IR 05000335/1987007
| ML17219A578 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/05/1987 |
| From: | Anderson C, Chung J, Joe Golla, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17219A577 | List: |
| References | |
| 50-335-87-07, 50-335-87-7, IEIN-85-071, IEIN-85-71, NUDOCS 8705190394 | |
| Download: ML17219A578 (16) | |
Text
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W y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30323 Report No.
50-335/87-07 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33102 Docket No.
50-335 Facility Name:
St. Lucie Unit
Inspection Conducted:
March 16-23, 1987 License No.
DPR-67 Inspectors:
eph
. Golla, Reac r Engineer date Bin W. Chung, Lead tor Engineer date Cliffo
.
An rson, Chief Plant Systems ection, EB, RI 46ne~
F. Jape, Chief Test Programs Section, RII dat date Accompanying Personnel:
Myuny-Yi0 Jung, Senior Engineer, KAERI/NSC Seon-Ho Song, Senior Researcher, KAERI/NSC Scope:
Routine unannounced inspection of procedure review, test witnessing and preliminary results evaluation of periodic containment inte-grated leak rate test.
Results:
No violations or deviations were identified.
87051903'P4 870512 PDR ADOCK 05000335
DETAILS 1.0 Persons Contacted 2.0
- J. Barrow, Operations Superintendent
"H. Bishop, Site Facilitator
- T. Diliard, Superintendent of Maintenance
"K. Gracia, FPL-QA
~K. Harris,'Site Vice President
- G. Longhouser, Section Supervisor
- L. McLaughlin, FPL - Technical Staff Engineer
- L. Motley, FPL - Technical Staff Engineer
- L. Pearce, Operations Supervisor
"C. Pell, FPL - Technical Staff Supervisor
- D. Sager, St.
Lucie Plant Manager
"D. Stewart,-FPL - Technical Staff Engineer
~E.
Munder lich, PSL -
RE Ebasco Service Inc.
- H. Bibb, Resident Inspector
- R. Crlenjak, Senior Resident Inspector
"F. Jape, Section Chief, Test Program Section, Region II R. Lipinski, NRR Korea Advanced Ener Research Institute
"*Song-Seon Ho
""Myung-Mo Jung The inspector also held discussions with other licensee employees during the inspection, including operations, technical supports, and other craft personnel.
- Indicates those present at the exit meeting held March 23, 1987.
- Indicates the observers from Korea to witness portion of the ILRT.
Administrative Controls of Inte rated Leak Rate Test (ILRT)
Pretest meetings were held several times with the licensee representatives to discuss the progress of test preparations, the scope of the test, and the testing methodology.
The following observations were made prior to the performance of the test:
The gA review of the test procedure was incorporated into the test procedure.
Several valve repairs were in progress including the V-100 and V-101 of the Steam Generator Blowdown lines, and the PORV (Power Operated Relief Valve).
ILRT valve lineups were not completed.
Temporary blowers would be used to circulate the air in the containment.
A total of 40 RTDs and 10 Dewpoint sensors would be used, and in-situ calibration checks of these devices were performed prior to the ILRT.
The inspectors also reviewed applicable station admi nistrative procedures and interviewed personnel to evaluate the licensee's administrative con-trol program and implementation.
2.1 Administrative Control 2.2 The inspectors interviewed selected licensee personnel and reviewed administrative documents, procedural sign-offs, data collection and the official Type A test-log of events.
The test activities were observed to verify that:
prerequisites were met; the test was conducted in accordance with the procedure; test directors were designated and their responsibilities were defined; and required plant parameters were being recorded.
The inspectors noted that the licensee maintained good control of containment and penetration area access before and during the ILRT.
References a.
St.
Lucie Unit 1 Technical Specifications Sections 4.6. 1.2 and 4. 6. 1. 6.
b.
IE Information Notice No. 85-71,
"Containment Integrated Leak Rate Tests."
C.
d.
Bechtel Topical Report "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants,"
BN-TOP-l, Rev.
1, November 1, 1972.
American National Standard ANSI N45.4-1972,
"Leakage Rate Testing of Containment Structures for Nuclear Reactors."
Appendix J,
CFR 50, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors."
2.3 Documents Reviewed a.
Operating Procedure No. 1-1300050, Rev.
6, "Integrated Leak Rate Test."
b.
Calibration Records for ILRT Instrumentation by the Florida Power and Light Company (FPL)
18C Department, Phys-Chemical Research Corporation, Mensor Corporation, Pennwalt Corporation, and John Fluke Manufacturing Company, Inc.
c.
Administrative Procedure No.
0010431, Rev.
5, "Preventive Maintenance Program."
d.
Administrative Procedure No.
0010432, Rev.
29, "Plant Work Orders."
e.
Administrative Procedure No.
0010435, Rev.
