IR 05000254/1986006

Insp Repts 50-254/86-06 & 50-265/86-06 on 860319-26.No Violation or Deviation Noted.Major Areas Inspected:Ler Followup,Containment Integrated Leak Rate Test & Local Leak Rate Test

ML20203D769
Person / Time
Site:	Quad Cities
Issue date:	04/17/1986
From:	Dupont S, Rescheske P, Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20203D758	List: IR 05000254/1986006 ML20203D755
References
50-254-86-06, 50-254-86-6, 50-265-86-06, 50-265-86-6, NUDOCS 8604220329
Download: ML20203D769 (6)

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U.S. NUCLEAR REGULATORY COMISSION

REGION III

Reports No. 50-254/86006(ORS); 50-265/86006(DRS)

Docket Nos. 50-254; 50-265 Licenses No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station, Units 1 and 2 Inspection At: Cordova, IL Inspection Conducted: March 19 through 26, 1986 Insp DakE

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M/ e![fg P. R. Rescheske Date Approved By: f Y7 Test Programs Section Date

Inspection Summary Inspection on March 19 through 26, 1986 (Reports No. 50-254/86006(ORS);

50-265/86006(DRS))

Areas Inspected: Action on previous inspection findings (92702), licensee event report-followup (92701), containment integrated leak rate test (CILRT)

(70307, 70313, 70323), local leak rate test and as found condition of CILRT results (61720).

Results: No violations or deviations were identifie s hoj422ggCgo5000254 O

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DETAILS Persons Contacted N. Kalivianakis, Station Manager R. Bax, Production Superintendent

+T. Tamlin, Technical Services Superintendent

• G. Spedi, Technical Services Assistant Superintendent

+*T. Lilou, Technical Staff Supervisor

.The inspectors also interviewed other licensee employees including members of the technical and operating staf " Denotes persons attending the exit meeting on March 23, 1986.

+ Denotes persons in attendance at the exit conducted via telecommunications on March 26, 198 . Action on Previous Inspection Findings (Closed) Open Item (265/85018-01): The containment volume of 288,737 ft3 used in the Containment Integrated Leak Rate Test (CILRT) did not agree with the referenced Final Safety Analysis Report (SAR) volume of 275,481 ft3 The volume contained in the SAR has been changed to agree with the licensee calculated volume of 288,737 ft3 The inspector finds this acceptable and has no further concern (Closed) Open Item (265/85018-02): The licensee's procedure did not contain rejection criteria for the rejection of individual sensors during the course of the CILRT. The inspector reviewed the Procedure QTS-150-6,

"Short Duration Integrated Primary Containment Leak Rate Test," Revision 4 which was revised to contain rejection criteria for individual sensor (Closed) Open Item (265/85018-03): The licensee committed to verify all atmospheric monitoring lines for water prior to startu The inspector verified that the " Prior to Startup Items" checklist incorporated the commitment. The checklist verified that the drywell and torus containment (atmospheric monitoring) sensing lines were backblown and free of water prior to startu i (Closed) Violation (265/85018-05): Four safety-related Atmospheric Containment Atmosphere Dilution (ACAD) pressure transmitters were modified with external calibration jacks without appropriate design modification review records. The licensee had installed the external test jacks in April 1979. At the time of installation, the station's interpretation of the threshold of routine maintenance which constitutes a design change was not consistent with the current interpretatio Since most Rosemount supplied instruments of that model came with installed external test jacks, the licensee interpretated the installation as not a design chang However, under the current Commonwealth Edison Nuclear Work Request system, these installations would be considered as design changes. The licensee removed the installed test jacks and returned the instruments to their original configuration The inspector has no further concern . .

3. Licensee Event Report Followup (Closed) Licensee Event Report No. 85-06-00 Item (265/85006-LL): Two Main Steam Isolation Valves (MSIV) failed their local leak rate test MSIV A0-2-203-28 had failed with leakage of 16.2 SCFH while A0-2-203-2D had leakage of 191.2 SCFH. The inspector reviewed the repair activities which included lapping the main seat, replacing the main disc, pilot seat and pilot dis The inspector also reviewed the after maintenance local leak rate test and verified that the MSIVs passed with 4.6 SCFH (AO-2-203-28) and 9.2 SCFH (AO-2-203-20).

4. Containment Integrated Leak Rate Test (CILRT) - UNIT 1 Procedure Review The inspector reviewed Revision 4 (March 1985) to procedure QT-150-6,

"Short Duration Integrated Primary Containment Leak Rate Test" and checklists 51, S4 and SS. The inspector determined that these procedures appeared to be consistent with the requirements of 10 CFR 50, Appendix J, and the Bechtel Topical Report, BN-TOP-1,

" Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Plants," Revision Instrumentation The inspector reviewed the instrument calibration data associated with performing the CILRT. A multipoint calibration of all instrumentation was performed. The inspector verified the following instrumentation used during the CILRT was calibrated and traceable to national standard Type Quantity RTDs 30 Flowmeter 1 Pressure Gauges 3 Dewcells 10 The inspector also reviewed the temperature survey conducted by the licensee, QTP 010-T2 prior to pressurization and found the survey to be satisfactor Test Witnessing The licensee began pressurization on March 22, 1986, stabilized, and began the measured leakage phase of the CILRT at 9:31 p.m., the same day. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> test was satisfactorily completed at 9:33 a.m., on March 23, 1986. The licensee than began the supplemental test by inducing a controlled leak through a flow meter. This test was

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completed satisfactorily.

