ML17264A187
| ML17264A187 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/06/1995 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML17264A188 | List: |
| References | |
| NUDOCS 9510160105 | |
| Download: ML17264A187 (15) | |
Text
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p PRIORITY 1 (ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)
ACCESSION NBR:9510160105 DOC.DATE: 95/10/06 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit. 1, Rochester G
05000244 P
AUTH.NAME AUTHOR AFFXLIATXON MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards response to request for addi info re 24 month cycle evaluation
& Rev 1 to "Guidelines for Instrument Loop Performance Evaluation
& Setpoint Verification."
DISTRXBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE-TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 I
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'UDOCS-ABSTRACT COPIES LTTR ENCL 1
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NOTE TO ALL "RIDS" RECIPIENTS:
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AND ROCHESTER GASANDEIECIICCORPORATION
~ 89EASTAVENUE, ROCHESTER, N Y Mht9 MOI AREA CODE 7I6 5'-270O ROBERT C. MECREDY Vice president Nvctear Operations October 6, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attention:
Mr. Allen R. Johnson Project Directorate I-1 Washington, D.C. 20555
Subject:
Conversion to Improved Technical Specifications 24 Month Cycle Evaluation, Response to Request for Additional Information Rochester Gas 2 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
(a)
Letter from A.R. Johnson, NRC, to R.C. Mecredy, RGE.E,
Subject:
Request forAdditionalInformation - Improved Technical Specifications-Attachinent H, Extension ofInslnrment Surveillance Intervals, R.L. Ginna Nuclear Power Plant (TACNo. M92963), dated September 21, 1995.
Dear Mr. Johnson,
By Reference (a), the NRC requested additional information with respect to the proposed technical specification changes to extend the instrument surveillance intervals to accommodate a
24-month fuel cycles.
Enclosed, please find the requested information. Please contact Mark Flaherty at (716) 724-8512 ifyou have additional questions on this response.
Very truly yours, Robert C. Mecre y MDF5769 3.600.0
'st510160105 951006 PDR ADQCK 05000244 P
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U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission (w/o attachment)
Mr. Carl Schulten (Mail Stop 011E22)
Office ofTechnical Specifications Branch Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King ofPrussia, PA 19406 Ginna Senior Resident Inspector
Response to Request for Additional Information dated September 21, 1995 1.
Provide a copy ofEngineering WorkRequest 5126, "GuidelinesforInstnunent Loop Performance Evaluation and Setpoint Verification, "August 1992.
A copy ofthe requested guidelines is attached.
Providej ustification to show how and what were the sample sizes chosenPom the instnmient population and based on what section ofMIL-STD-J05D, "Sampling Procedures and Tables forInspection ByAttributes, "to support a claim of95/95 confidence level.
The method of selecting the instrument population and sample sizes is contained in Section 7.1 ofthe Design Analysis (Ref. 1). However, this is further explained below.
The first step performed was to generate a list ofall instrumentation subject to the increased surveillance intervals in the proposed improved technical specifications (ITS) for Ginna Station (Ref. 2). This population is listed in Table 1 ofthe Design Analysis and contains the instrumentation forwhich the channel calibration surveillance interval is being proposed to increase from 18 months to 24 months. From this population listing, all components of each instrumentation loop were reviewed to identify those devices which were subject to driftconsiderations.
Devices such as transmitters, indicators, alarm bistables, and various signal processing modules were included while devices such as RTDs and thermocouples which have no inherent means for performing calibration adjustments were excluded from further consideration.
The devices subjected to drift considerations were then placed in a data base containing information such as equipment identification number (EIN), model number, and vendor name.
The data base was then sorted and grouped by vendor, model number, and EIN (see Table 2 ofDesign Analysis).
The data base contains 489 components subjected to driftconsiderations.
Itwas estimated that itwould take approximately 6 man months to retrieve the necessary data for each ofthese components.
Therefore, a sampling approach was selected.
This sampling approach was based on each model category specified in Table 2 of the Design Analysis. That is, a representative sample ofthe entire data base population was not performed; instead, a representative sample of each model number contained in the data base was performed.
This approach ensured that sufficient historical data was retrieved for each model number so that the increased surveillance frequency could be justified. It also resulted in the evaluation of 191 devices, or almost 40% of the total population.
MIL-STD-105DTable 1, "General Inspection Levels," Column IIand Table II-A, "Acceptable Quality Level," column "4.0" were selected for the determination ofthe representative sample sizes and the acceptance criteria. Table 1 ofthis standard provides a cross reference to Table II-Afor a given population size. For the purpose ofthe instrumentation review, the population size is based on the number ofEINs for each model number.
Table II-Aprovides the sample sizes for each model number population.
Column "4.0" ofTable II-Aprovides "acceptance" and "rejection" standards for these sample sizes.
This column shows the number ofnumber offailures which can be expected in a given sample population size (i.e., the number of "acceptable" failures) and the number offailures in which the sample size is considered invalid such that the 95/95 confidence level woufd no longer apply (i.e., the number of "rejection" failures). RGE.E used these two tables to determine the sample size for each model number and the maximum number offailures which could be tolerated in each sample population. A failure was defined as the failure ofa device to meet the TIUvalue as discussed in the response to Question 9. In no case did the sample size exceed the maximum number of allowed failures such that the sample size was invalid. (Note - for the LT-2039 "failure" discussed in the response to Question 10, there were only two level transmitters in the associated model population, both ofwhich were evaluated).