6, "Mechanical Maintenance Department Training Program."
.f.
Administrative Procedure No.
0010437, Rev.
17, "Schedule of Mechanical Maintenance Surveillance Requirements."
g.
Official Type A Log Book of Events.
~
~
~
3.0 Pre-Test Activities 3. 1 Malkdown Ins ection General plant tours were made several times from March 18 through March 22, 1987, and a pre-closeout containment inspection was con-ducted on March 20, 1987.
The objectives were for the inspector to become familiar with the plant equipment and systems, and to verify the location and status of the various plant equipment and instrumentation for the Integrated Leak Rate Test (ILRT).
General housekeeping and equipment tagging were observed, prior to the containment pressurization.
The position of selected Dewpoint sensors and RTDs inside the con-tainment was inspected for adequacy and consistency with the test procedure.
Six Coppus Blowers were temporarily installed in the containment to circulate the air in the vessel to prevent the presence of stagnant air, which could create erroneous calcula-tions of air mass inside the containment.
A ser ies of Chiller-Dryers wer e lined up with the air compressor s
to maintain the moisture content as low as possible during the containment pressurization.
The air was pumped through an 8" line, penetration No.
54, dedicated for the ILRT.
The containment pres-sure and the leakage data were monitored in the data center by two Mensor pressure instruments and a computer with a display system, respectively.
A data acquisition system converted the data and
transmitted the data to a computer for the leak rate calculations.
The data center was located at the electrical penetration area.
The inspector noted that according to the licensee's procedures and drawings, two air blowers were to be placed at the 112'levation in the containment free space, 180 degrees apart and facing each other on opposing walls.
The inspector noted that one of two blowers was not positioned at the designated 112'levation location.
The licensee was notified of this observation.
The blower was subse-quently relocated to the appropriate location.
3.2 S stem and Valve Lineu s Valve lineups and systems configurations were inspected during the containment pre-closeout inspection and the piping penetration walk-through tours.
The control room indications of system and valve positions were verified for consistency with the test procedure.
The following valves inside the containment were inspected to verify their position:
Component Cooling Mater (CCM) from RCP:
V-14375, V-14376, V-14377 Primary Makeup Mater:
V-15330, Y-15329 Charging:
V-2304, V-2305, NV-02-1, NV-02-2 Feedwater 1A:
I-Y-9102, I-V-9117 Feedwater 1B:
I-V-9118, I-V-9180 RCB Cooler CCW Supply:
14328 The inspectors noted that the appropriate tanks and systems were vented in accordance with the test procedure, including the quench tank.
System lineup was verified and the control room indication of the following remotely operating valves was verified:
The RHR system B was lined up with all four headers to remove the decay heat during the ILRT.
Containment Spray:
I-NV-07-3B, I-FCV-07-1B, I-NV-07-3A, I-FCV-07-1A Safety Injection System:
HCV-3645, HCV-3646, HCV-3647, NV-03-1B, HCV-3625, HCV-3626, HCV-3627 SG Blowdown Sample:
I-FCV-23-7
Containment Sump Suction:
I-NV-07-2B CCW to RCP:
I-HCV-14-7, I-HCV-14-1 Other accessible isolation valves located outside of the containment and near the piping penetration area were inspected.
The inspector was informed that procedural changes were made to apply end caps to the main steam line valves, 8100, 8101, 8132, and 8233, and that post-ILRT penalties to the ILRT results would be applied based on the "As Left" and "As Found" LLRT results of the isolated valves.
The inspector reviewed the Temporary Changes (TC) to the procedure that allowed the isolation.
No unacceptable conditions were identified.
3.3 Procedure Review By a letter dated January 23, 1987 to the Commission, the licensee stated that an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reduced-duration, ILRT (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
would be conducted in accordance with the methodology described in the Bechtel Topical Report, BN-TOP-1, Revision 1, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants."
The inspector reviewed the ILRT test procedure, 1-1300050, Revision 6, "Integrated Leak Rate Test" for:
consistency with the BN-TOP-1, Revision 1; adequacy of the procedure to perform the test; and system isolation.
The inspector noted that several Temporary Changes (TCs) to the procedure were made.
The inspector also identified several minor typographical errors in the procedure.
The inspector found that the acceptance criterion for the stabili-zation duration in the procedural step 8.4.8 was not consistent with one of the two criteria specified in section 2.3 of the BN-TOP-1.
Acceptance criterion 1 requires that the rate of change of the con-tainment temperature, averaged over the last two hours, be less than 0.5 F/hr/hr.
However, the procedure stated that the rate of change be averaged over the last hour.
The licensee subsequently revised the procedure so that the acceptance criteria in the revised proce-dure were consistent with BN-TOP-l, Revision l.
The computer software for calculating containment leakage was pro-vided by the Ebasco Service, Inc.
