IR 05000373/1979037
| ML19269F490 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/08/1979 |
| From: | Maura F, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19269F488 | List: |
| References | |
| 50-373-79-37, NUDOCS 7912210154 | |
| Download: ML19269F490 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSIO.7
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0FFICE OF INSPECTION AND ENFORCEMEN1
REGION III
Report No. 50-373/79-37 Docket No. 50-373 License No. CPPR-99 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
La Salle County Station, Unit 1 Inspection At:
La Salle Site, Marseilles, IL Inspection Conducted: October 17-19, 1979 ddm.~ 3r
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Inspector:
F. A. Maura lt /g[7 q
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J. F. Streeter, Chief
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Nuclear Support Section 1
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Inspection Summary Inspection on October 17-19, 1979 (Report No. 50-373/79-37)
Areas Inspected:
Routine, unannounced inspection of the preoperational test program; followup on items of noncompliance and unresolved items.
The inspection involved 24 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted
- R. Holyoak, S ition Superintendent
- E. Spitzner, A sistant Superintendent
- R. Bishop, Technical Staff Supervisor J. Renewick, Operating Engineer
- G. Croth, Flushing Coordinator
- E. Wendorf, Station Construction Field Engineer J. Courtney, RCI Manager D. Donath, RCI QC Engineer R. Spencer, GE Site Manager The inspector also interviewed other licensee employees including members of the technical and construction staffs, and employees of Reactor Controls Inc., and the General Electric Co.
- Denotes those attending the exit interviet.
2.
Licensee Action on Previous Inspection Iindings (Closed) Noncompliance (373/79-06-01): Failure to follow test change procedure. The inspector reviewed Startup Manual procedures LSU 500-1 and LSU 500-2 and noted that they reflect the NRC's position
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on procedure changes as stated in our letter (Keppler to Lee) dated June 21, 1979.
(Closed) Unresolved Item (373/79-06-02):
Terminal voltage of 250 VDC battery acceptance test. The inspector reviewed the test acceptance criteria with the licensee and determined that the criteria only established a minimum terminal voltage and did not require revision.
(0 pen) Noncompliance (373/79-06-03): Inadequate procedure lacks specific gravity correction for changes in electrolyte level. As noted in our Letter (Keppler to Lee) dated June 21, 1979, this item of noncompliance was deleted. However, the need to correct specific gravity for changes in electrolyte level remained a requirement.
The inspector reviewed the licensee's surveillance procedures (IOS-DC-MI and LOS-DCM2) and noted that they do not require electrolyte level correction. The inspector also note; that the present draft of the Technical Specifications require the specific gravity be corrected to full electrolyte level. The licensee stated that CECO is conducting a review of the battery procedures and practices for all the nuclear plants and La Salle is waiting for the results of the study before proceeding. This item is changed to an Unresolved It
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(Closed) Unresolved Item (373/79-06-04):
Specific gravity acceptance
criteria for 24/48 VDC battery IDC32E. The inspector determined that level corrections for the specific gravity readings at the " finish" of the test were not required since " finish" meant the battery was in its discharged condition.
(Closed) Noncompliance (373/79-06-05): Inadequate procedures to assure system cleanliness following opening for maintenance or modification. The inspector found that the licensee has almost completed ( 95%) a review of all MRD's to determine if a reflush is necessary. Six MRD's have been identified for reflush. The MRD system is being utilized to cover all work performed by Morrison Construction Company, outside of the original installation.
(Closed) Noncompliance (373/79-06-06): Failure to follow out-of-service card procedure. The inspector determined that the field engineers have been reinstructed in the mandatory use of the out-of-service card procedure once a system has been livened.
3.
Preoperational Test Program Status Of the 63 preoperational tests and system demonstratios required to be completed prior to fuel loading the licensee has approved for use 59 test procedures. Twenty-six tests are in progress with no comple-tions as of Octo'oer 19, 1979.
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4.
Review of Preoperational and Startup Test Procedures Preoperational test procedure PT-RD-102, "CRD Hydraulic," was reviewed and found to meet the requirements of Regulatory Guide 1.68, FSAR commitments, and Startup Manual requirements.
Startup program procedure STP-5, "CRD System," was reviewed in draft form as it compliments preoperational procedure PT-RD-102.
Initial comments discussed with the licensee were:
In-lude as a level 1 acceptance criteria a limit for under a.
piston pressure while friction testing each CRD. This pressure limit shall be based on the prototype testing results.
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Consider friction testing all CRD's when the unit first reaches operational temperature and pressure.
5.
Control Rod Blade Inspection The records indicate that the only inspection performed on the control rod blades for Unit I was a visual check for possible damage during shipment.
The use of envelope gauges was deleted in November 1978 by FDDR No. HAl-149.
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6.
Exit Interview
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The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspectirn on October 14, 1979. The inspector summarized the purpose and the scope of the inspection and the findings.
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