IR 05000285/1990009
| ML20012D152 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1990 |
| From: | Ray Azua, Seidle W, Singh A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20012D150 | List: |
| References | |
| 50-285-90-09, 50-285-90-9, NUDOCS 9003260535 | |
| Download: ML20012D152 (6) | |
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F U.S. NUCLEAR REGULATORY COMMISSION--
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REGION IV
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NRC Inspection Report: 50-285/90-09 Operating License: DPR-40>
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Docket:
50-285
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._ Licensee: OmahaPublicPowerDistrict'(0 PPD)
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444 South 16th Street Mall Omaha, Nebraska 68102-2247
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' Facility Name:- Fort Calhoun Station (FCS)
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Inspection At: Blair, Nebraska
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Inspection Conducted:
February 27 through March 2,1990 Inspectors:
3//7/7o A. Singh, Rpactor Inspbetor, Test Programs Date-
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Section, Division of Reactor Safety
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m R. V. Azut', Project Engineer, Section C Date Division of Reactor Projects Approved:
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W. C. Seidlet) Chief, Test Programs Section Date
- g.g Division of Reactor Safety Inspection Summary n
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, 89E -Inspection Conducted February 27 through March 2,1990 (Report 50-285/90-09)
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Areas Inspected: Routine, announced inspection of the FCS containment
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"O integrated leak rate test (CILRT).
L nx OS Results: Within the area inspected, no violations or deviations were o@
identified.
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$o-The licensee performed a 24-hour, Type A, total time test as de::cribed in S$c ANSI N45.4-1972 and 10 CFR Part 50, Appendix J.
The test was completed on March 4, 1990, at 6:15 a.m. (CST). Based on preliminary data, the identified total leakage did not exceed the.75La limit set forth in Appendix J of 10 CFR Part 50. The licensee implemented the CILRT procedures effectively.
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DETAILS
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1.
PERSONS CONTACTED OPPD
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C. Bloyd, Special Services -
- C. E. Boughter, Lead Engineer, Special Services
- C, J. Brunnet, Supervisor, Operations, Quality Assurance E
- R. L. Joworski, Manager, Station Engineering W. F. Lennox, Special Services S. Lindquist, Licensing Engineer
- D. N. Matthews, Supervisor, Station Licensing
- S'. K. Morales, Special Services Engineer
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W. Orr, Quality Assurance
- G. R. Peterson, Plant Manager,
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A. W. Richard, Assistant Plant Manager, FCS l
- R. W. Short, Supervisor, Special Service C..F. Simmons, Station Licensing Engineer
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Bechtel. Inc.
I L. Young, Engineer (CILRT)
B.Patel, Engineer (CILRT)
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- T. Reis, Resident Inspector, FCS
The inspectors also contacted other plant personnel including operators, j
technicians, and administrative personnel.
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- Denotes those present during the exit interview.
2.
CONTAINMENT INTEGRATED LEAK RATE TEST (CILRT)
The purpose of this inspection was to verify that the CILRT was conducted i
in accordance with the. licensee's procedures, Appendix J to 10 CFR Part 50 I
and ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for i
Nuclear Rear. tors." This was done-through direct observation, records review, and independent calculations.
2.1 Procedure Review (70307)
The inspectors reviewed the procedures listed in the attachment. The
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purpose of this review was to verify that the licensee had incorporated the associated regulatory requirements and commitments.
The inspectors compared the licensee valve lineup, as described in Procedure SS-ST-ILRT-0006, against a sample selection of the licensee's piping and instrumentation diagrams (P& ids) of individual containment i
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-building penetrations, and the P& ids for the chemical volume end control-system (CVCS), and the. safety injection-systems (SIS). This was done in-an effort to determine that all the appropriate valves in the selected systems were addressed in the procedure.. The inspectors also reviewed the
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test position of the valves._' listed in the same procedure, to verify that
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the associated systems were placed in correct alignment for the
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performance of the CILRT.
The CILRT Procedure SS-ST-ILRT-0001 gave the licensee the option either to perform the 24-hour, Type A Total Time Test, as described in ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for NuclearReactors"(datedMarch 16,1972) or, under favorable conditions, to perform a reduced time test, using the methodology described in.Bechtel Topical Report BN TOP-1. The inspectors reviewed the two options-and found them to be technically adequate.-
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In addition, the insnectors reviewed the revision changes that were made to the procedures listed in the attachment and found them to be
acceptable. The licensee did not alter, in any significant manner, the technical content of the procedures or the way in which the test-was being performed. The inspectors also verified that these changes were approved, as indicated by the appropriate signatures, and that these changes were made in accordance with the plant's standing orders.
