IR 05000271/1986014

Insp Rept 50-271/86-14 on 860621-24.No Violations or Deviations Noted.Major Areas Inspected:Test Witnessing & Primary Results Evaluation of Containment Integrated Leak Rate Test

ML20203E546
Person / Time
Site:	Vermont Yankee
Issue date:	07/15/1986
From:	Anderson C, Chung J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20203E524	List: IR 05000271/1986014 ML20203E521
References
50-271-86-14, NUDOCS 8607240173
Download: ML20203E546 (13)

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION I

t Report N /86-14 Docket No. 50-271 License No. DPR-28 Priority -

Category C Licensee: Vermont Yankee Nuclear Power Corporation I

RD 5, Box 169 Ferry Road Brattleboro, Vermont 05301 Facility Name: Vermont Yankee Nuclear Power Station Inspection At: Vernon, VT Inspection Conducted: June 21-24, 1986 Inspectors: 6/) . ead [ Rea A PW.' Chung, Engineer date

. Approved by: 7& h C.Andfson, Chief,PSS 'date Inspection Summary: Inspection on June 21-24, 1986 (Inspection Report Number 50-271/86-14)

Areas Inspected: Routing, unannounced inspection of test witnessing and primary results . evaluation of containment integrated leak rate test (CILRT),

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and tours of the facilit Results: No violations or deviations were identifie l

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' 8607240173 860716 PDR ADOCK 0500 1

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DETAILS 1.0 Persons Contacted L. Cantrell, SCR0

• G, Cappucio, Senior Mechanical Engineer D. Hamill, NSDQAD

• S. Jefferson, Assistant to Plant Manager

• M. Metell, Engineering Support Supervisor

• J. Pelletier, Plant Manager

• D. Phillips, CILRT Coordinator - Senior Electrical Engineer

• D. A. Reid, Operations Superintendent

• D. J. Wanczyk, Technical Services Superintendent U.S. Nuclear Regulatory Commission

• W. Raymond, Senior Resident Inspector

• Denotes those present at exit meeting held on June 24, 198 .0 Administrative Controls of CILRT

The inspector reviewed selected licensee's personnel qualifications and

, reviewed their training records for conformance with Technical Specifications; Station Administrative Control Procedures; ANSI N1 " Administrative Controls for Nuclear Power Plants"; " ANSI N18.1-1971"

" Selection and Training of Nuclear Power Plant Personnel"; Regulatory 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 adequate test procedur * Test director / coordinator was designated and responsibility was

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clearly defined.

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• Test was administered and performed in accordance with the licensee's requirements and commitment *

QA/QC participation and surveillance inspection were visible during the testin * Test procedures were adhered to during the test, and changes were implemented in accordance with the station procedural requirement _ . . _ _ ._ ._ . - -

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The following documents were reviewed:

ANSI /ANS 56.8-1981, Containment System Leakage Testing Requirement * 10 CFR, Part 50, Appendix * Station Organization Chart

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Operating Procedure (0P) 4029m Type A - Primary Containment Integrated Leak Rate Testing, Revision *

OP 4030, Ype B and C Primary Containment Leak Rate Testing, Revision 1 *

Temporary Procedure Change: DI 86-12, June 19,198 *

CILRT Test Personnel Assignment, June 19, 198 *

Vermont Yankee Technical Specification *

Selected CILRT Test Personnel Qualification Record The details of the findings are discussed in the corresponding section No unacceptable conditions were identified, other than those discussed in the procedure review sectio .0 Pretest Activities A pre-closeout walkdown inspection was conducted at 0515 hour0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, June 20, 1986 for final observations of system ventings, valve lineups, and of other precautionary step The inspector noted that 19 temperature elements and 4 Dewcells were installed. Originally, there were a total of 20 temperature elements, 14 in Drywell and 6 Torus. However, one temperature sensor failed in the Torus leaving 5 sensors in the Torus. Under ANSI N56.8-1981, a minimum of three Dewpoint temperature sensors are required and no Drybulb temperature i

sensors are allowed to represent a volume fraction greater than 10% during the test. These conditions were satisfied. The following is a summary of

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the CILRT sensors:

, No. Sensor Sensor Minimum Actual Temperature 10 19 Dewcell 3 4 Pressure 1 2

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The containment pressure was monitored via two Mensor pressure sensors, and one flow indicator was mounted on a Hydron analyzer line for instru-ment verification test. Four Reactor Recirculation Units (RRU) were aligned for containment air recirculation and mixing during the CILR .0 Containment Integrated Leak Rate Test (CILRT)

4.1 Procedure Review The inspector reviewed the CILRT procedure, OP 4029, Revision 3, for its adequacy and system isolation, including test administration, personnel responsibility during the test, detail steps during the test, acceptance criteria and verification testing. The following inadequacies were identified:

The procedure did not have detailed provisions for administra-tive controls and personnel. In addition the inspector noted that (except for the test coordinator and the day shift test director) test personnel and back-shift test engineers did not clearly understand the scope of the test, objectives, test conditions and instrumentatio *

The indicators and sensors were not identified in the procedure by their identification numbers (i.e., Reactor water level).

