IR 05000440/1980013
| ML19339B001 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/28/1980 |
| From: | Key W, Konklin J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19339A988 | List: |
| References | |
| 50-440-80-13, 50-441-80-12, NUDOCS 8011060133 | |
| Download: ML19339B001 (9) | |
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O U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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) Reports No. 50-440/80-13; 50-441/80-12 Docket Nos. 50-440; 50-441 Licenses No. CPPR-148; CPPR-149 i
Licensee: The Cleveland Electric Illuminating Company
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Post Office Box 5000 Cleveland, OH 44101
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Facility Name:
Perry Nuclear Power Plant, Units 1 and 2
Inspection At: Perry Site, Perry, Oli Inspection Conducte July 30 - August 1, 1980 0-e->at f
'onklin fi ~2 7-TO Inspectors:
J. E.
Nfgic e
Al. J. Key illiams,h
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CE c
Chief f-2 8 - 80 Approved By:
C. C.
Projects Section 2 Inspection Summary
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Inspection on July 30 - August 1, 1980 (Report No. 50-440/80-13; 50-441/80-12)
Areas Inspected:
Licensee and contractors' procedures, work activities, and
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j QA records related to design control; procedures and work activities related to installation of containment penetrations; work activities and radiographic records related to installation and welding of reactor coolant loop piping;
work activities related to installation and welding of other safety-related
piping. This inspection involved a total of 44 on-site inspector-hours by
two NRC inspectors.
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Results: No items of noncompliance were identified.
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i DETAILS
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Persons Contacted
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i Principal Licensee Employees
- M. Edelman, Manager, Nuclear QA Department
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- G. Groscup, Manager, Nuclear Engineering Department l
- W. Kacer, General rapervising Engineer, CQS
- R. Vondrasek, Supervisor, Quality Engineering
- E. Riley, Contracts Manager
- P. Martin, General Supervising Engineer, PQS
- J.
Kline, General Supervising Engineer, NED
- B. Barkley, General Supervising Engineer, Design a
j Other Personnel
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- D. Fitzpatrick, Site Construction Manager (KEI)
- T. Arney, Site Program Manager (GAI)
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- P. Gibson, CQC Supervisor (KEI)
R. Crofton, Construction Quality Engineer (GAI)
R. Williams, Construction Quality Engineer (GAI)
G. Parker, Construction Quality Engineer (GAI)
R. Mathews, Construction Quality Engineer (GAI)
K. Pech, Assistant Site Manager (GAI)
B. Ware, Supervisor (GE I&SE)
J. C naan, QC Engineer (GE I&SE)
J. f.eele, QA Supervisor (Pullman)
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J. McPherson, NDE Supervisor (Pullman)
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Accompanying NRC Personnel
- C. Williams, Projects Section Chief, RIII
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- J.
Hughes, Perry Resident Inspector, RIII
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- T. Gibbon, Commission Staff, HQ
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- Denotes those presert at the exit meeting on August 1, 1980.
The inspectors also contacted other licensee and contractor employees, including craftsmen and members of the quality, technical, and engineering staffs.
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Section I
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Prepared by J. E. Konklin Reviewed by C. C. Williams, Chief Projects Section 2
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Review of Licensee's Design Control System The RIII inspector initiated a review of the licensee's site design control system to determine whether adequate procedures are in place for design control, whether the procedural requirements are being satisfactorily imple-meuted by the licensee and by the site contractors, and whether the site quality assurance records accurately reflect the results of the design control activities.
During this inspection the inspector reviewed the licensee's procedures related directly to design control, the General Electric Company QA require-ments related to design control, and selected design change documentation related to the nuclear steam supply system (NSSS) installation activities being performed by General Electric. Other areas of site design control will be reviewed routinely in future inspections.
1.
Site Design Control Requirements The inspector reviewed the following requirements documents, which include twelve site-wide procedures relating to design control and the General Electric QA manual section relating to design control:
a.
CEI Corporate Nuclear Quality Program Procedure 0300, Revision 1, effective November 5,1979, " Design Control".
b.
GAI Interface Procedures, Volume 4, Procedure 4-0200, Revision 6, dated January 15, 1980, Section 3.0, " Design Assurance".
c.
CEI Nuclear Design and Procurement Instruction 35-0605, kevision 1, effective October 24, 1979, " Perry Construction Work Authorization".
d.
CEI Nuclear Design and Procurement Instruction 35-0606, Revision 1, effective March 14, 1980, " Processing Construction Engineering Change Notices".
e.
CEI Nuclear Design and Procurement Instruction 35-0607, Revision 0, effective April 25, 1980, " Processing Fabrication Engineering Change
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Notices".
