IR 05000369/1980033
| ML19340F095 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/11/1980 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19340F091 | List: |
| References | |
| 50-369-80-33, 50-370-80-18, NUDOCS 8101160734 | |
| Download: ML19340F095 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION
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.E REGION 11 o,
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101 MARIETTA ST N.W.. SUITE 3100
V g ATLANTA, GEORGIA 30303
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Report Nos. 50-369/80-33 and 50-370/80-18 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire, Units 1 and 2 Docket Nos. 50-369 and 50-370 License Nos. CPPR-83 and CPPR-84 Inspection at McGuire Site near Lake Norman, North Carolina and Engineering Offices, Charlotte, North Carolina.
Inspector:
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." ryant, Section Chie,, RCES Branch Date Signed SUMriARY Inspection on November 4-7, 1980 Areas Inspected This routine announced inspection involved 28 inspector-hours on site in the areas of IE Bulletins, and licensee identified items.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. H. Bradley, Manager, QA Engineering and Servf ces Division (E&SD)
D. Z. Hathcock, Lead Auditor, AD C. A. Bell, Supervisor, QA Mechanical, E&SD J. C. Rogers, Project Manager T. E. Touchstone, Senior Construction Engineer i
E. B. Abram, Project Manager, Hangers
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A. P. Cobb, Senior Design Engineer, McGuire Support Group W. O. Henry, QA Manager, Construction E. B. Miller, Senior QA Engineer
- R.
H. Ledford, QA Engineer G. B. Robinson, QA Engineer
- L.
J. Bare, Assistant Engineer, Licensing R. Helms, QC Inspector, Electrical J. Kisnet, Electrical Foreman NRC Resident Inspector (RI)
T. Donat l
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 7, 1980 with i
those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings None.
4.
Unresolved Items There were no new unresolved items identified during this inspection.
5.
Independent Inspection The inspector observed work.inside the Unit I and 2 reactor. building, and the auxiliary building, talked to various craf t personnel, and discussed construction status with the project engineer and the NRC senior resident
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-2-inspector. The current problems related to piping support and restraint design uncertainties may delay the January 1981 planned fuel loading date for Unit 1.
6.
IE Bulletins (IEB) Unit 2 Only These IEBs have been or will be inspected by the RI for Unit 1.
a.
(Closed) IEB 80-20, Failure of Westinghouse Type V-2 Spring Return to Neutral Control Switches. The inspector reviewed the DPC response to Region II dated August 20, 1980. The subject switches are not used or planned for use in safety-related applications at the McGuire Nuclear Station.
b.
(Closed) IEB 80-19, Failure of Mercury-Wetted Matrix Relays in Reactor Protective Systems of Operating Nuclear Power Plauts Designed by Com-bustion Engineering. The inspector reviewed the DPC response to to Region II dated August 28, 1980.
The subject relays are not used or planned for use in the reactor protective system at the McGuire Nuclear Station, c.
(Closed) IEB 80-16, Potential Misapplication of Rosemount Inc. Models 1151 and 1152 Pressure Transmitters With Either "A" or "D" Output Codes. The inspector reviewed the DPC response to Region II dated July 25, 1980. The subject pressure transmitters are not used or
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planned for use at the McGuire Nuclear Station.
d.
(Closed) IEB 80-09, Hydramotor Actuator Deficiencies.
The inspector reviewed the DPC response to the NRC dated October 15, 1980, the referenced correspondence, the DPC documentation of the required evaluation of the adequacy of the subject equipment, the adjustment of the spring tension of one actuator, and the testing of that adjusted actuator, e.
(Closed) IEB 79-24, Frozen Lines.
The inspector reviewed the DPC response to Region II dated October 31, 1979.
The inspector also reviewed DPC and Nelson Electric Company drawings of the vent and instrumentation lines on the refueling water storage tank and the overflow and recirculating lines that are heat traced, insulated and instrumented.
Protective measures have been taken to prevent safety-related instruments and sampling lines from freezing.
f.
(Closed) IEB 79-03A, Longitudinal Weld Defects in ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and
Engineering Company.
The Region II staff has determined that the response to Region II dated August 5, 1980 is acceptable. DPC has not used, and does not plan to use, the subject pipe in safety-related systems at greater than 85 percent of the Code allowable pressure stresses.
