ML041190309

License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a Licensee-Controlled Document

ML041190309
Person / Time
Site:	Nine Mile Point
Issue date:	04/19/2004
From:	Spina J Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NMPIL 1828
Download: ML041190309 (114)

Text

P.O. Box 63 Lycoming, New York 13093 Constellation Energy Group Nine Mile Point April 19, 2004 Nuclear Station NMP1L 1828 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Nine Mile Point Unit 1 Docket No. 50-220 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a Licensee-Controlled Document Gentlemen:

Pursuant to 10 CFR 50.90, Nine Mile Point Nuclear Station, LLC, (NMPNS) hereby requests an amendment to Nine Mile Point Unit 1 (NMP1) Operating License DPR-63 to incorporate proposed changes to the Technical Specifications (TSs). The proposed changes contained herein would revise Specification 3/4.6.2, "Protective Instrumentation," to establish an operating cycle (24-month) calibration surveillance frequency for the Intermediate Range Monitor (IRM) instrumentation, which would replace the current "prior to startup and normal shutdown" surveillance requirement. The proposed changes to Specification 3/4.6.2 also include associated conforming changes.

In addition, it is proposed to relocate the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) for selected control rod withdrawal block instrumentation from Specification 3/4.6.2 to the NMP1 Updated Final Safety Analysis Report (UFSAR), a licensee-controlled document. Attachment 1 provides an evaluation of the proposed changes. The proposed TS changes (mark-ups) are provided in.

The Bases for TS 3/4.6.2 will be revised to reflect the proposed changes to the TSs. The TS Bases changes (mark-ups) are provided in Attachment 3 for information only. TS Bases changes are controlled by the NMP1 TS Bases Control Program (TS 6.5.6) and do not require NRC issuance.

The proposed 24-month IRM calibration frequency is supported by plant-specific analyses that were developed using the guidance of NRC Generic Letter 91-04, "Changes in Technical Specification Intervals to Accommodate a 24-Month Fuel Cycle," and the NRC approved setpoint methodology of General Electric Topical Report NEDC-31336P-A, "Instrument Setpoint Methodology." The supporting plant-specific instrument calibration drift analysis, setpoint calculation, and calibration data are provided in Attachments 4, 5, and 6, respectively.

Page 2 NMP1L 1828 Consistent with the NRC "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors [58 FR 39132 (07/22/93)]," the requirements for selected control rod withdrawal block instrumentation have been evaluated (see ) for retention in the TSs. Since the selected instrumentation does not satisfy any of the four screening criteria defined in 10 CFR 50.36(c)(2)(ii) for retention in the TSs, the applicable LCOs and SRs are proposed to be relocated to the NMP1 UFSAR and controlled under the 10 CFR 50.59 program. The proposed relocated requirements are consistent with the Improved Standard TSs for General Electric Plants (NUREG-1433 and NUREG-1434).

The proposed changes have been evaluated in accordance with 10 CFR 50.91(a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that the changes involve no significant hazards considerations.

NMPNS requests approval of this application and issuance of the license amendment by January 31, 2005 with 60 days allowed for implementation. The amendment is needed prior to shutdown for the Spring 2005 refueling outage (RFO18) since it directly affects plant shutdown, refueling, and startup activities. This letter contains two new commitments as reflected in Section 5.3 of Attachment 1.

Pursuant to 10CFR50.91(b)(1), NMPNS has provided a copy of this license amendment request and the associated analyses regarding no significant hazards considerations to the appropriate state representative.

Very truly yours, J

es A. Spina ice President Nine Mile Point JAS/CDM/bjh

Page 3 NMP1L 1828 STATE OF NEW YORK

TO WIT:

COUNTY OF OSWEGO I, James A. Spina, being duly sworn, state that I am Vice President Nine Mile Point, and that I am duly authorized to execute and file this request on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

A. Spina cPresident Nine Mile Point Subscribed and sworn before me, a Notary Public in and for the State of New York and County of Oswego, this Iee day of_

2004.

WITNESS my Hand and Notarial Seal:

Juno6 J ~s lpgrn pio~a MON to elel O~lqnd ne° GlVMSO TV Nf S My Commission Expires:

Notary Public C// 9 to Li Notary P StaoDate Coualifiedin Oswego Cou7, Attachments:ComslnEpe

1. Evaluation of Proposed Technical Specification Changes

2. Proposed Technical Specification Changes (Mark-up)

3. Technical Specification Bases Changes (Mark-up For Information Only)

4. Nuclear Engineering Report No. NER-II-002

5. Calculation No. SP-SRMIRM-RGO7JRHO1

6. Intermediate Range Monitor Calibration Data cc:

Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)

Mr. John P. Spath, NYSERDA

ATTACHMENT 1 EVALUATION OF PROPOSED TECHNICAL SPECIFICATION CHANGES

Subject:

License Amendment Request Pursuant to 10 CFR 50.90: Revision of Intermediate Range Monitor Surveillance Frequency and Relocation of Selected Instrumentation Requirements to a Licensee-Controlled Document

2.0 PROPOSED CHANGE

S

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY SAFETY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

Page 1 of 23

1.0 DESCRIPTION

This letter is a request to amend Operating License DPR-63 for Nine Mile Point Unit 1 (NMP1).

The proposed changes would amend the Operating License to incorporate proposed changes to the Technical Specifications (TSs). The proposed changes would revise Specification 3/4.6.2, "Protective Instrumentation," to establish an operating cycle (24-month) calibration surveillance frequency for the Intermediate Range Monitor (IRM) instrumentation, which would replace the current "prior to startup and normal shutdown" surveillance requirement. The proposed changes to Specification 3/4.6.2 also include associated conforming changes. In addition, it is proposed to relocate the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) for selected control rod withdrawal block instrumentation from Specification 3/4.6.2 to the NMP1 Updated Final Safety Analysis Report (UFSAR), a licensee-controlled document. The TS Bases will be revised to reflect the proposed changes to the TSs.

The proposed changes to the TSs and associated changes to the TS Bases are indicated in the marked-up pages provided in Attachments 2 and 3, respectively. The TS Bases changes are provided for information only and will be controlled by the NMP1 TS Bases Control Program (TS 6.5.6).

2.0 PROPOSED CHANGE

S TS Table 4.6.2a. "Instrumentation that Initiates Scram," SRs Neutron Flux IRM Upscale and Inoperative Parameters:

The current Sensor Check requirement per Note (f) to "...check once per shift..."

is replaced with the equivalent tabular frequency of "Once per shift ('." To conform with this change and the other IRM Parameter changes described below for this Table, the current Note (g) Source Range Monitor (SRM)JIRM and IRM/Average Power Range Monitor (APRM) overlap requirements are moved to Note (f).

The current Instrument Channel Test requirement per Note (f) to "...test once per week..." is replaced with the equivalent tabular frequency of "Once per week I)."

As indicated above, the current Note (g) requirements are moved to Note (f). As such, the Instrument Channel Test frequency is modified by a new Note (g) which requires the test to be performed "...within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before startup, if not performed within the previous 7 days," and allows the performance of the test to be delayed "...during shutdown until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering startup from run."

The current Instrument Channel Calibration requirement in Note (f) to "Calibrate prior to startup and normal shutdown..." is replaced with the tabular frequency of "Once per operating cycle (n).,' The Calibration frequency is modified by the Page 2 of 23

addition of Note (n) which reflects the current industry and NMP1 practice of excluding calibration of the neutron detectors.

Neutron Flux APRM Upscale Parameter:

The current Instrument Channel Calibration tabular frequency is modified by the addition of Note (n). As indicated above, Note (n) is added to reflect the current industry and NMP1 practice of excluding calibration of the neutron detectors.

TS Table 3.6.2g. "Instrumentation that Initiates Control Rod Withdrawal Block." LCOs SRM Detector not in Startup Position, Inoperative, and Upscale Parameters:

The LCO requirements and Notes (a) and (e) for the Parameters are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMPl UFSAR.

Recirculation Flow Comparator Off Normal, Flow Unit Inoperative, and Flow Unit Upscale Parameters:

The LCO requirements for the Parameters are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMP1 UFSAR.

Scram Dump Volume Water Level Scram Bypass Parameter:

The LCO requirements for the Parameter are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMP1 UFSAR.

TS Table 4.6.2g. "Instrumentation that Initiates Control Rod Withdrawal Block." SRs SRM Detector not in Startup Position, Inoperative, and Upscale Parameters:

The SRs for the Parameters are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMPI UFSAR.

IRM Detector not in Startup Position, Inoperative, Downscale, and Upscale Parameters:

The current Instrument Channel Test requirements per Note (g) to "...test [the Detector not in Startup Position and Inoperative Parameters] prior to startup and normal shutdown" and "...once per week..." and "...test [the Downscale and Upscale Parameters] once per week..." are replaced with the equivalent tabular frequency of "Once per week (9)." To conform with this change and the other IRM Parameter changes described below for this Table, the current Note (g)

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calibration and testing requirements are replaced with a new Note (g) which requires the Instrument Channel Test to be performed "...within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before startup, if not performed within the previous 7 days," and allows the performance of the test to be delayed "...during shutdown until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering startup from run."

The current Instrument Channel Calibration requirement in Note (g) to "Calibrate prior to startup and normal shutdown..." is replaced with the tabular frequency of "Once per operating cycle 0)." The Calibration frequency is modified by the addition of Note (i) which reflects the current industry and NMP1 practice of excluding calibration of the neutron detectors.

APRM Upscale (Biased by Recirculation Flow) and Downscale Parameters:

The current Instrument Channel Calibration tabular frequency is modified by the addition of Note (j). As indicated above, Note (j) is added to reflect the current industry and NMP1 practice of excluding calibration of the neutron detectors.

Recirculation Flow Comparator Off Normal, Flow Unit Inoperative, and Flow Unit Upscale Parameters:

The SRs for the Parameters are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMPI UFSAR.

Scram Dump Volume Water Level Scram Bypass Parameter:

The SRs for the Parameter are replaced with the word "Deleted" to indicate that the requirements are being removed from the TSs and relocated to the NMPI UFSAR.

TS Bases 3/4.6.2. "Protective Instrumentation" Bases Pages 251, 251a, 252, 253, and 254:

The scram and control rod withdrawal block instrumentation surveillance interval information on pages 252 and 253 will be updated to include a reference to Generic Letter (GL) 91-04, "Changes in Technical Specification Intervals to Accommodate a 24-Month Fuel Cycle." The changes to Bases page 253 will also include an editorial correction. The APRM downscale setpoint referenced on Bases page 254 will be updated to reflect the current setpoint (5.28/125 divisions of full scale) as approved in License Amendment No. 153, which was issued on March 3, 1995. This change corrects an apparent omission from the Bases changes previously identified for the amendment. In addition, the current IRM setpoint deviation (i.e., tolerance) of "+/- 2.5% of rated neutron flux" as listed on page 251 will be updated to specify the calculated setpoint Allowable Values Page 4 of 23

(AVs) resulting from the setpoint calculation (provided in Attachment 5) performed to support the proposed 24-month IRM calibration frequency. The AVs are as follows:

IRM Upscale Scram, AV is < [121.55/125] divisions of full scale IRM Upscale Rod Block, AV is < [114.2/125] divisions of full scale IRM Downscale Rod block, AV is 2 [5.61/125] divisions of full scale The setpoint deviations (tolerances) on page 251a for the Recirculation Flow Upscale and Comparator Parameters will be deleted since the associated LCOs and SRs are being removed from the TSs.

3.0 BACKGROUND

3.1 24-Month IRM Calibration Frequency NRC approved General Electric (GE) Topical Report NEDC-30851P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System," March 1988, provided a detailed analysis to confirm the acceptability of the then current Allowed Outage Times (AOTs)/Surveillance Test Intervals (STIs) for the Boiling Water Reactor (BWR) Reactor Protection System (RPS). This analysis led to changing several STIs from monthly to quarterly and in extending the AOTs for many components and functions. An important finding from the analysis was that for each of the RPS initiating events, the RPS unavailability was determined to be insensitive to changes in component failure rates. A factor of 10 increase in the failure rates produced a negligible (0.1%)

impact on RPS unavailability for each of the initiating events analyzed. The resultant impact on RPS failure frequency was also found to be negligible. Additionally, it was found that reduced redundancy (i.e., unavailability of any one sensor channel) during testing has negligible impact on RPS unavailability.

The RPS IRM functions were not explicitly modeled in NEDC-30851P-A because the events for which these functions provide protection are so mild that safety limits are not violated. As such, the RPS IRM functions have low impact on core melt frequency.

Consequently, the NEDC did not propose changes to the existing AOTs or STIs for the RPS IRM functions. The results of the AOT/STI evaluation from NEDC-30851P-A were incorporated in the NMP1 TSs by License Amendment No. 139, which was issued on February 24, 1993.

In GL 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," issued April 2, 1991, the NRC provided generic guidance for addressing the effect of increased surveillance intervals on instrument drift and safety analysis assumptions. In order to justify an increased instrument calibration interval, the GL identifies 7 actions that a licensee should address when evaluating the proposed increased calibration interval. Nine Mile Point Nuclear Station, LLC, (NMPNS) has addressed the 7 actions for the proposed 24-month IRM calibration Page 5 of 23

frequency. The evaluation justifying the proposed calibration frequency is provided in Section 4.1 of this Attachment.

By letter dated July 21, 1994 (NMP1L 0838), as supplemented on December 14, 1994 (NMP1L 0886), Niagara Mohawk Power Corporation (the previous licensee for NMPI) proposed changes to the NMP1 TSs which included a 24-month IRM calibration frequency similar to that requested in this submittal. The proposed 24-month (+ 25%)

calibration frequency was supported by a plant-specific setpoint calculation (GE-NE-909-002-0294) prepared by GE using the methodology contained in Topical Report NEDC-31336, "General Electric Setpoint Methodology." However, by letter dated February 1, 1995, the request for a 24-month IRM calibration frequency was withdrawn because the available historical calibration data was insufficient to adequately address Action 1 of GL 91-04. As discussed in the withdrawal letter, it was intended to pursue the 24-month calibration frequency at a later date when adequate historical calibration data was available to support the change.

Currently, as indicated in the IRM calibration data provided in Attachment 6, approximately 9 years of historical calibration data (04/11/94 to 04/19/03) are now available. NMPNS contracted with Alion Science and Technology Corporation (formerly Innovative Technology Solutions Corporation) to analyze this data for statistical drift. The IRM drift analysis uses the methodology of Electric Power Research Institute (EPRI) Report TR-103335, "Guidelines for Instrument Calibration Extension/Reduction," Revision 1, October 1998, and, in general, follows the guidance of GL 91-04. Other plants have used similar methods to support extended surveillance intervals. FirstEnergy's Perry plant was issued a License Amendment on August 29, 2000 (Accession No. ML003747690) supporting a 24-month fuel cycle based on analyses using this methodology and Entergy's Vermont Yankee plant used this methodology in the analyses supporting their May 21, 2003 submittal proposing TS changes (Accession No. ML031490416) to extend instrumentation surveillance intervals. The details of the IRM drift analysis performed for NMP1 are provided in Attachment 4.

The IRM calibration data and the results of the drift analysis were used in a plant-specific setpoint calculation which ensures that sufficient setpoint margins are maintained to support the proposed 24-month (a maximum of 30 months accounting for the 25% grace period allowed by TS 4.0.2) calibration frequency. The setpoint calculation was prepared based on the NRC approved methodology of GE NEDC-31336P-A. The setpoint calculation is provided in Attachment 5. Note that the drift analysis (Attachment 4) and setpoint calculation (Attachment 5) support a 24-month calibration frequency for both the SRMs and IRMs. However, NMPNS is asking for NRC review and approval of a 24-month calibration frequency for the IRMs only. As such, the information in the drift analysis and setpoint calculation pertaining to the SRMs may be ignored for the purposes of this license amendment request.

NMPNS has concluded that the drift analysis and setpoint calculation demonstrate that IRM performance will support a 24-month (30-month maximum) calibration frequency with no changes to the applicable safety analyses required. As further discussed in Page 6 of 23

Section 4.1 of this Attachment, NM[PNS intends to adopt the setpoint AVs calculated in the setpoint calculation.

