IR 05000373/1981045
| ML20040E029 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/15/1982 |
| From: | Jackiw I, Lanksbury R, Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20040E026 | List: |
| References | |
| 50-373-81-45, NUDOCS 8202020501 | |
| Download: ML20040E029 (3) | |
Text
_
_
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
,
Report No. 50-373/81-45
Docket No. 50-373 License No. CPPR-99
'
Licensee: Commorwealth Edison Company Post tffice Box 767 Chicago, IL 60690 Facility Name:
LaSalle County Nuclear Station, Unit 1 a
Inspection At:
LaSalle Site, Marseilles, IL Inspection Conducted: December 8, 14, 15, 17, 18, 21-23 and 28-30, 1981
@D k
(//g/6L Inspectors:
TD.
n Date '
'
a
~
'.'
achiw
!M /L
.
/(Dece er 8)
Date
~
'
///5/S4 M
ng (December 14, 15, 21 and 22)
Da te'
i QM
/ /
S' 2.-
'
Approved By.
Kiw, Chief
.
st Pr rams Section Date Inspection Summary
Inspection on December 8, 14, 15, 17, 18, 21-23 and 28-30, 1981 (Report No. 50-373/81-45)
Areas Inspected: Routine, announced inspection to review test procedures and results, previous open items, and witness preoperational testing in progress. The inspection included 84 inspector-hours onsite by tt.ree NRC inspectors including 11 inspector hours onsite during off shifts.
Results: No apparent items of noncompliance or deviation were identified.
,
l
!
.
l f
,
8202020501 820119 PDR ADOCK 05000373
,
e PDR
'
__ -
_.
..
_
-
-.
-
-
-,
..
. _ _ _ _ _ _ _.
.
DETAILS 1.
Pereons Contacted
- R.~ Holyoak, Plant Superintendent
- R. Bishop, Assistant Superintendent
- W. Huntington, Assistant Technical Staff Supervisor
- J. Ahlman, QA Engineer
- E. Kotrich, QA Engineer The inspectors also interviewed other licensee employees, including members of the quality assurance, technical and operating staff.
- Denotes those attending the exit interview of December 30, 1981.
2.
Licensee Action on Previous Inspection Findings (Closed) Open Item (373/81-20-06): The "0" diesel generator fuel consumption rate exceeded the maximum allowed rate of 186 gal./hr.
stated in the FSAR. The inspector verified that the licensee has made adjustments to the diesel fuel system to lower the fuel con-sumption rate below the FSAR requirement and has retested the system to verify this.
(Closed) Noncompliance (373/81-20-13A): The acceptance criteria for the low level alarms of the "O,"
"1A," and "2A" fuel oil storage tanks (6.4i 0.1 psi) and "1B" fuel oil storage tanks (6.65 0.1 psi) per-mitted the amount of stored fuel to fall below the minimum requirement specified in the FSAR (31,250 and 29,750 gallons, respectively). The inspector verified that the licensee has raised the alarm setpoints for the "O," "1A," and "2A" fuel oil storage tanks to 6.6i 0.1 psi and for the "1B" fuel oil storage tank to 6.751 0.1 psi. This action increases the minimum amount of fuel oil in the storage tanks to an acceptable level of between 31,285 to 32,301 gallons for the "O," "1A," and "2A"
-
tanks cnd between 29,868 to 30,774 gallons for the "1B" tank.
(Open) Open Item (373/81-43-03): Test evaluation records for the Laboratory HVAC System Preop Test (PT-VL-101) indicated that the counting room would not conform to design. System modification is planned such that it would meet the required design criteria.
3.
Preoperational Test Results Review The inspectors reviewed the following test procedure and test results against the FSAR, the SER, Regulatory Guide 1.68, and the QA Manual and found them satisfactory unless otherwise noted. Deficiencies which remain unresolved must be reviewed by QA prior to system release for operation. At that time, all items which must be corrected prior to fuel loading will be identified. Open items covering the inspector review of the corrective actions taken by the licensee appear with the preop test listed below.
-2-
.
'
..
a.
PT-LD-101, Leak Detection System Preoperational Test (1) Open iten (373/81-45-01)~ unresolved deficiencies, PT-LD-101.
b.
SD-FW-101, Reactor Feedwater - review of test results.for. this system demonstration is still in progress.
No items of noncompliance or deviations were identified.
4.
Preoperational Test Witnessing-The inspector witnessed local leak rate testing (LLRT) of the following containment isolation valves to ascertain through observation, records review, and independent calculations whether the testing was conducted in accordance with approved acceptable procedures; to independently verify the acceptability of the test results; and to evaluate-the performance of the licensee personnel during the test.
a.
"A" FW Primary Containment Outboard Isol. Testable Check.
b.
IB21-F032B
"B" FW Primary Containment Outboard Isol. Testable Check c.
"B" RHR Pump containment Spray Upstream Isol.
d.
IE12-F017B
"B" RHR Pump Containment Spray Downstream Isol.
e.
IE12-F042B
"B" RKR LPCI Injection Line Stop f.
IE12-F053B
"B" RHR Shutdown Co'oling Discharge Isol.
g.
"C" RHR LPCI Injection Line Stop h.
IE12-F053A
"A" RHR Shutdown' Cooling Discharge Isol.
During witnessing of some of the above testing the inspector had'
some concerns regarding the testing methodology utilized by the station test engineers. These concerns were discussed with the Assistant Super-intendent who initiated corrective-action to resolve the inspector's Concerns.
No items of noncompliance or deviations were identified.
5.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1).
on December 30, 1981. The inspector summarized the scope and findings of the inspection.
.
.
k
-3-
!
l L:
-.. - - - -
,.-- _. --