IR 05000302/1987043
| ML20148S888 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/19/1988 |
| From: | Bernhard R, Jape F, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20148S875 | List: |
| References | |
| 50-302-87-43, NUDOCS 8802030166 | |
| Download: ML20148S888 (7) | |
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P Eth UNITED STATES
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Report No.:
50-302/87-43 Licensee:
Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No.:
50-302 License No.: OPR-72 Facility Name:
Crystal River 3 Inspection Conducted:
December 7-17, 1987 Inspectors:
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Engineering Branch Division of Reactor Safety SUMMARY Scope: This special, announced inspection was conducted on site and in the Region II Office in the areas of integrated safeguards test witnessing, review of test precedures for emergency diesel generator (EDG) load testing, and review of procedures for flow balance testing of selected safety-related components.
Results:
No violations or deviations were identified.
8802030166 890122 PDR ADOCK 05000302 Q
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- D. Beach, Nuclear Project Engineer, Site Nuclear Engineering Services (SNES)
G. Becker, Manager, SNES J. E. Colby, Manager, Nuclear Mechanical, SNES
- K. H. Hudak, Nuclear Project Manager
- M. S. Mann, Nuclear Compliance Specialist S. E. Primo, Engineer, SNES
- W. L. Rossfeld, Manager, Nuclear Compliance E. Welch, Manager, Nuclear Electrical /I&C, SNES
- K. R. Wilson, Manager, Nuclear Licensing Other licensee employees contacted included engineers, technicians, operators, security force members, and office personnel.
Other Organization T. Giaramita, Controlotron Corporation NRC Resident Inspector J. E. Tedrow, Resident Inspector 2.
Exit Interview The inspection scope and findings were summarized on December 10, 1987, with those persons indicated in Paragraph 1 above and 'j telephone on December 17, 1987, with K. Wilscn.
The inspectors described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the !n>pectors during this inspection.
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Licensca Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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5.
Emergency Diesel Generator Loading Issue a.
General From 1980 to October 1987, a potential existed for placing electrical loads automatically on emergency diesel generator IA (EDG-1A) that exceeded the EDG 30 minute maximum load rating (3300 KW) specified by the EDG manufacturer. This was determined by an evaluation performed
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by Florida Power Corporation (FPC). FPC determined that the loading problem does not apply to EDG-18.
After determining that the automatically connected loads exceeded the 30 minute rating, FPC made several modifications and performed additional analyses to reduce the load below 3000 KW for EDG-1A.
This issue is discussed in several FPC letters to the NRC.
Inspection of this issue is discussed in more detail in NRC Inspection Report 50-302/87-41.
During a meeting between the NRC and FPC on November 5,1987, FPC committed to perform additional testing of the seven major pumps loaded on EDG-1A to confirm the values used in the EDG-1A load analyses for the pumps.
FPC commitments to resolve the EDG-1A loading issue and commitments to resolve other issues discussed
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during the meeting on November 5, 1987, are discussed in a NRC Region II Confirmation of Action Letter (CAL) to FPC dated November 17, 1987.
The following discusses some of the procedures for the EDG-1A loading tests and is based on review of licensee records and discussions with licensee representatives.
The inspe: tors reviewed the Performance
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Test (PT) procedures listed below.
Some of the procedures had received final approval, while others were in final draf t form.
PT-136, DC and SW System Flow Me. surements and EGDG-1A KW Loading Due to ES Pumps, Rev. O PT-303, DHP-1A and BSP-1A Power and Flow Measurements for EGDG-1A KW Loading Verification, Draft PT-311, MVP-1A Power and Flow Measurements for EGDG-1A KW Loading Verification, Rev. O PT-312, RWP-2A and RWP-3A Power and Flow Measurements for EGDG-1A KW Leading Verification, Draft The purpose of the above pts, along with the pts for the other pumps, was to obtain motor data for the selected pumps.
The data includes starting voltages and currents and the measurements of power (watt),
voltage, current, and power factor readings under different pump flows.
This includes testing the pumps as near as practicable to each pump's condition during a postulated large break loss of coolant accident (LOCA) coincident with a loss of offsite power.
The inspectors noted that the pts only performed the running of the
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equipment and the recording of the specified data. The data was then sent to FPC's corporate offices for evaluation and comparison to the calculated values. The inspectors reviewed the results for completed procedure PT-311.
The results showed that the calculated load for makeup pump 1A was greater than the measured value.
This was the only pump which nad been tested at the conclusion of the inspection, b.
Integrated ECCS Testing In addition to reviewing the above procedures, the inspectors reviewed surveillance procedure SP-457, Refueling Interval ECCS
Response to Safety Injection Test Signal, Revision 5.
The inspectors i
also witnessed portions of SP-457.
Dbjectives of SP-457 included l
demonstrating the operability of each ECCS subsystem and each EDG.
The ECCS subsystem operability would be demonstrated by verifying that each automatic valve in the flow path activates to its correct position on a high pressure or low pressure safety injection test signal as appropriate; and by verifying that each high pressure (
injection (HPI) and low pressure injection (LPI) pump test starts I
automatically upon receipt of a high pressure or low pressure safety injection test signal as appropriate.
Each EDG is demonstrated operable by verifying the generator capability to reject a load
>515 KW without tripping; verifying the EDG operates for at least 60 minutes.
During the first five minutes but no greater than six minutes of the test, the EDG shall be loaded to >3248 KW but less than 3300 KW, and during the remaining time of the 60 minute test, the EDG shall be loaded to >2750 KW but less than 3000 KW. This last objective reflects testin'g requirements included in a recent Technical Specification (TS) change request submitted by the licensee and is related to the EDG-1A loading issue.
