IR 05000247/1978034
| ML19322A055 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/03/1978 |
| From: | Baunack W, Kister H, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19322A053 | List: |
| References | |
| 50-247-78-34, NUDOCS 7901020092 | |
| Download: ML19322A055 (10) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l
Region I RIport No.
50-247/78-34 Docket No.
50-247 License No.
DPR-26 Priority Category C
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Licensee:
Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Facility Name:
Indian Point Nuclear Generating Unit 2 Inspection at:
Buchanan, New York Inspection conducted: October 17-20, 1978 b^
Dfvf7I Inspectors:
W. H. Batinack, Reactor Inspector date signed b
h[M bes Ufvf7[
R. P. Ztmherman, Reactor Inspector date signed date signed Approved by:
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'H. B. Kister,Mhief, Nuclear Support da'te signed
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Section No.1, RO&NS Branch Inspection Summary:
Inspection on October 17-20, 1978 (Report No. 50-247/78-34)
Areas Inspected: Routine, unannounced inspection by regional based inspectors of licensee action on previous inspection findings: administrative control of safety related calibrations; surveillance calibration of safety related components and equipment required by Technical Specifications; calibration required by Technical Specifications of components and equipment associated with safety related systems and/or functions; inspector witnessing of calibrations; cali-bration and control of test equipment; administrative controls for surveillance procedures; surveillance testing; inspector witnessing of surveillance tests; technician qualification; and facility tours.
The inspection involved 52 inspector-hours onsite by two NRC regional based inspectors.
Results: No items of noncompliance were identified during this inspection.
Region I Form 12 730102009}
(Rev. April 77)
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DETAILS 1.
Persons Contacted
- A. Brescia, I&C Supervisor
- W. Carson, Test Engineer
- E. Dadson, Central QA Manager
- A. Decker, Technical Engineer J. Halpin, Maintenance Engineer
- L. Kawula, Test and Performance Engineer
- T. Law, Plant Manager C. Limoges, Reactor Engineer
- W. Monti, Manager - Nuclear Power Generation
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- A. Nespoli, Operations Engineer
- M. Shatkouski, Chief Operating Engineer The inspectors also interviewed other licensee employees, including members of the maintenance, instrument and control, and engineering staff, reactor operators, and general office personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Item of noncompliance (247/77-34-01): Failure to properly review and approve procedures associated with calibration of safety related components.
The inspector verified, through the course of the inspection, that the licensee has reviewed ano approved the procedures as required by Technical Specification 6.8.2.
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Administrative Control of Safety Related Calibrations The inspector performed an audit of the licensee's administrative controls in this area by conducting a sampling review of the below
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listed administrative procedures with respect to the requirements of the Technical Specifications, Section 6, " Administrative Controls,"
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ANSI N18.7, " Administrative Controls for Nuclear Power Plants" and
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Regulatory Guide 1.33, " Quality Assurance Program Requirements."
Station Administrative Order - 117, Calibration and Control of
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Measuring and Test Equipment, Revision 4, August 1,1978.
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I Administrative Directive - IC-AD-7, Periodic Instrument Cali-
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bration, Revision 3, July 12,1978.
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Administrative Directive - TAD-5, Surveillance Test Procedure
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Issuance and Review Process, Revision 3, November 23, 1977.
No items of noncompliance were identified.
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4.
Surveillance Calibration of Safety Related Components and Equipment
Required by Techn cal Specifications
a.
'The inspector reviewed calibration procedures and associated data sheets on a sampling basis to verify the following:
Calibration frequency requirements have been met;
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Applicable system status during canponent calibration was f
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j in conformance with Technical Specification limiting conditions for operations; Procedure format provided detailed stepwise instructions;
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Procedure review and approval were as required by Technical
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Specifications; Trip points of calibrated components were in conformance
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with Technical Specification requirements; and,
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Technical content of procedures was sufficient to result.
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in satisfactory component calibration.
b.
