IR 05000282/1979008

IE Insp Repts 50-282/79-08 & 50-306/79-07 on 790212-16 & 0314-16.Noncompliance Noted:Delayed Conduct of Fire Sys Surveillance

ML20062H271
Person / Time
Site:	Prairie Island
Issue date:	04/19/1979
From:	Mcgregor L, James Smith, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19261D752	List: IR 05000282/1979008 ML20062H266
References
50-282-79-08, 50-282-79-8, 50-306-79-07, 50-306-79-7, NUDOCS 7906260330
Download: ML20062H271 (9)

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U.S. NUCLEAR RESULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-282/79-08; 50-306/79-07 Docket No. 50-282; 50-306 License No. DPR-42; DPR-60 Licensec: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Prairic Island Nuclear Generating Plant, Units 1 and 2 Inspection At: Prairie Island Site, Red Wing,.'0; Inspection Conducted: February 12-16 and March 14-16, 1979

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Inspectors: L. G. McGregor (Febr ary 12-16, 1979) / /' . >

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J. D. Smith (March 14-16, 1979) ..: ..,,,_7k[

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4 t 's - s, J. F. Streeter (February 14-t5, 1979)

B. M K. Wong (February 14-15, 1979) ]ilh_ .i .

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Approved By: Stracter' Chief 4f . j c7 . / er Nuclear Support Section 1 Inspection Summary Inspectica on February 12-16 and March 14-16, 1979 (Report No. 50-282/

79-08: 50-306/79-07)

Arecs Inspected: Routine, unannounced inspecti 7 of calibration and surveillence of safety related components an/ - zipment and implemen-tation of ASME Code Section 7.I and pump and Ja ls test program. The inspection involved 93 inspector- '* s onsitt b: var NRC inspect r Results: Of the three areas insps-+-- no Item., of .Noncempliance scre identified in two areas. One Item of Noncompliance (Deftciency -

delayed conduct of fire system surveillance, Paragraph 5.c) in one ste o

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DETAILS Persons Contacted

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+*F. Tierney, Plant Manager

+E. Watzl, Superintendent, Plant Engineer, Radiation Protectio A. Hunsted.. Staff Engineer

• Hoffman, Plant Engineer, Technical

! G. Sundberg. Instrument Engineer

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• R. Olschlager, Instrument and Control Coordinator l +B. Stephens, Mechanical Engineer D. Walker, Shift S'ipervisor R. Hoffey, Shift supervisor R. Ryan, Shift Supervisor The inspectors also talked with and interviewed several members of the operations, techanical and engineering staffs.

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• Denotes those present at the exit interview on February 16, 197 + Denotes those present at the exit interview on March 16, 197 . Calibration of Safety Related Components Required by Technical Specifications (Units 1 and 2)

The inspector reviewed plant calibration records, selected logs and records for the below listed calibration activities. This review was performed to determine that the frequency of calibration was ,

met; the service status of the system was in conformance with the applicable limiting conditions of operations; the procedures used to calibrate the components were reviewed and approved as required by the Technical Specifications; the procedutcs used contained acceptchle trip settings using applicable technical specification requirements; the procedures used contained detailed stepwis instructions; the technical centent of the procedures would result-in satisfactory calibration; the qualifications of two individuals in the I&C group having respensibilities for performing calibrations were adequate, " Reactor High Flux Intermediate Range Calibration,"

Test 2007 and 1007A " Reactor High Flux Power Range Calibration,"

Test 2009 and 1009 " Pressurizer Level Control Calibration,"

Test 2001, 2048, 2182, 1048, 1001 and 118 ,

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. " Emergency Core Cooling Temperature Element Calibration Safety Injection System,"

Test 108 and 2088 " Residual Heat Removal Pump Flow Calibration,"

Test 2020 " Accumulator Boron Concentrar. ion Tests "

Tests 1065 and 2065 " Containment System Emergency Charcoal Filter Pressure Drop Calibration,"

Tests 1114 and 2114 "Containnent Pressure Calibratiou Sensing Instrumentation "

Tests 1001, 2001 and 2045 " Containment Temperature Calibration,"

Tests 1038 and 2036 " Station Battery Lead Test,"

Test AJ98 and 2098 "4 KV Volt and Frequency Calibration,"

Tests 1014 and 1015 " Containment Sump Level Instrument Tests and Calibration,"

Tests 1030 and 2030 " Refueling k'ater Storage Tank Level Calibration,"

Test 2023 " Volume Control Tank Level Channels Calibration CVC System,

Test 2025 " Boric Acid Makeup Flow Channel Calibration,"

Test 2029 " Accumulator Level and Pressure Test ard Calibration,"

Test 2031 " Control Rod Drive Exhaust Air Temperat. e Calibration,"

