IR 05000306/1981016
| ML20010A282 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/28/1981 |
| From: | Jackiw I, Robinson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20010A277 | List: |
| References | |
| 50-306-81-16, NUDOCS 8108110275 | |
| Download: ML20010A282 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF.TNSPECTION AND ENFORCEMENT
REGION III
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-Report No. 50-306/81-16
Docket No. 50-306 License No. DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall-q Minneapolis, MN 55401
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Facility Name: Prairie Island Nuclear Generating Plant, Unit 2
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Inspection At:
Prairie Island Site, Red Wing, MN Inspection C nd d: July 13-14, 1981
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Inspectors:
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Approved By:
... Jackiw, Acting Chief
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Test Program Section
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Inspection Summary l
Inspection on July 13-14, 1981 (Report No. 50-306/81-16)
Areas Inspected: Routine, announced inspection of Cycle 6 scram time tests;
reactor thermocouple /RTD cross calibration; incore/excore calibration; control i
rod worth measurements;' reactor shutdown margin determination; isothermal i
temperature' coefficient measurement; power coefficient of reactivity measure-ment; target axial flux difference calculation; core thermal power evaluation;
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core power distribution limits; determination of reactivity anomalies. The inspection involved a total of 18 inspector-hours onsite by two NRC inspectors including 0 inspector-hours onsite during offshifts.
Results: No items of noncompliance or deviations were identified.
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DETAILS'
1.
Persons Contacted
- F. Tierney, Plant Manager'
- E'. Watzl, Plant Superintendent, Plant Engineering and Radiation
' Protection J. Hoffasn, Superintendent, Technicai Engineering
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~*M. Klee, Nuclear Engineer
- S. Northard, Nuclear Engineer P. Ryau, Shift Supervisor
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H. Pemble, Reactor Operator W. Mather, Reactor Operator
- C, Feierabend, USNRC Senior Resident Inspector
- B. Burgess, USNRC Resident Inspector
- Denotes those present during the exit interview.
2.
Verification of Conduct of Startup Physics Testing The inspector reviewed the startup physics testing.for Prairie Island 2 Cycle 6 and verified that the licensee conducted the following:
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Rod Drive and Rod Position Indication Checks t
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Core Power Distribution Limits
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Incore/Excore Calibration d.
Core Thermal Power Evaluation e.
Determination of Shutdown Margin f.
Isothermal Temperature Coefficient g.
Control Rod Worth Measurement h.
Tars:t Axial Flux Difference Calculation i.
. Determination of Reactivity Anomalies 3.
Control Rod Drive and Position' Indication Checks The inspectors reviewed the results of surveillance-test procedure number 2046, Revision 6, " Full Length Control Rod Drop Timing,".for
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Unit.2 conducted on April 5,'1981 and concluded that all rod drop times satisfied the acceptance criteria of 1.8 seconds or less re-quired by the Technica1' Specifications. The inspectors. verified that-2-
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rod drive and rod position indication checks were perforued in accord-ance with surveillance calibration procedure number 2013, Revision 5,
" Analog Rod Pisition System Test and Calibration," on April 6,1981.
No items of noncompliance or deviations were identified.
4.
Reactor Thermocouple /RTD Cross Calibration The; inspectors noted that the licensee no' longer routinely performs.
reactor thermocouple /RTD cross calibrations following a_ refueling outage, but does check the RTD control: and protection signal outputs from the, narrow range transmitters as part of the plant primary and secondary calorimetric associated with startim after refueling. The inspectors'-
concluded that all applicable Technical. Specifications had been met.
No items of noncompliance or deviations were identified.
5.
Incore/Excore Calibration The inspectors reviewed information related to incore/excore monitor-calibration as described in surveillance procedure r. umber 2006, Revision-9, " Nuclear Power Range Axial Offset-Calibration," for Unit 2 conducted on April 15,1981. ' The inspectors reviewed the four power range channels and noted that calibration currents were properly obtained for the_ upper and the lower excore detectors. The inspectors determined that the li--
censee-had satisfied the Technical Specification requirement to calibrate the nuclear power range channels quarterly.
No items of noncompliance or deviations wert identified.
6.
Control Rod Worth Measurement The inspectors reviewed information related to Cycle 6 determination of control rod worths for Unit 2 as described'in procedure D-30, Revision 3,
" Post Refueling and Startup Test," conducted _on April 8,.1981.