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CEI Nuclear Design and Procurement Procedure 3-0301, Revision 1, effective July 30, 1979, " Field Variance Authorization".
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CEI Nuclear Design and Procurement Procedure 3-0302, Revision 3,
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effective March 14, 1980, " Construction Specification - Related
Engineering Change Notices".
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CEI Nuclear Design and Procurement. Procedure 3-0303, Revision 2, effective March 14, 1980, " Construction Drawing - Related Engineering Change Notices".
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CEI Nuclear Design and Procurement Procedure 3-0305, Revision 0, effective March 14, 1980, " Field Disposition Instructions / Field
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Deviation Disposition Requests."
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CEI Nuclear Design and Procurement Procedure 3-0306, Revision 0, effective April 25, 1980, " Fabrication Engineering Change Notices".
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CEI Nuclear Design and Procurement Procedure 3-0350, Revision 1, effective May 16, 1980, " Construction Changes".
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CEI Corporate Nuclear Quality Assurance Program Procedure 0500, Revision 1, effective November 5, 1979, " Instructions, Procedures, and Drawings".
CEI Construction Quality Section Procedure 2-0303, Revision 1, m.
j effective April 9, 1980, " Field Design Change Review".
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GE's General Nuclear Quality Assurance Manual for the Perry Nuclear Power Plants, Revision 0, dated December 10, 1979, Section 3.0,
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" Design Control".
2.
Review of Specific Design Changes The inspector reviewed selected CEI and GAI records relating to design changes, including logs or files for nonconformance reports (NR's),
engineering change notices (ECN's), field questions (FQ's), field variance authorizations (FVA's), field disposition instructions (FDI's),
field deviation disposition requests, (FDDR's), corrective action requests (CAR's), and construction work authorizations (PCWA's).
The inspector selected at random and reviewed five FDDR's and one FDI relating to General Electric activities and five FQ's relating to Newport News activities and then located and reviewed the ECN's and FVA's associated with the FD1 and the FQ's.
The following specific documents were reviewed:
a.
FDOR No. KL1-045, dated December 7, 1979, titled, "RPV Recire Nozzle Modification".
b.
FDDR No. KL1-050, dated January 8, 1980, titled, "RPV Recirc Nozzle Modification".
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FDDR No. KL1-057, dated February 15, 1980, titled, " Reactor
i Vessel".
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FDDR No. KL2-030, dated April 8, 1980, titled, "RPV Nozzle
Modification".
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FDDR No. KL1-064, dated May 15, 1980, titled, "Recirc Discharge
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Block Valve".
f.
FDI No. 41/82412, Revision 0, dated June 20, 1980, titled,
" Inclined Fuel Transfer System (IFTS)", and t he associated ECN No. NH05214, issued on May 9, 1980.
g.
FQ No. 8210, dated May 23, 1980, titled, " Unit 2 Upper Drywell Liner", and the associated ECN No. 4588-96-61, dated May 22, 1980.
h.
FQ No. 8216, dated Ma y 27, 1980, titled, " Unit 1 Polar Crane Girders", aad the associated FVA No. 2037-17-15.
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FQ No. 8248, dated May 28, 1980, titled, " Unit 1 Personnel Access Lock Shield Doors and Monorail", and the associated ECN No. 4703-85-85, dated June 11, 1980.
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FQ No. 8707, dated June 23, 1980, titled, " Unit 1 Personnel Airlock Shield Doors", and the associated ECN No. 4875-96-64, dated July 7, 1980.
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FQ No. 8733, dated June 9, 1980, titled, " Unit 1 Embedment Plate -
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Upper Drywell Wall", and the associated FVA No. 2093-96-48.
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i The inspector also reviewed sixteen other ECN's selected at random to determine whether appropriate QA invelvement had been obtained.
3.
CEI/GAI/GE Interface Based on the review of procedures anc design change documents noted above, the inspector discussed with the licensee and with GAI engineering personnel the interfaces between CEI/GAI and General Electric for the NSSS installation work. The inspector expressed concern regarding two interface areas:
a.
FDI's and FDDR's initiated by General Electric are reviewed by GAI only for interface considerations, and not fcr engineering adequacy, b.
On the FDI and FDDR's reviewed, there were no CEI or GAI QA reviews noted and the CEI procedures do not appear to require such a QA review.
In addition, a CEI audit of General Electric in late April 1980 found that GE has not been performing QA/QC reviews on FDDR's.
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The licensee informed the inspector that a significant effort is
undervay to redefine the CEI/GAI/GE interfaces, including the planned issuance of new procedures.
