrical penetration assemblies and instrumentation cables ir.spected are as follows:
Penetration Assembly Cables 2ZSE233 4GSY01CB ZNE279 3BBI15HB 3AEIO8KB 3AEIO8HB 3AEIO8LB 3AEIO8GB 3AEIO8JB The NRC inspectors also examined the following tools used during the above
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termination activities:
Surndy Crimper MR 10G6 (Control No. GII-1676)
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Date of last calibration - September 27, 1982 l
Burndy Crimper MR 10G6 (Control No. GII-1641)
Date of last calibration - October 11, 1982 Wire Stripper (Control No. GII-2106)
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Date of last calibration - September 15, 1982 The certification card of the DIC QC inspector for electrical penetration assembly 2ZSE233 was examined by the NRC inspectors.
The DIC inspector's qualifications are listed below:
DIC Inspector Date of Qualified For Certification Equipment Inspection Level II August 30, 1981 Raceway Inspection Level II May 11, 1982 Termination Inspection Level II July 6, 1982 Cable Pulling Inspection Level II July 24, 1982 Instrumentation Inspection Level II July 24, 1982 l
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t The NRC inspector; examined completed DIC termination work at Analog
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Terminal Cabinet RJ 160D. The eight instrument cables inspected are listed below:
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48GR01BB 4EMR14MA 4BGR43FA 4EMR14NA 48GR43GA 4ENR01BB 4EGR01BB 4NER02AB
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The NRC inspectors verified that the above terminations agreed with the QC cable termination cards.
The scope of this verification included:
cable number, wire color, terminal board, cable codes, and termination points.
The NRC inspectors witnessed the termination by Westinghouse of the following instrumentation cable:
Cable No. - SEJIl0EA Item - Pressure Transmitter PT-614 (Model 753)
System - Residual Heat Removal Location - Elevation 1974'
Drawing - 8765D44G02 - Westinghouse l
Crimper - Burndy MR10G6 (Date of last calibration - October 6,1982)
The NRC inspectors verified that the termination of PT-614 agreed with the Westinghouse Traveler EJ-07000-1.
The scope of this verification in-l cluded:
instrument number, cable number, wire color, terminal board, cable codes, and termination points.
A control cable being terminated by Westinghouse at solenoid HY-8800A for f
control valve HCV-8800A was inspected in progress.
The valve connects the
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refueling water storage tank to the refueling pool isolation tank.
The following documents were examined:
Westinghouse Traveler BN-07000-2
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Bechtel Drawing E-CR8900
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No violations or deviations were found in this portion of the inspection.
10.
QA Program and Procedures - Instrumentation Cable The purpose of this inspection was to determine whether appropriate and adequate QA procedures exist to assure compliance with NRC requirements and licensee commitments-for the performance of the following activities l
dealing with electrical instrumentation cable:
receipt inspection and storage, handling and installation, inspection and testing, identification, raceway separation and protection, cable redundancy and separation, raceway loading, cable nondestructive examination (NDE) after installation, and design changes and deviations.
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The QA program and procedures examined during the NRC inspection of June 8-11, 1982, (Report No. 82-08) for electrical cable pertain also to instrumentation cable.
There are a few additional procedures where Westinghouse is involved in some areas of terminating work.
The procedures in Report 82-08 are those of DIC.
The DIC procedures shown in Report 82-08, as well as the Westinghouse procedures examined during this inspection, are listed below.
a.
Receipt Inspection and Storage The NRC inspector examined the licensee's QA procedures for receipt inspection and storage of electrical cable.
The procedures examined and the licensee's adherence to these procedures appeared to meet NRC requirements and licensee commitments.
The procedures examined are listed below.
