IR 05000311/1986035
| ML20212K879 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/09/1987 |
| From: | Anderson C, Chung J, Joe Golla NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212K857 | List: |
| References | |
| 50-311-86-35, NUDOCS 8701290227 | |
| Download: ML20212K879 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 50-311/86-35 Docket No.
50-311 License No. DPR-75 Priority
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Category C
Licensee:
Public Service Electric and Gas Company P. O. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name: Salem Nuclear Generating Station, Unit 2 Inspection Ati Hancocks Bridge, New Jersey Inspection Conducted: November 19-27, 1986 Inspectors:
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/@N cv 151. Chun'g, Lea Wactor Engineer date/
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Eph G911, 7., Rea' or Engineer d te
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Approved by:
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C. J./ Anderson, Chief date Plant Systems Section Inspection Summary:
Inspection on November 19-27, 1986 (Inspection Report No. 50-311/86-35).
Areas Inspected:
Routine unannounced inspection of test witnessing and preliminary evaluation of containment integrated leak rate test (CILRT), and tours of the facility.
Results: No violations or deviations were identified.
8701290227 870116 PDR ADOCK 05000311 G
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DETAILS 1.
Persons Contacted
- R. Brandt, Inspection Service Engineer C. Conner, ISI Supervisor P. Isenburg, Test Director - Back Shift R. Kirk, Jr., ISI Supervisor
- L. Lake, ISI Engineer
- D. Perkins, Station QA Manager
- S. Sienkiewitez, Test Director
- T. Spencer, Senior Maintenance Supervisor
- W. Treston, Senior ISI Supervisor PSE&G Research and Testing Laboratory R. Bennington, Test Engineer G. Gruffner, Test Engineer B. dicks, Materials _ Test Engineer H. Worthington, Technician Others E. Cilmiewicz, Gilbert Associates F. Dickey, Interfacts Inc.
K. Getty, Stone & Webstei-The inspectors also interviewed other licensee employees during the inspection, including Operations Staffs, Technical Support 2nd performance personnel.
- denotes those present at the exit interview on November 27, 1986.
2.
Pre-Test Review a.
The inspectors reviewed the Containment Integrated Leak Rate Test (CILRT) procedure and procedure changes for conformance with Technical Specifications, Station Administrative Control Procedures, and Appendix J of 10 CFR 50 to verify that:
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Procedures and changes were reviewed and approved.
- Procedures were technically adequate and included sufficient details, such as; air pressurization method for each penetra-tion on valve; venting of internally isolated volumes; initial pressure plateau; prerequisites, limits, precautions, and acceptance criteria.
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Design Modifications were incorporated into the test procedure.
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Test instruments were calibrated and in servic.
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b.
The following documents and records were reviewed:
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Inservice Inspection Procedure M9-ILP-CT-2, Reactor Containment Building Integrated Leak Rate Test (Type A Test), Salem Unit 2, Revision 00, November 5, 1986.
ANSI /ANS 56.8-1981, Containment System Leakage Testing Requirements.
- 10 CFR, Part 50, Appendix J.
Station Organization Chart.
- CILRT Test Personnel Assignment.
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Technical Specifications.
- Selected CILRT Test Personnel Qualification Records.
On-the-spot-changes (OTSC).
- Drawings: 20531 A8762-19; 205342 A8763-29 Deficiency Report MT-86-156.
c.
Findings The inspector determined that the Reactor Containment Building ILRT Procedure M-9-ILP-CT-2 was technically adequate to perform the test satisfactorily, and the procedure specified sufficient details including:
Test duration (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) and Stabilization period (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />),
Supplemental CILRT Instrument verification test,
Initial conditions and prerequisites, and Calculational Methods.
(1) A pre-closecut walkdown inspection was conducted at 0930 hour0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, November 21, 1986 for final observations of system venting, valve lineup, and of other precautionary steps, inside the containment building.
The inspector noted that 24 temperature elements and 6 Dewcells were installed.
Under ANSI N56.8-1981, a minimum of three Dewpoint temperature sensors are required and no Drybulb tempera-l ture sensors are allowed to represent a volume fraction greater
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than 10% during the test.
These conditions were satisfied.
The following is a summary of the CILRT sensors:
No. Sensor Sensor Minimum Actual Temperature
24 Dewcell
6 Pressure
2 (2) The test procedure M9-ILP-CT-2 required that the specifications given in ANSI N56.8-19El be followed.
It was noted that the licensee employed the mass point calculational method, which is not endorsed by the Type A test methodology specified in Appendix J, 10 CFR 50. However, the licensee stated their view that the mass point method was an acceptable method endorsed in ANSI N56.8-1981.
This is an unresolved item pending NRC clari-fication of the acceptability of this test method (50-311/86-35-1).
(3) The inspector noted that the service water was bypassed for fan cooling units #22 end #24, and three units, #21, #23, and #25, were in service to allew air mixing.
3.
Administrative Controls of CIRLT a.
