IR 05000333/1979007
| ML19210E511 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/21/1979 |
| From: | Kister H, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19210E464 | List: |
| References | |
| 50-333-79-07, 50-333-79-7, NUDOCS 7912050131 | |
| Download: ML19210E511 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report Nr. 79 07 Docket No. 50-S33 License No. DPR-59 Priority:
Category:
C
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Licensee:
Power Authority of the State of New York P.O. Box 41 Lycoming, New York Facility Name: James A. Fitzpatrick Nuclear Power Plant Inspection at: Scriba, New York Inspection conducted:
May 29-June 1, 1979
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Inspectors:
R. P.tZimmerman, Reactor Inspector 4at si
[>_-//gned
Approved by:
w H'. B. Kistdrr Chief, Nuclear Support date s/gned Section No. 2, RO&NS Branch Inspection Sumary:
Inspection on May 29-June 1, 1979 (Report No. 50-333/79-07)
Areas Inspected:
Routine, unannounced inspection by regional based inspector of licensee action on previous inspection findings; admini-strative controls for safety-related maintenance and calibrations associated with safety-related systems; inspector witlessing of calibra-tions; calibration required by Technical Specifications of components and equipment associated with safety-related systems and/or functions; surveillance calibration of safety-related components and equipment required by Technical Specifications; and review of safety related maintenanceactivities.
The inspection involved 25 inspector-hours a
on site by one NRC regional based inspector.
Results: Of the six areas inspected, no items of noncompliance were found in five areas; and one apparent item of noncompliance was found in one area (Deficiency - Failure to include acceptance criteria in TS surveillance calibration and subsequent review and approval of erroneous results, Paragraph 6.c.).
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DETAILS 1.
Persons Contacted
- E. Abbott, Operations Superintendent
- R. Baker, Maintenance Superintendent
- R. Converse, Assistant Operations Superintendent B. Fernandez, Assistant Maintenance Superintendent
- J. Flaherty, Instrument and Control Foreman H. Keith, Instrument and Control Superintendent (Acting)
- J. Leonard, Resident Manager
- R. Pasternak, Superintendent of Power The inspector also interviewed other licensee employees, including members of the technical and engineering staff, general office personnel and reactor operators.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresol"ed Item (333/78-04-04):
Scheduling of monthly fire extinguisher inspections.
Surveillance test procedure ST-76I has been incorporated in the Surveillance Test Schedule.
Data from the initial surveillance, performed May 31, 1979, was reviewed by the inspector, with no discrepancies noted.
(Closed) Noncompliance (333/79-02-02):
Failure to log suppression pool temperature.
Surveillance test ST-22B, Automatic Depressuri-zation System, has been revised to include logging suppression pool temperature as required by TS 4.7.A.1.
(Closed) Unresolved Item (333/79-02-OS):
Fuel oil tank curve.
The appropriate tank curve figure has been attached to all con-trolled copiri of surveillance test F-ST-76C, Diesel Fire Pump Operational Check.
(Closed) Unresolved Item (333/79-02-06):
Torque wrench identi-fication.
Surveillance test F-ST-15F, Pressure Suppression Cham-ber - Drywell Vacuum Breaker Differential Simulated Automatic Actuation Test, has beea revised to include a step to identify the particular wrench used.
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(Closed) Unresolved Item (333/78-03-05):
Review of Technical Specification required calibrations and identification of problems through review of results.
During the review of TS required calibrations, an apparent item of noncompliance was identified in lHf 250
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the above area.
Details are discussed in Paragraph G.c.
Unresolved item 333/78-03-05 is being closed administratively, and licensee action will be followed under item number 333/79-07-01.
(0 pen) Unresolved Item (333/78-04-03):
Establishment of calibra-tion program for Technical Specification Balance of Plant Instru-mentation.
The inspector noted that many generic procedures do not contain documentation recording the shift supervisor's approval to perform the work, specific acceptance criteria, second level data review, and returning the instrument to service.
The licen-see representative stated that the items mentioned above would be documented in all subsequent ~ balance of plant, technical specifi-cation related calibrations.