It was noted that in preparing for the test, the licensee identified a few errors in the CILRT procedures after the procedures had already been signed off as completed. One such error was identified in'the valve lineup sheet of Procedure SS-ST-ILRT-0006 for Penetration M-80.
Two valves were accidentally omitted, and because of this error the licensee failed to vent a section of piping before the containment was pressurized.
The' licensee took the appropriate actions to correct this error, which included adding a penalty factor to the final results of the CILRT. The
inspectors concluded that the probable cause of these errors was the result l-of the licensee's hurried efforts to meet the planned test schedule and the number of changes that were being made to the test procedure prior to the CILRT. Both of these conditions placed a strain on the personnel involved and may have affected the quality of the procedure review process. The inspectors urged the licensee to consider reviewing the CILRT procedures again, once the test was completed, to verify that all the errors had been identified.
No violations or deviations were identified in the review of this program area.
2.2 CILRT Surveillance (70313)
The inspectors performed tours of the reactor containment building. This was done to verify the installation of the test equipment and the valve lineup process.
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.The licensee maintained strict access control to'the containment building.
during the preparation.for the CILRT. This effort effectively minimized
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the possibility of any of the equipment involved in the test from being accidentally altered or damaged. The valve lineup process was performed using Procedure SS-ST-ILRT-006.
It was noted that the containment penetration piping and instrumentation diagrams (P& ids) provided in the g
Fort Calhoun USAR were an effective aid in identifying the containment j
penetrations and the associated valves being tested.
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y The inspectors observed approximately 70 percent of the valves that had
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been positioned'for the test. No errors or discrepancies were noted. The
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operators that accompanied the inspectors during the valve walkdown were-found to be very knowledgeable of containment piping and penetrations.
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The calibration documentation for the test equipment (RTDs, dewpoint hygrometers, and pressure gauges) were reviewed by the inspectors.
No errors were detected and all instruments were found to be in calibration L
for the period encompassing these tests. The inspectors also reviewed the
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certification and training records of three of the technicians involved in inspecting,. testing, and installing the test equipment; no deficiencies
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l were identified.
The inspectors reviewed the local leak rate test (LLRT) data that was obtained prior to or during the preparation for the CILRT. !!o significant leakages were noted that would affect the final results of the CILRT.
In addition, the methodology used in performing these tests was reviewed. No discrepancies were noted.
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The personnel airlock to the reactor containment building was closed, and-
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the initiation of the containment pressurization began on March 1, 1990.
The-minimum test pressure of 60 psig was reached on March 2, 1990. At 6:15 a.m. on March 3,1990, the licensee met the-stabilization criteria as l~
described in Procedure SS-ST-ILRT-0001. The licensee, at this time, began
taking test data every 15 minutes, marking the official start of the CILRT.
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The inspectors reviewed the licensee's controlled copy of Procedures SS-ST-ILRT-0001 and SS-ST-ILRT-0006, to verify that the proper sections had been signed off, and that all the prerequisites had been met.
The CILRT was completed on March 4, 1990, and based on the preliminary data, no leakage was detected that exceeded the.75La limit, established in Appendix J to 10 CFR Part 50. The accuracy of the licensee's CILRT preliminary results was verified by the inspectors through independent calculations. The inspectors will perform a review of the official results when the final report is issued. The results of this review will be documented in a subsequent NRC report.
No violations or deviations were identified in the review of this program are P
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EXIT lilTERVIEW An exit meeting was held on March 2, 1990, with the personnel identified in paragraph 1.of this report. At the exit interview, the inspectors summarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the information provided to, or reviewed
by, the inspectors.
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ATTACHMENT
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Procedure No.
Title Date i
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SS-ST-ILRT-0001 Containment Integrated 2/28/90 Revision 2 Leak Rate Test (ILRT)
SS-ST-ILRT-0006 Operations ILRT Preparation 2/27/90
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Revision 1 and Recovery
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SS-ST-ILRT-0009 ILRT Test Instrumentation ~
2/14/90-Revision 0 Installation
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SS-ST-ILRT-0015 Containment Pressurization 2/14/90 Revision 0 and Controlled Leakage Set Up Local Leak Rate
Determination i
- ST-CONT-3 Containment Isolation Valves 9/2/88 Revision 29 Leakage Rate Test, Type C
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