The inspector reviewed selected licensee personnel qualifications and reviewed their training records for conformance with Technical Specifications; Station Administrative Control Procedures; ANSI N18.7
" Administrative Controls for Nuclear Power Plants"; ANSI N18.1-1971
" Selection and Training of Nuclear Power Plant Personnel"; Regula-tory Guide 1.33 " Quality Assurance Program Requirements".
The inspector also observed the conduct of testing and reviewed procedure / data sheets to verify that:
The test was conducted in accordance with the test procedure.
- Test director / coordinator was designated and responsibility was clearly defined.
- Test was administered and performed in accordance with the licensee's requirements and commitments.
- QA/QC participation and surveillance inspection were visible Test procedures were adhered to during the test, and changes were implemented in accordance with the station procedural requirement.
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b.
Findings (1) The inspector observed that special access tags and tag log books were issued for the test personnel. This procedure enabled the test director to control various test activities during the CILRT.
(2) The inspector reviewed the vendor control and audit document, and verified by review of the QA vendor list that the CILRT test personnel and consultants from the testing laboratory were qualified to perform the test and were controlled by the licensee's vendor surveillance program.
4.
Test Instrument The inspector reviewed the calibration records of the instruments and sensors used for the CILRT.
It was ascertained that the instruments were calibrated within the six month period prior to the test and that the standards used were traceable to the National Bureau of Standards.
The inspector verified that the instruments and their systems satisfied the instrument selection guidance in ANSI /ANS 56.8-1981. The inspector also reviewed the location of the temperature elements and Dewcells from the drawings and observed the automatic data collection system and their readings.
The calibration records reviewed included the following:
Verification Flow Mass Step change 3M-125-T.C. Roots Meter, October 29, 1986.
Mensor pressure indicator; 1089 and 1090; calibration performed October 29, 1986; Quartz calibration standard.
- 30 Thermocouples, calibrated October 20, 1986.
EG&G and Generation Dewcells, calibrated October 16, 1986.
- Covax RTDs, calibrated October 20, 1986.
Omega RTDs, calibrated October 4, 1986.
HP 2804A Quartz Thermometer, Standard, calibrated September 16, 1986.
- Merion Laminar Flow Element, Standard, certified calibration date of March 13, 1986.
The inspector also reviewed the primary calibration sources, traceable to the NBS, No unacceptable conditions were identifie.
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5.0 "As Found" CILRT Failure
.Due to the excess Local Leak Rate Test (LLRT) results of the Containment Ventilation System Valves, the licensee determined that the "As Found" CILRT did not meet the 0.75 acceptance criteria. The incorporation of the LLRT results to the CILRT was conducted per NRC I&E Information Notice 85-71.
The inspector reviewed completed Work Order No. 0099186179 and 099186195 on the Containment Ventilation System Valve 2VC-5, and Deficiency Report MT-86-195. The LLRT result on 2VC-5 indicated that the leakage rate exceeded the acceptance criteria for both "As Found" LLRT and CILRT.
6.0 Containment Integrated Leak Rate Test (CILRT)
6.1 Visual Inspecton a.
Visual Inspection of Access Areas A visual inspection had been conducted on November 21, 1986 and the licensee's inspection sign-off sheet was reviewed.
The areas inspected were the control room, penetrations and the containment building.
The final closeout was delayed due to leakage of the outboard isolation valve 2VC-4.
b.
Closeout Inspection Prior to containment pressurization the licensee's final close-out inspection was conducted from 1700-2000 hours, November 22, 1986. The NRC inspectors' concurrently conducted an independent inspection tour to verify that locations of the test sensors, system / component lineups, and other conditions were in conform-ance with the requirements specified in the test procedure. The NRC. inspectors observed the following:
All fire extinguisher bottles were vented.
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On a selective sampling basis, the inspectors verified that
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the system / valve lineups were in accordance with the test procedure.
SA120 venting cap was removed.
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SWS lines for #22 and #24 containment fan cooler units were
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isolated with caps.
One fluorescent lamp and a CRT monitor inside the contain-
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ment building were remove..
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6.2 Pressurization.
The co'ntainment' pressurization was commenced at midnight, November 22, 1986 with an average rate of 3 psi per hour. Shortly V
after the pressurization a 10" containment vent valve, 2VC-5, developed a leak, and the licensee determined that a liner for the
. butterfly valve was either misaligned or displaced during the pressurization, developing a leak.
The leak gradually increased beyond an acceptable. limit, and the licensee determined to depressurize the containment.
The licensee decided to vent the containment O
pressure through a temporary manual valve, whose operation would be much slower than the air-operated butterfly valve 2VC-5 (less than 10 seconds to close), if the venting had to be terminated due to excess radiation level. Therefore, as a preventive measure, an Area
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Monitoring System (AMS) alarm setpoint was lowered to 0.5 KCPM (50
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times lower than normal) and a radiation surveyor was temporarily installed at the air vent to monitor the release rate.
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The venting was commenced at 1440 hour0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />, November 23, 1986, after completion of an air sampling test. The 2VC-5 valve was subsequently repaired for its missing skim and shaft pin, and the containment pressurization was commenced again at 0905 br., November 25, 1986.