The inspector informed the licensee that this will be designated an unresolved item (50-440/80-13-01; 50-441/80-12-01) pending review of the licensee's corrective actions during fut.re RIII inspections.
No items of noncompliance were identified.
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Section II
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Prepared by W. J. Key Reviewed by D.11. Danielson, Chief Engineering Support Section 2
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1.
Containment Penetrations The following Pullman welding, quality control and installation procedures for piping and penetrations were reviewed by the inspector:
Welding Procedures l
l GWS-CS-III, General Welding Standard for Welding ASME-P1, Carbon Steel Materials
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1T1-III-1-K1-12, P1 to P1 IT1-III-1-BR-2, P1 to P1 IT10-III-1-0B0-1, P1 to P1 i
IT11-III-1-0B-2, P1 to P1 IT12-III-1-0B-12, P1 to P1 13-III-1-0B-2-F3/F4, P! to P1 GWS-SS-III, General Welding Standard for ASME P8 Stainless Steel Materials 24-III-8-K1-12, P8 to P8 26-III-8-0B-2 P8, to P8 408-III-45-0B-1, P45 go P45
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Quality Control Procedures I
11-4, Inspection and Testing Personnel Control and Administration of i
Training, Examination, Qualification and Certification 11-8, Welder Performance Qualification V111-3, control of Welding Materials (Field)
1X-3, Fabrication and Field Installation Specification for Nuclear Power Plant Components, Piping Systems and Appurtenances X111-11, Standard Method of Protecting Ends of Fabricated Pipe for Nuclear Service Personnel Qualifications Qualification records of the following NDE and welder personnel were reviewed for the requirements of ASME Section III and IX.
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Welder Qualifications
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E. Hiam Stamp BX S. J. Birch Stamp KG j
D. M. Wigner Stamp TA
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NDE Qualifications RT PT MT UT VT J. McPherson II II II J. Steele III III III III III
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J. Hevey I
II D. Denlinger I
II Weld Material Control The inspector examined the warehouse storage facility for welding
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materials and issuance to the field rod rooms. The inspector also
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i examined control at rod issue room at elevation 599' in tbc auxiliary
building.
The following storage ovens and portable rod ovens were examined for calibration and contents.
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Rod oven S/N-3 Rod oven S/N-10
Rod oven S/N-12 Rod oven S/N-13 i
Portable ovens, S/N-39, 167, 82 and 135.
Chemtron electrodes E7018 Heat No. 401B4021-3/32" Heat No. 402B1441-1/8" Heat No. 432A7641-5/32"
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Master Dial Thermometers 3/N-FM0-500/GK0-501 Observation of Activities The inspector observed the fit-up, tack welding, and root pass welding of suppression pool suction penetration No. P-102 to containment vessel sleeve and work in process on penetrations P-103, P-401, P-402, P-403,
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and P-101.
In-process welding on the residual. heat removal system, weld No. 09 on ISO 1-E12-41, and weld No. 14, on ISO 1-E12-31, were observed. The
inspector reviewed radiographs of the following completed welds in the following systems.
I RHR system, ISO 1-E12-35, Welds No. 06 and 05 Low pressure core spray system (LPCS)
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No items of noncompliance or deviations were identified.
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Safety Related Piping i
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j Procedures
The following GEI and SE procedures were reviewed by the inspector.
i GWP-1003, Welder Performance Qualifications GWP-1010, Weld Metal Control and Storage i
GEP-1010, Weld Metal Control and Storage
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GEP-AP-0012, Examination and Testing Personnel Qualification and Certification i
GEP-GQI-0005, Material Control
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Gk'P-1000, General Welding Procedure for Nuclear Services Projects
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GWP-1001, General Weld Repair Procedure Observation of Activities
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During this inspection the inspector observed work being performed on
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the following:
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Fit-up and welding of main steam quencher S/N-8CN770-8A18 j
Alignment and tack welding of main steam quencher 8CN770-8A7 j
Reviewed traveler T1-B-21-07 for main steam quencher 8CN770-8A4 The inspector examined the rod issue room for GE I&SE located in the auxillary building and checked rod ovens and control of portable ovens for calibration and control No items of noncompliance or deviations were identified
' Unresolved Items
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Unresolved items are matters about which more information is required to determine whether they are acceptable items, items of noncompliance, or
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deviations. An unresolved item disclosed during the inspection is discussed in Section I, Paragraph 3.
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Exit Interview
The inspectors met with licensee representatives (denoted under Persons Contacted) at the conclusion'of the inspection on August 1, 1980. The inspectors summarized the purpose and findings of.the insepetion. The
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licensee acknowledged the findings reported herein.
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