IR 05000289/1977028
| ML19256D193 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1977 |
| From: | Bannack W, Dante Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D187 | List: |
| References | |
| 50-289-77-28, NUDOCS 7910170691 | |
| Download: ML19256D193 (8) | |
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U'S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77-28
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Docket No.
50-289 i
j License No.
DPR-50 Priority Category C
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Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylrania 19603 Facility Name:
Three Mile Island Inspection at:
Middletown, Pennsylvania
Inspection conducted:
September 13-16, 1977 b bu7rdf777 Inspectors: [/. (I.,
w W.H.Bdunack,ReactoryInspector
'date signed '
date signed
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,date signed Approved by: //8 /7
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ntam W
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D. F. Jahrtson, Acting ChWf, Nuclear
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Aate si~ned g
j Support Section No. 2, RO&NS Branch i
Inspection Sumary:
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Inspection on September 13-16, 1977 (Recort No. 50-289/77-28)
Areas Inspected:
Routine, unannounced inspection of administrative control of safety related calibrations; calibration of components required by i
Technical Specifications; qualification of technicians; calibration and control of test equipment; witnessing of calibrations; calibrations of
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l components associated with safety related systems; facility tour. The inspection involved 33 inspector hours onsite by one NRC inspector.
Results: No items of noncompliance were identified during this inspection.
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1 0 59101
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Region I Fonn 12 1447 003
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(Rev. April 77)
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O DETAILS i
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Persons Contacted
- Mr. C. Hartman, Lead Electrical Engineer
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Mr. C. Lawrence, I&C Foreman Mr. R. Menser, Instrument Man First Class
- Mr. J. O'Hanlon, Station Superintendent
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Mr. W. Sawyer, Maintenance Engineer Mr. J. Sipe, Instrument Technician, Nuclear
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Mr. G. Stanbau5h, Maintenance Foreman Mr. R. Toole, I&C Foremen The inspector also interviewed other licensee employees, including members of the technical staff, I&C personnel and reactor operators.
- denotes those present at the exit interview.
2..
Administrative Control of Safety Related. Calibrations Q
The inspector reviewed the licensee's administrative procedures relating to the performance of ca11 orations of. safety related components as a basis for reviewing test procedures and calibration data sheets. The following procedures were reviewed.
Administrative Procedure 1001, Document Control, Revision 10,
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June 23,1977.
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Administrative Procedure 1010, Technical Specification Surveillance
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Program, Revision 19, November 10, 1976.
Admini.strative Procedure 1022, Control of Measuring and Test
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Equipment, Revision 4, July 27, 1977.
No discrepancies were identified.
3.
Calibrition of Components Required by Technical Soecifications a.
The inspector reviewed calibration procedures and associated
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data sheets on a sampling basis to verify the following:
(1) Calibration Frequency requirements have been met.
j (2) Applicable system status during compo: net calibration was
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in conformance with the Technical Specification limiting ({';
conditions of operation.
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(3)
Procedure format provided detailed stepwise instructions.
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Procedure review and approval were as required by Technical
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Specifications.
(5) Trip points of calibrated components were in confor-mance with Technical Specification Requirements.
(6) Technical content of procedures was sufficient to result in satisfactory component calibration.
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b.
The following calibration procedures were selected for the above review.
(1)
Surveillance Procedure 1302-1.1, Power Range Calibration, Revision 8, August 15, 1977.
Perfonned August 17, 1977 through August 31, 1977.
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(2) Surveillance Procedure 1302-5.12, Pressurizer Temperature
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Channel, Revision 3, July 13, 1976.
Performed November 1976.
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Q (3) Surveillance Procedure 1302-5.2 and 5.3, Reactor Coolant High and Low Pressure Channels, This surveillance performed on April 28,.1977 in accordance with a work request which replaced existing pressure transmitters.
The surveillance was done in accordance with a procedures change (TCN 77-89) which modified the existing surveillance procedure 1302-5.2 and 5,3 to accomodate calibration
of the new transnitters.
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(41 Surveillance Procedure 1302-5.18, High and Low Pressure Injection Flow Channel, Revision 0, November 16, 1977.
f Data sheet 2 of 8 of the surveillance performed on March
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29, 1977 indicates the low flow alarm had not been
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calibrated, and also the acceptance valve for the setpoint mil 11 voltage for this alann was incorrect in the procedure.
These items appeared not to have been detected during the licensee's review of the completed procedure.
This item (289/77-28-01) is unresolved pending the resolution of the low flow alarm calibration and the necessary correction made to the procedure,
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(5) Surveillance Procedure 1302-5.25, Reactor Building Sump Level, Revision 4, January 13, 1977, performed September 30, 1976.
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(6) Surveillance Procedure 1302-5.31, 4160 Volt D and E Bus
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l Undervoltage Relay System, Revision 3, January 28, 1976 performed August 17, 1976.
No items of noncompliance were identified.
4.
Qualifications of Technicians The inspector reviewed the qualifications of four instrumentation department personnel involved in the performance of the calibrations identified in Paragraph 3.b.
Records of experience and training maintained by the licensee verify all four individuals exceeded the
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requirements of ANSI.N18.1-1971,, Selection and Training of Nuclear Power Plant Personnel.
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The inspector had not further questions in this area.