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( CILRT Data Evaluation

! The inspector independently monitored and evaluated the leak rate data to verify the licensee's calculation of the leak rat There was

. acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):

Measurement Licensee Inspector Leakage rate calculated .229 .229 (Lam) during CILRT Lam at 95% confidence level .298 .297 Lam at 95% confidence level .447 .446 adjusted to reflect penalties (Paragraph 4.g.)

Appendix J Acceptance Criterion at 95% confidence level = 0.75 La =

0.75(1.0) = 0.75. As indicated above, the adjusted Lam at the 95%

confidence level was less than the Appendix J Acceptance Criterion of 0.75 Supplemental Test Data Evaluation After satisfactory completion of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> BN-TOP-1 test on March 23, 1986, a known leakage of 1.0 weight percent / day was induce The inspector independently monitored and evaluated the leak rate data to verify the licensee's supplemental leak rate calculations. There was acceptable agreement between the inspector's and licensee's calculations as indicated in the following summary (units are in weight percent per day):

Measurement Licensee Inspector Calculated leakage (Lc) rate during supplemental test 1.274 1.288 Induced leakage rate (Lo) 1.000 wt %/ day Appendix J Acceptance Criterion:

.25 La<Lc-(Lam +Lo)<+.25 La ( .25<.045<+.25). As indicated, the supplemental test results satisfied the Appendix J requirement CILRT Valve Lineup Penalties Due to valve configurations, which deviated from the ideal penetration valve lineup requirements for the CILRT, the following penalty of

.149 weight percent per day was added using the minimum pathway leakage metho . - - - - - . . _ - . - . _- - --- - . -

... . . Summary Both the. Type A test and the Supplemental test met the acceptance l requirements of 10 CFR 50, Appendix J.

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! No violations or deviations were identifie . Local Leak Rate Program and Test Procedure Review The inspectors reviewed the local leak rate test results to determine the adequacy of past licensee corrective action related to excessively leaking

containment isolation valves. The total as-found leakage exceeded the

Technical Specification limit for Types B and C leakage. The inspectors ,

noted that the following isolation valves were repaired:

l l l VALVE Leakage (SCFM)  :

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l i Main Steam Isolation Valve (MSIV) 203-2A 146.3 i MSIV 203-28 18.43 MSIV 203-2C 48.4 i "B" Feedwater Check Valves 220-628 and ,

l 220-58B 2687.1 (total)  ?

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I Cleanup suction valves 1201-2 and 1201-5 >60 (total) Drywell/ Torus Purge Exhaust Valves 1601-23, 1601-24,1601-60,1601-61,1601-62 and 1601-63 207 (total) Drywell Floor Drain Sump 2001-3 and 2001-4 93.1 (total) Drywell Equipment Drain Sump 2001-15 and i 2001-16 >60 (total) i HPCI Steam Supply Valves 2301-4 and 2301-5 >51.9 (total) HPCI Steam Exhaust Valves 2301-45 >60 , Analyzer Suction 8801D and 88020 16.3 (total) j Drywell Head >60

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A previous unresolved item (265/85018-04) was identified for Unit 2 to address the maintenance history of individual isolation valves that had repeatedly failed local leak rate test. This will also be an unresolved ,

item (254/86006-01 (DRS)) until the inspector carf review the maintenance history for Unit 1 isolation valves to determine the adequacy of corrective action No violations or deviations were identified; however, one item requires further evaluation and is being treated as an unresolved ite . As Found Condition of CILRT Results The as found condition is the condition of the containment at the beginning of the outage prior to any repairs or adjustments to the containment boundar If adjustments are made to the containment bound.ry prior to the Type A test, local leak rate tests must be performed to dete*mine the leakage rates before and after the repair or adjustment. The as fo'.nd Type A test result can then be obtained by adding the difference between tne affected path leakages before and after the adjustments to the over all Type A test result . - - , . - . , . - - - . - - , -

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The inspector reviewed as found and as left local leak rate test results to determine an as found Type A test resul The following is a summary of the as found containment leak rate (units are in weight percent per day):

Measurement Penalties incurred due to repairs or adjustments prior to the CILR .43 As-Found Type A test results 2.88 As indicated, the as found condition exceeded the allowable limit of Appendix J (0.75 wt %/ day). The previous CILRT performed on Unit 1 also exceeded the as found Appendix J limit. As two consecutive as found conditions have failed to meet the 10 CFR 50, Appendix J, Section III.A.6.(b)

acceptance criteria, the next Type A test shall be performed at the next plant shutdown for refueling unless exempted by the NR No violations or deviations were identifie {

l 7. Unresolved Items 1

Unresolved items are matters about which more information is requiJed in order to ascertain whether they are acceptable items, items of violation, or deviations. An unresolved item disclosed during the inspection is discussed in Paragraph . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on March 23, 1986, and summarized t.he scope and findings of the inspectio The licensee acknowledged the inspector's statements. The inspector discussed the likely informational content of the inspection report with regard to documents reviewed by the inspecto The licensee did not identify any such documents as proprietar A teleconference was held on March 26, 1986, to further discuss the findings identified and to finalize the inspection.

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