ML20054J596
| ML20054J596 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/09/1982 |
| From: | Jackiw I, Lanksbury R, Maura F, Robinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20054J590 | List: |
| References | |
| 50-373-82-25, NUDOCS 8206290318 | |
| Download: ML20054J596 (6) | |
See also: IR 05000373/1982025
Text
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-373/82-25(DETP)
Docket No. 50-373
License No. NPF-11
Licensee: Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name: LaSalle County Station, Unit 1
Inspection At: LaSalle Site, Marseilles, IL
Inspection Conducted: April 19-23, 27-30, May 6, 7, 11, 13-18 and 21, 1982
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Inspectors:
F. ttura
b - 8- E 2a
(April 19, 21, May 6, 7,
13, 14, 16-18,
and 21, 1982)
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R. Lanksbury
b -8 -$ 2,
(April 20-23, 27-30, 1982)
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.R
inson
h -8- 81
(May 1 and 15, 1982)
Approved By: &
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Test Program Section Date
Inspection Summary
Inspection on April 19-23, 27-30, May 6, 7, 11, 13-18 and 21, 1982
(Report No. 50-373/82-25(DETP))
Areas Inspected: Routine, announced inspection to review start up test
procedures, witness primary containment integrated leak rate test, and
review previously opened items. The inspection involved 147 inspector-
hours onsite by three NRC inspectors including 42 inspector-hours during
offshift.
Results: Of the three areas inspected, no items of noncompliance were
identified in two areas. On the remaining area one item of noncompliance
was identified (failure to follow procedure, Paragraph 4.c.).
8206290318 820609
PDRADOCK05000g
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DETAILS
1.
Person Contacted
- R.
Bishop, Assistant Superintendent
- J.
Renwick, Technical Staff Supervisor
- W. Huntington, Assistant Tech Staff Supervisor
E. Pfister, Lead Nuclear Engineer
J. Atchley, Shift Engineer
- R. Koenig, Technical Staff Engineer
- R.
Kyrouac, QA Supervisor
T. Watts, SNED Project Engineer
The inspectors also interviewed other licensee employees including
members of the technical and operations staff.
- Denotes those attending the exit interview of May 21, 1982.
2.
Licensee Action on Previous Inspection Findings
(Closed) Open Item (373/81-20-12): Diesel generators "0" and 1A
unresolved deficiencies. This item was closed in Inspection Report
No. 50-373/82-20,Section II, Paragraph 3.
(Closed) Open Item (373/82-14-01, 373/82-14-02, and 373/82-14-03):
Unresolved deficiencies in PT-RP-102, PT-PC-103, and PT-RR-101,
respectively. These open items were closed by Inspection Report
No. 50-373/82-18, Paragraph 6, but were erroneously omitted.
(Closed) Unresolved Item (373/81-20-08):
Licensee objected to count-
ing all start attempts following the completion of the 23 starts
reliability tests of diesel generators 0, 1A and 1B and to adjust
frequency of testing based on Regulatory Guide 1.108.
The inspector reviewed the licensee's chronological listing of all
Unit 1 diesel generators starts since the last recorded failure
(12/26/81). The starts can be categorized as " valid" (per Regulatory
Guide 1.108 definition); " partials" (where the diesel generator was
started and loaded for less than one hour); and " starts" (where the
unit is started, but not loaded).
Based on those definitions, the
history from 12/26/81 to 4/7/82 is as follows:
Diesel Generator
Starts
Valid
Partial
0
36
9
9
1A
42
8
6
1B
26
5
7
Total
104
22
22
Based on the above, NRR has concluded that the reliability goal of
Regulatory Guide 1.108 has been met.
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3.
Review of Startup Program Test Procedure
The following startup program test procedures were reviewed and
found to meet the requirements of the FSAR; SER; Regulatory Guide 1.68, Revision 0; licensce's QA Manual; and have incorporated all
General Electric recommendations unless otherwise stated:
a.
STP-5, CRD
b.
STP-25, MSIV -
c.
STP-28, Shutdown from Outside Control Room
d.
STP-27, Turbine Stop Valve Trip and Generator Load Rejection:
The inspector provided the' licensee with a list of additional
acceptance criteria covering basic reactor safety design. The
licensee reviewed the list and responded that since these
acceptance criteria were not in the FSAR test abstract that
was approved by NRR no requirement existed for them to be in
the procedure. The inspector informed the licensee _that even
though these acceptance criteria were not in the procedure,
they would be used by the Region III in determining the accept-
ability of the test results. These acceptance criteria are:
(1) Reactor pressure does not exceed 1146 psig (lowest
safety valve setting) during any transient.
(2) All safety and ECCS systems (such as RPS, HPCS, DG's,
RCIC, etc.) function as designed without manual
assistance,' if called upon, during any transient.
The inspector provided a list of comments to the licensee, in
addition to the above for resolution. This is an open item
(373/82-25-01) pending review of the licensee's response by
the inspector.
e.
STP-30, Recirculation System:
The inspector provided a list of comments to the licensee for
resolution. This is an open item (373/82-25-02) pending review
of the licensee's response by the inspector.
In addition the following startup test procedures were reviewed
and verified to have incorporated all General Electric recommendations:
a.