3.2 Relocation of Control Rod Withdrawal Block Instrumentation Requirements According to the NRC "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors [58 FR 39132 (07/22/93)]," the purpose of TSs is to impose those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. The NRC's rule regarding the content of TSs is set forth in 10 CFR 50.36, which codifies the criteria for establishing TS LCOs. The criteria delineate those constraints on design and operation of nuclear power plants that are derived from the plant safety analysis report or Probabilistic Safety Assessment (a.k.a.,

Probabilistic Risk Assessment (PRA)) information and that belong in TSs in accordance with 10 CFR 50.36. Those LCOs which do not meet any of the criteria may be removed from the TSs and relocated to licensee-controlled documents (e.g., UFSAR).

NMPNS has applied the screening criteria to the TS Table 3/4.6.2g control rod withdrawal block LCOs for the SRM, Recirculation Flow, and Scram Dump Volume Water Level Scram Bypass instrumentation. The evaluations comparing the LCOs to the screening criteria are provided in Section 4.2 of this Attachment. Based on the evaluations, the selected instrumentation LCOs do not satisfy any of the four screening criteria defined in 10 CFR 50.36(c)(2)(ii) for retention. Accordingly, the applicable LCOs and associated SRs are proposed to be relocated to the NMP1 UIFSAR and controlled under the 10 CFR 50.59 program. The proposed relocated requirements are consistent with the Improved Standard TSs for GE Plants (NUREG-1433 and NUREG-1434) (ISTS).

4.0 TECHNICAL ANALYSIS

4.1 Basis for 24-Month IRM Calibration Frequency 4.1.1 GL 91-04 Assessment In GL 91-04, the NRC provided generic guidance for evaluating a 24-month surveillance test interval for TS SRs. The GL identifies 7 actions that a licensee should address when evaluating a proposed 24-month calibration interval. The following defines each of the NRC prescribed actions and provides the NMPNS evaluations to address the actions, and thereby, justify the proposed 24-month IRM calibration frequency.

Action 1:

Confinn that instntment drift as determined by as-found and as-left calibration data from surveillance and maintenance records has not, except oln rare occasions, exceeded acceptable limits for a calibration interval.

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NMPNS Evaluation:

With respect to the proposed 24-month IRM calibration frequency, in order for an IRM instrument failure to potentially impact safety, the failure would have to occur during the operating cycle and only be detected by performance of the calibration. Accordingly, the effects of the proposed 24-month (30-month maximum) IRM calibration frequency were evaluated by reviewing the surveillance test history for the affected instrumentation, including the supporting plant-specific instrument calibration drift analysis. When necessary (e.g., to investigate missing/incomplete data, data anomalies, etc.),

maintenance history records were also reviewed. The surveillance history data and drift analysis for the instruments demonstrate that, except on rare occasions, instrument drift has not exceeded acceptable limits. The data indicate that there were a small number of data points that were outliers (removed from the data set) and other data points that were beyond the 95/95 drift values (not covered). However, when taken together, the outliers and not covered data points represent 5% or less of all the available data. An exception to this is the IRM 13 INOP trip which had two outliers resulting from calibrations dated from 04/12/94 to 03/29/96. These two outliers are not considered significant as they were in the conservative direction (high) and subsequent data are not indicative of a trend to failure with time. Therefore, the drift analysis and historical maintenance and surveillance data support the conclusion that the effect on safety of the proposed 24-month IRM calibration frequency is small. Additional details regarding the drift analysis are provided in Attachment 4. The calibration data used in the drift analysis are provided in Attachment 6.

Action 2:

Confirm that the values of drift for each instnument type (make, model, and range) and application have been determined wvith a high probability and a high degree of confidence. Provide a summary of the methodology and assumptions used to determine the rate of instrument drift with time based upon historical plant calibration data.

NMPNS Evaluation:

A plant-specific analysis was performed for each applicable TS function of the IRMs to statistically assess the rate of instrument drift using instrument calibration data accumulated during the past 9 years. The analysis was performed using a methodology that is consistent with EPRI TR-103335 guidance and accepted industry practice. The Outlier and Instrument Resetting Evaluations were analyzed to meet 95/95 acceptance criteria as defined in Regulatory Guide 1.105, "Setpoints for Safety-Related Instrumentation," Revision 3, December 1999 (i.e., there is a 95% probability that the constructed limits contain 95% of the population of interest for the surveillance interval selected). The Instrument Resetting Evaluation justified the longest calibration intervals

(> 3 years), which bound the requested 24-month (30-month maximum) IRM calibration surveillance frequency. Using this method, the intermediate (no adjustment) calibrations were discarded from the data sets, which decreased the number of data points and increased the two-sided tolerance factors needed to achieve 95/95 drift values. Since the Page 8 of 23

resulting 95/95 drift values have coverage of the data, the analysis meets or exceeds statistical expectation to assure a high probability and a high degree of confidence that the IRM instrument drift will remain within the setpoint tolerance during the proposed 24-month (30-month maximum) calibration surveillance frequency. Moreover, the results of the drift analysis show that the drift magnitudes are independent of the calibration interval. Additional details regarding the drift analysis are provided in. The calibration data used in the drift analysis are provided in Attachment 6.

Action 3:

Confinn that the magnitude of instnument drift has been detennined with a high probability and a high degree of confidence for a bounding calibration interval of 30 months for each instniment type (make, model number, and range) and application that perfonns a safety finction. Provide a list of the channels by TS section that identifies these instnument applications.

NMPNS Evaluation:

In accordance with the methodology described in the evaluation of Action 2 above, the magnitude of instrument drift was determined for a bounding calibration interval (i.e., 30 months) for each affected LRM instrument. The Instrument Resetting Evaluation resulted in calibration intervals in excess of 3 years. The IRM instruments associated with the TS Table 4.6.2a and 4.6.2g Instrument Channel Calibration requirements are identified below:

Table 4.6.2a IRM Upscale and Inoperative Parameters:

Fission Chamber Detector Preamplifier Monitor (includes DC Amplifier)

Range Switch Trip Auxiliaries Unit GE Model 112C3144G002 GE Model 112C3144G008 GE Model 112C3144G038 GE Model 112C2218G1 GE Model 194X672 GE Model 216X494G21 GE Model 194X940G8 Table 4.6.2g IRM Downscale and Upscale Parameters:

Fission Chamber Detector GE Model 1 2C3144G002 GE Model 112C3144G008 GE Model 112C3144G038 Page 9 of 23

Preamplifier r-GE Model 112C2218G1 Monitor GE Model 194X672 (Includes DC Amplifier)

Range Switch GE Model 216X494G21 Trip Auxiliaries Unit GE Model 194X940G8 Action 4:

Confinn that a comparison of the projected instrument drift errors has been made with the values of drift used in the setpoint analysis. If this results in revised setpoints to accommodate larger drift errors, provide proposed TS changes to update trip setpoints.

If the drift errors result in a revised safety analysis to support existing setpoints, provide a summary of the updated analysis conclusions to confinn that safety limits and safety analysis assumptions are not exceeded.

NMPNS Evaluation:

A setpoint calculation, provided in Attachment 5, was prepared utilizing the results from a plant-specific drift analysis to ensure that sufficient margins are available to support the proposed 24-month (30-month maximum) IRM calibration frequency. The setpoint calculation is based on the NRC approved methodology of GE Topical Report NEDC-31336P-A. The AVs and Nominal Trip Setpoints (NTSPs) have been calculated consistent with the topical report. The 24-month (30-month maximum) drift value was compared with the drift uncertainties associated with the current IRM setpoints for the Upscale Scram and the Downscale and Upscale Control Rod Withdrawal Block. Because the results of the setpoint calculation more accurately account for the instrumentation and calibration errors, NMPNS is adopting the AVs calculated in the setpoint calculation.

Consistent with the current TS Bases format and content, the Bases will be revised to include the calculated IRM AVs. The adoption of the AVs calculated for the proposed 24-month (30-month maximum) calibration frequency provides assurance that the safety actions will be initiated consistent with the existing safety analysis assumptions. The Bases changes will ensure that the appropriate setpoint deviations (tolerances) are applied to the existing TS setpoints. Accordingly, no revisions to the safety analyses are necessary to accommodate the proposed 24-month (30-month maximum) calibration frequency.

Action 5:

Confirm that the projected instrument errors caused by drift are acceptable for control of plant parameters to effect a safe shutdown with the associated instrumentation.

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NMPNS Evaluation:

As previously discussed, the effects of a 24-month (30-month maximum) IRM calibration frequency were evaluated in a setpoint calculation to ensure that sufficient margins are available to accommodate the projected instrument drift errors. It was concluded that the adoption of the AVs calculated for the proposed 24-month (30-month maximum) calibration frequency provides assurance that the safety actions will be initiated consistent with the existing safety analysis assumptions. Therefore, the current safety margins for control of plant parameters to effect a safe shutdown are preserved.

Action 6:

Confinr that all conditions and assumptions of the setpoint and safety analyses have been checked and are appropriately reflected in the acceptance criteria of plant surveillance proceduresfor channel checks, channelfitnctional tests, and channel calibrations.

NMPNS Evaluation:

As previously discussed, a setpoint calculation was prepared utilizing the results from a plant-specific drift analysis to ensure that sufficient margins are available to support the drift errors resulting from the proposed 24-month (30-month maximum) IRM calibration frequency. Since the calculation shows that in all cases the current procedure setpoints are conservative relative to the TS trip setpoints and calculated AVs and NTSPs, no changes to the setpoint criteria in the implementing surveillance procedures are necessary. Also, since the current procedure setpoint tolerances do not allow the specified TS trip setpoints to be exceeded, adequate administrative controls are in place to ensure that sufficient margins to the Design Basis Limits are maintained.

Action 7:

Provide a summary description of the program for monitoring and assessing the effects of increased calibration surveillance intervals on instnument drift and its effect on safety.

NMPNS Evaluation:

Instrument setpoint drift is monitored during channel calibration tests when the setpoints are required to be verified and/or set. The IRM as-found and as-left calibration data are recorded, as required, for each applicable instrument and the data sheets are reviewed by maintenance supervision for satisfactory completion of the acceptance criteria and test requirements. In addition, NMPNS will enhance the existing NMP1 surveillance program to include monitoring and assessing the effects of the 24-month (30-month maximum) IRM calibration frequency on instrument drift and its effect on safety. It is anticipated that the enhancements to the NMP1 surveillance program will be similar to those incorporated into the Nine Mile Point Unit 2 (NMP2) surveillance program in 2000 to support its conversion from an 18-month to a 24-month fuel cycle.

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4.1.2 Discussion of Changes IRM Functional Descriptions (Affected TS Parameters Only)

TS Table 4.6.2a Parameter (9)(a)(i): Neutron Flux - IRM Upscale Scram The RPS IRMs monitor neutron flux levels from the upper range of the SRMs to the lower range of the APRMs. The function of the IRM upscale neutron flux scram is to limit maximum reactor power to prevent fuel damage in the intermediate power range. In this power range, the most significant source of reactivity change is due to control rod withdrawal. The IRM upscale scram function is required to be operable when the reactor mode switch is in the "Startup" and "Refuel" positions. The IRM upscale scram provides a diverse protection function from the Rod Worth Minimizer (RWM), which monitors and controls the movement of control rods at low power. The RWM prevents the withdrawal of an out-of-sequence control rod during startup which could result in an unacceptable neutron flux excursion. The IRM upscale scram provides mitigation of the neutron flux excursion. To demonstrate the capability of the IRM scram to mitigate control rod withdrawal events, a generic analysis was performed (

Reference:

GE NEDO-23842, "Continuous Control Rod Withdrawal Transient in the Startup Range," April 18, 1978) to evaluate the consequences of control rod withdrawal events during startup that are mitigated only by the IRM scram function. This analysis, which assumes that one IRM channel in each trip system is bypassed, demonstrates that the IRMs provide protection against local control rod withdrawal errors and the continuous rod withdrawal transient in the startup range, and also provides backup protection for the APRMs. There are 8 instrument channels for the IRM upscale scram function. The 8 channels are divided into two trip systems, with 4 channels inputting to each trip system. The trip of any of the 4 IRM channels will actuate its associated trip system, producing a half-scram signal. The simultaneous trip of both trip systems will cause a full reactor scram. One channel in each trip system may be bypassed without initiating a trip. Therefore, 3 channels are required to be operable per trip system to ensure that no single instrument failure will preclude an IRM upscale scram.

TS Table 4.6.2a Parameter (9)(a)(ii): Neutron Flux - IRM Inoperative Scram The function of the IRM inoperative scram is to provide assurance that a minimum number of IRMs are operable. An IRM inoperative scram signal will be initiated anytime (1) the mode switch is placed in a position other than "Operate," (2) the detector voltage drops below a preset level, or (3) when one of the plug-in modules is removed or disconnected. This function is required to be operable when the reactor mode switch is in the "Startup" and "Refuel" positions. There are 8 instrument channels for the IRM inoperative scram function. The 8 channels are divided into two trip systems, with 4 channels inputting to each trip system. The trip of any of the 4 IRM channels will actuate its associated trip system, producing a half-scram signal. The simultaneous trip of both trip systems will cause a full reactor scram. Since only one IRM channel in each trip system may be bypassed, only one channel in each trip system is allowed to be inoperable without resulting in a scram trip signal. Therefore, 3 channels are required to be operable Page 12 of 23

per trip system to ensure that no single instrument failure will preclude an IRM inoperative scram.

TS Table 4.6.2g Parameter (2)c: IRM Downscale Control Rod Withdrawal Block The function of the IRM downscale control rod withdrawal block is to block control rod withdrawal during startup when there is indication that the IRM instrumentation has failed or the sensitivity has decreased such that the instrumentation would not adequately respond to changes in control rod motion. This provides assurance that a minimum number of IRMs are operable. An IRM downscale rod block trip signal is initiated when the detector voltage drops below a preset level. The IRM downscale rod block function is required to be operable when the reactor mode switch is in the "Startup" and "Refuel" positions. In order to permit startup, the IRM range switches are selected to the lowest range, which bypasses the IRM downscale rod block channels. There are 8 instrument channels for the IRM downscale rod block function. The 8 channels are divided into two trip systems, with 4 channels inputting to each trip system. The trip of any of the 4 IRM channels will actuate its associated trip system and the trip of either trip system will produce a control rod block. Thus, the trip of any of the 8 IRM downscale rod block channels will result in a control rod block. Since only one IRM channel in each trip system may be bypassed, only one channel in each trip system is allowed to be inoperable without resulting in a control rod block signal. One channel in each trip system may be bypassed without initiating a trip. Therefore, 3 channels are required to be operable per trip system to ensure that no single instrument failure will preclude an IRM downscale control rod block.

TS Table 4.6.2g Parameter (2)d: IRM Upscale Control Rod Withdrawal Block The function of the IRM upscale control rod withdrawal block is to block control rod withdrawal during startup when the IRM range switch is not selected to the proper range for monitoring neutron flux changes due to control rod movement. The IRM upscale rod block provides local as well as gross core protection. In addition, the IRM upscale rod block provides protection against a control rod withdrawal error transient. The IRM upscale rod block function is required to be operable when the reactor mode switch is in the "Startup" and "Refuel" positions. There are 8 instrument channels for the IRM upscale rod block function. The 8 channels are divided into two trip systems, with 4 channels inputting to each trip system. The trip of any of the 4 IRM channels will actuate its associated trip system and the trip of either trip system will produce a control rod block. Thus, the trip of any of the 8 IRM upscale rod block channels will result in a control rod block. One channel in each trip system may be bypassed without initiating a trip. Therefore, 3 channels are required to be operable per trip system to ensure that no single instrument failure will preclude an IRM upscale control rod block.

Additional information on the IRM instrumentation and associated protective functions is provided in the NMP1 UFSAR, Sections VIII-C.1 and XV-B.3.4.

Page 13 of 23

Safety Assessment The changes discussed below are described in detail in Attachment 2 and Section 2.0 of this Attachment.