Therefore, the 95/95 confidence level was met.
Asampling approach was considered acceptable since almost 40% of the total population was eventually evaluated.
RG8'cE has also committed to a program for monitoring and assessing the effects of the increased calibration surveillance intervals. In addition, the Maintenance Rule (10 CFR 50.65) requires a program to monitor the effectiveness of maintenance activities at Ginna Station.
3.
Instrunient DriftStudy is based on only a sample ofthe installedinstrumentation at Ginna. Is this appropriate considering: instrument types, installation, characteristics, manufacturer and service requirementsxplain the bases forstating that the confidence level is 95i95.
The basis for determining the sample size and stating that the confidence level is 95/95 is discussed in the response to Question 2. As stated above, the sample size appropriately considered instrument types, installation, characteristics, manufacture, and service requirements since all sample sizes were based on the number of devices with the same model number and almost 40% of the total population was evaluated.
4.
Are the instrument uncertainties listed referenced to the sensorltransmitter only or to all components in the loop?
In the Setpoint Analysis (Ref. 3), instrumentation uncertainties are calculated for every device in the instrument loop. The values provided in the Design Analysis are the uncertainties associated with each applicable device (i.e., the total instrument uncertainty (TIU)value provided in the Design Analysis is for each device, not for the instrument loop).
Driftis the difference bet>veen as-left and asfound In the submittal, the year data sheet uses "desiredlcalculated" and "as-found" values.
Explain the difference.
This issue is explained in Section 7.3 ofthe Design Analysis. However, this is further explained below.
The data sheets which are completed by I&Ctechnicians during their calibration of an instrument loop typically contain 5 fields (see attached example).
The firstfield contains-the "input" value(s) used in the test. Most components are tested over a wide range of "input" values to ensure their operability. The second field is the "desired/calculated" value which contains the expected output value for each "input." The third field is the "as found" value which is to completed by the I&Ctechnician during the channel calibration. The fourth field contains the "allowable tolerance band," typically a 1% span around the "desired/calculated" value. The final field is the "as left" value to be completed by the I&Ctechnician. Ifthe "as found" value is approaching or has exceeded the "allowable tolerance band," the device is adjusted. Ifthe "as found" value is considered acceptable by the I&Ctechnician, no change is made and the "as found" and "as left" values willbe same.
For the purpose ofthe Design Analysis, instrument driftwas determined by calculating the difference between the previous test "as left" value and the next test "as found" value.
This was performed for 5 years ofhistorical data (i.e., 1990 through 1994) and provides information with respect to instrument driftfor a typical 12 months between tests.
However, for the first year of data sheets, the previous test "as left" value was not known (i.e., the 1989 value was not retrieved).
Therefore, in this case, the "as left" value was compared to the "desired/calculated" value (i.e., the "desired/calculated" value was assumed to be previous test "as left" value for the first year data sheets).
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4 The submittal states that the worst case consecuti ve three year variance is selected.
What is the basis forselecting three co'nsecuti ve calibration results?
Also, our review of the data indicates that the selected intervals widely vary (1.5 to > 3 years), not always three years.
RG&E proposes to increase the channel calibration surveillance interval from 18 months to 24 months.
However, SR 3.0.2 ofthe ITS for Ginna Station allow this surveillance interval to be increased by up to 25% such that the maximum surveillance interval could actually be 30 months. RG&E performs most ofthese channel calibrations during refueling outages.
Since these outages are currently on an annual basis (i.e., 12 months),
a three year window was selected for purposes ofthe historical data review. That is, if the historical data showed that the observed instrument driftwas acceptable over a 3 year window, then this would bound the worst case surveillance interval of30 months.
II As stated in the response to Question 5, a total of 5 years ofhistorical data was retrieved.
This data was retrieved for each test point (i.e., a device is typically tested using multiple input values as discussed above).
The "as found" and "as left" values were then determined for each test point. The single worst case difference (or "variance") between all test points was then selected and added to the summary sheets contained in Attachment Aofthe Design Analysis. This worst case "variance" was then determined for every channel calibration performed during the 5 year window and added to the summary sheets.
The summary sheets were then reviewed to determine what the worst case "variance" would be over any 3 year window in the 5 years of data.
Since absolute values were not used, the worst case "variance" could actually occur in less than 3 years (e.g., ifyou added additional "variance" values after 1.5 years, this would no longer be the worst case).
Absolute values were not used since the summary sheets contain the worst case "variance" of all test points for each test as discussed above.
Consideration of any data beyond 3 years was unnecessary since the maximum surveillance interval would only be 30 months.
The submittal states that the 3 consecutive calibration intervals demonstrates acceptable instrument performance for calibration intervals greater than 30 months. Explain the methodology and assumptions to support'his conclusion. Howis the instrument calibration handled when included in the 3 consecutive interval criteria (no longer representative ofa 36 month interval) 7 See response to Question 6.