The procedure did not have procedural steps or instructions relating to NRC IE information Notice 85-71: " As Found" and "As left" data and provision for a correction of CILRT results from the "As Found" and "As Left" Local Leak Rate Test result *

Acceptance criteria for stabilization period was not consistent with that of ANSI /ANS 56.8-1981, which was referenced in the test procedur * Bypass flow for the instrument verification test was not included in the procedur This led to some confusion during the test.

, These above items were not included in the procedure and could lead

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to improper conduct of test. The licensee recognized the above inadequacies and stated that the test procedure would be cancelled and an extensive revised procedure would be implemented three months prior to the next CILR This is an unresolved item, pending implementation of revised procedure and NRC:R1 review of the revised procedure (50-271/86-14-01).

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4.2 Test Instrumentation The inspector reviewed the calibration records of the instruments and sensors used for the CILRT . It was ascertained that the instruments werc 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 temper-ature elements and Dewcells from the drawings and observed the auto-matic data collection system and their readings. The calibration records reviewed included the following: -

Flow Meter, certificate of conformance, Emerson Electric Co. ,

May 23, 198 *

Mensor pressure indicator, VY 3742: calibration chart, May 29, 1986; certificate of compliance and calibration, May 29, 198 *

Mensor pressure indicator, VY 3743: calibration chart, May 29, 1986; certificate of compliance and calibration, May 29, 198 * Drywell - Torus Differential Pressure Calibration Data Sheet:

(1) PT ID M007, PR-1-156-3, June 8, 1986 (2) DPT-1-158-6, DPI-1-158-6. June 8, 1986

Drywell Absolute Pressure Transmitters, PT ID M005 and M006, June 19, 198 *

Torus Water Level Input Verifications - Torus Narrow Range Water Level Transmitter Loop Calibration, LT-16-19-38A, June 19, 198 * Computer RTD: Resistance in the Decade Box, June 7, 1986 for:

PI ID M012, M013, M014, M015, M016, M017, M018, M019, M020, M021, M022, M023, M024, M025, M026, M027, MJ28, M029, and M03 *

Dewpoint Servo Checks: June 7, 1986 for M031 and M032, March

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28, 1986 for M033 and M03 No unacceptable conditions were identifie .3 "AS FOUND" CILRT Results At 2338 hour0.0271 days <br />0.649 hours <br />0.00387 weeks <br />8.89609e-4 months <br />, June 20, 1986, the containment pressure was secured and the stabilization period was commenced. The containment pressure was 120.7 inch Hg. In accordance with the acceptance criterion for the stabilization period, the stabilization period was ended at 0338 hour0.00391 days <br />0.0939 hours <br />5.588624e-4 weeks <br />1.28609e-4 months <br />, June 21, 1986, and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT was commence . _ _ _ _ _ _ .__.. _ _ -. - _ _ _ _ . _ _ _ , ,_

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The inspector performed independent mass point calculations in order to verify the' licensee's computer algorithms. The inspector con-cluded that the differences between the computer points and the inspector's calculations were negligible and caused by minor trun-cation errors, and that the mass point calculations were correc The absolute mass points and the air leakage during the first four hours into the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test indicted that the mass data points were fluctuating but their fluctuation amplitudes were damping down to a stable value.A straight line correlation of the data point for first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> indicated that the containment leakage was approximately 0.8 %/ Day by weight. The acceptance criterion for the CILRT was weight %/ Day. Subsequently, the licensee acknowledged that the "AS FOUND" CILRT was a failure and the test was terminate The licensee subsequently identified the following leaks:

Torus to Drywell Vacuum Breaker shaft packing leaks:

Maintenance Request (MR) #86-1396 was issued on June 20, 1986, and the repair was mad *

TIP tubing leaks (SB 7A, 6A, 10, 11A, and 11B): packing leaks were repaire *

Instrument line of SB 32A isolation valve was leaking and was repaired per MR #86-139 *

Drywell Manway was the major source of the leak during the Type

"A" test. MR #86-1397 was issued and the Manway bolts were re-torqued. To insure that the manway was properly tested under LLRT Type "B" testing requirements, Tests conducted on June 19, 1984 and September 25, 1985 were reviewed.