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-3-7.
Licensee Identified Items (LII),10 CFR 50.55(e) (CDR)
a.
(Open) LII 369/80-33-02, 370/80-18-02 Pipe Support Hanger Loads Incorrect.
On October 28, 1980 DPC informed Region II of a potential CDR relative to the subject. During a re-evaluation of piping supports and restraints resulting from a review of LOCA loads, it was noted that a mismatch existed between the piping analysis loads and the hanger design loads.
DPC has initiated a review of the math models and the design loads used by DPC and their design contractor, EDS Incorporated, to properly identify the problems, the causes, and the corrective action program. A DPC response to Region II is due November 2 5, 1980.
The inspector reviewed the subject with the on site hanger senior design engineer and the project hanger manager. The potential CDR appears to be limited to the work by EDS on piping supports and restraints inside the reactor building, the DPC review of EDS work, and the design interface and communications between DPC and EDS. The it actor reviewed the design manual used by DPC onsite for pipe hangers..cside the reactor building, MCSRD procedure 8.0 revision 0 and ;.ne design memos 1-4, 6, and 8-10 relative to MCSRD procedure 8.0.
The inspector also reviewed the Design Engineering QA Program procedure PR 821
" Control of QA Procedure and Manuals", section 6 " Supplementary Procedures" which provides for the control design manuals and wock procedures for QA condition design work. The inspector also reviewed the following Design Engineering QA Program procedures:
PR-840 Internal Audits PR-101 Engineering Calculations PR-901 Document Control PR-931 Design QA Records Collection, Maintenance and Storage MPR-101 Design Documents for Mechanical Systems MPR-130 Mechanical System piping supports and restraints Design Drawings, Field Revisions The inspector also reviewed the following QA Department QA procedures and audits:
QA-160 Performance of Corporate QA Audits QA-210 Department Audit Procedure QA-230 Department At t Scheduling and Followup Audit E-80-2 March d-April 2,
1980 re: IEB 79-02 and 79-14 Audit E-80-3 April 28-June 9,1980, Document Control Discussions with the DPC staff responsible for the auditing and sur-
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l veillance of the de,ign engineering work indicates that their program work does not include the control of design manuals, or work proce-dures used by Design Engineering.
Inspector followup item (IFI)
369/80-33-01 and 370/80-18-01, Document Control of Design Manuals C
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-4-Procedures, is identified as a specific need to review this item further for the overall DPC design work and the design work of their contractors such as EDS, Incorporated.
The DPC response for the subject LII is expected to provide information relative to the control of design documents and the QA audits of DPC and vendor (contractor)
programs.
b.
(Open) LII 369/80-33-03, 370/80-18-03, Additonal Axial Load on Piping Penetration Not Considered. On October 31, 1980 DPC informed Region II of a potential CDR relative to the subject. The initial review of the post LOCA loads of piping supp rus and restraints (paragraph 7.a)
indicates that the containment pressure due to LOCA was not considered as a loading on cold penetration flued heads attached rigidly to piping.
An analysis considering the additional axial loading on the piping, the nearby supports and restraints and the building penetra-tions. A DPC response to Region II is due December 1,1980.
c.
(Closed) LII 369/80-33-04,370/80-14-01, Design Deficiency in Auxiliary Feedwater System (AFS) pumps. The inspector reviewed the DPC responre to Region II dated April 12, 1978.
A safety-related instrumented switchover system has been implemented to automatically align the AFS pump suction to the nuclear service water (NSW) source upon detection of low suction pressure'. Previously operator action was required for suction switchover for the AFS pumps. The inspector reviewed the Unit I shutdown requests 616 and 665 that documents that the work was completed and inspected by October 25, 1978.
The inspector also reviewed the design drawings for the piping and instrumentation for the modifications for Units 1 and 2 (MC-1499, CA-1, CA-12, and MC-2499 CA-1, and CA-12). The inspector observed representative examples of the modified piping and the instrumentation in Unit I and the auxiliary building. This item had not been previously reported for Unit 1; it is closed for both units.
d.
(Closed) LII 370/80-18-04, Westinghouse 7300 Series Process I&C Card.
The inspector cor firmed that (as stated in the November 29, 1979 DPC reponse to Region II) none of the cards at Unit 2 were affected.
