IR 05000443/1987003

Insp Rept 50-443/87-03 on 870127-30 & 0209-13.No Violations Identified.Major Areas Inspected:Surveillance Testing Program of Instrumentation & Control Dept & Operations Dept & Licensee Actions on Previous Insp Findings

ML20207S864
Person / Time
Site:	Seabrook
Issue date:	03/10/1987
From:	Blumberg N, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20207S849	List: IR 05000443/1987003 ML20207S848
References
50-443-87-03, 50-443-87-3, NUDOCS 8703200343
Download: ML20207S864 (9)

Text

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(t U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-03 Docket N License N CPPR-135 Licensee: Public Service of New Hampshire P.O. Box 330, Manchester, New Hampshire 03105 Facility Name: Seabrook 1 Inspection At: Seabrook, New Hampshire Inspection Conducted: January 27-30, 1987 and February 9-13, 1987 Inspector: c h '" 0 7 JamesPrell,ReactorEnginep// date Approved by: Y t /-

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Norman Blumber ActingChief date Operational Pr grams Section, OB, DRS Inspection Summary: ROUTINE UNANNOUNCED INSPECTION ON JANUARY 27-30, 1987 AND FEBRUARY 9-13, 1987 (REPORT NUMBER 50-443/87-03)

Areas Inspected: Surveillance Testing Program of the I & C Department and Operations Department and licensee actions on previous inspection finding ,

' Results: No violations were identifie e703200343 G70310 l PDR ACOCK 05000413 0 PDR

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DETAILS 1.0 PERSONS CONTACTED NEW HAMPSHIRE YANKEE xxD. Abely, Maintenance Department Supervisor xxS. Barraclough, Lead Quality Control Engineer

• R. Begor, Surveillance Supervisor D. Bemis, Senior Reactor Operator B. Beuchel, Senior Engineer (YAEC)

• xxS. Buchwald, QA Supervisor

• R. Connelly, QC Inspector

• xxR. Cooney, Technical Projects Manager

• W. DiProfio, Assistant Station Manager R. Gwinn, Systems Engineer W. Hinton, I&C Foreman

• G. Kann, Technical Support Programs Manager xxJ. Malone, Operations Administrative Supervisor xxD. Moody, Station Manager

• xxT. Murphy, I&C Supervisor

• xxD. Perkins, Licensing Engineer

• xxT. Pucko, Senior Licensing Engineer R. Strickland, Shift Superintendent

• xxW. Temple, Licensing Coordinator C. Vincent, QC Supervisor

• xxL. Walsh, Operations Manager xxJ. Warnock, Nuclear Quality Manager U.S. NUCLEAR REGULATORY COMMISSION xxA. Cerne, Senior Resident Inspector .

• D. Ruscitto, Resident Inspector

• Denotes, those present at the exit meeting on January 30, 1987.

xxDenotes, those present at the exit meeting on February 13, 1987.

The inspector also interviewed other personnel during this inspection perio .0 LICENSEE ACTIONS ON PREVIOUS INSPECTION FINDINGS (0 pen) Unresolved Item (50-443/86-27-06)

Tolerances established by the licensee's I&C department calibration procedures appear to conflict with the finite limits provided by the Technical Specifications (TS), Limiting Conditions for Operations (LCOs)

and surveillance test requirement . ,

T.S. paragraph 2.2.1 (Basis) and T.S. paragraph 3.3.2.a support the l licensee's position. T.S. paragraph 2.2.1 states in part: "The setpoint for a Reactor Trip System or interlock function is considered to be adjusted consistent with the nominal value when the "as-measured" setpoint is within the band allowed for calibration accuracy. .. 0perations with setpoints less conservative than the Trip Setpoint but within the Allow-able Valve is acceptable, since an allowance has been made in the safety analysis to accommodate this error." T.S. paragraph 3.3.2. a states in part... "with an ESFAS Instrumentation or Interlock Trip Setpoint trip less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-4, adjust the Setpoint consistent with the Trip Setpoint valve."