The Instrument Channel Calibration frequency in TS Table 4.6.2a for the IRM Upscale and Inoperative Parameters and TS Table 4.6.2g for the IRM Downscale and Upscale Parameters are being changed from "...prior to startup and normal shutdown..." to "Once per operating cycle." As discussed in the Bases for TS 4.0.2, an operating cycle (i.e., fuel cycle) for NMP1 is 24 months. An LRM calibration is a complete check of the instrument loop (excluding the neutron detectors), and verifies that each channel, including the associated actuation, alarm, and trip functions, responds with the necessary range and accuracy.

As described above, the current "...prior to startup and normal shutdown..." IRM calibration surveillance frequency requirement is being replaced with a 24-month calibration frequency requirement. The calibration surveillance requirements, in conjunction with the channel check and functional testing surveillance requirements, provide assurance that the IRMs will function as designed when required. An evaluation of the proposed 24-month (a maximum of 30 months was evaluated to account for the 25% grace period allowed by TS 4.0.2) calibration frequency was performed based on the approach described in NRC GL 91-04. Furthermore, a plant-specific drift analysis and setpoint calculation were performed using IRM calibration data accumulated during the past 9 years to ensure that sufficient setpoint margins are maintained to support the proposed 24-month (30-month maximum) calibration frequency. The drift analysis used the methodology of EPRI TR-103335 and the 95/95 acceptance criteria of RG 1.105 to statistically determine that the calibration data supported a calibration frequency in excess of 3 years, which bounds the proposed 24-month (30-month maximum) calibration frequency. Other plants have used similar methods to successfully support extended surveillance intervals. The setpoint calculation used the NRC approved methodology of GE NEDC-31336P-A to demonstrate that IRM performance will support a 24-month (30-month maximum) calibration frequency with adoption of the AVs calculated for the proposed 24-month (30-month maximum) calibration frequency. No changes to the applicable safety analyses are required. Based on the IRM surveillance test history and the results of the drift analysis and setpoint calculation, there is a high probability and a high degree of confidence that the IRM instrumentation will operate reliably during the proposed 24-month (30-month maximum) surveillance frequency.

Although the proposed changes result in changes to surveillance intervals, the impact, if any, on system availability is small based on (1) other more frequent testing that is performed, (2) the existence of redundant equipment, and (3) overall system reliability.

Consistent with the findings of previous industry evaluations, the NMP1 plant-specific qualitative analyses, which consisted primarily of the surveillance and associated failure history reviews and drift analyses, have shown no evidence of time-dependent failures that would impact the availability of the affected systems. Accordingly, the proposed changes will have minimal, if any, impact on the capability of the IRMs to perform their RPS safety functions. The historical reviews of surveillance test results and associated Page 14 of 23

maintenance records do not invalidate this conclusion. It is, therefore, concluded that the proposed 24-month (30-month maximum) IRM calibration frequency is acceptable.

Conforming changes add a Note (n) to Table 4.6.2a and a Note (j) to Table 4.6.2g modifying the calibration frequency to indicate that a calibration of the APRMs and IRMs excludes the neutron detectors. This is the current accepted industry practice and, although not previously specified in the NMP1 TSs, is also the current NMP1 practice based on the neutron detectors being passive devices, with minimal drift, and because of the difficulty in simulating a meaningful signal. APRM and IRM neutron detector sensitivity is periodically checked by performing the weekly APRM calorimetric calibration (Table 4.6.2a Note (m)) and the IRM overlap verification testing (current Table 4.6.2a Note (g), overlap testing requirements moved to Note (f) as an additional conforming change (see below)). These conforming changes are consistent with the ISTS and considered acceptable.

Additional conforming changes to Tables 4.6.2a and 4.6.2g involve changes to the format and content of the IRM SRs requiring a weekly Instrument Channel Test. These changes affect the IRM Upscale and Inoperative Parameters in Table 4.6.2a and the IRM Detector not in Startup Position, Inoperative, Downscale, and Upscale Parameters in Table 4.6.2g.

An Instrument Channel Test is the NMP1 equivalent to a channel functional test in the ISTS and is defined as the injection of a simulated signal into the channel to verify its proper response, including alarm and/or trip initiating action. The weekly IRM Instrument Channel Test requirement is retained in Tables 4.6.2a and 4.6.2g, only being reformatted to a tabular listing. The listed "once per week" test frequency in each of the two Tables is modified by a new Note (g) requiring the test to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before plant startup, if not performed within the previous 7 days, and also to be performed during plant shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering startup from run (i.e.,

within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after changing the reactor mode switch position from "Run" to "Startup"). In the case of Table 4.6.2a, it was necessary to move the current SRM/IRM and IRMIAPRM overlap verifications in Note (g) to Note (f) to accommodate the addition of the new Note (g) requirements described above. These conforming changes are consistent with the current NMP1 requirements for performance of a weekly IRM Instrument Channel Test and provide assurance that the test is performed prior to a plant startup and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering the startup mode from the run mode during a plant shutdown, consistent with the ISTS. The 12-hour delay in performing the IRM Instrument Channel Test is reasonable to allow performance of the test and since industry evaluations and NMPI plant-specific analyses have shown no evidence of time-dependent failures that would impact the availability of the affected systems. Also, note that, for the IRM Upscale and Inoperative Parameters in Table 4.6.2a and Downscale and Upscale Parameters in Table 4.6.2g, the Instrument Channel Test requirements are met by performance of the Instrument Channel Calibration (see TS Definitions 1.6 and 1.7),

which will be required to be performed at a maximum interval of 30 months as previously discussed. The 24-hour allowance for performance of the Instrument Channel Test prior to a plant startup is more restrictive than the ISTS, which allows 7 days (per SR 3.0.4). Therefore, based on the above discussion, these conforming changes are considered acceptable.

Page 15 of 23

Conforming changes to the TS 3/4.6.2 Bases are also to be incorporated which update the references to include GL 91-04, correct a reference to the APRM downscale setpoint, and provide an editorial correction. These changes are for clarity only, do not establish or alter any technical requirements, and are administrative in nature. In addition, consistent with the current TS Bases format and content, the Bases will be revised to include the IRM setpoint AVs calculated in the setpoint calculation performed to support the 24-month (30-month maximum) calibration frequency. The adoption of the calculated IRM AVs provides assurance that the safety actions will be initiated consistent with the existing safety analysis assumptions and the associated Bases changes will ensure that the appropriate setpoint deviations (tolerances) are applied to the existing TS setpoints.

Therefore, the Bases changes will have no negative impact on plant safety. These changes will be made upon implementation of the approved amendment in accordance with the NMP1 TS Bases Control Program (TS 6.5.6).

4.2 Basis for Relocation of Control Rod Withdrawal Block Instrumentation Requirements The NRC's rule regarding the content of TSs is set forth in 10 CFR 50.36, which codifies the criteria for establishing TS LCOs. Those LCOs which do not meet any of the four screening criteria defined in 10 CFR 50.36(c)(2)(ii) may be removed from the TSs and relocated to licensee-controlled documents (e.g., UFSAR). The following evaluations apply the screening criteria to the TS Table 3/4.6.2g control rod withdrawal block LCOs for the SRM, Recirculation Flow, and Scram Dump Volume Water Level Scram Bypass instrumentation. The evaluations demonstrate that the selected instrumentation LCOs do not satisfy any of the four screening criteria for retention, thereby justifying their relocation to the NMPI UFSAR and control under the 10 CFR 50.59 program.

TS LCO 3.6.2 Statement: The setpoints, minimum number of trip systems, and minimum number of instrument channels that must be operable for each position of the reactor mode switch shall be as given in Table 3.6.2g.

4.2.1 Table 3/4.6.2g Parameter (1):

SRM

a. Detector not in Startup Position

b. Inoperative

c. Upscale Discussion:

The SRM control rod withdrawal block functions to prevent control rod withdrawal error during reactor startup utilizing SRM signals to create the rod block signal. SRM signals are used to monitor neutron flux during refueling, shutdown, and startup conditions. The Page 16 of 23

SRMs perform no automatic safety function. No design basis accident (DBA) or transient credits the rod block signals initiated by the SRMs.

Comparison to Screening Criteria:

Criterion 1. Installed instnumentation that is used to detect, and indicate in the control room, a significant degradation of the reactor coolant pressure boundary.

Response: The SRM control rod withdrawal block instrumentation is not used for, nor capable of, detecting a significant abnormal degradation of the reactor coolant pressure boundary prior to a DBA.

Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of afission product barrier.

Response: The SRM control rod withdrawal block instrumentation is not used to monitor a process variable that is an initial condition of a DBA or transient analyses.

Criterion 3. A structure, system, or component that is part of the primary success path and which finctions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of afission product barrier.

Response: The SRM control rod withdrawal block instrumentation is not part of a primary success path in the mitigation of a DBA or transient.

Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

Response: As discussed in Sections 3.5 and 6, and summarized in Table 4-1 (Item 137) of NEDO-3 1466, the loss of the SRM control rod withdrawal block function was found to be a non-significant risk contributor to core damage frequency and offsite releases.

NMPNS has reviewed this evaluation, considers it applicable to NMP1, and concurs with the assessment based on the plant-specific PRA.

==

Conclusion:==

Since the screening criteria have not been satisfied, the control rod withdrawal block LCO (and corresponding Notes) and SRs applicable to the SRM instrumentation may be removed from TS Table 3/4.6.2g and relocated to the NMP I UFSAR, a licensee-controlled document.

4.2.2 Table 3/4.6.2g Parameter (4):

Recirculation Flow Page 17 of 23

a. Comparator Off Normal

b. Flow Unit Inoperative

c. Flow Unit Upscale Discussion:

An increase in reactor recirculation flow causes an increase in neutron flux which results in an increase in reactor power. However, this increase in neutron flux is monitored by the Neutron Monitoring System which would initiate an RPS scram if the instrumentation flux setpoints are reached. No DBA or transient credits the rod block signals initiated by the recirculation flow instrumentation.

Comparison to Screening Criteria:

Criterion 1. Installed instrwnentation that is used to detect, and indicate in the control room, a significant degradation of the reactor coolant pressure boundary.

Response: The recirculation flow control rod withdrawal block instrumentation is not used for, nor capable of, detecting a significant abnormal degradation of the reactor coolant pressure boundary prior to a DBA.

Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity ofa fission product barrier.

Response: The recirculation flow control rod withdrawal block instrumentation is not used to monitor a process variable that is an initial condition of a DBA or transient analyses.

Criterion 3. A stnrcture, system, or component that is part of the primary success path and which fimrctions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity ofa fission product barrier.

Response: The recirculation flow control rod withdrawal block instrumentation is not part of a primary success path in the mitigation of a DBA or transient.

Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

Response: As discussed in Sections 3.5 and 6, and summarized in Table 4-1 (Item 140) of NEDO-31466, the loss of the recirculation flow control rod withdrawal block function was found to be a non-significant risk contributor to core damage frequency and offsite Page 18 of 23

releases. NMPNS has reviewed this evaluation, considers it applicable to NMP1, and concurs with the assessment based on the plant-specific PRA.

==

Conclusion:==

Since the screening criteria have not been satisfied, the control rod withdrawal block LCO and SRs applicable to the recirculation flow instrumentation may be removed from TS Table 3/4.6.2g and relocated to the NMP1 UFSAR, a licensee-controlled document.

The TS Bases will be updated to delete the references to the instrument setpoint deviations (tolerances).

4.2.3 Table 3/4.6.2g Parameter (8):

Scram Dump Volume Water Level Scram Bypass Discussion:

The Scram Dump Volume (SDV) water level scram bypass control rod withdrawal block functions to prevent control rod withdrawals during reset of an RPS initiated scram. An RPS scram (in addition to control rod insertion) closes the SDV drain and vent valves.

During a scram, the SDV partially fills with water causing an SDV high water level scram signal to be inserted. Since a scram also inserts an SDV drain and vent valve closure signal, the SDV high-level sensors must be bypassed to allow reset of the scram, which in turn, will allow the drain and vent valves to be opened to drain the SDV.

Manual bypass of the SDV high-level sensors creates the SDV water level scram bypass control rod block signal by interlock action within the Reactor Manual Control System.

The sensors can only be bypassed if the reactor mode switch is in the refuel or shutdown position. Thus, the SDV water level scram bypass control rod block is essentially redundant to the shutdown and refuel mode switch position control rod withdrawal blocks. No DBA or transient credits the rod block signals initiated by the SDV water level scram bypass instrumentation.

Comparison to Screening Criteria:

Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant degradation of the reactor coolant pressure boundary.

Response: The SDV water level scram bypass control rod withdrawal block instrumentation is not used for, nor capable of, detecting a significant abnormal degradation of the reactor coolant pressure boundary prior to a DBA.

Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Page 19 of 23

Response: The SDV water level scram bypass control rod withdrawal block instrumentation is not used to monitor a process variable that is an initial condition of a DBA or transient analyses.

Criterion 3. A stnrcture, system, or component that is part of the primary success path and wvhich functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

Response: The SDV water level scram bypass control rod withdrawal block instrumentation is not part of a primary success path in the mitigation of a DBA or transient.

Criterion 4. A stnrcture, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

Response: As discussed in Section 3.5 of NEDO-31466 and Supplement 1, Section 6, and summarized in Table 4-1 (Item 365) of Supplement 1, the loss of the SDV water level scram bypass control rod withdrawal block function was found to be a non-significant risk contributor to core damage frequency and offsite releases. NMPNS has reviewed this evaluation, considers it applicable to NMP1, and concurs with the assessment based on the plant-specific PRA.

==

Conclusion:==

Since the screening criteria have not been satisfied, the control rod withdrawal block LCO and SRs applicable to the SDV water level scram bypass instrumentation may be removed from TS Table 3/4.6.2g and relocated to the NMP1 UFSAR, a licensee-controlled document.

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Analysis The proposed changes to the Technical Specifications (TSs) would establish an operating cycle (24-month) calibration surveillance frequency for the Intermediate Range Monitor (IRM) instrumentation, which would replace the current "prior to startup and normal shutdown" surveillance requirement. The proposed changes also include associated conforming changes. In addition, it is proposed to relocate the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) for selected control rod withdrawal block instrumentation to the Nine Mile Point Unit 1 (NMP1) Updated Final Safety Analysis Report (UFSAR), a licensee-controlled document. The TS Bases will be revised to reflect the proposed changes to the TSs.

Nine Mile Point Nuclear Station, LLC, (NMPNS) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing Page 20 of 23

on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1.

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response

No.

The proposed changes are limited to: (1) establishing a 24-month calibration frequency for the IRM instrumentation in lieu of the current "prior to startup and normal shutdown" requirement and incorporating the associated conforming changes, and (2) the relocation of certain instrumentation requirements from the TSs that do not satisfy the screening criteria for retention in the TSs. The proposed changes do not introduce any new modes of plant operation, make any physical changes to the plant, or alter any operational setpoints in a manner which could degrade the performance of, or increase the challenges to, any safety system assumed to function in the accident analysis. In addition, evaluations of the proposed changes pursuant to NRC and industry guidance demonstrate that the availability and reliability of equipment and systems required to prevent or mitigate the radiological consequences of an accident are not significantly affected. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response

No.

The proposed changes establish a 24-month IRM calibration frequency in lieu of the current "prior to startup and normal shutdown" requirement and relocate certain instrumentation requirements to the UFSAR. As such, the proposed changes do not eliminate any requirements or impose any new requirements, and adequate controls of existing requirements are maintained. Furthermore, since the proposed changes do not make any physical changes to the plant, no new accident initiators or failure mechanisms are introduced, and the accident assumptions and initial conditions will remain unchanged. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident evaluated.

3.

Does the proposed change involve a significant reduction in a margin of safety?

Response

No.

The proposed changes establish a 24-month IRM calibration frequency in lieu of the current "prior to startup and normal shutdown" requirement and relocate certain instrumentation requirements to the UFSAR. Although the proposed changes result in changes to surveillance intervals, the impact, if any, on system availability is small based on (1) other more frequent testing that is performed, (2)

Page 21 of 23

the existence of redundant equipment, and (3) overall system reliability.