WP-XI-302, " Protection of Electrical Equipment," Revision 3,
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dated February 11, 1982 WP-I-01, "Special Receiving, Storage, Preservation and Maintenance
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Requirements for Safety and Non Safety Related Materials and Items," Revision 10, dated March 16, 1982 QCP-I-01, " Receipt, Storage and Preservation of Safety Related
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Materials and Items," Revision 12, dated February 19, 1982 QCP-X-303, " Installation of Cable," Revision 4, dated June 4,
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1982 These procedures provide for adequate inspection of cable upon receipt to assure that it is undamaged and it conforms to purchase specifications.
Documentation of inspection reports and qualification tests is adequately addressed by the examined procedures.
Adherence to these procedures will assure that storage requirements, including environmental protection and segregation of nonconforming material, are met.
No violations or deviations were identified in this portion of the inspection.
b.
Identification The licensee's QA procedures for identification of electrical cable and cable terminations were examined by the NRC inspector.
These identification procedures appeared to adequately assure cable trace-i ability from receipt through installation and proper segregation of
nonconforming cable.
NRC requirements and licensee commitsents appeared to be met by the examined procedures.
The procedures examined are listed below.
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AP-VI-02, "Nonconformance Control and Reporting," Revision 13,
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dated April 14, 1982 WP-I-01, "Special Receiving, Storage, Preservation and Maintenance
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Requirements for Safety and Non Safety Related Materials and Items," Revision 10, dated March 16, 1982 QCP-I-01, " Receipt, Storage and Preservation of Safety Related
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Materials and Items," Revision 12, dated February 19, 1982 Westinghouse Electric Corp., Nuclear Service Division,
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Traveler AB-07000-1, " Electrical Termination," Revision 0, dated August 4, 1982
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No viciations or deviations were identified in this portion of the inspection.
c.
Raceway Loading The NRC inspector examined the licensee's QA procedure dealing with raceway loading.
The procedure examined appeared to adequately meet NRC requirements and licensee commitments. The procedure examined is listed below.
QCP-X-303, " Installation of Cable," Revision 4, dated June 4,
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1982 No violations or deviations were identified in this portion of the inspection.
d.
Design Changes, Deviations, and Unusual Problems The NRC inspector reviewed Wolf Creek inspection (QA/QC) procedures and related documentation and determined that the established proce-dures and instructions assure adequate control of proposed, identified, and approved design changes; identified deviations (nonconformances or deficiency reports); and unusual problems (nonconformances,
I deficiency reports, and IEEE Standards and NRC requirements).
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NRC inspector reviewed documentation, including the following:
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Selected nonconformance and deficiency reports, and the dis-
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position of the identified topics Selected design change requests, including review, approval, and
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disposition QCP-X-304, Cable Termination, Revision 2, dated January 27, 1982
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Becht 1 Drawing E-01013, Installation, Inspection, and Testing
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Details for Electrical Equipment and Cable
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Westinghouse Electric Corp., Wolf Creek Generating Station,
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" Traveler Package Control Procedure," SAP-EII-007, Revision 0.
No violations or deviations were identified in this portion of the inspection.
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Cable Redundancy and Separation The NRC inspector reviewed Wolf Creek cable separation requirements, procedures, and instructions.
The NRC inspector determined that the applicant meets the separation criteria, redundancy requirements, and separation of cables (power, instrum9at, and control) and quality assurance implementing procedures by reviewing the following:
Computer printout of electrical equipment / instruments, dated
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April 2, 1982
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Computer printout of cable and termination status report, dated
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May 21, 1982 Jumper Report, " Wolf Creek Nuclear Project," issue 36, dated
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April 2, 1982 Bechtel Drawing E-7000, " Basic Electric Termination Schedule,"
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issue 35, February 10, 1982 Bechtel Drawing E-17000. (Site unique cables in power block
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listed), dated February 10, 1982 Field Change Requests (selected)
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Design Change Requests (selected)
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Cable Termination Cards (Daniel file)
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QC Cable Termination Cards (vault) NOTE:
Information identical
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to Cable Termination Cards
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lished procedures are followed, as specified, the as-installed records will reflect that the safety-related cable conforms to the applicable separation criteria.