Test 2043 No items of noncompliance or deviations were identifie _ _____-_ )

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3. Calibration of Safety Related Components Not Specified by Technical Specification (Units 1 and 2)

The inspector reviewed plant calibration records for the below listed components. This review was performed to determine if tne operating range / accuracy of components were consistent with applicable Technical Specifications /SAR; the procedures used to calibrate the components were reviewed and approved as required by Technical Specifications; the procedures used contained acceptance criteria consistent with Technical Specificat;ons/SAR; the procedures used contained detailed instrutrions commensurate with the complexity of the calibration and that the technical content of the procedures would result in satis-factcry calibratio Systems (1) " Analog Reactor Control System "

Test 1548 and 2548 (2) " Diesel Tire Pump Weekly Test and Calibration,"

Test 1524 (3) " Tire Protection System Test and Calibration,"

Test 1568 (4) " Explosive Detector Calibration,"

Test 1621 (5) " Turbine Bearing Fire Protection Test and Calibration,"

Test 1592 and 2592 (6) " Electrical Penetration Surveillance Test and Calibration "

Test 2537 Instruments (1) " Mixed Eed A EFF Conductivity Cell,"

CEC-6 System ODE (2) " Reactor Coolant Draia Tank !;3 Supply Pressure,"

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IPC 1014 System CWL (3) "WST fank Rad lfonitor,"

Inst. 59062 Syster DRD

(4) " Station Air Compressor Receiver Pressure Switch and Valve,"

Inst. 16086 and 31191 System OSA (5) "Decon Area Sump Level Switch,"

Inst. 16677 System OVL (6) " Turbine High Pressure Cylinder Flange Temperature "

Inst. 42083-04 System ITB (7) " Hydrogen Recombiner Product Gas Oxygen Analyzer,"

10 AR-1119 System ONG 20 AR-1119 System OWC Recorder and Alarm No items of noncompliance or deviations were identified.

4 Surveillance Test Witnessing The following surveillance testing was witnessed to verify that all test prerequisites were met and the stepwise procedures were completed as required:

, Test SP 1186 Emergency Diesel Generator Start and Operation, Unit 1 (Rev. June 16, 1978). Test SP 1106A Diesel Driven Cooling Water Pump. Unit 1 (Rev. June 16, 1978). Test SI 1088 Operational Test of Safety Injs: tion Pumps, Unit 2 (Rev. June 16, 1978).

No items of noncompliance or deviations were identified.

5. Surveillance of Safety Related Components or Equipment (Units 1 and 2) Purpose of Review The inspector reviewed plant surveillance records to determine if test procedures are approved in accordance with the Tech-nical Specifications; test procedures include appropriate (1)

prerequisites and preparations, (2) acceptance criteria, and (3) instructions to ensure tested item is restored to operation following the test; technical content of procedures assures compliance with the Technical Specifications and Inservice Inspection Program; tests were performed within the time

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Coatrary to the above, the initial tests (SP 1189) of the alarm circuits were not conducted until (Decemoer 28, 1978) approximately 10 1/2 months after the technical specifications became effectiv This is an Item of Non-complianre (50-282/79-L-01; 50-306/79-0-01) of the Deficiency leve (2) The monthly emergency diesel generator fuel oil sample analysis for viscosity, water, and sediment was not performed during the period November 21, 1978 through January 12, 1979, as required by Technical Specification 4. 6. A. l . c . However, the inspector verified that this was an isolated exampl (3) A few examples were noted where the tester was identified in the test documentation but the tester's signature was not documented, where there were delays in forwarding test results from the group supervisor to the Surveil-lance Coordinator, where temporary test equipment used to obtain performance data was not specifically identi-fied, and where test documentation did not indicate abnormal conditions were promptly brought to the attention of the appropriate supervisor. The licensee instructed personnel involved in the conduct and review of tests of the importance of the proper conduct, review, and docu-mentation of test No other items of importance were note . Plant Tour (Units 1 and 2)

The inspector conducted a tour of various areas of the plant to observe operations and activities in progress, general housekeeping and cleanliness, and equipment caution or lockout tags. ' Exceptional cleanliness was observed throughout areas toure No items of noncompliance or deviations.were identifie . Exit Interviews The inspector =et with licensee representatives (denoted in Paragraph 1) on February 16, 1979, and at the conclusion of the inspection on l

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March 16, 1979. The inspectors summarized the purpose, scope', and findings'of the inspectio . . _ .

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frequeacies specified in the Technical 3pecifacetions and Inservice Inspection Program; tests were performed by qualified individuals; test results were reviewed as required by facility administrative requirements; test results were in conformance with Technical Specifications and Inservice Inspection Program; app: opriate action was taken for test results not meeting t l 4 acceptance criteria, b. Administrative Documents, Personnel Oualifications and Test Records Reviewed .