Consistent with the findings of previous industry evaluations, the NMP1 plant-specific analyses have shown no evidence of time-dependent failures that would impact the availability of the affected systems. Furthermore, plant-specific evaluations and the adoption of the calculated IRM setpoint Allowable Values ensure that the setpoint margins are maintained for a 24-month (30-month maximum) calibration frequency. The proposed relocated requirements are consistent with the Improved Standard TSs (NUREG-1433 and NUREG-1434) and 10 CFR 50.36, and will be maintained in accordance with 10 CFR 50.59.

Accordingly, the proposed changes will have no significant impact on the condition or performance of structures, systems, and components relied upon for accident mitigation. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above, NMPNS concludes that the proposed amendment presents no significant hazards considerations under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

5.2 Applicable Regulatory Requirements/Criteria The following documents contain the regulatory requirements and guidance criteria used to evaluate the acceptability of this proposed license amendment:

10 CFR 50.36, "Technical specifications"

• NRC "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors [58 FR 39132 (07/22/93)]"

• NUREG-1433, "Standard Technical Specifications - General Electric Plants, BWR/4," Revision 2

• NUREG-1434, "Standard Technical Specifications - General Electric Plants, BWR/6," Revision 2

• GL 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," April 2, 1991

• RG 1.105, "Setpoints for Safety-Related Instrumentation," Revision 3, December 1999

• NEDC-30851P-A, 'Technical Specification Improvement Analyses for BWR Reactor Protection System," March 1988, and Supplement 1, October 1988

• NEDC-31336P-A, "General Electric Instrument Setpoint Methodology," September 1996

• NEDO-23842, "Continuous Control Rod Withdrawal Transient in the Startup Range," April 18, 1978

• NEDO-31466, "Technical Specification Screening Criteria Application and Risk Assessment," November 1987, and Supplement 1, February 1990

• EPRI Report TR-103335, "Guidelines for Instrument Calibration Extension/Reduction," Revision 1, October 1998

• NMP1 License Amendment No. 153 and NRC Safety Evaluation (TAC No.

M89981), March 3, 1995 Page 22 of 23

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.3 Commitments The following table identifies those actions committed to by NMPNS in this document.

Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

REGULATORY COMMITMENTS Due Date/Event (1.) NMPNS will enhance the existing NMP1 surveillance Concurrent with program to include monitoring and assessing the effects of the 24-implementation of TS month (30-month maximum) IRM calibration frequency on amendment.

instrument drift and its effect on safety.

(2.) Relocate the Control Rod Withdrawal Block LCOs and SRs Concurrent with for the following TS Table 3/4.6.2g instrument parameters to the implementation of TS UFSAR:

amendment

1. SRM Detector not in Startup Position, Inoperative, and Upscale Parameters.

2. Recirculation Flow Comparator Off Normal, Flow Unit Inoperative, and Flow Unit Upscale Parameters.

3. Scram Dump Volume Water Level Scram Bypass Parameter.

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement.

However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

Page 23 of 23

ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)

The current versions of Technical Specification pages 202, 203, 226, and 228 through 233 have been marked-up by hand to reflect the proposed changes.

TABLE 4.6.2a (cont'd)

INSTRUMENTATION THAT INITIATES SCRAM Surveillance Regiflrement Instrument Sensor-Check Channel Test None Once during each major refueling outage Parameter (8)

Shutdown Position of Reactor Mode Switch (9)

Neutron Flux (a) IRM (i)

Upscale

{ii)

Inoperative (b) APRM (i)

Upscale (ii)

Inoperative (10) Turbine Stop Valve Closure (11) Generator Load Rejection Instrument

'Channel Calibration None.

1



ZLr 4IdLk None None None None Once per 3 months Once per weeklm)

Once per 3 months7 l

Once per 3 months Nona Once per 3 months Once per operating cycle Once per 3 months Once per 3 months AMENDMENT NO. IW, 1 202

NOTES FOR TABLES 3.6.2a and 4.6.2a (a)

May be bypassed when necessary for containment inerting.

(b)

May be bypassed in the refuel and shutdown positions of the reactor mode switch with a keylock switch.

(c)

May be bypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi, or for the purpose of performing reactor coolant system pressure testing andlor control rod scram time testing with the reactor mode switch in the refuel position.

(d)

No more than one of tHe four IRM inputs to each trip system shall be bypassed.

(e)

No more than two C or D level LPRM inputs to an APnM shall be bypassed and only four LPRM Inputs to an APRM shall be bypassed in order for the APRM to be considered operable. No more than one of the four APRM inputs to each trip system shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed. A Traversing In-Core Probe (TIP) chamber may be used as a substitute APRM input If the TIP is positioned in close proximity to the failed LPRM it is replacing.

If) alibrate prig( to startup nd normal sh tdown and t reafter checy once per Gift and te once per/yeek unt'lno long r requyled.

l (g) erify SRM/IRM channels overlap during startup after the mode switch has been placed in startup. Verify IRMIAPRM channels overlap r-!Ry at least 112 decade during entry into startup from run (normal shutdown) If not performed within the previous 7 days.

(h)

Each of the four isolation valves has two limit switches. Each limit switch provides input to one of two instrument channels in a single trip system.

(i)

May be bypassed when reactor power level is below 45%.

QI) Trip upon loss of oil pressure to the acceleration relay.

(k)

May be bypassed when placing the reactor mode switch in the SHUTDOWN position and all control rods are fully inserted.

(I)

Only the, trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2a, the primary sensor will be calibrated and tested once per operating cycle.

(m)

This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when THERMAL POWER 2 25% of RATED THERMAL POWER. Adjust the APRM channel if the difference is greater than +2.01-1.9% of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 2.1.2a shall not be included in determining the difference.

8t)

ALfuLro" IL&-tars drL ewr tfJd.l HLW;4hM 24 hourU

-LAOLS rUitup a

HOt/fr.

4 rI-b4LdWv;llfL4 LprLht;us 7 dSas. Mel rA4uirvtd LLp-rULfziv61 AMN lShaA bL14it$;L a

inO AW;.

scamp xer" ruo.

L 203 AMENDMENT NO.

203

TABLE 3.6.2g INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK LimitingCondition for Oneration Minimum No.

of Tripped or Operable Trip Systems Minimum No. of Operable Instrument Channels per Operable

--Trip SYstem (I)-

• Reactor Mode Switch Position In Which Function Must Be Onerable Parameter Set Point C

0:3 r-a U)

,0cc U)

(1)

.1rA-RR-4

I a.

Detec r not in Sta p Position b.. Inoprative

c.

Mpscale 2

2 2

21) 2(a) 1

/t

,s 105 cqG~nts/sec x

x

. x I

I (2)

IRM

a. -Detector not in Startup Position

b.

Inoperative AMENDMENT NO.442 2

2 3(b) x x

3(b) x x

226

TABLE 3.6.2g (cont'd)

INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Limiting Condition for Overatlon Minimum No.

of Tripped or

'Operable Trip Systems Minimum No. of Operable Instrument Channels per Operable Trip System Reactor Mode Switch Position In Which Function Must Be Operable Pararnmeter Set Point C

0

4.

i 4-0cc in C

cc (4)

(5)

Refuel Platform and Hoists (6)

Mode Switch in Shutdown 2(f) 1

. 1 1

x x

AMENDMENT NO.4422 228

TABLE 3.6.2g (cont'd)

INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Limiting Condition for OQeration Minimum No.

of Tripped or Operable Trio Systems Minimum No. of Operable Instrument Channels per Operable Trir System Reactor Mode Switch

• Position In Which Function Must Be Ooerablo Set Point C

0

.cn 0.

.4-C cr

17)

Mode Switch in Refuel (Blocks withdrawal of more than 1 rod) 1 1

x 1()

Scrnm Dump olume W er Level St l

am Bypasse

-2"a

/2

/

1/

/

-*1

/

x

/x1 I

AMENDMENT NO.4422 229

TABLE 4.6.2g INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Reguirement Instrument Channel Test Instrument Channel Calibration Sensor Check (1)

SRM a./

(.2 i (2)

IRM

a.

Detector not in Startup Position

b.

Inoperative

c.

Downscale

d.

Upscale N/A N/A N/A N/A N/A N/A lDn"at:LA pa

~ra4;14 ttr-I i) 1 AMENDMENT NO. 442 230

TABLE 4.6.2g (conted)

INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Reauirement Instrument Channel Test (3)

(4)

Parameter APRM

a. Inoperative

b.

Upscale {Biased by Recirculation Flow)

c.

Downscale R circulation low/.

/.ComparatoKf/

Normalg

b.

Flow Ji/

Iopn ative

c.

Fl Unit Upscal nsor Check None None Once per 3 months Once per 3 months Instrument Channel Calibration None

• Once per 3 months i

Once per 3 months None

-DI4-- 1 Once per 3 months None No None I

Once per months Onc per 3 month nce per 3 ths

/ Once pea3 months Onc per 3 mont nce per 3 mr nths

, I AMENDMENT NO. 1442 231

TABLE 4.6.2g (cont'dJ INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Requirement Parameter Sensor Check Instrument Channel Test Instrument Channel Calibration (5)

Refuel Platform and Hoists (see 4.5.2)

Once during each major refueling outage

-i..

(6)

Mode Switch in Shutdown I

(7)

Mode Switch in Refuel (Blocks withdrawal of more than 1 rod)

Once during each major refueling outage (8) i ScramrDum A/4volumeW~er La Scra ass

/

-__/

/

Once durin each major. /

/

refuelyin outage

/

/

3 Fel AMENDMENT NO. 442-232

NOTES FOR TABLES 3.6.2g and 4.6.2g (a) l[6 moreffian o e of tho four MM inpts to to single/trip sy tem solI be a ed.

3 l

(b)

No more than one of the four IRM inputs to each instrument channel shall be bypassed. These signals may be bypassed when the APRMs are onscale.

Cc)

No more than one of the four APRM Inputs to each Instrument channel shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed. No more than two C or D level LPRM inputs to an APRM shall be bypassed. and only four LPRM inputs to only one APRM shall be bypassed in order for the APRM to be considered operable. In the Run mode of operation, bypass of two chambers from one radial core location in any one APRM shall cause that APRM to be considered Inoperative. A Travelling In-Core Probe (TIP) chamber may be used as a substitute APRM input If the TIP is positlohed in close proximity to the failed LPRM it Is replacing. If one APRM In a quadrant is bypassed and meets all requirements for operability with the exception of the requirement of at least one operable chamber at each radial location, it may be returned to service and the other APRM in that quadrant may be removed from service for test and/or calibration only If no control rod is withdrawn during the calibration and/or test.

(d)

May be bypassed In the startup and refuel positions of the reactor mode switch when the IRMs are onscale.

(e)

Thi /functniOn maybe by asse whor/the cgnt raj Is W100 0

S.<

3l (f)

One sensor provides input to each of two Instrument channels. Each instrument channel Is in a separate trip system.

(g) alibr te andl/r test pr 6r to stq tup and ormal shtdown. Yhereafter test one per w ek until o londr re u iead.l (h)

The actuation of either or both trip systems will result In a rod block.

li)

A channel may be placed in an Inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the Trip System In the tripped condition, provided at least one other operable channel In the same Trip System is monitoring that Parameter.

_i )

H/tu4rond

,JdL-do ar L 4t-

'rXds.

I l

k)J;44i~n 2L1ha~urs kaAIL#OVL S~a V*AP

1-bMbtP4v-f2r4&llL Wds4 Wtpt/Pr;OUS 7&d[. -Jb ua;se-o1A ~La.pSPrLa4Iau r;ws AMENDMENT NO.442-2 233

ATTACHMENT 3 TECHNICAL SPECIFICATION BASES CHANGES (MARK-UP)

(FOR INFORMATION ONLY)

The current versions of Technical Specification Bases pages 251 through 254 have been marked-up by hand to reflect the proposed changes. These Bases pages are provided for information only and do not require NRC issuance.

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION The set points on the generator load rejection and turbine stop valve closure scram trips are set to anticipate and minimize the consequences of turbine trip with failure of the turbine bypass system as described in the bases for Specification 2.1.2. Since the severity of the transients is dependent on the reactor operating power level, bypassing' of the scrams below the specified power level is permissible.

Although the operator will set the setpoints at the values indicated in Tables 3.6.2.a-1, the actual values of the various set points can differ appreciably from the value the operator is attempting to set. The deviations include inherent instrument error, operator setting error and drift of the set point. These errors are compensated for in the transient analyses by conservatism in the controlling parameter assumptions as discussed in the bases for Specification 2.1.2. The deviations associated with the set points for the safety systems used to mitigate accidents have negligible effect on the Initiation of these systems. These safety systems have initiation times which are orders of magnitude greater than the difference in time between reaching the nominal set point and the worst set point due -to error. The maximum allowable set point deviations are listed below:

Neutron Flux JljdM The APRM scram and rod block setpoints have been derived based on GE setpoint methodology as outlined in NEDC-31336, "GE Instrumentation Setpoint Methodology."

In this methodology, the setpoints are defined as three values, Nominal Trip Setpoints,'

Allowable Values, and Analytical Limits. Theranalytical limits are listed in Specification 2.1.2a Therallowable values are listed below:

The minimum of:

For W ; 0°%:

S s (0.55W + 64.46%) T with a maximum value of 1 19.5%

San.

( 40.55W + 59.46%) T with a maximum value of 114.5%

AND:

For 14.42% %6 W s 45%:,

S s (1.287W + 16'6%)

Sag -

(1.287W + 9.312%)

WHERE:

S or SI = The respective scram or rod block allowable value W = Loop Recirculation Flow as a percentage of the loop recirculation flow which produces a rated core flow of 67.5 MLB/HnI T = FRTP/CMFLPD (T is applied only if less than or equal to 1.0)

FRTP = Fraction of Rated Thermal Power where Rated Thermal Power equals 1850 MW CMFLPD = Core Maximum Fraction of Limiting Power Density InM 2.5W orate ne ron Yux AMN N

N.

ES 3/4.IA. 2 DAI4EP AMENDMENT NO.

dl.v l9a4st 251

BASES 3/4.6.2 INSERT IRM Upscale Scram, allowable value is < [121.55/125] divisions of full scale IRM Upscale Rod Block, allowable value is < [114.2/125] divisions of full scale IRM Downscale Rod block, allowable value is 2 [5.61/125] divisions of full scale

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION The APRM downscale rod block setpoint has been derived based on GE setpoint methodology as outlined in NEDC-31336, "GE Instrumentation Setpoint Methodology.'

In this methodology, the setpoint is defined as three values. Nominal Trip Setpoint, Allowable Value, and Analytical Limit. Table 3.6.2g shows the nominal trip setpoints. The corresponding allowable value is as follows:

APRM Downscale Rod Block, allowable value is >l4.2411251 divisions of full scale IRecifculation plow Upsaleo, *1.$% of raled recircto tion flow/ lanalytikfl limit is/107.10/6/of ratepflow)'

1R1,6irculatiof Flow Coyhparator./+/- 2.09,% of rated fecirculatidhn flow (fflalytical/imit is 10% flov/differe!AiaI)J Reactor Pressure, i 15.8 psig Containment Pressure +/- 0.053 psig Reactor Water Level, +/- 2.6 inches of water Main Steam Line Isolation Valve Position, +/-2.5% of stem position Scram Discharge Volume, +0 and -1 gallon Condenser Low Vacuum, +/- 0.5 inches of mercury AMENDMENT NO. 4t 251a

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION High Flow-Main Steam Line, +/- 1 psid High Flow-Emergency Cooling Line, i 1 psid High Area Temperature-Main Steam Line, +/- 10'F High Area Temperature-Clean-up and Shutdown, +/- 6 OF High Radiation-Main Steam Line, + 100 % and -50% of set point value High Radiation-Reactor Building Vent, + 100% and -50% of set point I

DIW High Radiation-Refueling Platform, +100% and -50%/a of set point Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System,"l'MDE-77-0485, "Technical Specification Improvement Analysis for Nine Mile Point Nuclear Station, Unit 1r" l,

A dd 6L&muc._Lambt.~- 91-04, " ch Ls,'

S t6-f~a4ow 2Sgr,.li -I

.uu~a t

AIzdt-4Mou4A SU/t/~

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851 P-A.