STP-3, Fuel Loading
b.
STP-6, SRM Performance and Control Rod Sequence
No items of noncompliance or deviations were identified.
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'4.
Containment Integrated Leak Rate Preoperational Test
a.
Procedure Review
1
The inspector reviewed procedure PT-PC-101, Revision 24, and
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LTS 300-4, Revision 2, which controlled the performance of the
primary containment integrated leak rate test and verified that
they were technically adequate and met regulatory requirements.
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b.
Instrumentation
The inspector reviewed the calibration data and determined that
all the instruments to be used in the ILRT had been calibrated
as required. All volume weighing factors were placed into the
computer program as required. The following instrumentation
was used in the ILRT:
Type
Quantity
4
RTD's
30
i
Dewcells
10
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Pressure gauges
2
Flowmeter
1
During the test, one of the dewcells in subvolume #3 became
defective. For the duration of the test, its reading was
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assumed to change by the same magnitude experienced by the
other dewcell in that subvolume. At the completion of the
test, the licensee reprogrammed-its computer to delete the
defective dewcell reading, and the test results were very
close to the independent results obtained by the inspector
(which did not include the inoperative dewcell from the start).
c.
Witness of Test
The inspector witnessed portions of the ILRT on May 15-18,
1982, and noted that test prerequisites were met and appropriate
revisions to the procedure were in use by test personnel. The
temperature stabilization criteria was met prior to the start
of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT phase. The test had to be restarted three
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additional times due to interruptions caused by excessive-leak-
age thru instrument valves. loss of power to data acquisition
unit, loss of loop seal in hydrogen recombiner system, and
additional problems cith the data acquisition / transmission
setup. The final test restart took place at approximately
0224 on May 17, 1982. At approximately 0530, 83 gallons were
pumped out of the drywell equipment sump. The control switches
for IRE 024 and 025 were found in the auto position. Earlier,
during one of the interruptions to to the ILRT, the licensee had
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pumped the sump and failed to return the valve control switches
to the closed position as required by the ILRT procedure.
Failure to comply with the test procedure upon reinitiation of
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the test is considered to be a violation of Technical Speci-
fication, Section 6.2. A.7 'and is an item of noncompliance
(373/82-25-03).
d.
Valve Lineups
During containment pressurization, the inspector verified that
the valve lineups were conducted and documented in accordance
with the approved test procedures.
e.
CILRT Valve Lineup Penalties
Due to valve configuration which deviated from the ideal valve
lineup requirement for the CILRT, the result.of the local leak
rate tests for such penetrations must be added as a penalty to
Lam at the 95 percent UCL. The penalty for LaSalle Unit 1,
excluding penetration M-16 (RBCCW Supply) which has not been-
tested yet due to valve problems, is 9.10 scfh or 0.019 weight
%/ day. When repairs to the valve are completed the leakage
rate of penetration M-16 must not axceed 0.082 weight %/ day,
f.
ILRT Data Evaluation
A 26 hour3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> ILRT was performed during May 17-18, 1982. The
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inspector independently monitored and evaluated leak rate
data to verify the licensee's calculation of the leak rate.
There was acceptable agreement between the inspector's and-
licensee results as indicated by the following summary (units
are in weight %/ day).
,
Measurement
Licensee
Inspector
1
Leakage rate
0.374
0.372
measured during ILRT
(Lam)
Lam at upper 95 %
0.375
0.375
confidence level
Lam at upper 95%
0.394
0.394
!
confidence level ad-
justed to reflect
penalties-(See Paragraph
4.C.)
Appendix J acceptance criteria at 95% UCL = 0.75 La
= 0.75 (0.635 weight %/ day) = 0.476 weight %/ day.
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g.
Supplemental Test Data Evaluation
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After the satisfactory completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT on May 18,
,
1982, a known leakage of 320
10 scf/hr or 0.526
.016 weight
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%/ day was induced. The inspector independently monitored and
evaluated Icak rate data to verify the licensee's test results.
There was acceptable agreement between the inspector's and the
licensee's leak rate calculations as indicated by the following
summary (units are in weight %/ day).
Measurement
Licensee
Inspector
Measured leakage rate
0.818 i 0.036
0.805 i 0.043
Lc, during supplemental
test
Induced leakage rate,
0.526 i 0.016
0.526 i 0.016
Lo
Lc-(Lo+ Lam)
-0.082 1 0.039
-0.093 i 0.046
Appendix J acceptance criteria:
.1595 [Lc- (Lo+ Lam)] 5+0.159
5.
Off Site Review and Approval of Startup Test Results
Initial licensee plans were for the Station Nuclear Engineering
Department (SNED) to perform the review and approval of startup
test results following completion of the program. After discussion
with the inspector, SNED has agreed to review and approve startup
test results for all STP's completed at the.end of a Test Condition
and prior to testing at the next test condition.
6.
Exit Interview
The inspector met with licensee representatives (denoted in Paragraph
1) on May 21, 1982. The inspector summarized the scope and findings
of the inspection.
The licensee acknowledged the statement by the inspector with r.apect
to the item of noncompliance.
(Paragraph 4.c)
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