The total-time calculational method was employed to analyze the ILRT data.
This was consistent with the method specified in the topical report.
The following is a list of the TCs issued for the ILRT procedure:
Temporary Procedure 1-87-113 Temporary Change 1-87-119 Temporary Change 1-87-120
Temporary Change 1-87-123 Temporary Change 1-87-125 Temporary Change 1-87-127 Temporary Change 1-87-128 4.0 Containment Inte rated Leak Rate Test During the period March 20 through March 22, 1987, a periodic containment integrated leak rate test was performed at St.
Lucie Unit 1.
The test was performed in accordance with Operating Procedure No. 1-1300050, Revision 6,
"Integrated Leak Rate Test" and BN-TOP-1, Revision 1, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants."
The purpose of this inspection was to ascertain that the CILRT was conducted in compliance with the requirements and commitments referenced in sections 2.2 and 2.3 of this report, and that the test results met the acceptance criteria specified in the station test procedures, BN-TOP-l, Revision 1, and Appendix J,
CFR 50.
4. 1 Test Instrumentation The inspectors reviewed the calibration records for the ILRT instru-mentation to ascertain that the instruments were within proper calibration tolerance for the test.
These records indicated that the standards used were traceable to the National Bureau of Standards (NBS).
The inspectors observed the operation of the automatic data collection system during the conduct of the test.
Under BN-TOP-1 recommendations, the ILRT should employ a minimum of twelve to twenty-four temperature sensors, at least six Dewpoint sensors, and one precision pressure gage.
The following is a summary of the sensors used for the test.
Sensor Drybulb Temperature Dewpoint Temperature Pressure
" started with 40 RTDs
"" started with 10 sensors
39*
BN-TOP-1 Recommended Min>mum c ual The latest industrial standard, ANSI N56.8-1981, specifies a minimum of three Dewpoint sensors.
This standard specifies that no Drybulb temperature sensor be allowed to represent a volume fraction greater than 10K during the CILR.2 Stabilization Period The following summarizes results of the stabilization period as compared with the acceptance criteria:
a.
Test Ouration - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
Acce tance Criteria - 1) The rate of change of average temper-ature is less than 1'F/hr averaged over the last two hours.
-or-2) The rate of change of temperature changes less than 0.5'F/hr/hr averaged over the last two hours.
Criterion 1:
('F/hr)
Acceptance Actual Criteria Results 1.0 0. 689 Criterion 2:
('F/hr/hr)
4.3 Inte rated Leak Rate Test (ILRT) Result 0.5 0. 075 The licensee computed the containment leakage using the total time method (TTM) in accordance with BN-TOP-1 acceptance criteria.
The preliminary results indicated a successful CILRT for both the "As-Found" and "As-Left" conditions.
A plot of the leakage trend may be seen on Attachment where the leak rates measured and the 95K upper confidence limit (UCL) values are plotted as a function of time, the design and allowable limits are shown by two flat straight lines.
It is interesting to note that the measured and 95K UCL not only meet the acceptance criterion but also decrease, away from the limits.
A final evaluation of the test results will be performed by the NRC on receipt of the licensee's summary technical report on the test.
A summary of the acceptance criteria and test results is as follows:
a.
Inte rated Leak Rate Test The test period started at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on March 21, 1987 and ran for 8.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
b.
S ecifications and the Results The calculated and 95K Upper Confidence Limit (UCL) leakage rates were 0.078%/day and 0. 131K/day respectively.
They met the acceptance criterion of 0.375K/da = 0.500%/day Containment Desi n Leaka e Rate L
ILRT Acce tance Criteria 0.75 L
= 0.375%/day Fitted Total Time CILRT Leaka e Rate L
= 0.078%/day U
er Limit of 95% Confidence Level UCL
= 0. 131%/day c.
BN-TOP-1 Reduced Duration ILRT Termination Criteria The results presented above in item b were compared with specific criteria given in the BN-TOP-1 as follows:
(1)
The trend of the total time calculated leakage rate shall indicate that the magnitude of the leakage rate is tending to stabilize at a value less than or equal to 75% of La (0.375%/day).
Lam = 0.078% per day with a negative skew The result met the acceptance criterion of 0.375%/day.
I (2)
At the end of the ILRT, the upper limit of the 95% con-fidence level shall be less than or equal to 75% of La (0.375%/day).
95% UCL = 0.131% per day The 95% UCL indicated a value less than 0.375%/day and thus met the requirement.
(3)
The mean of the measured leakage rates over the last five hours or twenty data sets, whichever provides the most points, shall be less than or equal to 75% of La (0.375%/day).
Mean of simple leakages from SN112 to SN132 = 0.142%
per day.
4. 4 Inte rated Leak Rate Test Su lemental Verification Test:
ontro e
ea ate est a.
Test period started at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on 3/22/87.