Suppl2,."Technical Specification Improvement Analyses for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," and.

with NEDC-31 677P-A, "Technical Specification Improvement Analyses for BWR Isolation Actuation Instrumentation." Because of local high radiation, testing instrumentation in the area of the main steam line isolation valves can only be done during periods of Station shutdown. These functions include high area temperature isolation and isolation valve position scram.

AMENDMENT NO.

76 252

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P-A, "BWR Owners' Group Technical Specification Improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation),* Parts 1 and 2 and RE-003, 'Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Nine Mile Point Nuclear Station, Unit 1."

Specified surveillance Intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented In the SER (letter to R. D. Binz IV from C. E. Rossi dated July 21, 1992).

Testing of the scram associated with the shutdown position of the mode switch can be done only during periods of Station shutdown since it always involves a scram.

b.

The controlrod block functions are provided to prevent excessive control rod withdrawal so that MCPR Is maintained greater than the SLCPR. The trip logic fori fuy ctfon 1 out of n; e.g., any trip on one of the eight APRM's, eight IRM's or four SRM's will result in a rod block. The minimum instrument channel requirements provide sufficient instrumentation to assure the single failure criteria is met. Specified surveillance Intervals and surveillance and maintenance outage times have'been determined in accordance with NEDC-30851 P-A Suppl 1, "Technical Specification Improvement Analyses for BWR Control Rod Block Instrumentation," @1 l

Ii1GENE-770-06-1, 'Bases for Changes to Surveillance'Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R. D. Binz IV from C. E.

Rossi dated July 21, 1 992)%

JG.A 91-6q/ t_ "-hnk s im Todl1-.;..

& 745&1

.e*b Lavial /s l Act4ryarM.+r1 The APRM rod block trip Is flow biased and prevents a significant reduction in MCPR especially during operation at reduced flow.

The APRM provides gross core protection; Le.. limits the gross core power Increase from withdrawal of control rods In the'normal withdrawal sequence. The trips are set so that MCPR is maintained greater than the SLCPR.

The APRM rod block also provides local protection of the core; i.e., the prevention of critical heat flux in a local region of the core, for a single rod withdrawal error from a limiting control rod pattern. The trip point is flow biased. The worst case single control rod withdrawal error has been analyzed and the results show that with the specified trip settings rod. withdrawal is blocked before the MCPR reaches the SLCPR, thus allowing adequate margin. Below - 60% power the worst case withdrawal of 'a single control rod results in a MCPR > SLCPR without rod block action, thus below this level it is not required..

The IRM rod block function provides local as well as gross core protection. The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level. Analysis of the worst case accident results in rod block action before MCPR approaches the SLCPR.

AMENDMENT NO. 442-2'53

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION A downscale indication on an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough. In either case the instrument will not respond to changes in control rod motion and the control rod motion is prevented. The downscale rod blocks are set at 5 percent of full scale for IRM and J.pjJ of full scale for APRM (APRM signal is generated by averaging the output signals from eight LPRM flux monitors).

AMENDMENT NO. 442 254

ATTACHMENT 4 NUCLEAR ENGINEERING REPORT NO. NER-1I-002, "SRM/IRM CALIBRATION DATA ANALYSIS"

Constellation Nuclear Nine Mile Point Unit 1 Nuclear Engineering Report Tale:

SRM/IRM Calibration Data Analysis Report Number NER-1 1-002 Rev Number 0 Prepared By:

George K. Bochosian Date:

03/13/04 Reviewed or Design Verified By Approved By:

A.

aim A//,&C Date:

.//5/4 Date:

//

iP Remarks:

Page 1 NEP-DES-02 Rev 05

Report Number: NER-1 1-002 Rev Number:

0 Table of Contents Page Purpose Design Inputs Evaluation Criteria and Assumptions Methodology Results and Conclusions References 3

3 3

3 3

3 Page 2 NEP-DES-02 Rev 05

1.0 PURPOSE The purpose of this NER is to perform a statistically based drift calculation based on actual SRMIIRM calibration data. The data from this calculation will be used to prepare another calculation for SRM/IRM setpoint impacts for increased surveillance intervals. The results will be used to justify in a License Amendment a change to the calibration frequency of the SRMWIRM's.

2.0 DESIGN INPUTS The design inputs to the drift calculation were extracted from past surveillances for the SRMWIRM's.

The data was provided to Alion Science and Technology for preparation of this calculation.

3.0 EVALUATION CRITERIA AND ASSUMPTIONS The evaluation criteria and assumptions are detailed in the attached calculation.

4.0 METHODOLOGY The methodology used is detailed in the attached calculation.

5.0 RESULTS AND CONCLUSIONS Results and conclusions are detailed in the attached calculation.

6.0 REFERENCES

References are provided in the attached calculation.

Page 3 NEP-DES-02 Rev 05

6000 Uptown Blvd, NE, Suite 300 Albuquerque, NM 87110 A L I O N tel: 505.872.1089 fax: 505.872.0233 SCIENCE AND TECHNOLOGY www.alionscience.com March 3, 2004 Mr. Ed Riskosky Constellation Nuclear Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093

Subject:

Analysis and Recommendation to Extend SRM/IRM Calibration Frequency, Rev. 1

Dear Mr. Riskosky,

Alion Science and Technology Corporation (Alion), formally Innovative Technology Solutions Corporation (ITSC), is pleased to submit this report to document the analysis of SRM/IRM drift data and the subsequent recommendation from the analysis of SRM/IRM clearly indicates that the instrument performance will support 24 month calibration intervals (or 30 months including the 25%

grace period).

This submittal completes task 6 of ITSC proposal NMPNS 02-PROP-03-028-00-000 Rev. 2 dated August 12, 2003. Alion appreciates the opportunity to work with NMPNS. If you have any technical questions or concerns, please contact me at (505) 872-1089 or Andy Krinzman at (860) 235-5358.

Sincerely, Donald F. Lincoln Director, Commercial Utility Programs cc:

A. Krinzman M. Coffing

Alion Science and Technology SRM/IRM Calibration Data Analysis

References:

1. "Probability and Statistics for Engineers", Irwin Miller and John Freund, Prentice-Hall 1965.

2. Generic Letter (GL) 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle."

3. Calculation VYC-2236 Rev 0, "Drift Calculation for Intermediate Range Monitors", Vermont Yankee Nuclear Power Station.

4. EPRI Report TR-1 03335 Rev. 1, "Guidelines for Instrument Calibration Extension/Reduction Programs."

5. GE-NE-909-002-0294 (DRF No. C51-00106), "General Electric Company: Impacts On SRM/IRM Due To Increasing The Surveillance Intervals For Niagara Mohawk Power Company Nine Mile Point Unit One."

6. Nl-ISP-092-101 R1, "Source Range Monitor Instrument Calibration."

7. Nl-ISP-092-204 R4, "Intermediate Range Monitor Calibration."

8. Nl-ISP-092-205 R5, "Intermediate Range Monitor calibration."

9. Correspondence from USNRC to Mr. R. W. James, EPRI, Dated December 1, 1997, "Status Report on the Staff Review of EPRI Technical Report TR-1 03335, "Guidelines for Instrument Calibration Extension/Reduction Programs," Dated March 1994."

==

Introduction:==

This letter describes the analysis of Nine Mile Point I SRM and IRM calibration data for the purpose of a License Amendment Request to change the calibration frequency for the SRM/IRM instruments.

The methodology for the analysis of drift generally follows the guidance of GL 91 - 04 (Reference 2) in that it uses the analysis of instrument calibration data to determine statistically based drift.

The analysis specifics are based on Reference 4 and are consistent with the methods other utilities have used (See Reference 3). Typically previous As-Left calibration data is subtracted from current As-Found data to yield a drift data point. The data is then analyzed statistically to determine its standard deviation which is taken as drift. In this SRM/IRM analysis the traditional drift analysis was done as well as an Instrument Resetting Evaluation which is addressed in Reference 9. In that Reference the NRC expressed no concerns about the use of an Instrument Resetting Evaluation, as long as the data does not overlap, or as long as the constructed longer interval data is not used in conjunction with the shorter interval data used to construct the longer intervals. In the Instrument Resetting Evaluation Longer calibration periods were constructed from existing data by ignoring calibrations where the As-Found and As-Left information is identical, in other words, the instruments were not adjusted during calibration. This approach results in calibration periods as long as three years for the Nine Mile Point 1 SRMWIRM instruments. The drift values were examined for statistical outliers using the method described in section 7.2 of Reference 4. From the final drift data a statistical 1.96 sigma drift (for cases of two-sided safety concern) or 1.645 sigma drift (for cases of single-sided safety concern) was calculated. The statistically determined drift can be combined by square-root-sum-of-squares (SRSS) with other appropriate errors when the instrument uncertainty is calculated as in Reference 5.

A regression of drift with time is performed to determine the time dependency of the drift when the calibration data does not include periods sufficiently long in time to cover the desired change in Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 2 of I 1

Alion Science and Technology calibration frequency. For both the SRM and IRM instruments the Resetting Evaluation resulted in calibration time periods in excess of the desired calibration frequency, therefore the regression was not performed but plots of drift with calibration interval were used to determine whether there existed a strong correlation of drift with time.

Normality tests were not performed on the drift data. A data coverage technique was used for the Resetting Evaluation (described in Reference 4 and in paragraph 5.3 of Reference 3). This technique is applied by counting the number of drift data points that fall within the two a value of the drift. The estimate of a is considered conservative when the proportion of data covered is as expected (about 95%).

SRM Analysis:

Calibration data based on Reference 6 was gathered and analyzed for statistical drift. Data from the period 3/30/1996 to 3/11/2003 was included in the analysis. The As-Left condition from the previous calibration was subtracted from the As-Found condition of the latter calibration to create a drift data point. The points were pooled for each function or amplifier range and then the Excel functions for count, average (mean), and sample standard deviation was determined. Population standard deviation at 95% confidence was determined by applying a two-sided tolerance interval factor from Table XII of Reference 1. The 1.96 or 1.645 sigma values were then determined by multiplication of the population a. This was performed for the determination of trip or comparator unit drift and SRM pre-amplifier and amplifier drift (combined).

The outlier approach used was from Reference 4 and is based on the Critical Values for t-Test. This approach has been used by others (see Reference 3). This common approach identifies data that deviates from the sample statistics at the 5% level of significance. Therefore, there is at most a 5%

chance that an outlier is a good data point. One statistical outlier was identified and removed from each of the data sets for the Rod Block and Hi-Hi Trip functions. The traditional statistical results for SRM Trips are shown in the Table below.

SRM Trip Drift Population Results After Sample Std dev 1.645 One Outlier Count Mean Std Dev 95% Conf Sigma Hi Rod Blk Trip CPS 30 1171 5090 6620 10889 Hi Hi SCRAM CPS 30 1 6570 22570 29353 48286 Downscale Trip CPS 31

-0.063 0.299 0.389 0.640 Note: The drift results from 04/27/98 for EACH SRM are ignored. SRM 12 was not calibrated on 4/27/98 because the instrument was inoperable. The calibration data on 4/27/98 for the other SRMs indicates a change in ideal AF/AL for the INOP trip prior to the 4/27/98 calibration date. This indicates a calibration change before 4/27/98, therefore the drift resulting from the calibration prior to and including the 4/27/98 data is ignored for all SRM instruments.

The longest calibration period for the above data was 421 days. To extend the calibration frequency the Resetting Evaluation was also performed. Because of the smaller number of data points resulting from this evaluation, no outliers were allowed. This evaluation has results as shown in the Table Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 3 of 11

I

)

Alion Science and Technology below. The Table shows errors for both the SRM Trips and Amplifier. For reference, the longest resulting calibration interval is shown.

Max Cal SRM EXT Drift Sample Std Population Std Interval -

Results Count Mean Dev dev 95% Conf 1.645 Sigma Days Downscale Trip CPS 21

-0.007 0.330 0.463 0.761 1159 Rod Block CPS 21 292 11554 16223 26687 1159 Hi Hi Trip CPS 21 8671 27918 39199 64482 1159 104 ' Amplifier Volts 19

-0.0003 0.0030 0.0042 0.0069 1129 105' Amplifier Volts 19

-0.0005 0.0042 0.0060 0.0099 1129 10 ' Amplifier Volts 19

-0.0008 0.0048 0.0068 0.0111 1129 As expected, the estimated drift a is larger in the Resetting Evaluation and the longest calibration interval is beyond three years. The data coverage, by the estimated a is about 95% or better. The data points not covered by the two a estimate would have been identified as outliers had outlier criteria been applied. Since the proportion covered is still near 95%, the drift estimate is conservative.

Note that the drift means should be applied as a bias when they are in the non-conservative direction.

The Resetting Evaluation drift data can be used to calculate the random drift error in the SRM Technical Specification functions using SRM scaling of:

Volts=117*LOG1 0(CPS)+0.143, and CPS=1 0A((Volts_0.1 43)*7).

l CPS I

Volts J%ELFS jGE Value Rod Block l

90000 0.851 Upscale Trip 500000 0.957 Amplifier Drift Voltage error:

7 0.0111 7 1

Amplifier Error at Rod Block:

14753 0.860 0.942%

1.63%

Amplifier Error at Upscale Trip:

81962 0.967 0.942%

1.63%

Trip drift error at Rod Block 26687 0.867 1.611%

1.15%

Trip drift error at Upscale Trip 64482 0.965 0.753%

1.15%

Total Drift error for Rod Block:

30493 0.869 1.81%

Total Drift error for Upscale Trip:

104287 0.969 1.18%

The combined drift for SRM Rod Block, Hi-Hi trip and amplifier are shown in bold in the Table. The drifts were plotted against calibration interval to determine whether there is a correlation between time and the magnitude of drift. The majority of analyses done in the US and Canada have resulted in little or no correlation between time and drift. The graphs for the SRM illustrate that apparent drift can actually decrease with time when no outliers are removed. It is reasonable to say that SRM drifts are relatively independent of time.

Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 4 of 11

Alion Science and Technology Trip & Rod Block Drift with Time 60000 40000 U,,

20000 a.o 0

.S

-20000

.r

-40000 D

-60000

-80000

-100000 v

A a A --

A A.

NA to f

________-2 A

I I

• Rod Block Drift A Hi Hi Trip Drift 0

500 1000 1500 Calibration Interval - Days SRM Extended Amplifier Drift 0.01 -

0.005 -

_ -1

-~--

V

• 10A4 Calib Point

-0.005 a

10'5 Calib Point 0>

-0.01

-Al_

OA 10A6 Calib PointS

-0.015

-0.02 0

200 400 600 800 1000 1200 Calibration Interval - Days Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract COl Page 5 of 1 1 Page 5 of 11 Go

Alion Science and Technology IRM Analysis:

Calibration data based on References 7 and 8 was gathered and analyzed for statistical drift. Data from the period 4/11/94 to 4/19/2003 was included in the analysis. The IRM trip functions of Rod Block, Upscale trip, INOP Trip and DC amplifier zero drift were determined. IRM preamplifier drift analysis is not necessary at Nine Mile Point 1 for reasons similar to those at Vermont Yankee as described in Reference 3 on page 8. The As-Left condition from the previous calibration was subtracted from the As-Found condition of the latter calibration to create a drift data point. The points were pooled for each function and then the Excel functions for count, average (mean), and sample standard deviation were determined. Population standard deviation at 95% confidence was determined by applying a two-sided tolerance interval factor from Table XII from Reference 1. The 1.96 or 1.645 sigma values were then determined by multiplication of the population a. This was performed for the determination of trip or comparator unit drift and IRM amplifier zero amplifier drift.

The outlier approach used was from Reference 4 and is based on the Critical Values for t-Test at the 5% level of significance. Three statistical outliers were identified and removed from the drift data (the raw data set had 157 points). Three outliers are reasonable in light that they represent a proportion of just 2% of the original data (98% of the original data was retained). The application of the method was modified such that just one round of outlier processing was allowed for the data sets. The statistical results for IRM Trip and DC amplifier zero functions are shown in the Table below.