The cable separation requirements,
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as specified in the applicable procedures and indicated on the drawings and specifications, were reviewed by appropriate KG&E or contractor personnel to assure that cable installation separation criteria are met.
The procedures specified how redundant circuits would be routed and separated and routing cards are provided to provide routing information to the work crews and QA personnel.
The procedures and routing cards and related information provide criteria for the separation of power cables from instrument and control cables, including reactor protection system cable No violations or deviations were identified in this portion of the inspection.
f.
Inspection and Testing The NRC inspector reviewed applicable site procedures and Chapter 17 of the SNUPPS (Wolf Creek) SAR to ascertain that the quality assurance responsibilities and requirements had been established. A review of the following documentation verified that the Wolf Creek organization conforms to the facility (SNUPPS) QA Program as described in Chapter 17 of the SAR:
WP-I-06, " Safety Tagging," Revision 2, dated August 4, 1982
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QCP-X-300, " Installation of Electrical Raceway," Revision 8,
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dated April 15, 1982 Bechtel Drawing E-5000, " Electrical Cable and Raceway List"
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Bechtel Raceway Drawing E-OR Series
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QC Raceway Installation Card, Revision 3
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Quality Raceway Checklist, Revision 5
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QCP-X-302, " Installation of Electrical Raceway Supports,"
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Revision 9, dated April 22, 1982 QCP-X-303, " Installation of Cable," Revision 3, dated July 27,
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1981 Bechtel Drawing E-01013, " Installation, Inspection, and Testing
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Details for Electrical Equipment and Cable" t
Administrative Procedure, AP-VI-04, " Calibration and Control of
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Construction Instruments and Tools" QCP-X-304, " Cable Termination," Revision 2, dated January 27,
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1982 Westinghouse Electric Corp., Nuclear Service Division,
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Traveler AB-07000-1, " Electrical Termination," Revision 0, dated August 4, 1982 l
Westinghouse Electric Corp., Wolf Creek Generating Station,
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" Traveler Package Control Procedure, SAP-EII-007, Revision 0 Westinghouse Electric Corp., Wolf Creek, " Electrical Flexible
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Conduit and Cable Terminations," SAP-EII-004, Revision 2
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The NRC inspecter's review of the above procedures indicated that the construction testing and inspection procedures of installed electric cables, terminations, and raceways (cable ways) are established and
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being adhered to during testing and inspection.
The procedures provide for adequate inspection and testing, as specifiad, of related materials, components, and special tools (e.g., cable insulation, compartment boundary seals, and fire retardent coatings).
The results of inspections are transmitted to responsible QA and management personnel for review, approval, and permanent storage or documentation.
The acceptance criteria are specified in the applicable testing and inspection procedures.
No violations or deviations were identified in this portion of the inspection.
g.
Cable NDE After Installation The NRC inspector examined the licensee's procedures for verification cf cable NDE.
The following procedures were judged to satisfy the requirement:
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Quality Control Procedures QCP-X-304, " Termination of Cable,"
Revision 6, dated June 2, 1982 Work Procedures WP-X-304, " Termination of Cable," Revision 5,
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dated February 23, 1982 No violations or deviations were identified in this portion of the inspection.
h.
Handling and Installation The NRC inspector examined the licensee's procedures pertaining to the handling and installation of cable, termination components and related equipment (cable raceways ar.d raceway supports).
It appears that the licensee has adequate procedures established for the in-staller, supervisor, and QA and QC personnel.
