ML19350D898
| ML19350D898 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/09/1981 |
| From: | Baker K, Gildner M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19350D895 | List: |
| References | |
| 50-266-81-08, 50-266-81-8, 50-301-81-07, 50-301-81-7, NUDOCS 8105260318 | |
| Download: ML19350D898 (5) | |
See also: IR 05000266/1981008
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-266/81-08; 50-301/81-07
Docket Nos. 50-266;50-30I
Licensee: Wisconsin Electric Power Company
231 West Michigan Avenue
Milwaukee, WI 53201
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Facility Name:
Point Beach, Units 1 and 2
Inspection At:
Point Beach Site, Two Creeks, WI
Inspection Conducted: March 23-27, 1981
Inspector: ff
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Approved By:
. Baker, Chief
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Management Programs Section
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Inspection Summary
Inspection on March 23-27, 1981 (Reports No. 50-266/81-08; 50-301/81-07)
Areas Inspected:
Routine, unannounced inspection of calibration and surveil-
lance of safety-related components and equipment. The inspection involved a
total of 38 inspector-hours ensite by one NRC inspector. None of the in-
spector-hours were spent onsite during offshifts.
Resul t_s :
In the area inspected, the inspector identified one apparent item of
noncompliance.
The apparent item of noncompliance was a failure to follow the
acceptance criteria of a major calibration procedure per Details Paragraph 4.b.
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DETAILS
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Persons Contacted
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G. A. Reed, Manager, Nuclear Power. Division.
- J.'J. Zach, General Superintendent
- R.'E. Link, Superintendent Engineering,1 Quality,:and Regulatory
J. C. Reisenbuechler, I&C Engineer
- E. A. LeClair, I&C Supervisor.
M. E. Crouch, Maintenance Supervisor
Additional plant technical and' administrative personnel were-contacted
during the course of the inspection by the inspector.
- Denotes those personnel present during the exit meeting.
2.
Test Equipment-Calibration
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The inspector selected the below listed. test equipment used in-the
calibration of safety-related equipment and determined that the-
accuracy of those instruments was traceable to'the National Bureau
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of Standards or other independent testing agencies: the equipment
wer properly controlled; and storage of equipment was : adequate.
a.
Test. Equipment' Reviewed
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TI-10
-Mansfield/ Green Deadweight Tester Model T-50
TI-45-
Heise Test Gauge Model CCM6191
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TI-90
Fluke Digital Multimeter 8600A
TIS-1002 ~ General Radio Decade Resistance 1433-F'
TIS-1009 Fluke D. C. Calibrator Model 3330B
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b.
Findings
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No items of noncompliance or deviations were identified in this
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subarca.
3.
Surveillance of Safety Related Components or Equipment
The inspector reviewed plant surveillance / calibration procedures listed
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below. This review was performed to determine if. the surveillance. test
was covered by properly approved procedures;-the procedures contained
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prerequisites and preparations for the test; the procedures contained
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functional testing of instrumentation; the procedures included acceptance
cri'.eria; the procedures included operational checks prior to returning
equipment to service; the technical content of the procedures would result
in satisfactory testing.
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a.
Documents Reviewed
ICP 2.1 Reactor Coolant. Flow Test
ICP 2.1 Reactor' Power VS Delta T Test
ICP 2.1 Steam' Generator Pressure Test-
ICP 2.1 Containment Pressure Isolation Valve Test
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ICP 4.1 Reactor Coolant Temperature Calibration
ICP 4.1 and ICP 4.3 Pressurizer Water Level Calibration
ICP 4.1 and ICP 4.8. Containment Spray-Calibration
ICP 4.1, ICP 4.6, and ICP 4.7 Steam Generator Flow Mismatch l
Calibration
ICP 4.12 Accumulator Pressure Cal'bration
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ICP 4.17 Volume Control Tank Level Calibration
ICP 4.22 Containment Sump Level Calibration
ICP 4.30 Refuel Source Range Drop-In Detector Calibration -
b.
. Findings
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No_ item's of noncompliance or deviations-_were identified in this
subarea,
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4.
Calibration of- Safety Related Components Required by Technical Specifications
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The inspector reviewed plant calibration records and selected. logs and.
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records for the below listed calibration-activities. .'TNi's review was
performed to determine that the frequency of = calibration was met; the
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service status of the system was in conformance with the applicable
limiting conditions of operation; the procedures used to calibrate _the-
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components were reviewed and approved as required by the Technical
Specifications; the procedures used contained accept ble trip settings -
using applicable technical specification ~ requirements; the procedures
used contained detailed stepwise instructions, the technical content of
the procedures would result in satisfactory calibration; the. trip points
conformed to applicable Technical Specifications; the qualifications of'
two individuals in the I&C Group having responsibilities for performing
calibrations were adequate.