Population IRM Summary After Sample Sigma 1.96 1st Outlier Count Mean Sigma

@95% Conf Sigma Amp Zero 1

% Span 155

-0.002%

0.058%

0.0639%

0.125%

Amp Zero 2

% Span 156 0.0002%

0.162%

0.180%

0.353%

Rod Block

% Span 155 0.048%

0.551%

0.61%

1.20%

Upscale Trip

% Span 156 0.049%

0.531%

0.59%

1.15%

IRM Downscale - % Sp 157

-0.005%

0.137%

0.15%

0.30%

INOP Trip Volts 154 0.035 0.661 1

0.732 1.204 The longest calibration period in the above data was 431 days. To extend the calibration frequency the Resetting Evaluation was also performed. One round of the outlier tool was applied to this data.

One statistical outlier was identified and removed from the Amp Zeroes and INOP trip functions (see Table after IRM Summary EXT Table). The one outlier removed from this data is reasonable when viewed as a small proportion of the data for each function. No outliers were identified or removed from the Rod Block, Upscale or Downscale trip functions. This evaluation has results as shown in the Table below with values to be used in the Nine Mile Point 1 setpoint calculation identified in bold.

Population Max Cal Sample Sigma 1.96 Interval -

IRM Summary - EXT Count Mean Sigma

@95% Conf Sigma Days Amp Zero 1

% Span 60 0.001%

0.084%

0.100%

0.197%

1523 Amp Zero 2

% Span 60 0.009%

0.216%

0.257%

0.503%

1523 Rod Block

% Span 40 0.118%

0.656%

0.819%

1.605%

1385 Upscale Trip

% Span 40 0.140%

0.607%

0.757%

1.484%

1385 IRM Downscale % Sp 40

-0.020%

0.167%

0.208%

0.408%

1385 INOP Trip Volts 35 6.9E-02 0.707 0.916 2.121 1497 Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 6 of 1 1

Alion Science and Technology Function Data Outlier Criteria Outlier Data Count Point Amp Zero 1 61 37.123 mVdc 67.5 mVdc Amp Zero 2 61 72.625 mVdc 75.4 mVdc INOP Trip 36 3.118 Volts 4.290 Volts As expected, the estimated drift a is larger in the Resetting Evaluation and the longest calibration points not covered by the two a estimate would have been identified as outliers had outlier criteria been applied. Since the proportion covered is still better than 95%, the drift estimate is conservative.

The drift values from the Table can be combined by square root sum of squares to determine a total random drift. The drift means that are greater than 0.05% of span should also be applied in the non-conservative direction. The total random and bias error due to drift for the extended calibration interval is:

DT = SQRT(D 2zero 1 + D2zero 2 + D2Trip) + Bias The graphs of the DC Amplifier zero and trip functions are very similar to the SRM graphs. The drift for IRM trips and DC amplifier zero were plotted against calibration interval to determine whether there is a correlation between time and the magnitude of drift. The graphs for the IRM are shown below and on the succeeding page. The graphs illustrate that IRM trip and DC amplifier zero drift is relatively independent of time.

DC Amplifier Zero Drift 60 50 40 30 20 i

10 0

E -10

-20

-30

-40

-50 U

U A.

_U

• Zero 1 Drift l Zero 2 Drift 0

500 1000 1500 2000 Calibration Interval Days Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract C Q'z Page 7 of 11

Alion Science and Technology IRM Trip Drift 2.0% -

1.5%-

1.0%

0.5% -

• Rod Block X 0.0%

U-apscaleTrip u

-0.5% -

Downscale Trip

-1.0%

-1.5%- _

-2.0%-

0 500 1000 1500 Calibration Interval Days IRM INOP Trip Drift 2-1.5 -

0.5 -__

0z

• Senesi

-0.5

-1.5 0

500 1000 1500 2000 Calibration Interval Days Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page8of 11

..I......... _1111

Alion Science and Technology Comparison of Nine Mile Point 1 Drift & Calibration Data to the Criteria of GL 91-04 The following discussion provides a comparison of the evaluation of the calibration and drift data with the specific quoted guidance contained in GL 91-04.

1.

"Confirm that instrument drift as determined by as-found and as-left calibration data from surveillance and maintenance records has not, except on rare occasions, exceeded acceptable limits for a calibration interval."

The calibration data supplied as basis for this evaluation has been reviewed. The maintenance histories for the covered instruments have not been reviewed. The surveillance history for the instruments results in calibration data, which reflected that instrument drift, was beyond acceptable limits only on rare occasions. In fact the data indicate there was some small number of drift data that were Outliers (removed from the data set) and other drift data that were beyond the 95/95 drift values (not covered). Taken together the outliers and not covered data represent 5% or less of all the available data. An exception to the preceding statement is the INOP Trip that is discussed below. This information is summarized as follows:

SRM Count Outliers Coverage IRM Count Outliers Coverage 10A4 Amplifier 19 0

all Zero 1 60 1

-2 OA^5 Amplifier 19 0

all Zero 2 60 1

-1 10A6 Amplifier 19 0

-1 INOP 35 1

all Downscale 21 0

all Downscale 40 0

all Rod Block 21 0

-1 Rod Block 40 0

all Hi-Hi Trip 21 0

-1 Hi-Hi Trip 40 0

all Of particular note, because the proportion of outliers to total data is higher than all others, is the IRM 13 instrument INOP trip that had two outliers resulting from calibrations dated from 4/12/1994 to 3/2911996. First, the outliers were in the conservative direction (the INOP trip drifted high which is conservative) and second, the data since then for all IRM INOP trips has been within tolerance. Therefore the two outliers are not viewed as significant to safety or indication of a trend to failure with time.

2.

"Confirm that the values of drift for each instrument type (make, model, and range) and application have been determined with a high probability and a high degree of confidence.

Provide a summary of the methodology and assumptions used to determine the rate of instrument drift with time based upon historical plant calibration data."

Nine Mile Point 1 used a process consistent with good industry practice, and Reference 4, to statistically analyze instrument calibration data specific to each group of SRM/IRM functions.

The outlier criteria and Instrument Resetting Evaluations were analyzed to meet 95/95 acceptance criteria as defined in Regulatory Guide 1.105 Rev 3. When the Resetting Evaluation was done the intermediate (no adjustment) calibrations were discarded from the data sets which decreased the number of data points and increased the two-sided tolerance factors needed to achieve 95/95 drift values. The resulting 95/95 drift values have coverage of the data which meets or exceeds statistical expectation.

Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 9 of I 1

Alion Science and Technology

3.

"Confirm that the magnitude of instrument drift has been determined with a high probability and a high degree of confidence for a bounding calibration interval of 30 months for each instrument type (make, model number, and range) and application that performs a safety function. Provide a list of the channels by TS section that identifies these instrument applications."

This methodology considers the probability and confidence for the instrument drift associated with a potential maximum 30-month calibration interval. The Resetting Evaluation resulted in some calibration intervals in excess of three years. The list of the affected instrument channels will be provided later.

4.

"Confirm that a comparison of the projected instrument drift errors has been made with the values of drift used in the setpoint analysis. If this results in revised setpoints to accommodate larger drift errors, provide proposed TS changes to update trip setpoints. If the drift errors result in a revised safety analysis to support existing setpoints, provide a summary of the updated analysis conclusions to confirm that safety limits and safety analysis assumptions are not exceeded."

This will be provided by Nine Mile Point 1.

5.

"Confirm that the projected instrument errors caused by drift are acceptable for control of plant parameters to affect a safe shutdown with the associated instrumentation."

Nine Mile Point 1 will confirm that drift effects on plant setpoints will be resolved to satisfy Item

1. 4. Once that Item is met this Item #5 will also be satisfied.

6.

"Confirm that all conditions and assumptions of the setpoint and safety analyses have been checked and are appropriately reflected in the acceptance criteria of plant surveillance procedures for channel checks, channel functional tests, and channel calibrations."

Nine Mile Point 1 plant procedures and tests have been used as input to this calibration frequency evaluation. New acceptance criteria for plant surveillance procedures will be added to the existing procedures when the changes to calibration frequencies are approved. Nine Mile Point 1 will confirm, for items covered by this evaluation, that instrument drift and other errors, as well as assumptions of the analyses supporting the proposed surveillance extensions, are consistent with the acceptance criteria included in plant surveillance procedures. This review will include channel checks, channel functional tests, and the calibration of channels for which surveillance intervals are being increased.

7.

'Provide a summary description of the program for monitoring and assessing the effects of increased calibration surveillance intervals on instrument drift and its effect on safety."

Nine Mile Point 1 will provide a discussion of its drift monitoring program which is expected to be similar to the Nine Mile Point 2 program.

Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 10 of 11

114 Alion Science and Technology Summary:

SRM and IRM calibration data has been analyzed to determine the instruments statistically based drift values. The drift and As-Found data shown in graphs have magnitudes independent of the calibration interval with As-Found values that are normally within expected. The analysis of SRM/IRM calibration data clearly indicates that the instrument performance will support 24 month calibration intervals (or 30 months including the 25% grace period). A calibration isn't necessary before startup or shutdown as long as the SRM/IRM instruments are calibrated every 30 months. It is important to note that the panel checks and functional tests are required to support the future performance of the SRM/IRM instruments.

Use or disclosure of data is subject to the restrictions of the Terms and Conditions of this contract Page 11 of 11

ATTACHMENT 5 CALCULATION NO. SP-SRM/IRM-RG07/RH01, "SRM/IRM SETPOINT IMPACTS DUE TO INCREASING SURVEILLANCE INTERVALS"

INUCLEAR ENGINEERING CA C

L T O

Pg1(NxlAj I-ECALCULATION COVER SHEE l Total _ (Includes IA) 1; t;

t

ILast 14I Project: NIN`E MILE POINT NUCLEAR STATION Unit (1, 2 or O=Both) :1_

Discipline:

Instrumentation & Controls Title Calculation No.

SRMNIRM SETPOINT IMPACTS DUE TO INCREASING SP-SRM/IRM-RG07/RH01 SURVEILLANCE INTERVALS (Sub)system(s)

Building Floor Elev.

Index No.

092 TBI 277 E21 Originator(s)

G. BOGHOSIAN Reviewcr(s) / Approver(s)

F.J. CONSTANCE /U. BUIVA Eval., DER, or Prep'd Reviewed Rev Description Change No.

By Date By Date App Date 0

INITIAL ISSUE N/A GE 3/29/94 JJC 6/28/94 MLS 6/29/94 1

SEE PG. IA REMARKS

JCS, 4t13102 FJC 4/14/02 FJC 4/17/02 2

Incorporated Drift Data NER-1I-002 3/05/04 FJC 3/19/04 3/19/04 I.'_

£4

__t

_~e Computer Output/Microfilm Filed Separately (Yes I No / NA): NA Safety Class (SR / NSR I Qxx): SR Superseded Document(s) : REV I Document Cross Reference(s) - For additional references see page(s): For additional references see page(s) 13 and 14 Ref Doc No Document No.

Type Index Sheet Rev General Reference(s):

SEE CALCULATION SECTION 7.0 Remarks:

Confirmation Required (Yes / No): No Final Issue Status:

Turnover Required See Page(s) : N/A.

(APP, FIO COL, INA): APPI (Yes / N/A): N/A 10CFR50.59 Evaluation Number(s): N/A Component ID(s) (As shown in MEL):

Copy of Applicability Determination or 50.59 Screen Attached?

NAM-RHOIA, NAM-RHOIB. NAM-RHOIC, NAM-RHOID. NAM-RHOIE.

Yes 0 No E NAM-RHOI F. NAM-1RHOIG. NAM-RHOI H, NAM-RG07A. NAM-RG07B, NAM-RG07C AND NAM-RG07D.

Key Words: SRM, IRM, SOURCE RANGE MONITOR, INTERNIEDIATE RANGE MONITOR, SURVEILLANCE, FREQUENCY

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[NUCLEAR ENGINEERING CALCULATION CONTINUATION SHEET Page 1A I

(Next 2)

Project: Nine Mile Point Nuclear Station Unit: 1 Disposition: N/A Originator/Date Reviewer/Date Calculation No.

Revision G. Boghosian SP-SRMWIRM-RG07/RH01 02 Ref.

Revision Summary Revision Number Description 0

Initial Issue I

a)

Change Final Issue Status to INA b)

Reflect Correct Component ID's on page I

2.

Incorporated Plant Specific Drift Data from NER-I1-002. This calculation was originally prepared by GE and used generic drift data. This revision deleted the generic, non plant specific drift data and used drift data extracted from NMPNS Unit 1 Surveillance procedures (i.e. as-left/as-found values). Because plant specific drift data was used, the LER avoidance portion of the calculation was not significant to the final results. This revision also updated the calibration tolerance in Section 4.2 and incorporated plant specific setpoints.

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SP-SRM/l RM-RG07/RH01 Page of-Jf

1.0 INTRODUCTION

Currently the Nine Mile Point Nuclear Station Unit 1 (NMP1) operates at a fuel cycle of 24 months. Utilizing Actual Plant Specific Drift Data from NER 002 this calculation confirms that there are sufficient margins for implementing the 30-month surveillance on the SRM/IRM's in accordance with Technical Specifications.

2.0 SCOPE The scope of this evaluation is limited to the SRM/IRM trip setpoints and their associated instrument accuracies. As previously evaluated, the system hardware will neither cause any accidents, nor increase the occurrence or consequences of the accidents.

NMP1 Technical Specification SRM/IRM trip setpoints, including uIRM Upscale Hi-Hi", UIRM Upscale Rod Block", IRM Downscale" and USRM Hi Rod Block", are to be considered, based on the NRC approved methodology documented in the GENE proprietary information document, NEDC-31336, "GE Instrument Setpoint Methodology" (Reference 7.17). Maintaining the current SRM/IRM trip settings as specified in the NMP1 surveillance procedures (Reference 7.4), CEG will provide the Design basis of each trip setpoint and the corresponding allowable value.

3.0 DESIGN BASIS The following assumptions have been made in establishing the conclusion of this evaluation.

3.1 Consistent with the NMP1 Technical Specifications or Design Basis Limits and GENE Setpoint Methodology, the following analytical limits/design basis are used:

a.

IRM Upscale Hi-Hi

b.

IRM Upscale Rod Block

c.

IRM Downscale

d.

SRM Hi Rod Block

e.

SRM Hi-Hi Scram for Range 10 for Range 9 for ranging 65% of rated power 25% of rated power (SL 2.1.1 b) 100% full scale 94.0%

0% of full scale 93.65%ELFS 98.22% ELFS 3.2 The only values in the current NMP1 Technical Specification Tables 3.6.2a & g to be used as the allowable values of the SRM Rod Block/iRM trips in calculations of this report are:

a.

IRM Upscale Hi-Hi

b.

IRM Upscale Rod Block

c.

IRM Downscale

d.

SRM Hi Rod Block for Range 10 for Range 9 for ranging See Section 4.2.1 See Section 4.2.1 96% full scale (Table 3.6.2a) 88% of full scale (Table 3.6.2g) 5% of full scale (Table 3.62g) 1.0E + 5cps (Table 3.6.2g)

I

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SP-SRM/I RM-RG07/RHO1 Page 3

of L4 3.3 The setpoint values in the current NMP1 surveillance procedures (Ref. 7.4) are used as the nominal trip setpoint of the SRM/IRM trips in calculations of this report.

a.

IRM Upscale Hi-Hi for Range 10 37.6% of rated flux (ILS3.2.1.2b) for Range 9 11.75% of rated flux (ILS3.2.1.2b) for ranging 94% of full scale

b.

IRM Upscale Rod Block 86% of full scale

c.

IRM Downscale 6% of full scale

d.

SRM Hi Rod Block 9.OE + 4cps

e.