The following procedures were reviewed:
Work Procedure WP-X-303, " Installation of Cable," Revision 7,
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dated February 10, 1982 Quality Control Procedure QCP-X-303, " Installation of Cable,"
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Revision 4, dated June 4, 1982 Work Procedure WP-X-304, " Termination of Cable," Revision 5,
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dated February 23, 1982 Quality Control Procedure QCP-X-304, " Termination of Cable,"
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Revision 6, dated June 2, 1982
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Work Procedure WP-X-300, " Installation of Electrical Raceway,"
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Revision 10, dated April 23, 1982 Quality Control Procedure QCP-X-300, " Installation of Electrical
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Raceway," Revision 8, dated April 15, 1982
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Work Procedure WP-X-302, " Installation of Electrical Raceway
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Supports," Revision 5, dated November 30, 1981 Quality Control Procedure QCP-X-302, " Installation of Electrical
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Raceway Supports," Revision 9, dated April 22, 1982 Administrative Procedure AP-VI-04, " Calibration and Control of
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Construction Instruments a'nd Tools" Quality Control Procedure QCP-I-02, " Calibration of Specific
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Test and Inspection Instruments and Equipment," Revision 8, dated May 18, 1982 Westinghouse Electric Corp., Nuclear Service Division,
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Traveler AB-07000-1, " Electrical Termination," Revision 0, dated August 4, 1982 Westinghouse Electric Corp., Wolf Creek Generating Station,
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" Traveler Package Control Procedure," SAP-EII-007, Revision 0 Westinghouse Electric Corp., Wolf Creek, " Electrical Flexible
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Conduit and Cable Tc"minations," SAP-EII-004, Revision 2 No violations or deviations were identified in this portion of the inspection.
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Raceway (Cableway) Separation and Protection The NRC inspector audited the licensee's QC procedure established for raceway separation and protection.
The following quality control procedure was judged to be adequate.
QCP-X-300, " Installation of Electrical Raceway," Revision 8,
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dated April 15, 1982 No violations or deviations were identified in this portion of the l
inspection.
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11.
Review of Licensee's QA Audit Reports The NRC inspectors reviewed the last three licensee QA audits of electric cable installation and associated equipment.
The reports were examined to determine whether the required audits were performed and whether defi-ciencies identified were corrected (or being corrected in a timely manner),
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and documented.
Also, the reports were examined to ascertain whether the corrective action was such that repetition of the deficiency and similar deficiencies, would be precluded.
The audit documents examined are as follows:
Kansas Gas & Electric Co. Audit K74, " Identification and Installation
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of Electrical Cable," dated August 16, 1982 Daniel International Corp., response to KG&E Audit K74, dated
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September 15, 1982 Kansas Gas & Electric Co. Audit K64, " Electrical Equipment," dated
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March 22, 1982 Kansas Gas & Electric Co. Audit K004, " Instrumentation Installation,"
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dated February 15, 1982 The licensee's audit program was found to satisfy NRC requirements.
No violations or deviations were found in this portion of the inspection.
12.
Safety Related Components I - Review of Quality Records The inspector reviewed the pertinent quality related work and inspection (QC) records relative to the pressurizer, pressurizer support, and the boron injection tank.
During this inspection, the inspector determined that the records were in conformance with the Wolf Creek (Kansas Gas and Electric Company) established procedures, that these reviewed records reflected the work accomplished, and that the work was consistent with the applicable requirements in the following areas:
a.
Storage Inspection i
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The pressurizer, the pressurizer support and the boron injection tank had been placed in their respective locations and work had been completed.
Intpections are not required for these components on a set frequency; however, inspections as appropriate are being conducted.
b.
Installation Inspection The required scope of inspection activities that had been performed was recorded.
The appropriate records confirmed that specifications l
and installation procedures were met.
Cleanliness requirements were
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adhered to and these procedures required appropriate cleanliness standards.
c.
Material and Fabrication Certifications / Test Reports I
The available records confirmed that the pressurizer and boron injection tank met quality rer;uirements, including specifications, l
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manufacturing and fabrication requirements, and specified qualifi-cation testing.
The reviewed records correlated with the pressurizer and boron injection tank identification. The certification system met NRC requirements, d.
Nonconformance/ Deviation Reports The established procedures had been followed for identified ncnconformance/ deviation reporting.
The nonconformances and devi-ations had been properly resolved and documented.
