ML19323E605
| ML19323E605 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/14/1980 |
| From: | Chow E, Hopkins J, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19323E600 | List: |
| References | |
| 50-254-80-08, 50-254-80-8, 50-265-80-01, 50-265-80-1, NUDOCS 8005270042 | |
| Download: ML19323E605 (6) | |
See also: IR 05000254/1980008
Text
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMEhT
REGION III
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Report No. 50-254/80-08; 50-265/80-01
Docket No. 50-254; 50-265
Licensee:
Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name: Quad-Cities Nuclear Generating Plant, I and 2
Inspection At: Quad-Cities Site, Cordova, IL
Inspection Conducted: January 4, March 6-7, 9-11,1980
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Ins,iectors :
E. T. Chow (January 4, March 6-7, 9-11, 1980)
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J. B. Hopkins (March 6-7, 9-11, 1980)
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F. Streeter (January 4, 1980)
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Approved By:
J. F. Streeter, Chief
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Nuclear Support Section 1
Inspection Summary
Inspection on January 4, March 6-7, 9-11, 1980 (Report Nos. 50-254/80-08
and 50-265/80-01)
Areas Inspected: Routine, announced inspection of the containment in-
tegrated leak rate test; review of previous Unresolved Items. The in-
spection involved 106 inspector-hours on site by three NRC inspectors.
Results: Of the two areas inspected, one Item of Noncompliance was
identified in one area.
(Deficiency - failure to follow procedure -
Paragraph 4.d)
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80052700 @ Q
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DETAILS
1.
Persons Contacted
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- N. Kalivianakis, Station Superintendent
- L. Gerner, Technical Staff Supervisor
- J.
Swales, Technical Staff
- J. Hoeller, Technical Staff
- J. Heilman, Q. A. Engineer
The inspector also talked with and interviewed several members of
the technical and engineering staffs.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings
(Closed) Unresolved Item (50-254/79-08-02): Drywell Temperature
Readings Test for Isolation of Drywell Cooler Damper Air Supply
Lines: The inspector determined that the licensee had performed a
special test, l'est No. 2-24, " Unit 2 Drywell Cooling Air Damper
Supply and Control Air Isolation," dated May 4, 1979, and verified
that the system could be isolated and the temperature distribution
inside the drywell was still adequate.
(0 pen) Unresolved Item (50-254/79-08-04):
Isolation of Drywell,
Torus, and Drywell to Torus Differential Pressure Switches: The
licensee maintained his previous position that there are no means
to locally test the switches. The licensee stated that, according
to the manufacturer's specification, the pressure switches could
sustain a maxiumum pressure of 200 psi. This item will remain open
pending further review by the inspectors.
(Closed) Unresolved Item (50-254/79-08-05):
Isolation of Air Supply
Lines to,Drywell Cooler Dampers: The licensee stated that the air
supply lines to the drywell cooler dampers are disconnected inside
the drywell. The inspectors visually verified that the lines were
disconnected and capped outside the drywell. The inspectors deter-
mined that the licensee's corrective actions were adequate.
(0 pen) Unresolved Item (50-254/79-08-06): Future Test Schedule for
Unit 1 CILRT: The licensee stated that an amendment to technical
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specifications relating to CILRT is still in the corporate office
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and will be submitted to NRR.
In the meantime the licensee will
request an official position from'NRR regarding the future test
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schedule for Unit 1 CILRT. This item is still unresolved pending
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the licensee's action.
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(Closed) Unresolved Item (50-265/76-24): TIP System Leakage: The
inspectors reviewed information relating to Procedure QTS 100-38,
Revision 1, " Automatic TIP Ball Valves and TIP Purge Line Local Leak
Rate Test," and verified that the local leak rate test on the TIP
system was performed as described in the licensee letter to RIII
dated December 10, 1976.
3.
Review of Licensee Event Report
(Closed) Reportable Occurrence Report No. R079-27/03L.
(Closed) Supplemental Reportabla Occurrence Report No. R079-27/03L-1.
The inspectors reviewed infon -_ ion relating to loctl leak rate
tests as described in Procedure QTS 100-1, Revision 4, " Local Leak
Rate Test, Pressure Decay Method," and Procedure QTS 100-2, Revision
4, " Local Leak Rate Test, Flowmeter Method." The inspectors noted
that all testing and corrective actions were completed regarding the
excessive leakages measured for primary containment during the Unit
2 End-of-Cycle 4 refueling outage local leak rate testing program.
The inspectors noted that the corrected local leak rates satisfied
Technical Specification requirements.
No items of noncompliance or deviations were identified.
4.
Containment Integrated Leak Rate Test (CILRT)
a.
Procedure Review
The inspectors reviewed procedure QTS 150-1, Revision 7,
" Integrated Primary Containment Leak Rate Test," and stated the
following:
(1) Based on the present and the previous CILkT, the reactor
water level dropped about one inch per liour during the
tests. The prerequisites of the test precedure should
include a guideline on the dropping of the reactor water
level.
(2) The test procedure should be more specific as to the
number of data sets required for the acceptability of the
induced leakage test results.