Status of specific instrument calibrations, as recorded initially in Inspection Report 333/79-02, are discussed in Paragraph 4.b.
This item remains open pending licensee action as stated above and subsequent NRC:RI review.
(0 pen) Unresolved Item (78-27-01):
Periodic review of facility procedures.
The inspector noted that numerous procedures have not yet received a two year periodic review.
The licensee representa-tive stated that it will be each department's responsibility to perform the periodic review and to document the review accordingly.
The method of documentation will be left up to the individual departments.
This item remains open pending licensee review of procedures and associated documentation, and subsequent NRC:RI review.
3.
Administrative Controls for Safety-Related Maintenance,and Calibrations Associated With Safety-Ralated Systems and/or Functions The inspector performed an audit of the licensee's administrative controls in the above areas by conducting a sampling review of the below listed procedures with respect to the requirements of the Technical Specifications, Section 6, " Administrative Controls,"
ANSI N18.7, " Administrative Controls for for Nuclear Power Plants" and Regulatory Guide 1.33, " Quality Assurance Program Requirements."
The following documents were reviewed.
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Administrative Procedure (AP)-4.1, Procedure for Department Surveillance Tests, Revision 2, April 12, 1979.
AP-1.4, Control of Plant Procedures, Revision 2, April 5,
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1978.
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AP-4.2, Control of Measuring and Test Equipment, Revision 1,
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October 20, 1978.
AP-4.4, Control of Permanent Plant Instruments, Revision 1,
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March 21, 1979.
AP-10.1, Control of Work Activity Control Procedures, Revi-
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sion 1, August 21, 1978.
AP-3.1, Procedure for Maintenance Procedures, Revision 1,
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October 31, 1977.
AP-1.2, Plant Operations Review Comittee, Revision 1, April
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1, 1977.
Procedure Number 10.1.1, Procedure for Control of Mainte-
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nance, Revision 1, July 25, 1978.
No items of noncompliance were identified.
4.
Calibration Required by Technical Specifications of Components and Equipment Associated With Safety-Related Systems and/or Functions a.
The calibration program for components associated with safety related systems was reviewed on a sampling basis.
These components are used to monitor system parameters to comply with Technical Specification safety limits, limiting condi-tions for operation, and surveillance requirements.
The following were varified:
Specific requirements have been established for the
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above calibrations including schedules and frequencies; Procedures have been reviewed and approved in accordance
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with Technical Specifications, contain acceptance criteria consistent with Technical Specifications, and contain detailed instructions commensurate with the complexity of the calibration; and,
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Technical content of procedures are adequate to perform a satisfactory calibration.
b.
The following data was reviewed:
Reactor Vessel Temperature Recorder (TS 4.6.A.1) 2-3-TR89
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Procedure F-IMP-2-3.5, Reactor Vessel Instrumentation Temperature. Data - February 9, 1979.
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Turbine Bypass Valve Position (TS 4.5.D.1.b) (ST-228).
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Data - March 21, 1979.
Pressure Indicator to Verify Diesel and Electric Fire
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Pump Start Pressure Switches (TS 4.12.A.1.b) (ST-76B and C) 76-PI-10.
Data - March 20, 1979.
Emergency Service Water Pump Discharge Pressure (TS -- 4.11.D.1.b)46-PI-118AandB.
Data - March 20, 1979.
Diesel Generator Loadmeters (TS 4.9.B.1), Procedure for
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Calibration and Functional Test of Protective Relay System and/or Meters, Revision 1, April 24,1979.
Data - March 22, 24 and 27, 1979.
Emergency Service Water Intake Deicing Heater Ameter
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(TS 4.11.E.1).
Data - May 31, 1979.
Standby Gas Treatment System Instrument Calibration (TS -- 4.7.B.a.1).
Data - February 7, 1978.
No items of noncompliance were identified.
5.
Inspector Witnessing of Calibrations a.
The inspector witaessed the performance of the following functional test, performed May 30, 1979, and reviewed the applicable procedure.