The reviewed records were legible, complete, had been reviewed / approved, and were properly controlled and stored.
The records adequately identified the specific component, the materials from which the completed
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components (pressurizer and boron injection tank) were manufactured and erected at their respective locations, e.
QA Audits The inspector reviewed the QA audit records for the two most recent audits associated with the pressurizer and boron injection tank.
The inspector ascertained that the applicable requirements were met in the following areas:
Records
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The reviewed records confirmed that the QA audits performed were of the scope and frequency required for these specified com-ponents.
No deficiencies were identified in these specific audits.
The QA auditors had been previously quali.fied by the licensee for the audit areas in which the auditors were assigned.
Documents reviewed for the pressurizer, pressurizer support, and the boron injection tank included the following:
(1) Pressurizer Base Suppo=t Drawing I-TBB03-01, including the location of the 24 carbon steel and 21 stainless steel shims and the bolted connection control record, Sheets C-1 through C-6, Revision 2 (dated November 14, 1979)
Special Instruction Sheets Z-1, Z-2, and Z-3 Daniel International Surveillance Report on Quality Control Welding (September 15, 1980) (nuts loosed after QC acceptance as snug tight)
Deficiency Report No. 1SD4535M (August 14, 1980) and Drawing /
150 D-1, Revision 2 (September 15, 1980)
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Deficiency Report No. ISD4538M (August 17, 1980) - failed to have proper documents for recording purposes Deficiency Report No. ISD3708M (April 10, 1980) ten gouges greater than 1/32" in depth Certification of Nondestructive Examination - Report
- PBT-MT-858 (June 10, 1980)
(2) Pressurizer Westinghouse Drawings (TBB03-Q-02) 1104J92 (outline) and 1101J22 (general arrangement)
Entry permit - to block off 6" pipe nipples (July 28, 1980)
Surveillance Report (Daniel International)
gouge in top nozzle weld prep area and manway cover did not adequately seal out foreign material or keep foreign material from entering the pressurizer (July 30, 1980)
Nonconformance Report (NCR) ISN2301M (July 31, 1980) - spray nozzle end prep damaged during shipping NCR 1SN1997M (April 29, 1980) - Pitting and gouges for rework Deficiency Report 1SD4538M (August 14, 1980) - spray nozzle end prep damaged during shipping (some damage as reported in NCR 1SN2301M, above)
Bill of Material - Drawing TBB03(Q) Sheet B-1 Special Receiving, Storage, and Maintenance Instruction, and Inspection Requirements - I-TBB03(Q)-02, Revision 6 (October 14, 1980)
Special Instruction Sheets Z-1 through Z-10 with assorted revisions (Revision 1 through Revision 6)
i Special Instruction Sheets Z-1 through Z-10, Revision 0 (July 17, 1980)
Bechtel Piping Drawing No. M03BB01 (Q)
(3) Boron Injection Tank The boron injection tank (BIT) was installed by Reco.
This BIT is designated as component TBN01.
The following records were included in the records review:
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Material Certifications Welding Personnel Qualification Certifications NDE records Cleanliness records No violations or deviations were identified in this portion of the inspec-tion.
13.
Safety-Related Components II - Review of Quality Records The inspector reviewed the pertinent quality related work and inspection (QC) records relative to pressurizer relief valves, pressurizer safety valves, and the block valves for the relief valves.
The inspector ascer-tained that the records are in conformance with established procedures, that these records reflect work accomplished, and that this work is consistent with applicable requirements in the following areas:
a.
Storage Inspection These components are installed in their specified locations and are covered or otherwise protected in their in situ positions.
Inspections are made to assure adequate protection.
Records are being maintained to confirm that these components are not damaged.
b.
Installation Inspection The required scope of inspection was performed and recorded on each of these valves.
The related records confirm that specifications and installation procedures were adhered to during installation.
The-cleanliness requirements were met.
c.