(1) Test Records .

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Test Procedure Date of Tests SP 1072-45, " Local Leakage Rate Test 3/25/77, 3/19/76 of Penetration 45" 4/29/75 and 4/26/75 r SP 1089, " Residual Heat Removal 2/13/79, 1/30/79, Pumps and Suction Valves from the 1/31/79 :

Refueling Water Storage Tank," .

Rev. 10 SP 1090, " Containment Spray Pump 2/22/79, 1/25/79 Test" Rev. 14, dtd 11/26/78 12/21/78 SP 1099, " Main Steam Isolation 4/12/78, 3/28/78, i Valves Closure Test," Rev. 2, 12/9/77 '

7/5/77 SP 1102, " Turbine-driven Auxiliary 1/31/79, 12/27/78, Feedwater Pump Test," Rev. 8, 11/28/78 8/2/78 SP 1106, "12 Diesel Cooling Water 2/23/79, 2/15/79, Pump Test," Rev. 4, 6/26/78 2/14/79 and 2/8/79 SP 1151, " Cooling Water System 1/23/79, 10/17/76, Test," Rev, 0, 4/16/77 7/18/77 SP 1155, " Component Cooling System 1/18/79, 12/13/7 Test," Rev. 5, 10/30/78 11/15/78

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SP 1156, " Low Level Gas Decay Tanks 12/5/78, 9/8/78, l co Plant Vent Control Valve Test," 6/6/78 Rev. 2, 6/5/78 i

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SP 1157 & 2157, " Post LOCA Hydrogen 4/10/78, 12/9/78 Control System Valve Operation,"

Rev. 2, 6/5/78 SP 1160, " Chilled Water Crossover 12/19/78, 9/19/76, Control Valve Test," Rev. 1, 6/22/78, 3/21/78, 6/5/78 12/20,77, 9/20/77, 6/21/77 SP 1161, " Control Room Chilled 2/20/79, 1/23/79, Water Puep Test," Rev. 3, 6/20/78 12/19/78, 11/21/78, 10/17/78, 9/19/78, 8/22/78, 7/18/78, 6/22/78, 5/23/78, 4/18/78, 3/21/78, 2/21/78, 1/17/78 SP 1160, " Diesel Cooling Water 1/26/79, 12/22/78, System Test," Rev. 3, 12/1/78 11/24/78 SP 1159, " Reactor Vessel Injection 2/27/79, 11/27/78, Isolation Valve Test," Rev. 1, 8/29/78 6/5/78 SP 1002, " Analog Protection 2/16/78 Functional Test," Rev. 5, 8/29/78 SP 1178, "CVCS Check Valve Test" 4/2/78, 12/9/78 SP 1187, " Diesel-driven Fire 1/78 thru 1/79 Pump Battery Inspection,"

Rev. 3, 8/2/78 SP 1096 & 1097, " Station Battery 1/78 thru 1/79 Monthly Test and Station Battery Ouarterly Inspection," Rev. 4, 10/30/78 SP 1053, " Fire Protection System 9/15/78, 10/13/78 Monthly Fire Pump Running Test," 11/17/78, 12/15/78, Rev. 6, 10/13/78 1/19/79 SP 1189, " Safety Related Fire 12/28/78 Detector Check," Rev. O, 9/28/78-7-6 . .

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SP 1190, " Emergency Diesel Generator 8/78 thru 1/79 Oil Storage Tanks Sampling Procedure,"

Rev. O, 11/15/78 SP 2130, " Containment Vacuum Breakers 12/29/77,' 3/28/78, Quarterly Test," Rev. 3, 8/2/77 6/27/78, 9/26/78, 12/28/79

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SP 2171, " Tech Spec Shock Suppressor 11/14/77, 12/20/78 ,

Check," Rev. O, 10/17/77 SP 1046, " Full Length Control Rod 12/14/78 Drop Timing," Rev. 4, 6/20/78 (2) Personnel Oualification Records The qualification records for two individuals involved in

~the tests identified above were reviewed to determine if the individuals were qualified in accordance with the Technical Specifications and ANSI N1 (3) Administrative Documents The following facility administrative documents were used during the review:

(a) Operations Manual Appendix G. Section 6, " Surveil-lance," dated January 31, 197 (b) " Northern States Power Company, Prairie Island Nuclear Generating Plant, ASME Code Section XI Inservice Inspection and Testing Program and Information Required for NRC Review of Requests for Relief from ASME Code Section y1 Requirements,"

Rev. 1, dated September 15, 197 c. Findings (1) Technical Specifications 4.16.A.1 and 4.16.A.2 became effective February 14, 1978, and require, respectively, that fire detectort ;xterior to primary containment be functionally tested once every six months and that the detector alarm circuits also be tested every six month ,

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