These statements appear to support the licensee's contention that setpoints can be set within a calibration band which may turn out to be on the non-conservative side of the allowed setpoint valu The same concern (as stated in this Unresolved Item) was also questioned in the Seabrook SER Item (1), Paragraph 7.3.2.13, Setpoint Methodolog A review of the licensee's correspondence related to this item indicated that the methodology used by Seabrook for establishing set points for protective instrumentation may be similar to that used at Calloway, Wolf Creek, Millstone Unit 3 and Byron. However, this item remains open pending additional NRC review of the licensee's set point methodology for human factors considerations as well as margin of safet .0 SURVEILLANCE TESTING PROGRAM The Instrumentation and Control (I&C) Department and the Operations (OPS)

Department program for surveillance testing and calibratio, were reviewed for conformance with regulatory requirement .1 REFERENCES The following references were used:

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Seabrook Station Technical Specification (TS), Sections 2, 3, and 4

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10 CFR 50.36, Technical Specifications

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ANSI 18.7-1976, Administrative Controls and Quality Assurance of the Operational Phase of Nuclear Power Plants

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Regulatory Guide 1.33, 1978, Rev. 2, Quality Assurance Program Requirements

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3.2 PROGRAM REVIEW A review of administrative procedures, surveillance and calibration procedures, and the master surveillance schedule was made to verify the following:

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that the requirements and commitments identified in section above were met;

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that a master surveillance schedule and administrative control system has been established which identified the frequency of each test, calibration, or inspection, the responsible group for performing each surveillance, and the status of each surveillance test;

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that responsibility has been assigned for maintaining the master surveillance schedule up to date;

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that procedures, written to an approved format, exist for conducting each surveillance or calibration;

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that responsibilities have been assigned for reviewing and evaluating the results of surveillance or calibration data;

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that calibration requirements have been established and maintained for equipment associated with safety related systems but which are not specified in Technical Specifications as requiring calibration;

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that a program had been established for scheduling and monitoring daily or less surveillance tests;

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that responsibility has been assigned for ensuring that required schedules for all tests and inspections are satisfied; and

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that the technical content of surveillance testing procedures comply with TS requirement The following procedures, drawings and administrative control documents were reviewed:

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Westinghouse Specification Modeling Report, November 11, 1986

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IX1662.410, Rev. 1, T-411A Loop 1 Delta T/Tave Protection Channel Calibration

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IX1622.241, Rev. 1, W-930 Refueling Water Storage Tank Level Operational Test

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IX1622.224, Rev. 1 W-2380 Refueling Water Storage Tank Level Instrument

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OX1436.02, Rev.1, Turbine Driven Emergency Feedwater Pump Monthly, Quarterly and 18 Month Surveillance Testing

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OX1436.03, Rev. 2, Electric Driven Emergency Feedwater Pump Monthly, Quarterly, 30 Day Cold Shutdown and 18 Month Initiation Surveillance Test

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OX1436.08, Rev. 2, SUFP Monthly and Quarterly Operability Surveillance

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OX1456.48, Rev.1, ESFA SI Slave Relay Go Test (K610) Train B

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OX1405.07, Rev. 2, Safety Injection Quarterly and 18 Month Pump Flow and Valve Test

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PIO 1-RC-820843, Rev. 3, Reactor Coolant System Loop No. 3

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PID 1-FW-820687, Rev. 2, Feedwater System Details

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PID 1-CO-820426, Rev. 4, Condensate Systen Detail

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PID 1-SI-820446, Rev. 3, Safety Injection System Intermediate Head Injection System Detail

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PID 1-51-B20445, Rev. 2, Safety Injection System Overview

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PID 1-SI-820447, Rev. 4 Safety Injection System High Head Injection Systems Detail i

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151640.392, Rev.1, P-4258 Emergency Feedwater Pump 378 ,

Discharge Pressure Calibration '

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151640.394, Rev. O, P-4257 Emergency Feedwater Pump Suction Pressure Calibration

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TC2.2, Rev. 3 Technical Specifications Surveillances Scheduling and Performance

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MA3.1, Rev. 7 Work Request

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MA3.2, Rev. 2, Repetitive Task Sheets

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MODE CHANGE CHECKLISTS, MODE 7 to 6 AND MODE 6 TO 5

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BFA177, NHY-TECH. SPEC. MODELING REPORT FOR ALL SURVEILLANCES I

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The inspector verified that the licensee has an established surveillance testing program that meet the criteria identified in paragraph In addition, the following trip setpoints were recalculated to determine:

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the proper conversions and voltages / trip setpoints related to the Refueling Water Storage Tank level indicators W-930 and W-2380 .