The following calibration procedures / data were selected for the above review:
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l PC-R11, Refueling Water Storage Tank Level Transmitter
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Calibration, Revision 4, November 21, 1977.
Data reviewed i
for calibration performed on February 16, 1978.
PT-V1, Nuclear Source Range Analog Channel Test, Revision 10,
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August 17, 1977.
Data reviewed for tests performed on July 28,1978 and September 30, 1978, i
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PC-R3, Pressurizer Level Transmitter Calibration, Revision 2,
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October 21, 1976.
Data reviewed for calibration performed February 28, 1978.
PT-M4, Pressurizer Level Analog Channel Test, Revision 6,
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September 13, 1977.
Data reviewed for tests performed July 11, 1978; August 11, 1978; September ll,1978; and, October ll,1978.
PC-R7, Steam Generator Level Transmitter Calibration, Revision
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3, November 18, 1976.
Data reviewed for calibration per-formed March 1, 1978.
PT-M8, Steam Generator Level Analog Test, Revision 7,
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November 23, 1977.
Data reviewed for tests perfonned June 15,1978; July 15,1978; August 17,1978; and, September 16, 1978.
PC-R20, Independent Electrical Overspeed Protection System
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Calibration, Revision 7, August 23, 1977.
Data reviewed for calibration performed February 25, 1978.
PT-M13, Turbine Electrical Overspeed Analog Test, Revision 7,
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August 23, 1977.
Data reviewed for tests performed July 3, 1978; August 2,1978; September 1,1978; and, October 1,1978.
PT-M13(A), Turbine Electrical Overspeed Logic Test, Revision
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3, August 23, 1977.
Data reviewed for tests performed July 3, 1978; August 2,1978; September 1,1978; and, October 1,1978.
PC-R14, Containment Pressure Transmitter Calibration,
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Revision 2, December 7, 1976.
Data reviewed for calibration perfonned March 20, 1978.
PT-M9, Containment Pressure Analog Test, Revision 6,
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December 28, 1977.
Data reviewed for tests performed July 13,1978, August 14, 1978; September 15,1978; and, October 13, 1978.
No items of noncompliance were identifie.
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5.
Calibration Required by Technical Specifications of Components and Equipment Associated with Safety Related Systems and/or Functions a.
'The inspector reviewed on a sampling basis, the program established for calibration of components associated with safety related systems required by ANTI 18.7-1972 and Appendix "A",
USNRC Regulatory Guide 1.33, November 1972. These components are used to monitor system parameters to canply with the safety limits, limiting conditions of operation, and/or meet the surveillance requirements of the Technical Specifications.
Most of the sample selected had been pe'rformed with procedures written prior to undergoing Station Nuclear Safety Committee review and approval on October 14, 1977 following the item of noncompliance from the previous inspection.
(247/77-34-01)
Many procedures were revised prior to being reviewed and approved and are being implemented as the safety related components come due for calibration.
The following were verified:
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Specific requirements have been established for the below calibrations including schedules and frequencies; Procedures have been reviewed and approved in accordance
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with the Technical Specifications, contain acceptance criteria consistent with the Technical Specifications, and contain detailed instructions commensurate with the complexity of the calibration; and, Technical content of procedures are adequate to perform
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a satisfactory calibration.
b.
Calibration data f r the following components were reviewed.
Preventive Maintenance Package (PMP)-288, Containment
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Temperature, Revision 0, October 14, 1977.
Data reviewed for tests performed on July 12, 1977 and February 27, 1978.
PMP-121, Boron Injection Tank Temperature, Revision 0,
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October 14, 1977.
Data reviewed for test performed August 19, 1978.
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PMP-ll2, Spray Additive Tank Level, Revision 0, October 14,
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1977.
Data reviewed for test perfomed January 1,1977.
PMP-176, Condensate Storage Tank Level, Revision 0, October 14,
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1977.
Data reviewed for test performed May 24, 1977.
PMP-303, Diesel Generator 22 Fuel Oil Day Tank Level,
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Revision 0, October 14, 1977.