6.3 Chronology of CILRT Sequence
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1700 Pre-closecut inspection performed.
November 23, 1986 1550 Initial pressurization failed due to valve 2VC-5 liner leak.
November 25, 1986 0907 Official test initiated and containment pressurization
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commenced.
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0910 Valve lineups (BEZEL checks) in control room and penetration i
leak checks were conducted by the inspector. Observed QA activities.
0925 Nine (9) compressors in operation.
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i 2338 The containment reached the accident pressure, 63.196 psia.
November 26, 1986
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0015 Commenced Stabilization period.
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0415 Completed Stabilization period:
0.4 F/hr for 4 -hrs. and 0.25'F/hr for last one hour.
0453 Commenced 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT.
November 27, 1986 0453 Completed 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test:
Leak Rate 0.037%/ Day
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UCL 95%
0.04%/ Day
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0750 Instrument Verification Test commenced:
A superimposed bypass flow of 7.60SCFM was imposed.
1150 CILRT Test completed.
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6.4 Conduct of CILRT a.
The inspector conducted an independent. calculation of selected data points and observed the performance of the testing to verify that:
Leakage barrier differential pressure was at least Pa (Peak
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reactor building pressure) during the Design Basis Accident: 63.696 psia.
Testing was conducted in accordance with the procedure.
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Test data was recorded only after test conditions were
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stabilized.
Supplemental verification test was performed.
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Tr. sting was satisfactory and met the requirements
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specified in the Technical Specifications and Appendix J of 10 CFR 50.
Test results were within the acceptance criteria.
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tvaluation and calculations were in conformance with the
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requirements.
The inspector did not find any unacceptable conditions, b.
Stabilization - 4 Hours (1) The averages' of the RTD readings and pressure sensors were 60.3 F and 63.05 psia respectively at the beginning of the stabilization period, and quickly stabilized to 59.06'F and 62.88 psia in two hours. The I hour variation during the 4 - hour stabilization period were;
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AT : 0.39 F/ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 0.24 F/last hour.
-AW : 159 lbs. (calculated)
The acceptance criterion for the stabilization and the initiation of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT required less than-0.5 F/hr temperature variation during the last one hour from the rate of change over 4' hours.
(2) "As Left" ILRT The inspector independently calculated three mass points and compared these with the preliminary calculations obtained from the licensee's computer terminal.
The differences between the inspector's and computer calcula-tions were less than 0.01%.
The following is the summary of the preliminary results:
Test Period:
0453, 11/16 - 0453, 11/27 Test Points:
Leak Rate:
0.037%/ day 95% Confidence Interval:
0.040%/ day Acceptance:
0.075%/ day The containment satisfied the "As Left" ILRT acceptance requirements.
The following additional information was monitored through-out the entire test period:
Atmospheric Temperature
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Barometric Pressure
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Every two hour readings of sump levels, steam
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generators, pressurizers, accumulators, and refueling water storage tank.
The following is a summary of average readings obtained during the course of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test:
Equipment Readings (Initial-End)
Reactor Vessel 91% - 91%
Pressurizer (cold cal.)
70% - 70%
SG #21 (wide range)
99% - 99%
SG #23 (wide range)
100% - 100%
RCDT 22% - 22%
PRT 22% - 22%
Accumulator #21 53% - 53%
Accumulator #23 54.5% - 54.5%
RWST 33.2% - 33.2%
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Instrument Verification Test The licensee superimposed a known leak rate of 7.60 SCFM, which was equivalent to a maximum allcwable leak rate (La)
of 0.1%/ day. The deviation of the total combined leak rate (Superimposed plus containment leak rate) was within 25% of the La.
7.0 CILRT personnel Training and Qualifications The Qualific3tions Records of Test personnel were reviewed, and selected test personnel interviewed.
Their qualifications met the requirements specified in ANSI N 18.1-1971 " Selection and training of nuclear power plant personnel". They were knowledgeable of their responsibilities and technical aspects of leak testing.
No unacceptable conditions were identified.
8.0 Tours The inspectors made several tours of the plant including the reactor building, control room and plant exterior (containment and compressor) in order to monitor the activities related to the performance of the CILRT.
No unacceptable conditions were identified.
9.0 QA The inspector observed active participation of site QA monitors, and conducted a routine surveillance tour with a QA individual.
The inspector also reviewed the vendor surveillance list and audit documents to verify the acceptability of the vendor control program and its implementation.
No unacceptable conditions were identified.
10. Unresolved Items Unresolved items are matters about which more information is required to clarify whether they are acceptable items, items of noncompliance, or deviations. An unresolved item was identified and detailed in paragraph 2.C.(2).
11.
Entrance and Exit Interview Licensee Management was informed of the purpose and scopc of the inspection at the entrance interview, and the findings of the inspection were periodically discussed with the licensee representative during the inspectio i
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The inspector conducted an exit interview with licensee representatives-(denoted in paragraph 1) at the conclusion of the inspection on
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November 27, 1986. The licensee acknowledged the inspection findings.
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