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the correct voltage outputs for trip setpoints related to the Emergency Feedwater Pump pressure indicators FW-PI-4257 and FW-PI-4258 and flow transmitter FT-4279

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the required TS time constants used in the OT A T lead / lag circuits The calculations used by I&C for the above systems were reviewed. A tour of the Primary Auxiliary Building, Tunnel, and Tank Farm was made to verify the location and type of the following instruments as indicated on the appropriate P& ids:

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Chemical and Volume Control Tank level transmitters WT185, WT112

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Charging Pump 28 flow element FE 121

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Seal water return filter pressure indicators PI 175 and PI 176

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Refueling Water Storage Tank temperature element TE 2391 and level transmitter LT 2381 Surveillance tests 0X1456.48 and OX1405.07 (see title above) were witnessed. It was independently verified that the licensee correctly resolved problems occurring during the test and that the following ,

measurements were taken and met requirements for the train B SI '

system: suction pressure, discharge pressure, differential pressure calculation, flowrate, RWST temperature and level, and vibration reading of the SI pump. Independent opening and closing timing measurements of the following valves closely correlated with licensee measurements; SI-VIII, SI-VI34, SI-V70, SI-V131, SI-V158, SI-V89 and

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CBS-V53. The inspector also verified both physically and against the 1 appropriate PID's that the above valves were the proper valves for the Train B SI syste The following I&C and Operations department completed surveillance tests were reviewed to verify conformance with administrative and regulatory requirements:

-- IX1668.323, PCC7 Safety Injection Accumulator Tank Pressure Instruments Operational Test - February 4, 1987

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IX1668.223, PCC7 Safety Injection Accumulatory Tank Level Instruments Operational Test - February 2,1987

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IX1660.663, R-6535-B Fuel Manipulator Crane train B Radiation Monitor Operational Test - January 28, 1987

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IX1656.913, N-32 Source Range Channel IV32 Operational Test -

January 30, 1987

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IX1662.323, P-457 Pressurizer Pressure Protection Channel III Operational Test - January 30, 1987

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IX1640.217, Channel IV Steam Generator Level Operational Test -

December 23, 1986

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OX1456.80, Minimum ECCS Subsystem Mode 4 Monthly Surveillance -

February 8, 1987

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OX1446.05, Bus E-6 LOP and Degraded Voltage Surveillance -

February 11, 1987

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OX1460.01, Air Lock Door Seal 72 Hour Air Flow Rate Test -

February 5, 1987

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OX1400.01, Remote Safe Shutdown System Monthly Channel Check -

February 1, 1987 i

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OX1413.01, RHR Pump 8A Quarterly Flow and Valve Stroke Test -

February 3, 1987 3.4 FINDINGS l

No violations or deviations were identifie .0 QA/QC INTERFACE The QC department monitors approximately 10% of the surveillance

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tests conducted. QC is divided into 3 groups - mechanical, electrical and

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I&C, and Technical. QC provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage during Startup Testin The QC department staff consists of 14 inspectors plus 5 constructor

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personnel. QC hold points have been established for startup testin For surveillance testing, QC reviews the Plan of the Day to determine which tests to monito No violations were identified.

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5.0 PLANT TOURS During the course of the inspection several tours of the facility were made to observe instrumentation, monitor surveillance test activities and independently verify test readings. Areas toured were the control room, I&C shop, primary auxiliary building, tunnel, vault #1 and tank farm. A review of the work in progress, security, cleanliness and housekeeping was made and found to be in good orde .0 INDEPENDENT CALCULATIONS / MEASUREMENTS The inspector independently recalculated the following:

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the proper conversions and voltages / trip setpoints related to the Refueling Water Storage Tank level indicators W-930 and W-2380

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the correct voltage outputs for trip setpoints related to the Emergency Feedwater Pump pressure indicators FW-PI-4257 and FW-PI-4258 and flow transmitter FT-4279

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the required TS time constants used in the OT a T lead / lag circuits The inspector'also reviewed and analyzed the setpoint methodology used by the license '

The following measurements were independently verified: SI pump suction and discharge pressure, SI flowrate, RWST temperature and level and SI pump vibration readings. The opening and closing times for the following valves was independently measured: SI-VIII, SI-VI134, SI-V70, SI-V131, SI-V158, SI-V89, and CBS-V5 No problems were identifie .0 EXIT INTERVIEWS Exit meetings were held on January 30, 1987 and February 13, 1987, to discuss the inspection scope and findings, as detailed in this report (see paragraph 1.0 for attendees).

At no time was written material given to the licensee. The inspector determined that no proprietary information was utilized during this inspection.