IR 05000373/1982017
| ML20054D080 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/06/1982 |
| From: | Walker R, Wescott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054D077 | List: |
| References | |
| 50-373-82-17, NUDOCS 8204220318 | |
| Download: ML20054D080 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-373/82-17(DPRP); 50-374/82-02(DPRP)
Docket Nos. 50-373, 50-374 Lit.snses No. CPPR-99; CPPR-100 Licensee: Commonwealth Edison Company Post Office Box 767
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Chicago, IL 60690 Facility Name: LaSalle County Nuclear Station, Units 1 and 2 Inspection At: LaSalle Site, Marsellies, IL Inspection Conducted: March 24-26, 1982 o-tva /A(b 4 [1 Inspector:
H. M. Wescott
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c Approved By:
R. D. Walker, Chief mA.$ T(/dk Reactor Projects Section 1C
Inspection Summary Inspection on March 24-26, 1982 (Reports No. 50-373/82-17(DPRP);
50-374/82-02(DPRP))
Areas Inspected: Routine announced inspection; review of 10 CFR 50.55(e)
reports; review of ASME N-5 forms. The inspection involved a total of 32 inspector-hours onsite by one NRC inspector including 0 inspector-hours during off-shifts.
Results: Of the two areas inspected no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- B. B. Stephenson, LaSalle County Station Project Manager
- R. H. Holyoak, Station Superintendent
- R. D. Kyrouac, Quality Assurance Engineer
- G. J. Diederich, Station Operating Assistant Superintendent
- R. D. Bishop, Administrative and Support Services, Assistant Superintendent
- E. Stevak, Quality Assurance
- J. J. Maley, Manager of Projects
- T. E. Quaka, Site Quality Assurance Superintendent
- J. W. Gieseker, Assistant to Site Construction Superintendent
- D. L. Shamblin, Staff Assistant, Project Manager's Office W. H. Donaldson, Assistant Construction Superintendent
- B. R. Shelton, Project Engineering Manager
- G. L. Swihart, LSCS Licensing Group Leader The inspector also interviewed other licensee employees including members of the technical, operating, and construction staff, as well as certain licensee contractor employees.
- Denotes persons present at management interview conducted at the close of the inspection period on March 26, 1982.
2.
Licensee Action on Previously Identified Items (0 pen) 10 CFR 50.55(e) Report No. 50-373/81-06 dated August 8, 1981, Subject; Crosby SRV solenoids would not actuate at low DC voltage under LOCA conditions.
a.
The inspector reviewed CECO's correspondence to USNRC Region III as follows:
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(1) Interim Report Dated September 6, 1981 (2) Interim Report Dated November 6, 1981 (3) Interim Report Dated December 15, 1981 (4) Final Report Dated February 9, 1982 (5) Final Report Dated March 24, 1982 b.
The inspector further reviewed G.E. test data as follows:
(1) FDI No. 128-57434, Revision 1, dated July 15, 1981, indicating that the crosby solenoids were not satisfactory.
(2) FDI No. 133-57434, Revision 0, dated December 22, 1981, which states under " Design Verification Statement" that " capability of the design to perform its required IE function is as docu-
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mented in MED Memo 126-03, Revision 0 dated February 26, 1982, (copy filed in DRF No. 207C-B21/22F013-K) with no affect on safety or reliability" verified March 2, 1982.
The inspector considers this item open pending the licensee's
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long term fix as stated in CECO's final report to NRC Region III dated March 24, 1982, and the requirements of NUREG's-0588 and 0737 as delineated in Paragraph 2.C.(16) of LaSalle County Station, Unit 1 facility operating license, license No. NPF-11.
However, the interim fix as stated in CECO's final report to NRC Region III dated March 24, 1982, appears adequate to support OL issuance.
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(0 pen) 10 CFR 50.55(e) Reports No. 50-373/81-08 and 50-374/81-08, dated September 30, 1981, Subject; Zack Company documentation deficiencies. The inspector reviewed CECO's final report to NRC Region III dated December 2, 1981.
The inspector considers this item open pending satisfactory close out of the NCR's referenced in CECO's final report to NRC Region III dated December 2, 1981.
(0 pen) 10 CFR 50.55(e) Reports No. 50-373/81-10 and 50-374/81-10, dated December 28, 1981, Subject; RCIC underground suction and return piping determined to have faulty welds.
The inspector reviewed CECO's final report to NRC Region III dated January 25, 1982.
The inspector considers this item open pending the licensee's replace-ment and successful testing of the subject piping. However, in that the subject piping for unit 1 has been successfully tested as stated in the final report and will be replaced by July 1982, the existing piping appears to be adequate to support OL issuance.
(Closed) 10 CFR 50.55(e) Report No. 50-373/82-02 dated January 29, 1982, Subject; GE's vertical lift metal clad switchgear equipment, model 4.16-350 that is used on the high pressure core spray system was rated at 78,000 amps momentary short circuit current. Tests have shown that bus support dielectric damage can occur with momentary currents above 66,000 amps.
The NRC inspector reviewed the following documentation:
I GE's " Installation and Service Engineering Division" traveler a.
No. HAl-1523-T, indicating that the modification to the subject switchgear was completed on March 17, 1982.
b.
The traveler package No. HAl-1523 contained the following:
(1) FDDR No. RAl-1532, dated February 25, 1982.
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(2) Instruction Reports for modifying M26 or M26N vertical lift switchgear.
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(3) RFR No. 278 with modification parts list.
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The inspector considers this item closed and in conformance with CECO's final report to NRC Region-III.
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3.
-Review of ASME N-5 Form Status
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The inspector reviewed ASME N-5 packages as follows:
a.
Main Steam (MS-1 and M5-2)
b.
Nuclear Boiler (NB-1 and NB-2)
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Reactor Recirculation (RR-1 and RR-2)
The above contained:
i (1) The signed N-5 form with index/ record location.
i (2). Modified N-5 form for installation of nuclear power plant components, component supports, and appurtenances.
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(3) Certification of the design specification and data sheet.
(4) Certification of the stress report.
(5) ASME form NPP-1 data report for fabricated nuclear piping i
subassemblies.
The inspector further verified that certified stress analysis packages for M5-05, NB-NB2, RR-01 Revision 01 and RR-01 Revision 02, to assure
that appropriate calculations were included in the packages.
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No items of noncompliance or deviations were identified.
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4.
Exit Meeting The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on March 26, 1982. The inspector I
summarized the scope and findings of the inspection.
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