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Torus to Drywell plug was leaking and it was tightene In accordance with the requirements specified in Appendix J, 10 CFR

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50, and 10 CFR 50.73 reporting requirements, the licensee stated that an LER would be issued and a new test schedule for the type "A" CILRT would be submitted to NRC for approva No unacceptable conditions were identifie .4 Chronology of CILRT Sequence

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June 20, 1986 0615 Pre-closeout inspection performe Containment pressurization commenced.

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1935 Performed an inspection at 15 psi . , - . , - - - ., , ., - , - - . - . , , . - - - . . , - . _ , - - - - - - - - - - - - - - - , - . , -

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2030 All 4 RRU runnin Containment Pressure: 40.3 psig DW Average: 87.6 F Torus Average: 85.1 F 2338 Commenced Stabilization period Containment Pressure: 120.12" Hg i

DW Average: 85.9 F Torus Average: 82.3 F June 21, 1986 0338 Stabilization period completed and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test commence RRU #1 secured at 70 am RRU #2, #3, & #4 runnin Excess leaks' identified in Torus-to-DW vacuum breaker; TIPS; Instrument lin Test terminated and declared "AS FOUND" CILRT failure.

1500 Sump. pumps pumped out sumps: identified leaks were

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repaire Started repressurizatio Commenced new stabilization perio Completed stabilization period: met the acceptance criteria for the stabilization perio Drywell Floor Drain Sump Flow integrater: 0038085 CW Equipment Drain Sump Flow integrater: 1164278 (.eadings did not change for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) ,

Reactor Water Level (LI 2-3-57A): 131 inche June 22, 1986 2000 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT completed:

Inspector Estimation: (based on the data points and linear correlation)

"AS LEFT" CILRT = * 0.190 weight %/ Day with 95% UCL

, "AS LEFT CILRT = 0.165 weight %/ Day

. Acceptance = 0.60 weight %/ Day 2018 Verification test initiated with 3.0 SCFM

! June 23, 1986

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0325 Verification bypass flow was increased to 6.0 SCFM j 0825 Competed verification tes j Verification Test: Measured bypass flow =6.0 SCFM, 95% UCL Measured bypass flow =5.8 SCFM

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5.0 "AS LEFT" CILRT Results j The following preliminary results were estimated by the inspector:

Stabilization Period (figure 1)

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Delta T for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: F i Delta T for last hour: 0.07 F/ hour Delta T Change for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: 0.10 F/ hour CILRT (figures 2 and 3)

CILRT with 95% UCL  : 0.19 weight %/ Day Acceptance Criterion  : less than 0.6 weight %/ Day

The inspector therefore determined that the "As Left" test was acceptable l and that the Appendix J requirements were satisfied , prior to the plant

restar i l Verification Test (figure 4)

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Measured bypass flow was within less than 1% of the superimposed bypass flow. The acceptance criterion calls for 25% accurac .0 CILRT Personnel Training and Qualifications

The Qualifications Records of Test personnel were reviewed, and test personnel interviewed. Their qualifications met the requirements speci-

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fied in ANSI N 18.1-1971 " Selection and training of nuclear power plant personnel". They were knowledgeable of their responsibilities and tech-nical aspects of leak testin No unacceptable conditions were identified.

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7.0 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.

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Areas inspected included:

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j Drywell Manway hatch from refueling floor

j Mensor and bypass flowmeter i Control room j

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Penetrations:

X-101C, electrical, recirculation pump

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X-107, electrical, spare X-1050, 480V power X-117, RHR-33 X-29, RV-188 Core spray Header penetration i

X-43 X-45 CRD Room: X-1018, X-101A, X-104A, X-10 Steam Tunnel: X-11, FW Check Valves (27A, 96A).

! 8.0 Unresolved Item Unresolved items are matters about which more information is required to clarify whether they are acceptable, or items of noncompliance, or

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deviations. One unresolved item was identified and detailed in Paragraph .0 QA/QC Coverage During the CILRT the inspector verified QA/QC surveillance. The

, inspector also verified that QA had a program of specific inspection items to verify before and during the tes No unacceptable conditions were identifie .0 Exit Meeting Licensee mariagement was informed of the purpose and scope of the inspection at the entrance interview. The findings of the inspection were periodically discussed and were summarized at the exit meetin 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 inspector.

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