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caiibration and contro1 of Test eauioment.
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The inspector reviewed the calibration and control of five pieces
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of test equipment used as standards in the calibration of components identified in Paragarph 3.b.
Results of the review indicate measuring and test equipment is
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j being maintained as required by Administrative Procedure.
Items verified included.
(a) Establishment and adherence to a calibration schedule.
(b) Calibration accuracy is traceable to the National Bureau of Standards or other testing organizations.
(c) Test equipment history.
(d) Storage and Labeling of test equipment.
The inspector had no further questions in this area.
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Inspector Witnessing of Calibration i
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The inspector witnessed the performance of Surveillance Procedure 1303-4.1, Reactor Protection System Monthly Surveillance (Channel C),
Revision 0, December 15, 1973.
The surveillance was performed and data recorded as required by the
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orocedre. One procedure change was initiated to clarify one step
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in the procedure. The procedure was adequately-detailed to insure performance of a satisfactory surveillance.
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The inspector had no further questions in this area.
7.
Calibration of Comoonents Associated with Safety Related Systems The inspector reviewed on a sampling basis the program for calibration
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of components associated with safety related systems but not specifically identified in the Technical Specifications as requiring calibration. These components are used to monitor system parameters to comply with the safety limits, limitir.g conditions of operation, and/or meet the surveillance requirements of the Technical Specifications.
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A revi,ew of calibration records for the below listed instruments revealed the following results.
(a)
Feedwater Flow (TE-266 A)-Stated to be scheduled for calibra-
- tion each refueling outage in accordance with " Heat Balance" calibrations. Last calibrated May 1976, No previous data available.
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(b)
Condensate Storage Tank Level (C0-LT-44)-Calibrations scheduled for three year intervals in accordance with a preventive maintenance program.
Last calibrated April 23, 1976.
No previous data available.
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Emergency Feedwater Pump Discharge Pressure (EF-PT-65)-Cal-j ibrations scheduled for three year intervals in accordance j
with a preventive maintenance program.
Last calibrated April
23, 1976. No previous data available.
(e)
Control Room Emergency Filter Delta Pressure-No records avail-able for this instrument.
(f)
Decay Heat Pump Flow (DH-1-DPT-2)-Calibrations scheduled for three year intervals in accordance with a preventive maintenance program.
Last calibrated January 7, 1977.
No previous data available.
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Feedwater Temperature (TE-266-A)-Stated to be scheduled for calibratian each refueling outage in accordance with " Heat
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Balance" calibrations. A one point calibration at 32 F last
performed May 1976.
No other data available.
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(h) Make-Up Discharge Header Pressure (MU-2-PT)-Calibrations
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i scheduled for three year intervals in accordance with a preventive maintenance program.
Last calibrated December 22,
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1973.
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Diesel Starting Air Press (PI-536A)-Calibrations scheduled for three intervals in accordance with a preventive maintenance program.
Gauge calibrated January 13, 1976. Alarm calibrated Janaury 2, 1977.
No other data available.
(j) Spent Fuel Cooling System Flow (SF-9-DPT-2)-Calibrations scheduled for three year intervals in accordance with a
preventive maintenance program.
Last calibrated December 14, 1973. Also said to have been performed last refueling but data not available.
O The inspector determined based on the ebove review, thet no formai program for the calibrai; ion of these components on a periodic basis has been developed, as evidenced by the fact that records show some instruments ha~ve not been calibrated since initial startup some
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have not been calibrated in accordance-with their preventive maintenance
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schedule, one has no calibration records, and in general, records do not indicate complete channel calibrations are being performed.
Th.e inspector noted the licensee's present program did not meet the requirements of ANSI 18.7-1972 and Appendix "A" USNRC Regulatory Guide 1.33, November 1972, in that no fomally established admin-istrative controls or policy has been developed to specify, what instruments / components must be calibrated, the frequency of cali-bration, the acceptance criteria, the review of completed data, and what procedure is to be used for the calibration.
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The licensee stated a program consistant with the requirements of
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ANSI 18.7 and USNRC Regulatory Guide 1.33 would be developed and imp'.emented. The target date for completion and ir..plementation would be the start of the next refueling outage.
However, no later than September 30, 1978.
This item (289/77-28-02) is unresolved pending completion of the
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licensee's action.
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Facility Tour The inspector toured various areas of the facility including the auxiliary building in the area of DH-V-6.
Conditions observed included radiation controls, pipe hangers. and restraints, the piping connecting DH-V-6 to a decay heat removal pump, and general
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housekeeping. An unplanned shutdown resulting from high feedwater conductivity was also observed in the control room.
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No unacceptable conditions were identified.
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9.
'anresolved Items Items about which more information is required to determine accept-ability are considered unresolved.
Paragraphs 3.b.(4) and 7 of this report contain unresolved items.
10.
Exit Interview The insp)ector met with licensee representatives (denoted in para-(]
graph 1 at the conclusion of the inspection on September 16, 1977.
The inspector summarized the purpose and the scope of the inspection
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and the findings.
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Wit Interview
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' ne inspector met with licensee representatives (denoted in Para-i graph 1) at the conclu.sion of the inspectior..
The inspector sumarized the purpose and scope of the inspection and the findings.
The licensee acknowledged the inspector's findings.
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