Corrective action relative to Unit I will be reported by the NRC Regional Resident Inspector, LII 369/80-10-03.
This item was not previously reported for Unit 2.
e.
(Closed) LII 370/80-14-03, Dropped Rod Analysis Deficiency.
The inspector discussed the subject with the Regional Resident Inspector.
This item has been closed for Unit 1 in report 50-369/80-32. The NRR will consider this item for Unit 2 in the required review of the tech-nical specifications for Unit 2.
f.
(Closed) LII 369/80-10-05, 370/80-06-04, Nelson Motor Control Center (MCC). The inspector reviewed the DPC responses to Region II dated January 10, 1980 and June 9,1980. The inspector reviewed documentation of the corrective action, NCI 9966 and the referenced installation
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specification, MCS-139001-00-75. The inspector discussed the modif *. ations
j with an electrical foreman and a QC inspector.
The work was completed on August 11, 1980 and the inspector observed representative
samples of the corrected terminations of the MCC on Unit 2 panels i
2EMXD and for the upper containment return air fan 2A', incore instru-t ment room air handling unit 2B and the pressurizer #2PWR operated
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safety relief isolation valve 2NC3 IB.
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(Closed) LII 370/80-06-05, Power Operated Relief Valves (PORV) Block Valves. The inspector reviewed the DPC response to Region II dated
January 16, 1980 and documentation that the valves have been returned i
to the vendor and repaired to modify the stem and gate of each valve.
A larger motor operator has been placed on each valve.
h.
(Closed) LII 369/80-10-08, 370/80-06-07, Electrical Cable Qualifica-tions.
The inspector reviewed the DPC response to Region II dated March 27, 1980. Documentation, showing that cables qualified for post accident conditions of 120 days have been installed per shutdown request 2863, was reviewed. Cable installation data sheets for cable with type N.3 insulation in place of cable with G.3 insulation was also reviewed. The cable cards for Units 1 and 2 were dated February 28, 1980 and May 7, 1980. The inspector observed representative samples of the changed cables in accumulator rooms 1A and ID to verify the cable installation data sheets.
i.
(Closed) LII 369/80-10-12,-370/80-06-10, Fire Protective Systems Valve Misapplication. The inspector reviewed the DPC response to Region II dated May 16, 1980. Documentation that the two class H valves have been replaced with class F valves to meet the seismic requirements was examined. Valve numbered 1RF959 and 1RF990 were replaced per shutdown request 2733 and NCI 10806. These valves are common to Units 1 and 2.
j.
(Closed) LII 369/79-28-04, 370/79-16-03, Emergency Feedwater System Design Deficiency. The inspector reviewed the DPC response to Region II dated September 7, 1979, ' drawings MC 1403-1.41-00 (Unit 1) and MC 2403-01.41-00 (Unit 2) that show the auxiliary feedwater (CA) piping layout in the auxiliary building. These note that the CA piping size has been increased from six inches to be eight inches as required by design change authorization MCSEAB-015 for Units I and 2.
The inspector also reviewed shutdown request 1839 and referenced the piping system installation and configuration inspection report.
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(Closed) LII 369/78-28-05, ~ Safety Related Instrumentation Design Deficiency.
The inspector reviewed the DPC response to Region II'
dated: September 7, 1980 and October 17, 1980 and the' documentation of
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the corrective action ~ program.
Class IE: solenoid valves have been-added to the instrumentation air lines immediately upstream of the.
affected. valve operators and downstream of all control grade compondnts.
This allows venting on the appropriate signal permitting the valve to fail safe. The inspector reviewed the following drawings for the
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-6-affected systems and components and verified that representative valves changed per the shutdown requests were powered from independent power sources:
Drawing Train A Valve Train B Valve Shutdown Request 1499-RN9 RNSV0680 RNSV1610 1946 1499-RN11 RNSV1660 RNSV1700 1946 1499-KC22 KCSV0570 KCSV0820 1947 1499-ND4 NDSV0291 NDSV0141 1950 1499-CA3 LASV0560 CASV0400 1949 1499-CA3 CASV0600 CASV0440 1949 1499-SM9 SVSV0011 SVSV0012 1949 1499-SM9 SVSV0131 SVSV0132 1948 i
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