Data reviewed for test per-fomed February 17, 1977.
PMP-307, Diesel Generator 23 Fuel Oil Storage Tank Level,
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Revision 0, October 14, 1977.
Data reviewed for test per-formed February 17, 1977.
6.
Inspector Witnessing of Calibrations The inspector witnessed the performance of the following functional test which was conducted on October 18, 1978 to verify perfonnance consistent with approved procedures and to verify the implementation aspects for the control of test equipment.
PT-Mll, Steam Line Pressure Analog Channel Test, Revision 2
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May 4, 1978.
The test was performed and data recorded as required by the procedure.
The procedure was adequately detailed to assure performance of a satisfactory surveillance.
No items of noncompliance were identified.
7.
Calibration and Control of Test Equipment The inspector reviewed the calibration and control of test equip-ment used as standards in the calibration of components identified in D ragraphs 4 and 5 to verify the following:
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Estulishment and adherence to calibration schedules;
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Maintenance of calibration records identifying standards used
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which have traceability to the National Bureau of Standards or other independent testing organizations; Proper storage and labeling of test equipment; and,
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Adequate control of test equipment including recordkeeping.
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The following devices were selected as a sampling:
Digital Volcmeter, IC-249, calibration performed July 1978.
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Frequency Counter, 73, calibration perfonned February 1978.
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Digital Voltmeter, IC-418, calibration performed September 1978.
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Pressure Gauge, IC-205A, calibration performed February 1978.
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Pressure Gauge, IC-248, calibration perfonned January 1978.
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No items of noncompliance were identified.
8.
Administrative Controls for Surveillance Procedures The inspector performed an audit of the licensee's administrative controls by conducting a sampling review of the below listed admin-istrative procedures with respect to the requirements of the Technical Specifications, Section 6, " Administrative Controls,"
ANSI N18.7 " Administrative Controls for Nuclear Power Plants" and Regulatory Guide 1.33 " Quality Assurance Program Requirements."
SA0100, Station Administrative Order Policy, Revision 6,
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July 15,1978.
SA0 102, Procedure / Procedure Change Approval Policy, Revision 4,
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February 24, 1976.
Administrative Directive No. TAD-2 Test Procedure Development
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and Approval Process, Revision 3, June 27, 1978.
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Administrative Directive No. TAD-5 Surveillance Test Procedure Issuance and Review Process, Revision 3, November 23, 1977.
No items of noncompliance were identified.
9.
Surveillance Testing a.
The inspector reviewed surveillance tests on a sampling basis to verify the following.
Tests required by Technical Specifications are available
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and covered by properly approved procedure. --
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Test format and technical content are adequate and provide
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satisfactory testing of rel.?ted systems or components.
Test results of selected tests are in conformance with
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Technical Specifications and procedure requirements have been reviewed by soaeone other than the tester or individual directing the test.
b.
The following surveillance tests were reviewed to verify the items identified above:
PT-SA3, Post Accident Containment Atmosphere Sampling
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System, Revision 2, September 30, 1975.
Data were reviewed for tests performed January 20, 1978 and June 30, 1978.
PT-SA2, Hydrogen Recombiner Control System, Revision 5,
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August 12, 1976.
Data were reviewed for tests performed April 16,1978 and September 7, 1978.
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PT-R15, Hydrogen Recombiner Functional Test, Revision 2,
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January 14, 1977.
Data were reviewed for test performed May 18, 1978.
PT-TM1, Hydrogen Recombiner, Revision 4, August 12, 1976.
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Data were reviewed for six tests performed December 28, 1977 through September 28, 1978.
PT-M18, Residual Heat Removal Pumps Functional Test, Revision
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6, October 5, 1977.
Data were reviewed for tests performed j
July 11,1978, August 8,1978, September 8,1978, and October 6, 1978.
PT-M20, Auxiliary Component Cooling Pump, Revision 7,
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August 30, 1978.
Data were reviewed for tests performed i
July 24, 1978, August 17, 1978, September 14,1978 and October 5, 1978.