The inspectors witnessed portions of Section 9.6 of SP-457, which verified the B Train HPI and LPI pumps auto started on the appropriate safety injection test signal, and operation of EDG-1B during the 60 minute load test. Minor discrepancies were identified during the test but all major components appeared to operate properly. Subsequent to the test licensee personnel stated that the portion of the test where EDG-1B was loaded to >2750 KW but less than
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3000 KW and run for >55 minutes, did not comply with the current TS requirements and would be repeated. The inspectors will review the test results during a later inspection after the licensee has completed the final review and approval of the test results.
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Meeting Summary The inspectors attended a meeting between NRC and FPC held in the NRC Region II Of fice on December 11, 1987.
The purpose of the meeting was to discuss in general the CAL issued on November 17, 1937, and discuss specifically the testing being performed to verify the load on EDG-1A (Item 1 of the CAL).
A list of meeting attendees is included as Attachment 1 to this inspection report. FPC stated that
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the additional testing was being performed to confirm that the values used in the EDG-1A load analyses were conservative.
The load for EDG-1A will continue to be based on their analyses.
Questions raised by NRC during the maeting included the following:
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Was the testing being performed adequate to determine EDG-1A load (e.g., number of points on the pump head curve, account for instrument accuracy, method for cetermining "other" loads on EDG-1A, etc. )?
Were plant specific pump curves used in the analyses?
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How will the motor control center 3AB change be administratively controlled?
Did FPC compare TS test requirements with diesel manuf acturer
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requirements?
Does FPC use lubricants recommended by the manufacturer?
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How much of the 30 minute rating intervals will remain after the
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proposed testing (this applies to EDG-1A and EDG-1B)?
FPC stated during the meeting that the test program being performed to determine the load on EDG-1A would be submitted to Region II for review.
In a letter dated December 16, 1987, the licensee described actions being taken to address each item of the CAL, the test program being performed to determine EDG-1A loading, and addressed questions raised by NRC during the meeting.
Region II reviewed the items discussed in the letter.
During a telephone conversation on December 17, 1987, Region II informed FPC that the actions being taken to resolve the issues identified in the CAL, and answers to questions raised during the meeting on December 11, 1987, appear to be adequate.
Region Il personnel further stated that it was the NRC's understanding that motor control centers loads which may not be in their fully loaded conditions during the integrated ES test will be taken into account when determining EDG total load.
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The inspectors will review the results of the EDG load testing during a later inspection.
No violations or deviations were identified in the areas inspected.
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Flow Verification of the SW System
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Action number two in the CAL dated November 17, 1987, specified that, prior to entry into Mode 3, flow testing be performed to demonstrate
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adequate flow to all critical components in the Nuclear Services Closed Cycle Cooling System (SW) to support emergency operations.
The inspectars reviewed performance test Procedure PT-136, "0C and SW system flow measurements and EDG-1A KW loading due to ES pumps",
Revision 0.
The procedure was verified against system drawings FD-302-631, Decay Heat Closed Cycle Cooling and FO-302-601, Nuclear Services Closed Cycle Cooling. Inspectors comments on the procedures were incorporated into Revision 1 of the procedure.
The inspectors asked if a program existed for inspecting or testing the air side of the reactor building cooling units.
Adequate water flow through the water side of the reactor building cooling units does not provide operability if the air side is fouled. The inspectors were told the units were disassembled and cleaned in refueling outage number four.
Preventative Maintenance (PM) Procedure PM-139, HVAC Equipment Inspection and Service, was provided as the PM that provided instruction for the
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work. A review was performed of the procedure. Preventative Maintenance Control Sheet Number 162, for AHF-001, directs PM-139 Sections 7.7 and 7.9 be performed on AHF001A, AHF001B and AHF001C every 547 days.
This equates to the 18 month fuel cycle. The date the test was last completed was 10/13/87, or this cycle.
Visual inspection and cleaning of the unit would provide assurance of normal heat transfer rates for the coolers.
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Flow measurement verification is to be measured in part by a Controlotron flow device. The instrument does not require elements in the primary flow stream, but instead measures the transit time of an ultrasonic signal and derives fluid velocity and flow from the result. The inspectors reviewed the instruments instruction manual for instrument limitations that might effect instrement accuracy. The Controlotron representative on site was interviewed on setup and operation of the instrument. The accuracy of the device with the on site flow check for verification of accuracy is less than 3% error according to the manual.
Results of the flow verificatica test will be reviewed by the inspectors during a later inspection. The flow verification program, as reviewed is adequate to address the question of adequate flow to components required to support a I.0CA.
No violations or deviations were identified in the area inspecte..
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t ATTACHMENT __1 DECEMBER 11, 1987
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ATTENDANCE LIST CRYSTAL RIVER MTG Name Organization B. A. Wilson Chief, Project Branch 2, NRC P. J. Fillion Plant Systems Section, RII, NRC R. H. Bernhard Test Programs Section NRC, RII E. C. Simpson FPC, Dir, Nuc. Ops Site Support H. Silver NRR PM K. R. Wilson FPC Mgr Nuc Licensing Rolf C. Widell FPC Dir. Nuc. Ops Eng & Projects Matee U. Rahman FPC, Nuc-Elect. Engineer. Nuclear Ops.
En'gg Tom Stetka SRI-$RC M:Kenzie Thomas Reactor Inspector, TPS, RII Paul Burnett Reactor Inspector, TPS Bruno Uryc Enforcement Coordinator. RII J. E. Tedrow Resident Inspector, CR-3, USNRC E. W. Merschoff DD, DRS, RII A. F. Gibson Director, DRS, RII C. W. Hehl DD, DRP, RII