IR 05000352/1980001
| ML19305D485 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/07/1980 |
| From: | Ebneter S, Gage L, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19305D480 | List: |
| References | |
| 50-352-80-01, NUDOCS 8004150143 | |
| Download: ML19305D485 (4) | |
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gs U. S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
REGION I
i 50-352/80-01 Report No.
50-353/80-01
50-352 Docket No.
50-353 CPPR-106
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License No.
CPPR-107 Priority Category A
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Licensee:
Philadelphia Electric Company 2301 Market Street
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Philadelphia, Pennsylvania 19101
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Facility Name:
Limerick Generating Station, Units 1 and 2
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Inspection At:
Philadelphia and Limerick, Pennsylvania j
Inspection Conducted:
danuary 9-11 and 16, 1980 Inspectors:
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/- 2.5~- PO L. Gage / React /r Inspectar date N @/s2fn
/-2 D fd G. Walton, Reactor Inspector date i
l date E/7[S'd Approved by:
e S. Ebneter, Chief, Engineering Support date Section #2, RC&ES Branch i
Inspection Summary-
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Inspection on January 9-11 and 16, 1980 (Report Numbers 50-352/80-01 and 50-353/80-01 Areas Inspected:
Routine, unannounced inspection by regional-based inspectors of work activities and records associated with (1) the quality-assurance program
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for the task of installing the reactor pressure vessel internals and the control rod drive hydraulic and neutron monitoring system, and (2) the inservice inspec-tion (preservice) for Unit 1.
The inspection involved 26 inspection hours on
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site by two NRC regional-based inspectors.
Results:
No items of noncompliance were identified.
Region I Form 12
(Rev. April 1977)
800.4150 / %
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DETAILS 1.
Persons Contactea Philadelphia Electric Company (PEco)
- D. Clohecy, QA Engineer
- J. Corcoran, Field QA Branch Head
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O. DiPaolo, QA Engineer
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- W. King, Construction Engineer Bechtel Power Company (Bechtel)
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- R. Faust, Subcontracts Engineer
- H. Foster, Project Field QC Engineer
- G. Kelly, QA Engineer
- E. Klossin, Project QA Engineer
- L. Pons, Resident Engineer
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- A. Weedman, Project Field Engineer Reactor Controls, Inc.
i S. Kepler, Site Manager U.S. Nuclear Regulatory Commission
- J. Mattia, Resident Inspector i
- Denotes personnel attending exit interview.
2.
Review of the Contractual Documentation i
The inspector reviewed the contractual documents that established the
requirements for the task of installing the reactor pressure vessel inter-nals and the control rod drive hydraulic and neutron monitoring system.
These included.
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Bechtel Specification 8031-M-108, titled, "RPV Intervals Installa-tion...," dated November 18, 1976.
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Bechtel Specification 8031-M-110, titled " Design Specification for
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Control Rod Drive Hydraulic and Neutron Monitoring Systems...," dated December 14, 1978.
i No items of noncompliance were identified.
3.
Review of the Implementing Documentation The inspector reviewed the implementing documents for the installation tasks l
described in paragraph 2.
These included:
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G.E. procedure 22A4111, titled " General Instruction for Reactor I
Assembly," Revision 0 b.
G.E. procedure 22A2724, titled " Equipment Storage Requirements," Rev. 3 c.
Reactor Controls' " Quality Assurance Manual," dated September 11, 1978 l
(General Electric, as the nuclear steam system supplier, provided the i
assembly and storage procedures; Reactor Controls, as the Bechtel Subcon-tractor for the installation tasks, provided the QA manual.)
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The inspector noted that the Reactor Controls' QA manual did not define how their organization would perform design verification, although it
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appeared that there was a considerable design effort involved in the instal-I lation task.
(Bechtel's letter of September 21, 1976 to PECo, in which the
installation-task bids were evaluated, stated that one vendor declined to bid because "...the work scope involved too much analysis and design...").
j Furthermore, PECo had recently (November 14, 1979) identified as many as 15 hangers associated with 1-inch control rod drive insert and withdrawal
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piping as being seismically unqualified in their Peach Bottom Unit 2
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facility:
Reactor Controls performed this installation.
Therefore, this I
was identified by the inspector as an item of concern.
PECo stated that they would determine, in detail, how Reactor Controls would perform design verification.
This information would be made avail-able to an NRC inspector during a subsequent inspection.
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No items of noncompliance were identified.
4.
Inservice Inspection (Preservice) Unit 1
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l The inspector witnessed volumetric (ultrasonic) examinations on two main i
steam system welds (M5005 and M5006) performed by Nuclear Energy Services.
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The welds were examined for compliance with the ASME B&PV Code Section XI, l
1974 Edition including the Summer 1975 Addenda and Appendix III of the
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Winter 1975 Addenda.
The effort was reviewed to determine that:
Procedure 80A1566, Revision 2 is being followed
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Examination personnel are qualified and familiar with examination
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methods I
Calibration, equipment selection, extent of coverage, scanning direc-
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tions and speeds, and sensitivity are in accordance with the approved
procedure l
Reference level for monitoring and recording discontinuities is in
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compliance with the approved procedures Acceptance and rejection standards are followed
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i All areas reviewed met the requirements of ASME Section XI.
No items of noncompliance were identified.
5.
Follow-up of Calibration Documentation for Automatic Welding Machine
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(Refer to I.E. Inspection Reports 50-352/79-14 and 50-353/79-13)
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l The inspector examined the calibration documentation provided by the G.E.
letter of January 8,1980 to PECo.
No items of noncompliance were identified.
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Exit Interview
The inspector met with the licensee representatives (denoted in paragraph 1)
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The inspector summarized the purpose and scope of the
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inspection and the findings.
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