Test conducted for 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
The objective of this test is to verify the adequacy of the instru-ments employed for the ILRT.
The mathematics of the verification test is presented as follows:
b.
Fitted total time ILRT leakage rate Lam = 0.078K per day Containment design leakage rate La
= 0.500K per day Superimposed CLRT leakage rate Lo
= 0.318K per day Fitted CLRT total time leakage rate Lc
= 0.324K per day Lo +
Lam
- La/4 p,
Lc
<
Lo
+
Lam
+
La/4 0 318 + 0 078 0 125
< 0. 324
<
0. 318 + 0. 078 + 0. 125 0.271
<
0.324
<
0.521 The CLRT value of 0.324K/day was acceptable.
4.5
~tLRT Ch March 11 1987 1130 gC completed inspection of containment vessel and shield building.
No problems were identified.
March 14 1987 0900 Ebasco manager of testing conducted ILRT briefing with technical staff test group.
March 17 1987 1600 Containment cleanup, ILRT instrument operability checks and system lineups are ongoing.
March 20 1987 0830 1855 2120 Precloseout containment inspection conducted by NRC inspectors and test personnel.
Containment is closed up.
Final inspection of contain-ment by test personnel is complete.
Commenced pressurization of containment.
March 21 1987 0600 During pressurization found leakage at 3 penetrations, they are:
P-9 Instrument air - filled rubber glove in 15 sec.
P-14 N
supply - filled rubber glove in 30 sec.
P-26 letdown line - filled rubber glove in 3 se Continuing pressurization at a rate of 3.44 psi/hr.
Secured from pressurization.
Vented pressurization mani fo ld.
1400 Stabi 1 izati on criteri a has been met.
1645 Calculated leakage is indicating an unacceptable leak rate.
Leak survey team has been sent out to find the source.
2115 2130 Leak survey team found air in containment sump suction lines P-32 and P-33 at valves I-07002 and I-07004 indi-cating that MV-07-2A and NV-07-2B may be leaking.
Took measures to isolate the leakage at I-07002 and I-07004 by further closure of MV-07-2A and NV-07-2B.
These valves are not containment leakage paths for the accident con-dition (these valves would be flooded during an accident).
March 22 1987 0000 Noted decreasing trend in containment leak rate.
0600 The test was started from 2130 on 3-22-87 at the time the leakage was stopped at containment sump suction lines P-32 and P-33.
Data was collected to 0600.
Met acceptance criteria for ILRT.
0606 Started 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> controlled leak rate test (CLRT) stabili-zation period at a flow of 21.75 SCFN.
0700
'tarted CLRT.
1115 Net acceptance criteria for CLRT.
1120 Started depressurizing the containment.
5.0 A/ C Test Covera e
The inspector discussed gA/gC coverage during the ILRT and observed various gA activities related to the preparation, initiation, and per-formance of the test.
It was determined that gA surveillance and audit coverages were adequate in the following areas:
Pretest surveillance by gA.
Continuous gA survei llances during the ILRT performance.
Test procedure review and findings.
Corrective actions were imple-mented into the procedur.0 The inspector was informed that gA personnel training program was equivalent to the operator license training programs, and that senior gA staff members held senior reactor operator's license.
Even though no safety significant items were identified, the inspector was concerned with the timeliness of transmitting the gA findings to the plant operations personnel.
No formal administrative procedure existed to notify the plant operations personnel of deviations or discrepancies other than the audit reports.
These reports might take more than a week to issue, The gA findings regarding the ILRT test procedure were infor-mally given to the test director for corrective actions.
The gA findings would be documented later in the gA audit report.
However, the inspector determined that the audit program and the informal notification process were effective and no unacceptable conditions were found.
Plant Tours 7.0 The inspectors made several tours of the plant facilities, including the reactor and auxiliary buildings, emergency diesel generator rooms, control room, containment and plant exterior (compressors, ILRT data center, and piping penetration areas)
in order to monitor activities related to the preparation and conduct of the test.
The following findings were identi-fied during the facility tours:
The interior of the containment was clean and general housekeeping was good.
The administrative controls of the data center and air compressor areas were adequate for personnel access controls, and general housekeeping in the areas was good.
The housekeeping in the piping penetration needed improvement.
Mater and oil spills, debris, plastic sheets, and tools were found on the various areas in the penetration cubicles.
The licensee stated that the areas would be cleaned after completion of the ILRT.
No unacceptable conditions, deviations or violations were observed.
Exit Meetin Licensee management was informed of the purpose and scope of the inspec-tion at the entrance interview.
The findings of the inspection were periodically discussed and were summarized at the exit meeting on March 23, 1987.
Attendees at the exit meeting are listed in section 1.0 of this report.
At no time during the inspection was written material provided to the licensee by the inspectors.
ATTACHMENT:
Leak Rate Chart
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