The term "variance" as usedin the discussion and the sununary sheets appear to be misleading.
Does this represent the fluctuation ofthe data (10 point calibration results) around the meanP See response to Question 6.
The totalinstrument uncertainty (TIU) term referenced in the submittal appears to represent an "alloivable value. " Provide a description ofthe Ginna setpoint methodology and the development ofthe allowable value.
Asummary ofthe Ginna setpoint methodology and development of "allowable values" follows.
The accident analyses use conservative values for various unit parameters to provide margin with respect to normal operating conditions and to account for all process errors, environmental considerations, instrument uncertainties, and driftconsiderations.
The instrument loops for these unit parameters are comprised ofmany components including
'istables, transmitters, square root converters, etc. Each component ofthis loop is tested separately in the field such that, in general, an actuation value for the entire instrument loop is not generated during surveillances (otherwise a trip may occur). Therefore, even though the Ginna Station Setpoint Analysis (Ref. 2) is performed on an instrument loop basis, itfocuses on the devices which actually comprise the loop.
Trip setpoints are provided for unit parameters to ensure that the accident analyses remain valid after assuming worst case values for process errors, environmental considerations, instrument uncertainties, and driftconsiderations.
The Setpoint Analysis begins with the trip setpoints for each instrument loop and calculates the worst case values for each component.
This is performed by calculating a total instrument uncertainty (TIU)which is the statistical consideration ofinstrument accuracy, instrument drift, instrument calibration tolerance, and test equipment accuracy for each device in the instrument loop. This TIU does not include those process errors and environmental considerations which cannot be appropriately evaluated during normal system testing.
Therefore, the TIUcan be considered the "allowable value" for each device.
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Itshould be noted that TIU is not the "allowable tolerance band" contained on the calibration data sheets as discussed the response to Question 6. The "allowable tolerance band" is a smaller value than the TIU(typically only 1%) and provides the basis for the "as left" value ofthe devices. In addition, the TIU's, process errors, and environmental considerations for each device are not combined in the Setpoint Analysis to determine an bl I.Thi I
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be calculated since each device on this loop is tested and controlled separately.
Only an instrument loop trip setpoint is required.
10.
Sheet 5 ofthe driftstudy (LT-2039) proposes an increase ofTIUto 3.14% and total channel uncertainty to 4.57%. How does the change in acceptance criteria affect instrument operability determinations Itappears that the instnanent may infact be failingand is not indicative ofperformance for this type oftransmitter.
Sheet 5 ofAttachment Ato the Design Analysis relates to the results for the Viatran Model 8511 level transmitters.
For K,T-2039, itwas determined that the worst case variance over a three year period would be 3.14%. This exceeded the TIUvalue of+
1.24% as calculated in the Setpoint Analysis. The summary sheet's conclusion is that the instrument is not used for any EOP or safety related or technical specification requirement and was therefore, found to be acceptable.
LT-2039 is the containment sump A level transmitter.
This level transmitter was originally determined to be required for ITS LCO 3.4.15, "RCS Leakage Detection Instrumentation."
However, upon further review, this level transmitter only provides indication oflevel in the containment sump that is used for detecting normal operational leakage (a second sump is used for recirculation purposes following an accident).
The actual detection ofRCS leakage is performed by tracking the time between actuation of the sump pumps located in containment sump A. These actuation times are independent of the level transmitter.
However, since the Design Analysis had already performed the evaluation ofthis level transmitter, itwas included in the package.
RGB is aware ofthe performance issues related to this level transmitter and is reviewing the available options. However, this level transmitter is 'only a secondary instrument as noted above.
11.
The driftanalysis present'ed does not reference current industry guidance as expressed by EPM, ISA, 5'estinghouse or GI. Justify authenticity ofthe method chosen.
The Design Analysis is based on the "Guidelines for Instrument Loop Performance Evaluation and Setpoint Verification" that was requested in Question 1. This document references ISA-S67.04.
12.
Is RGd'cle 's conclusion that instrument driftgenerally occurs shortly after the calibration is based solely on observed data?
Then such data should be providedfor our review.
Surveillance intervals can be increased ifitis established by extensive data that the instrument driftis independent oftime after the cali bration.
RG&E has assumed that instrument driftgenerally occurs shortly after calibration based on industry and manufacturer information. RG&E does not have specific historical data to base this on since this would require real-time monitoring capability or a test program which performs channel calibrations over various time frames to see the different drift results.
However, GL 91-04 allows plants with limited or no operational experience to pursue 24 month cycles based on industry and manufacturer information. In addition, RG&E has committed to monitor the effects of the increased surveillance intervals in the future to ensure that the instrument loops remain operable.
Therefore, plant specific data is not considered necessary.
R~eferen e
Design Analysis DA-EE-95-0109, "Evaluation of 24 Month Instrument Surveillance Intervals."
2.
Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,
Subject:
Applicationfor Amendment to facilityOperating License, Conversion to Improved Technical Specifications," dated May 26, 1995.
3.
Engineering Work Request 5126, Ginna Station Instrument Loop and Setpoint Verification.
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