Material and Fabrication Certifications / Test Reports The associated records confirm that each of these components met quality requirements, including specifications, manufacturing and installation requirements, and specified qualification testing. The records identification system correlates each valve with its unique identification.
The certification system meets t!RC requirements.
d.
Nonconformance/ Deviation Reports The established procedures were followed in identifying and resolving NCR's and deviations.
The records reviewed by the inspector were legible, complete, reviewed / approved and controlled.
Records identi-fied the specific components, the materials and the work or testing performed.
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QA Audits The QA records of the two most recent QA audits associated with each of these safety-related components were reviewed.
The inspector ascertained that applicable requirements were met in the following:
(1) Records The records confirmed that these two audits were performed and that the scope and frequency specified were met.
Deficiencies identified during the audits were corrected and documented.
Tnere were no indications of repetition of the deficiencies or similar deficiencies during these two QA audits.
The auditors were qualified to perform the assigned audit work.
(2) Pressurizer Safety Valves (General Information)
Valves designed to relieve 420,000 pounds steam / hour.
Each valve had been hydrostatically tested at 3730 psi Wolf Creek designation numbers BB 8010A, BB 80108, and BB 8010C i
Valve serial nos. N60446-00-001, N60446-00-02, and N60446-00-03 Crosby Valve and Gage Company designated type 6RV88MTTB valves Documents reviewed by the inspector included tng following:
MRR # 21346 P. O. WE-250051 Material Certifications PT/MT and UT records Review of stress reports (certified by Westinghouse)
Pressure test records Valve seat tightness test records Performance test records Welding personnel qualification certifications NDE personnel qualification certifications ASME B&PV Code Form NV-1 for each valve Visual and dimensional inspections Cleanliness, paint and packing documentation (3) Power Operated Relief Valves (General Information)
Serial numbers P 103 and P 105 Wolf Creek designation numbers PCV-455B and PCV-455C Documents reviewed by the inspector included the following:
Traveler # I-M03BB04(Q)
Material Certifications Heat Treatment records
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PT, MT, UT, and Visual inspection records Dimensional inspection records
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Pressure test records Welding Personnel qualification certifications NDE personnel qualification certifications ASME B&PV Code Form NV-1 for each valve Stress reports Cleanliness and packaging documentation (4) Block Valves for Relief Valves (General Information)
The block valves are 3" diameter motor operated gate valves Documents reviewed by the inspector included the following:
MRR # 12930 Westinghouse Drawing 214224 RIR # 12930 - Receiving inspection report (Quality release)
RSIC # 12930 - Receiving, storage inspection check (Quality release)
ASME B&PV Code Data Report # W-15122 Serial No. 0006 - Valve I. D. 3GM88FNB Serial No. 0005 - Valve I. D. 3GM88FNB Drawing IM13BB04-Q Weld Control Record F-101 (Weld Nos. F-001 through F-023)
Engineering Change Reports ECR No. I-M03BB04(Q) ECR-01 ECR No. I-M13BB(Q) ECR-02 ECR No. I-M13BB04(Q) ECR-03 RT on F-021 - IM13BB04(Q)
NCR # ISN4663P. W. - incorrect welding rod may have been used. Weld cut out and rewelded.
NCR acceptable.
Deficiency Report No. 1SD9549P (February 16, 1982) -
Spool fabricated too short.
New spool.
Deficiency acceptable.
Deficiency Report No. ISD10019P - Craft error.
Piping not installed per design.
Corrected and acceptable.
Deficiency Report No. INN 3234MW - Orientation incorrect.
Corrected by orienting per design and acceptable.
PT inspection records No violations or deviations were identified in this portion of the inspec-tion.
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14.
Exit Interview The NRC inspectors met with licensee representatives (denoted in para-I graph 1) and Messrs. T. E. Vandel and W. S. Schum, NRC Resident Reactor Inspectors, at the conclusion of the inspection on October 22, 1982. The~
NRC inspectors sumarized the purpose, scope, and findings of the inspec-tion.
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