(3) The subvolume No. 11 free air volume was calculated using
the reactor vessel air volume above 5".
The number 5
should be used in the equation for calculating containment
dry air mass in procedure QTS 150-T3, Revision 6, " Cal-
culations Performed for IPCLRT Data," instead of the number
30 as used in the current equation. The modification of
the equation will increase the measured leak rate slightly.
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(The licensee acknowledged the above comments and stated he
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would modify the test procedure and computer program accordingly.)
(4) The inspectors noted that the licensee did not test the
drywell, torus, and drywell to torus differential ' ressure
p
switches during the Unit 2 CILRT. This is an Unresolved
Item (50-265/80-01-01) pending further review by the
inspectors.
No items of noncompliance or deviations were identified.
b.
Instrumentation
The inspector reviewed the calibration data associated with
performing the CILRT. A multipoint calibration of all instru-
mentation was performed. Correction values were generated
based on the difference between measurements of resistance from
a NBS verified resistance box and actual resistance measured.
All corrections were placed as an array or equation into the
CILRT computer.
Type
Quantity
Serial Ntunber
30
44209-44238
Flowmeter
1
7910A912GR1
Pressure Gauge
2
PPG 1-2
Dewcells
10
5835-1 to 8
No items of noncompliance or deviations were identified.
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c.
Witness of Test
The inspector witnessed portions of the CILRT on March 10,
1980, and verified that:
Appropriate revision of procedure was in use by test personnel.
Test prerequisites were met.
Proper plant systems were in service.
No items of noncompliance or deviations were identified.
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d.
Direct Observation of Valve Lineups
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The inspectors visually verified the positons of the valves
2-1402-33A, 2-1402-33B, 2-8801A, 2-8801B, 2-8801C, 2-8802A,
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2-8802B, 2-8802C, 2-4699-46, and 2-4799-157.
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The inspectors noted that Procedure QTS 150-57,
. vision 6,
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" Unit 2 IPCLRT Valve Lineup," required that Valv,, 2-1402-33A
and 2-1402-33B (Local leak test valves for core spray isolation
valves) be locked closed. Although the valves were checked off
as being verified locked closed, the inspectors found the valves
closed but unlocked. However, the inspectors visually verified
that series Valves 2-1402-32A and 2-1402-32B were locked c2osed.
Technical Specification 6.2.A requires that " Detailed written
proceduresincluding applicable checkoff lists
. shall be
...
prepared, approved, and adhered to."
Contrary to the above, Procedure QTS 150-57, Revision 6, " Unit
2 IPCLRT Valve Lineup," was not adhered to in that valve posi-
tion verification was not carried out on March 8, 1980, to
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verify that Valve 2-1402-33A and Valve 2-1402-33B were locked
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closed as required. This is considered an item of noncom-
pliance (50-265/80-01-02) of the deficiency level.
No other items of noncompliance or deviations were identified.
c.
Blowdown and Containment Inspection
The inspector verified that blowdown was within Technical
Specification radioactivity release limits.
No items of noncompliance or deviations were identified.
f.
CILRT Data u.aluation
The 24-hour CILRT was started on March 10, 1980, at 12:00 a.m.
The 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's leak rate calculations as indicated in the following
summary (units are in weight percent per day):
Measurement
Licensee
Inspector
Leakage rate measured (Lam)
.4743
.4795
during CILRT
Lam at 95% confidence level
.4854
.5037
The 10 CFR Part 50, Appendix J acceptance criterion at the 95%
confidence level = 0.75 (La) = 0.75 (1) = 0.75.
As indicated
above, Lam at the 95% confidence level was less than that value.
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A preliminary calculation by the licensee indicated that the
measured integrated leak rate with the addition of local leak
rate differences prior to and after repair was .8 wt%/ day.
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No items of noncompliance or deviations were identified.
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g.
Supplemental Test Data Evaluation
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 /> test o'n
March 11, 1980, 12:00 a.m. a known leakage of .4623 weight
percent / day was induced. The inspector independently moni-
tored and evaluated leak rate data to verify the licensee's
calculation of the supplemental leak rate.
There was accept-
able agreement between the inspector's and licensee's leak
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rate calculations as indicated in the following summary (units
are in weight percent per day):
Measurement
Licensee
Inspector
Leakage rate mersured (Lc)
.8293
.8324
during supplemental test
Lc @ 95% confidence level
.8483
.8839
Indaced leakage rate (Lo) =
.4623
Appendix J Acceptance Criterion:
Lo+ Lam-0.25La <Lc4
Lo+ Lam +0.25La.
As indicated above, the supplemental test
results satisified the requirements of 10 CFR Part 50,
Appendix J.
No items of noncompliance or deviations were identified.
5.
Unresolved Items
Unresolved Items are matters about which more information is required
in order to ascertain whether they are acceptable items, Items of.
Noncompliance, or Deviations.
An Unresolved Item disclosed during
the inspection is discussed in Paragraph 4.
6.
Exit Interview
The inspectors met with licensee representatives (denoted in Paragraph
1) at the conclusion of the inspection on March 12, 1980. The in-
spector summarized the purpose and the scope of the inspection and
the findings.
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