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a.
Calibration Records Reviewed
Note: All records reviewed were the most recently completed
test / calibration for both units.
ICP 4.2 Reactor Coolant Flow Transmitters
ICP 4.4 Pressurizer Pressure Transmitters
ICP 4.7 Feedwater Flow Transmitters
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ICP 4.8 Containment Pr essure Transmitters
ICP 4.11 Accumulator Level Transmitters
ICP 4.14 Boric Acid Control System
ICP 4.17 Volume Control Tank Level Transmitters
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ICP 4.20 Residual Heat _ Removal Pump Flow
ICP 4.22 Containment Sump Level
ICP 4.29 Analog Rod Position
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b.
Findings
Of the twenty (20) sets of calibration data for the procedures
listed above, five.-(5)' contained as left values outside the
acceptance criteria for the procedure. An additional twenty
(20) sets of calibration data from " Series 4.0" procedures were
examined 'and two (2) more similarLoccurances were noted.
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Noncompliance
Point Beach Nuclear Plant Technical Specification Section 15.6.8.1
states, in part that the plant shall be operated and maintained
in accordance with approved procedures. Major procedures. . .shall be
provided for the following operations where these operations involve
nuclear safety of the plant. -Category No. 7 is surveillance and
testing of' safety related equipment' .
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10 CFR 50 Appendix B.Section XI states'in part that test results-
shall be documented and evaluated to assure that..the test: require-
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ments have been satisfied.
Contrary to the above, the inspector found the following calibra--
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tions to be-outside_the. test acceptance criteria with no evider.ce
of the technician noting these. conditions and the tests accepted
by the I&C supervisor and.the I&C engineer. Each of these. tests
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has a section for noting problems and disposition of the problem.
In each case, the area was blank. Discussions with~the-I&C engineer
indicated that he did review results for violating technical
specification limits and conservativeness.
ICP 4.7
Unit I dated December 4, 1980
Feedwater Flow
FI-466
FI-476
ICP 4.11 Unit 2 dated April 18, 1980
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Accumulator Level
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ICP 4.14 Unit I dated December 9,1980
F111
Boric Acid Dilution Flow
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ICP 4.14 Unit 2 dated May 6, 1980
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Boric Acid Dilution Flow
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ICP 4.19 Unit 2 dated April 17, 1980
LI-920
Refueling Water Storage
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Tank Level
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ICP 4.21 Unit I dated December 18, 1980
Charging Water Flow
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ICP 4.22 Unit 2 dated April 18, 1980
LT-4107>
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Containment Sump "A" Level
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Of particular concern is ICP 4.7 for feedwater flow. Discussions
on the review of this item with the I&C Engineer indicated that it
was conservative from the standpoint of feed flow / steam flow mis-
match, but had not considered understatement of feed flow impact on
the reactor calorimetric calculations. Discussions with the reactor
engineers indicated they had not.been informed of the feedwater. cal-
ibration errors.
(266/81-08-01; 301/81-07-01)
5.
Calibration of Safety Related Coinponents Not Specified by Technical'
Specifications
The inspector reviewed plant calibration records listed below. This
review was performed to determine if specific calibration requirements
have been established; the operating range / accuracy of components were
consistent with applicable Technical Specifications /SAR; the procedures
used to calibrate the components were reviewed and approved as required
by Technical Specifications; the procedures used contained acceptance-
criteria consistent with Technical Specifications /SAR criteria; the
procedures used contained detailed instructions commensurate with the
complexity of the calibration; the technical content of the procedures
would result in satisfacto;y calibration.
a.
Calibration Records Reviewed
ICP 5.18 Rod Speed Control
ICP 5.19 Steam Dump Control
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ICP 5.20 Pressurizer Pressure Control
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ICP 5.21 Pressurizer Level Control
ICP 6.12 Auxiliary Feedwater
ICP 6.15 Auxiliary Coolant
ICP 6.17 Safety Injection
PT-M-1 Station Batteries
PT-A-1 Emergency Diesel Inspection
PT-R-4 Testing of Safeguard Protective Relaying
b.
Findings
Noncompliance
ICP 6.17 for Unit I dated November 10, 1980 left FIT-930 for_ Chemical
Addition Tank Inlet Flow outside the. test acceptance values without
evidence of evaluation.
This is a further example of the problem described in Subsection 4.b.
6.
Exit Meeting
The exi. meeting was held with those plant personnel indicated by an
asterisk in Paragraph 1 on Friday, March 27, 1981. The findings of
this report were discussed with those present.
The inspector indicated to those present his appreciation of the
caoperation by plant personnel during the conduct of this inspection.
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