PT-M21, Diesel Generator Functional Test, Revision 8
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August 23, 1977.
Data were reviewed for six tests performed April 13,1978 through September 18, 1978.
PT-M16, Cable Tunnel Ventilation Fans Test, Revision 4,
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September 13, 1977.
Data were reviewed for tests performed June 20,1978, July 18,1978, August 21,1978, and September 20, 1978.
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PT-R20, Diesel Generator Full Load Test, Revision 2, January
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20, 1977.
Data were reviewed for test performed April 13, 1978.
PT-R14, Safety. ejection System Electrical Load Test,
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Revision 4, July 19,1977.
Data were reviewed for test performed May 2,1978.
PT-M23, Motor Driven Auxiliary Boiler Feed Pumps Test,
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Revision 6, July 12,1978.
Data were reviewed for tests performed July 31, 1978, August 25, 1978, September 14, 1978, and October 'i2, 1978.
PT-R7/PT-R22, ABFWP's Full Flow Test, Revision 2, January 11,
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1977.
Data were reviewed for tests performed December 11, 1976, September 26,1976, May 19,1978, and October 2,1978.
No items of noncompliance were identified.
10.
Inspector Witnessing of Surveillance Tests a.
The inspector witnessed the performance of surveillance testing of selected components to verify the following.
Surveillance test procedure was available and in use.
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Special test equipment required by procedure was cali-
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brated and in use.
Test prerequisites were met.
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The procedure was adequately detailed to assure performance
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of a satisfactory surveillance.
b.
The inspector witnessed the performance of:
PT-M21, Diesel Generator Functional Test, Revision 8,
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August 23, 1977, performed October 18, 1978.
PT-M16, Cable Tunnel Ventilation Fan Test, Revision 4,
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September 13, 1977, performed October 18, 1978.
PT-R31, Cable Tunnel Vent Fans Control System Test, Revision 1
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December 8, 1976, performed October 19, 1978 on PE 21-3.
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c.
As a result of the above witnessing the following item was identified.
During the performance of PT-M16, Cable Tunnel Ventilation Fan Test, an attempt was made to uart the ventilation fans from their associated temperature controllers. This is not the nonnal method for starting the fans specified in the monthly surveillance test.
Normally the fans are started from a control room switch. Attempting to start the fans from the controller revealed that one of the four controllers was inoperable. These temperature controllers had been tested and calibrated during the last refueling outage.
During the evaluation of this matter a number of questions arose relating to the adequacy of testing the Rmperature controllers and the effectiveness of the air operated controllers under worst case conditions. The licensee stated that the operation and control of the cable tunnel venti-lation fans would be reviewed in detail by the Station Nuclear Safety Committee.
This item is unresolved pending review by NRC:RI of the comittee's findings.
(247/78-34-01)
The inoperable temperature controller was imediately repaired and the remaining three controllers checked.
11. Technician Qualification The inspector reviewed the qualification records of selected tech-nicians having responsibility for calibration and surveillance tests of safety related systems and components to verify that the individuals'
experience level and training were in accordance with ANSI N18.1, Selection and Training of Nuclear Power Plant Personnel.
No items of noncompliance were identified.
12.
Facility Tours On several occasions during the inspection, tours of the facility were conducted of the Auxiliary Building, Turbine Building, Diesel Generator Room, and portions of the Security Fence.
During the tours, the inspectors discussed plant operations and observed housekeeping, radiation control measures, monitoring instrumentation, and controls for Technical Specification compliance.
In addition, the inspec+or observed control room operation for control room manning, and facility
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operation in accordance with administrative and Technical Specification requirements.
One matter relating to the control of an unlocked security gate in an area where maintenance was being performed was discussed with the licensee.
No items of noncompliance were identified.
13. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable, an item of noncom-pliance, or a deviation. An unresolved item discussed during the inspection is discussed in Paragraph 10.c.
14.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on October 20, 1978.
The purpose, scope and findings of the inspection were summarized.
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