Control rod worths were obtained using the boron dilution technique. The rod worth _ measurement met the acceptance criteria in that1the individual worths'of control banks A, B, C, and D were within 15% of design and the summation of control bank rod worths A, B, C, and D were 'within 10% of
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the design value given in the Prairie Island Unit 2 Cycle 6 Startup_and Operation Report of January 1981.
No items of noncompliance or.ieviations were identified.
7.
Determination of Shutdown Margin -
TF.e inspectors reviewed information related to an analytical determina-tion' of Cycle 6 shutdown margin at beginning of life (BOL)~ and end.of -
life (EOL) conditions as-given in Prairie Island Unit 2 Cycle 6 Safety-3-
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o Analysis Report of October 1980. The inspectors noted that the results of tha ccatrol rod worth measurements'are used in lfeu of a specific physics test to verify shutdown margin. The inspecf. ors' evaluations indicated that the applicable Technical Specifications would be met.
No items of noncompliance or deviations were identified.
8.
Isothermal Temperature Coefficient The inspectors reviewed information related to the Cycle 6 determination of the isothermal temperature coefficient for Unit 2 as described in procedure D-32, Revision 2, " Temperature ccefficient at Hot Zero Power."
The licensee's acceptance criterion requires that the measures isothermal temperature coefficients be less than 0 pcm/ F.
The inspectors determined that this requirement was met. For the all rods out condition (ARO) the measured isothermal temperature coefficient was--2.21 pen / F compared to a predicted value of -0.71 pcm/ F given in the aforementioned Safety Analysis Report.
No items of noncompliance or deviations were: identified.
9.
Power Coefficient of Reactivity
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The inspectors noted that the licensee does not perform power coefficient'
of reactivity measurements and is not required to do so by Technical Specifications.
10.
Target' Axial Flux Difference Calculation The inspectors reviewed information related to the Cycle 6 determination of target axial flux difference for Unit 2 as described.in surveillance -
procedure number 2135, Revision 4, "AI Target Measurement." ~ The inspec-tors examined surveillance test data for both the current and previous fuel cycles and' concluded that the licensee had' satisfied the Technical
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Specification requirements to determine the target axial flux difference at least once per equivalent full' power quarter and to update target differences monthly.
No items of noncompliance or deviations were identified.
11.
Core Thermal Power Evaluation The inspectors reviewed information related to the evaluation of core l
thermal power as determined by the onsite ' computer calorimetric'and by hand calculation as described in surveillance procedure number. 2005,
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Revision 7, " Unit 2 Nuclear-Power Range Daily Calibration." The in-i spectors verified-that the onsite computer program was working properly, l
and that the core thermal power calculated with the above procedure was-in good agreement with that determined by the computer.
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No items of noncompliance or deviations were identified.
12.
Core Power Distribution Limits The inspectors reviewed surveillance procedure number 2116, Revision 6,
" Monthly Power Distribution Map,"
and the results of full core maps taken at 99% power on April 13, 1981. The inspectors noted that the BOC incore power distribution measurements for Unit 2,. Cycle 6 indicated a core radial power tilt of approximately 3.2% at hot zero power con-ditions (HZP). The tilt diminished with increasing power, measuring 1.9% at 48% power and 1.6% at 100% power. Although the tilt exceeded the licensee's acceptance criteria of 2% at HZP, the deviation was judged to have no safety significance by both the Operations Committee and the fuel vendor. With this exception, the inspectors determined that all prerequisites were met, the onsite computer was using input values from the actual plant conditions, all thermal margins satisfied Technical Specification requirements, and the calculated values by the computer were within the acceptable criteria established by the licensee.
No items of noncompliance or deviations were identified.
13.
Determination of Reactivity Anomalies The inspectors reviewed information related to the determination of reactivity anomalies for Cycle 6 as described in surveillance procedure number 2014, Revision 2, " Reactivity Anomalies," and concluded that the applicable Technical Specification was met.
The inspector noted that the computer code (FOLLOW) was used to infer the measured boron concentration to critical boron concentration at ARO and equilibrium xenon condition, and the inferred boron concentration values were compared with the Exxon predicted values. The inspector noted that the Exxon critical boron concentration values were slightly higher, and the differences between Exxon and the inferred values were within 1% of reactivity.
No items of noncompliance or deviations were identified.
14.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on July 14, 1981. The inspectors summarized the purpose, the scope of the inspection, and the findings.
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