SRM Hi-Hi Scram 5.OE + 5 cps 3.4 The calibration accuracies are calculated by assuming that a Fluke Digital Multimeter (DMM) Type 8060A or equivalent is used for calibration. (Reference 7.15) 3.5 The radiation effect to the equipment in the specified environmental conditions does not exceed the normal integrated doses of 175 rads in the reactor control room and 350 rads in the general floor area inside the secondary containment. (Reference 7.8) 3.6 The normal environmental (temperature/humidity) conditions for the NMS equipment mounted in the control room should be 60 to 90 degrees Fahrenheit and 40 to 50 percent relative humidity, and those for the preamplifier panels mounted on the drywell are 40 to 104 degrees Fahrenheit and 20 percent to 90 percent relatively humidity. (Reference 7.8) 3.7 All inaccuracy terms are values of two standard deviations (97.7 percent confidence level).

3.8 The setpoint margins are greater than or equal to a 95 percent confidence level.

3.9 In order to account for 25 percent tolerance on the surveillance interval that is required by the NMP-1 Technical Specification (Reference 7.6), the instrument drift for a period of 30 months is used in the calculation.

3.10 The last decade SRM monitoring error due to counting losses resulting from pulse overlaps is compensated for by setting the analytical limit for the SRM Hi-Hi Scram trip to 7.5E +5 cps, which is the value used in the NMP1 procedure for checking detector saturation.

3.11 The bottom decade IRM noise would not be considered in the safety margin calculation because it would increase the IRM reading in a conservative direction.

3.12 The current NMP1 Tech Specs allow for a 25% extended surveillance interval (Reference 7.6) which for 24 months equates to 30 months.

3.13 The IRM will not be inserted partially during power operation.

3.14 The APRM flow biased scram setpoint at zero recirculation flow is considered as the upper limit or the design basis of the IRM Hi-Hi Scram (Reference 7.14).

3.15 The design basis of the SRM Hi-Hi Scram (AL1) is assumed to be the acceptance criteria for the SRM detector saturation in the NMP1 surveillance procedure (Reference 7.4j).

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SP-SRWIRM-RG07/RH01 Page 4!

of 14 4.0 CALCULATION In this calculation, all inaccuracies are considered as independent and random in nature. The total loop uncertainty is the square root of the sum of the squares of each equipment inaccuracy in the loop of the trip channel, which is based on the methodology documented in the GENE proprietary information document, NEDC-31336, 'GE Instrument Setpoint Methodology" (Reference 7.17)

By applying Assumption 3.12, the nominal trip setpoints and the allowable values will be first calculated from their analytical limits/design bases (Assumption 3.1). The calculated values are then compared with their desired nominal trip setpoints (Assumption 3.3) and allowable values (Assumption 3.2). If they are low for upscale and high for downscale, the setpoint values in Assumption 3.3 are used to calculate their corresponding allowable values and design basis values. These new values are then compared with values in Assumptions 3.2 and 3.1.

4.1 Source Range Monitor (SRM)

Table I shows the inaccuracy and drift values used for each equipment in the SRM Upscale trip loops (Reference 7.9 and 7.1 1)

TABLE I I

I EQUIPMENT DESCRIPTION UNIT INACCURACY DRIFT Signal Cond.

SRM + Preamp.

%ELFS 2.24 Equipment Trip Unit Upscale

%ELFS 1.12 SRM+Preamp+Upscale

%ELFS 1.18 Trip Unit SRM+Preamp +

%ELFS 1.81 Rod Block Trip Unit APEA I

DPEA

%ELFS 0.944 0

PMA

%ELFS 0

0 Al I

l

%ELFS 2.50 NOTE:

ELFS = Equivalent Linear Full Scale The Signal Conditioning Equipment accuracy is calculated by taking the square root of the-sum of the squares of the inaccuracies from the SRM (2% ELFS) and the preamplifier (1% ELFS).

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SP-SRM/I RM-RGQ7/RHO1 Page 5i of I't The channel calibration accuracy for the SRM channel (Cl) is calculated by statistically combining accuracies in the following equation:

Cl = 2/3'SQRT(2-(Ceq)A2 + CpA2)

a.

accuracy of the Fluke DMM8060A used in calibration (Ceq) =

b.

tolerance allowance by procedure for SRM Hi-Hi Scram (Cp) =

c.

tolerance allowance by procedure for SRM Hi Rod Block (Cp) =

0.03

%ELFS 0.00

%ELFS 0.34

%ELFS C11 =

0.03

%ELFS C12=

0.23

%ELFS for SRM Hi-Hi Scram for SRM Hi Rod Block The primary element accuracy (PEA), which is the sensitivity and nonlinearity of the detector, is equal to 0.944. This term will be treated as an accuracy term (APEA) and the drift term (DPEA) is equal to zero (0).

The process measurement accuracy (PMA) is assumed to be zero referring to Assumption 3.10.

PMA=

0

%ELFS The total loop inaccuracy (Al) is calculated by taking the square root of the sum of the squares of the inaccuracies from the SRM (2% ELFS), the preamplifier (1% ELFS) and the trip unit 1.12% ELFS).

Al=

2.50

%ELFS The total loop drift (Dl1) for the SRM upscale trip for a surveillance period of thirty (30) months is calculated in reference 7.16 and is 1.18%.

Dl =

1.18

%ELFS Similarly, the total loop drift (Dl 2) for the SRM Rod Block for a surveillance period of thirty (30) months is calculated in reference 7.16 and is 1.81%.

D12=

1.81

%ELFS The allowable value (AVx) and the nominal trip setpoint (NTSPx) are then calculated by using the following equations:

AVx NTSPx

= ALx-MARGIN1x

= ALx-MARGIN2x where ALx MARGINlx MARGIN2x

=

Analytical Limit (x = 1 for Hi-Hi Scram

= 2 for Hi Rod Block),

= CONSTANT(SQRT(A1A2 + C1xA2+ APEAA2 + PMA1A2)),

= CONSTANr(SQRT(A1A2 + C1xA2+ APEAA2 + PMA1A2 + D1A2))

+ DPEA

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of IAL CONSTANT Al DI

=

0.8225 conversion factor from 97.7% (2 standard deviations)

=

instrument accuracy, and

=

instrument drift for thirty month period.

With a probability (Z) corresponding to a value greater than 90 percent for a single channel to avoid occurrence of a Licensee Event Report (LER), the nominal trip setpoint is adjusted as follows:

NTSPx =

AVx - (Z) (SIGMAX) where SIGMAx =

SIGMAl =

SIGMA2 =

=

lk'(SQRT(Al'2 + C1A2 + D1'2) 1.38 %ELFS 1.55 %ELFS 1.282 4.1.1 SRM Hi-Hi Scram Based on Assumption 3.15, the design basis of the SRM Hi-Hi Scram (ALl) is determined as follows:

AL1 =

7.50E + 05 cps

=

98.Z2

%ELFS The allowable value (AVI) and the nominal setpoint (NTSP1) are then calculated as the following:

MARGIN11 =

MARGIN21=

AVI =

NTSP1 2.20 2.40 96.02 95.82

%ELFS

%ELFS

%ELFS =

%ELFS =

I

• 5.25E + 05 5.08E+05 cps cps I

Using the calculated AV1 value, the corresponding NTSP value is calculated to allow a probability of LER avoidance of 90%.

Given:

AVI =

96.02

- %ELFS NTSP1' = 94.25

%ELFS 5.25E + 5 cps Calculated:

=

3.95E + 05 cps I

Using the desired NTSP1 values from the NMP1 Procedure, the corresponding AV1' and AL1' values are calculated to allow a probability of LER avoidance of 90%.

Given:

NTSP1 =. 95.71

%ELFS 5.OOE + 5 cps Calculated:

AV1'=

AL1' =

97.49 99.68

%ELFS

. =

%ELFS

=

6.65E + 05 cps (too high - not used) 9.48E + 05 cps (too high - not used)

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SP-SRMWI RM-RG07/RHO1 Page 7_ of L4 Using the desired AVi value the corresponding NTSP1" value is calculated to allow a probability of LER avoidance of 90%.

Given:

AV1 =

95.71 NTSP1"=

93.94

%ELFS

%ELFS 5.OOE +05 cps Calculated:

=

3.76E + 05 cps I

I Based on the above results, the values used in Reference 7.4j are recommended to be used 7.50E + 05 cps is used as the design basis of the SRM Hi-Hi Scram and 5.25E + 05 cps used as the allowable value (AVi). The nominal trip setpoint (NTSP1) is then calculated from AV1 by the equation NTSP1 = AV1 - (Z)*(SIGMA) and is equal to 3.95E + 05 cps. The present setpoint of 5.OOE + 05 cps is acceptable because the margin between the setpoint and the design basis limit of 7.50E + 05 cps adequately covers the calculated margin (2.4%).

4.1.2 SRM Hi Rod Block The design basis of the SRM Hi Rod Block (AL2) trip is conservatively considered to be the calculated LER Avoidance trip setpoint of the SRM Hi Scram which is consistent with the GENE setpoint methodology.

AL2 =

3.76E + 05 cps

=

93.94

%ELFS The allowable value (AV2) and the nominal setpoint (NTPS2) are then calculated as following:

MARGIN12 =

MARGIN22 =

AV2 =

NTSP2 =

2.21 2.66 91.74 91.28

%ELFS

%ELFS

%ELFS

%ELFS

=

2.63E + 05

=

2.45E + 05 cps cps Using the calculated AV2 value, the corresponding NTSP2' value is calculated to allow a probability of LER avoidance of 90%.

Given:

AV2 =

91.74 NTSP2' = 89.75

%ELFS

%ELFS

=

2.63E + 05 cps

=

1.91E + 05 cps Calculated:

Using the desired NTSP2 value from the NMP1 procedure, the corresponding AV2' and AL2' values are calculated to allow a probability of LER avoidance of 90%.

Given:

NTSP2 =

85.07

%ELFS

%ELFS

%ELFS

=

9.OOE + 04 cps

=

1.24E + 05 cps

=

1.77E+05cps Calculated:

AV2' =

AL2'=

87.06 89.26 Based on the above results, the setpoint 9.ME + 04 cps, used in Reference 7.4j, is to be used as NTSP2 of the SRM Hi Rod Block and 3.76E + 05 cps used as the design basis limit (AL2). The allowable value (AV2) is then determined to be 2.63E + 05 cps from above.

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of 14 4.2 Intermediate Range Monitor (IRM)

Table II shows the inaccuracy and drift values used for each equipment in the IRM Upscale/Downscale trip loops (References 7.10, 7.12 and 7.16).

TABLE II EQUIPMENT DESCRIPTION UNIT INACCURACY DRIFT Signal Cond.

IRM + Preamp.

Equipment Upsc Hi-Hi

/125 3.39 NR Upsc Rod Block

/125 3.16 NR Downscale

/125 1.88 NR Amp Zero 1

/125

-0.197 Amp Zero 2

/125 0.503 Trip Unit Upsc/Downsc

/125 1.4 NR U

Rod Block

>30m 1.605 Upscale Trip

>30m 1.484 IRM Downscale

>30m 0.408 u

APEA DPEA

/125 1.18 0

PMA

/125 0

0 A3 D3

/125,>30m 3.67 1.579 A4 D4

/125,>30m 3.67 1.579 A5 D5

/125,>30m 3.67 1.579 A6 D6

/125, >30m 3.46 1.693 A7 D7

/125, >30M 2.34 0.677 The channel calibration accuracy for the IRM channel (Cl) is calculated by statistically combining:

a.

the accuracy of the Fluke DMM8060A used in calibration =

b.

the accuracy allowance for the calibration procedure

=

0.03

%ELFS 2

%FS I

Cb:=1.34 %FS 1.675 /125 I

The primary element accuracy (PEA), which is the sensitivity and nonlinearity of the detector, is equal to 1.18/125. This term will be treated as an accuracy term (APEA) and the drift term (DPEA) is equal to zero (0).

The process measurement accuracy (PMA) is assumed to be zero (0) referring to Assurhption 3.11.

The total loop inaccuracies (A13, A16, and A17) for the IRM Upscale Hi-Hi, Upscale Rod Block, and Downscale trips, which are calculated by taking the square root of the sum of the squares of the inaccuracies from the IRM, the preamplifier and the trip unit are equal to 3.67/125, 3.46/125 and 2.34/125 respectively.

Based on Assumption 3.1, the analytical Iimit/design basis of the IRM Upscale Hi-Hi (AL3), the IRM Upscale Rod Block (AL6) and the IRM Downscale (AL7) trips are determined. The allowable values (AVx) and the nominal trip setpoints (NTSPx) are then calculated by using the following equations:

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SP-SRM/I RM-RG07/RH01 Page G5 of 14 4.2 (Cont)

AVx

=

ALx-MARGINlx

=

ALx -MARGIN2x NTSPx where Aix

= Analytical Limit (x

= 3 for Upscale Hi-Hi at Range 10,

= 4 for Upscale Hi-Hi at Range 9,

= 5 for Upscale Hi-Hi for ranging,

= 6 for Upscale Rod Block,

= 7 for Downscale),

MARGINlx =

MARGIN2x =

CONSTANT Aix Dlx CONSTANT*(SQRT(A1xA2 + C1A2 + APEAA2 + PMA1A2)),

CONSTANT*(SQRT(A1xA2 + C1A2 + D1xA2 + APEAA2 + PMA1A2) + DPEA),

=

conversion factor from 97.7 percent to 95 percent confidence level (0.8225),

=

instrument accuracy, and

=

instrument drift for thirty month or greater period.

I The allowable values for the Upscale Hi-Hi, the Upscale Rod Block and the Downscale (AV3, AV6 and AV7) are determined and are not dependent on how long are their surveillance periods. The nominal upscale trip setpoints (NTSP3, NTSP6 & NTSP7) are determined for a surveillance period of thirty months.

With a probability (Z) corresponding to a value greater than 90 percent for a single channel to avoid occurrence of Licensee Event Report (LER), the nominal trip setpoint is adjusted as follows:

NTSPx = AVx - (Z)*(SIGMAx) where SIGMAx SIGMA3 SIGMA6 SIGMA7 z

=

1/2*(SQRT(A1xA2 + C1A2 + D1xA2)

=

2.16

/125

=

1.73 %FS

=

2.10

/125

=

1.68 %FS Rodblock

=

1.48

/125

=

1.18 %FS Downscale

=

1.282 or 0.81 (for IRM Upscale Hi-Hi only) 4.2.1 IRM Upscale Hi-Hi Based on Assumption 3.14, the design bases of the IRM Upscale Hi-Hi (AL3) are determined as follows:

AL3=

65 %power for Range 10 AL4=

25 %power for Range 9 AL5=

100 %FS for ranging

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/0 of 14 4.2.1 (Cont)

Using the desired nominal trip setpoint (NTPSx) in Section 3.3, the corresponding allowable values (AVx) values are then calculated as follows:

MARGIN13 =

MARGIN23 =

NTSP3

=

NTSP4

=

NTSP5

=

3.45 3.69 37.60 11.75 94.0

/125

=

/125

=

% rated neutron flux

% rated neutron flux

%FS

=

2.76 2.95

%FS

%FS 117.5

/125 AV3 AV4 AV5

=

37.69

=

11.78

=

94.23

% rated neutron flux

% rated neutron flux

%FS

=

117.8

/125 Using the NTSPx from the NMP1 procedure, the allowable values (AVx) and the design basis values (ALx) are then calculated to allow a probability of LER avoidance of 90%.

Given:

NTSP3 =

NTSP4 =

NTSP5 =

37.60 11.75 94

% rated neutron flux

% rated neutron flux

%FS

=

37.60

=

11.75

=

117.5

/40

/12.5

/125 Calculated:

AV3' AV4' AV5'

=

38.16

=

11.93

=

95.40

% rated neutron flux

% rated neutron flux

%FS

=

38.16

=

11.93

=

119.25

/40

/12.5

/125 AL3' AL4' AL5'

=

39.26

=

12.27

=

98.16

% neutron flux for Range 10

% neutron flux for Range 9

%FS 122.7 40% pwr 12.5% pwr

< 125/125 Based on the above results, the values calculated for AV and AL values are as follows. The IRM Upscale Hi-Hi setpoint will then be < 38.81/40 for even ranges and *121.31/125 for odd ranges. The allowable values are then determined to be 38.89/40 for even ranges and 121.55/125 for odd ranges. The AL value, which is less than or equal to the values listed in Section 3.1, is determined to be equal to 1 00%FS (40/40 or 125/125).