Procedure Number F-ISP-13-1, RCIC Turbine High Exhaust
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Pressure Instrument Functional Test / Calibration, Revi-sion 1, March 20, 1979.
b.
At th' conclusion of the functional test, the inspector noted that t:e radiation monitor in use at the monitoring point, outside the Health Physics office, had a calibration sticker dated Juia 15, 1977. The calibration records for the detector showed tSt latest calibration as being performed April 24, 1979. A new calibration sticker was filled out reflecting the above calibration date and was affixed to the detector.
The inspector had no further questions.
6.
Surveillance Calibration of Safety-Related Components and Equipment Required by Technical Specifications a.
Calibration procedures / data were reviewed on a sampling basis to verify the following:
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Calibration frequency requirements have been met;
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Applicable system status during compenent calibration
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was 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, Technical content of procedures was sufficient to result
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in satisfactory component calibration.
b.
Data for the following calibrations were reviewed.
F-ISP-29-2, Suppression Chamber Water Level Instrument
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Calibration (Narrow Range), Revision 0, May 9, 1978.
Data - May 2, 1979.
F-ISP-29-1, Suppression Chamber Water Level Instrument
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Calibration, Revision 3, January 13, 1978.
Data - May 2, 1979.
F-ISP-4-5, Drywell Suppression Chamber Differential
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Pressure, Pevision 1, December 27, 1978.
Data -May 2, 1979.
c.
During the above review, it was noted that surveillance test F-ISP-4-5, Drywell-Suppression Chamber Differential Pressure, wr '. ten in part to satisfy TS 3.2.F and performed May 2, lo 3, did not contain acceptance criteria for the drywell p assure indicator PI-1028.
Further, the output data for PI-1028 did not appear to yield results that corresponded to the input signal from pressure transmitter PT-1028.
Review showed that the pressure transmitter PT-102B and pressure indicator PI-1028 were not compatible in that PT-102B con-tained an operating range of 10-20 PSIA, while PI-1028 con-tained an operating range of 0-20 PSIA.
The above calibra-tion test had received secondary level review and approval with no discrepancies noted.
The above condition represents noncompliance (deficiency level) with TS 6.8.A and ANSI N18.7-1972, Section 5.3.6 (333/79-07-01).
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The licensee installed a compatable temporary pressure indi-cator in place of PI-1028 and performed surveillance test F-ISP-4-5 on June 1, 1979.
The inspector found the results acceptable.
The licensee stated that a new pressure indi-cator would be ordered as a permanent replacement for PI-102B.
The inspector noted that PI-1028 is but one indication of drywell pressure and that other detectors exist which ensured that TS 3.7.A.7.a was satisfied.
7.
Review of Safety-Related Maintenance Activities a.
The inspector reviewed safety-related maintenance conducted by the licensee on a sampling basis to verify that:
Limiting Conditions for Operation (LCO's) were met while
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equipment was out of service; Required administrative approvals were obtained to
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perform the work; An approved procedure was used where required;
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Required inspections were performed;
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QA/QC records were available to substantiate quality of
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work and parts used; The maintenance was performed by qualified maintenance
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personnel; and A Reportable Occurrence Report, if required, by Technical
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Specifications, was submitted based on review of circum-stances associated with the maintenance activity.
b.
The documentation associated with the following safety-related maintenance activities was reviewed:
Work Request (WR)-12068, completed November 16, 1978,
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Containment Spray Valve - leaks by.
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WR-11661, completed November 17, 1978, Remove, Repair, and Reinstall 14 Control Rod Drives.
WR-329, completed March 19, 1979, Ground on 125 VDC
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Leads to Relief Valves.
WR-448, completed March 5, 1979, 'A' Core Spray Minimum
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Flow Valve - failure to open on signal.
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No items of noncompliance were identified.
8.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on June 1, 1979.
The scope and findings of the inspection were summarized.
The findings were also reviewed in a subsequent telephone discussion between Mr. R. Zimmerman and Mr. J. Flaherty on June 4,1979.
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