4.2.2 IRM Upscale Rod Block Based on Assumption 3.1, the design basis of the IRM Upscale Rod Block (AL6) trip is considered to be the nominal trip setpoint of the IRM Upscale Hi-Hi for ranging, which is consistent with the GENE setpoint methodology.

AL6=

94 %

=

117.5

/125 I

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of 14g 4.2.2 (Cont)

The allowable value (AV6) and the nominal setpoint (NTSP6) are then calculated as follows:

MARGIN16 =

MARGIN26 =

AV6

=

NTSP6

=

3.30 3.58 91.36 91.13

/125

/125

=

2.64

=

2.86

=

114.20 /125

=

113.91 /125 Using the limiting NTSP6 value as the AV from the NMP1 Technical Specification, the corresponding NTSP6' value is calculated to allow a probability of LER avoidance of 90%.

Given:

Calculated:

AV6

=

88

=

110/125

=

107.39/125 NTSP6'

=

85.91 Using the desirable NTSP6 from the NMP1 procedure, the corresponding AV6' and AL6' values are then calculated to allow a probability of LER avoidance of 90%.

Given:

NTSP6

=

86

=

107.5/125 Calculated:

AV6' AL6'

=

88.15 %

=

90.79 %

=

110.19/125

=

113.49/125 (<AL6)

Based on the above results, the IRM Upscale Rod Block maximum setpoint is calculated to be s 91.13%(113.92/125) of full scale. The allowable value (AV6) will then be 91.35% of the full scale (114.2/125) and the design basis AL is 94% (117.5/125).

4.2.3 IRM Downscale Based on Assumption 3.1, the design basis of the IRM Downscale (AL7) trip is considered to be the lowest limit of the IRM scale, which is zero (0) and consistent with the GENE setpoint methodology.

AL7=

0/125 The allowable value (AV6) and the nominal setpoint (NTSP6) are then calculated as follows:

MARGIN17 =

MARGIN27 =

AV7 NTSP7

=

2.56/125 2.62/125 2.56/125 2.62/125 Using the desired NTSP7 value as the AV from the NMP1 Technical Specification, the corresponding NTSP7' value is calculated to allow a probability of LER avoidance of 90%.

Given:

Calculated:

AV7

=

NTSP7' =

6.25

/125

=

8.14

/125

=

5.00 6.5

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SP-SRM/IRM-RG07/RH01 Page.. L of /4 4.2.2 (Cont)

Using the desirable NTSP7 from the NMP1 procedure, the corresponding AV7' and AL7' values are then calculated to allow a probability of LER avoidance of 90%.

Given:

NTSP7 =

7.5

/125

=

6%

Calculated:

AV7'

=

AL7'

=

5.61 3.05

/125

/125

=

4.48%

=

2.4%

Based on the above calculation results, the IRM Downscale setpoint used in the NMP1 procedure will be kept at 6 % of the full scale (7.5/125) with a conservative AL of 3.04/125 or 2.4%. The calculated allowable value (AV7) is therefore 5.61/125 or 4.48% and the calculated setpoint is therefore 5.66/125 or 4.53%.

5.0 SURVEILLANCE PROCEDURES.

NMP-1 surveillance data (Reference 7.16) has been reviewed. The review is based on the assumption that the values in the NMP-1 Procedures will be used as the nominal trip setpoints in this report.

6.0 CONCLUSION

Table IlIl summarizes the results of the calculations of margins allowing an extension of the surveillance period for the SRMs/IRMs to thirty (30) months. The SRM/IRM trip setpoints were determined consistent with the NRC approved GE setpoint methodology and from which the AV values are calculated. For the TS functions (i.e., SRM Hi Rod Block, IRM Hi - Hi Scram, IRM Rod Block, IRM Downscale), the calculated AV and NTSP values are closer to the design basis limits than the current TS values. Therefore, the margins to the design basis limits are conservative with the current TS and Procedure Values relative to the calculated NTSP values. For the IRM's, the new calculated AV's will replace the setpoint tolerances listed in TS Basis Section 3 / 4.6.2. The Table IlIl trip setpoints will meet their design bases, will not impact plant safety, and will improve the system availability in accordance with a 30 month surveillance interval.

TABLE IlIl I

I AUSL Design T.S.

Calculated Procedure Calculated TRIP FUNCTION Design Basis Values AV Values NTSP Basis Limits (Ref. 7.6)

(Ref. 7.4)

SRM Hi-Hi Scram (cps) 7.50E +5 N/A 5.25E + 5 5.OOE + 5 5.08E + 5 SRM Hi Rod Block (cps) 3.76E + 5 1.OOE + 5 2.63E + 5 9.OOE + 4 2.45E + 5 IRM HiHi-at R10 (/40)

<65%pwr 40 38.4 IRM Hi-Hi at R9 (/12.5)

<25% pwr 12.5 12 IRM Hi-Hi (/125) 125 120 121.55 117.5 121.31 IRM Rod Block (/125) 117.5 110 114.2 107.5 113.92 IRM Downscale (/125) 3 6.25 5.61 7.5 5.66

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/4

7.0 REFERENCES

7.1 Niagara Mohawk Power Company Purchase Order No. 78515,1/17/92.

7.2 GE-NE Proposal No. 295-1 CH8X-EA-1, EXTENDED SRM/IRM SURVEILLANCE FREQUENCY FOR NMP-1, November22, 1991.

7.3 NRC Generic Letter 91-04, CHANGES IN TECHNICAL SPECIFICATION SURVEILLANCE INTERVALS TO ACCOMMODATE A 24-MONTH FUEL CYCLE, April 2,1991.

7.4 NMPC NMP-1 Instrument Surveillance Procedures:

a.

N1-ISP-092-V204, Intermediate Range Monitor Instrument Channel calibration.

b.

N1-ISP-092-V205, Intermediate Range Monitor Instrument Channel calibration RPS Channel 12.

c.

N1-ISP-092-204, Intermediate Range Monitor Instrument Channel calibration RPS Channel 11.

d.

N1-ISP-092-V201, Intermediate Range Monitor Instrument Channel calibration

e.

Ni-ISP-V-092-V201, Intermediate Range Monitor Instrument Channel calibration.

f.

N1-ICP-A-NEU-2, Intermediate Range Monitor Instrument Channel calibration.

9.

N1-IMP-NEU-2, Intermediate Range Monitor Instrument Channel calibration

h.

N1-IMP-092-R200, Revision 02, IRM Detector drive Maintenance.

i.

N1-ISP-092-210, IRM Rod Block and Scram Instrument Channel Functional Test.

j.

Ni-ISP-092-101, Source Range Monitor Instrument Calibration.

7.5 NMPC Nuclear Engineering & Licensing Procedure No. NEL-415, Revision 4, 10CFR50.59 SAFETY EVALUATIONS -PREPARATION AND CONTROL.

7.6 NMP-1 Technical Specification, 4.0.2.

7.7 NMP-1 Instrument Surveillance Data from J. Cutri, kept in GE-NE DRF No. C51-101.

7.8 GE-NE Document No. 22A2928, UBWR Equipment Environmental Requirements, uRevision 2."

7.9 GE-NE Document No. 21A5417, 'SOURCE RANGE MONITOR SYSTEM," Revision 3.

7.10 GE-NE Document No. 21A5418, "INTERMEDIATE RANGE MONITOR SYSTEM," Revision 2.

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SP-SRMIRM-RG07/RH01 Page j4 of 14 7.11 GE-NE Document No.175A7631, "PULSE PREAMPLIFIER FOR SRM," Revision 0.

7.12 GE-NE Document No. 175A7632, "WIDE RANGE MONITOR (MSIV) AND VOLTAGE PREAMPLIFIER,' Revision 6.

7.13 Niagara Mohawk Power Company Purchase Order No. 78515 C/O 1, 1127194.

7.14 GE-NE-909-1093, "IRMWAPRM Overlap Improvement for Nine Mile Point Nuclear Station Unit One".

t 7.15 Fluke 8060A Digital Multimeter Instruction Manual, March 1982.

7.16 NER-1 1-002, "SRM/IRM Calibration Data Analysis" 7.17 NEDC-31336P-A, General Electric Instrument Setpoint Methodology", September 1996.

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ATTACHMENT 6 INTERMEDIATE RANGE MONITOR CALIBRATION DATA

Intermediate Range Monitor Analysis

References:

1 Probability and Statistics for Engineers, Irwin Miller and John Freund, Prentice-Hall 1965.

2 Calculation VYC-2236 Rev 0, "Drift Calculation for Intermediate Range Monitors", Vermont Yankee Nuclear Power Station.

3 EPRI Report TR-103335 Rev. 1, "Guidelines for Instrument Calibration Extension/Reduction Programs."

4 N1-ISP-092-204 R4, "Intermediate Range Monitor Calibration."

5 N1-ISP-092-205 R5, "Intermediate Range Monitor calibration."

Raw Drift Values for IRM Trips are As-Found minus As-Left values from IRM worksheets (includes calibration data from References 4 and 5):

IRM 11 Interval 14/11/199417/11/19941 2/2/1995 2/28/1995 3/28/1996 l 7/24/1996 l 4/9/1997 l 4/27/1998 14/30/19981 4/7/1999 15/15/199919/28/1999l 91 206 26 394 118 259 383 3

342 38 136 DC Amp Zero 1 Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts 11.1

-7

-2.6

-12.2 22.9

-19.1

-9.3 0.3

-2.6 3.7

-5.3 33

-0.003

-0.004

-0.001 0.0

-21.1

-0.001 0

0 0.5

-7.2 0.013 0.011 0.001 0.2

-2.2 18.9 0.006 0.005 0.001 0

0.3

-1.0 24.3

-0.003 0.005

-0.002 1.0

-20.1 0

0 0.002 0.0

-0.2 0.004

-0.007 0

-1.0 7.1 0.016 0.001 0.001 0.0 13.8 0.001 0

0

-1.0

-6.3

-0.01 0.006 0

0.0 IRM 11 Interval DC Amp Zero 1 Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts 2/24/2000 2125/2000 5/1/2001 5/8/2002 1 5/15/2002 12/5/2002 12/12/2002 3/13/200314/19/2003 149 1

431 372 7

204 7

91 37 22.4 2.7 2

-11.5 0.5 2.3

-0.9

-8 2.8 10.5 0.001

-0.003

-0.002 0.5 8.1 0

0.002 0.002 0.5 1.3

-0.003

-0.008

-0.001

-0.4

-3 0.011 0.006 0.001 0.0

-1

-0.003 0

-0.001

-0.2 6.8 0.009

-0.004 0.001 0.6

-0.9

-0.004 0.009 0

0.0 0.2 0.003 0.002

-0.001

-0.3 7.9

-0.011 3/28/96 outliers

-0.009 removed 0.001 0.3 CaLE

IRM 12 14/11/199417/11/1994 2/2/1995 2/28/19951 3/28/1996 l 7/24/1996 l 4/9/1997 l4/26/1998 4/29/1998 4/7/1999 5/15/1999l9/28/1999 Interval 91 206 26 394 118 259 382 3

343 38 136 DC Amp Zero 1 Drift DC Amp Zero mVDC 5.7

-5.2

-0.54 8.44

-5.86 0.99

-5.38 5

-1.7 2.5 5.1 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts 18.2

-15.68

-1.61 7.89

-8.86

-11.14 6.5

-7

-5.2 10.45

-10.25

-0.004 0.002 0.003 0.004

-0.001

-0.005

-0.002 0.003 0.004 0

-0.005 0.002 0.002 0.009 0.003

-0.004 0.004

-0.005 0.008

-0.006 0.001 0.004 0.001 0

-0.001 0

0 0.001 0.001

-0.002

-0.001 0.001

-0.002

-0.80 0.36 0.39 0.05

-0.80

-0.20 1.00

-0.90

-0.10 0.00 1.00 IRM 12 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 12/24/200012/25/20001 4/29/2001 1 5/8/2002 1 5/15/2002 1 12/5/2002 112/12/20021 3/13/200314/20/20031 149 1

429 374 7

204 7

91 38

-8.9 0.2 1.01

-0.51 1.4 0

0

-4.67 1.57

-24.7 1.3 0.5

-20.5

-0.1 5.1

-5.1

-7.4 2.8 0.001 0.003

-0.003

-0.001 0.001 0.005

-0.001

-0.004 0

0.002

-0.008 0.005 0.002 0

-0.005

-0.002

-0.003 0

0.003

-0.001 0

0

-0.001 0.001 0

-0.001 0

-1.00 0.60 0.66

-0.76

-0.50 1.00 0.30

-1.00

-0.30 IRM 13 14/12/199417/11/19941 2/2/19951 3/3/1995 l 3/29/1996 l 7/24/1996 l 4/10/1997 4/26/1998 14/29/19981 4/8/1999 15/15/199919/29/1999l Interval 90 206 29 392 117 260 381 3

344 37 137 DC Amp Zero 1 Drift mVDC 4

-3.25 0.86

-4.71 5.68

-2.13

-7.31 0.06 0.9 3.4

-1.5 DC Amp Zero 2 Drift mVDC 21

-27.5 1.36

-20.86 44.84 11.24 3.24 4.98

-44.2

-4.7

-20.1 Rod Block volts 0

0 0

0.002 0.004

-0.002 0

0

-0.001 0.004 Upscale Trip volts 0.009 0.003

-0.002

-0.001 0.008

-0.002 0

0

-0.001

-0.003 0.003 IRM Downscale - Volts 0.003

-0.003 0.004

-0.001 0

-0.002 0.002 0

-0.002 0.001 0

INOP Volts

-0.60 0.40 2 2.97 0.00 0.00

-0.24 0.24 1.00 0.30

-0.90 IRM 13 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 12/25/200014/30/20011 5/8/2002 l 5/15/2002 l 12/6/2002 12/12/20021 3/13/2003 4/20/2003 149 430 373 7

205 6

91 38

-7.5 12.2 3

-1.7 0.7

-0.1 2.1 5.4 2.9 16.1

-43.1

-0.8 47 0.4 15 0.003

-0.008 0.004

-0.001 0.001 0.001 0.001

-0.004 0.003

-0.002

-0.002 0

0 0.001 0.001

-0.004 0

0

-0.001

-0.001 0.002 0

-0.001 0

0.80 1.50

-0.70 0.00

-1.00 0.00 1.00 0.00 3/3/95, 5/15/99, 4/20/03 outliers removed C o $

I4/12/1994I7/11/1994I 2/2/19951 3/3/1995 I 3/29/1996 I 7/25/1996 I 4/9/1997 14/27/1998 14/29/19981 4/8/1999 I 5115/19991912911999 I IRM 14 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscal INOP 14/12/199417/11/19941 2/2/1995 1 3/3/1995 1 3/29/1996 1 7/25/1996 1 4/9/1997 1 4/27/1998 14/29/19981 4/8/1999 1 5/15/199919/29/1999]

90 206 29 392 118 258 383 2

344 37 137 mVDC NM

-3.7

-1.43

-1.37 9.33

-5.43 1.2

-0.2

-1.6 2.11 5.09 mVDC 4.7

-12.5

-4.3

-3.8 21.91

-5.11

-45.1

-2.6 1.2 6

15.4 volts

-0.002

-0.003

-0.002

-0.003 0.005 0.006 0.002

-0.004

-0.005 0.005 0

volts 0.004 0

-0.001

-0.002 0.003 0.005

-0.015 0.002 0.004

-0.002 0.001 e - Volts 0

-0.001 0.001

-0.001 0.001

-0.001 0

0.001

-0.003 0.002 0

Volts

-0.100 0.600 0.610

-0.310

-1.000 0.000 0.000 0.000 0.000 1.200

-0.200 IRM 14 Interval DC Amp Zero I Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 2/24/200012/25/20001 5/1/2001 1 5/8/2002 1 5/15/2002 1 12/6/2002 112/12/2002 3/14/200314/20/2003 148 1

431 372 7

205 6

92 37

-8.6 0.3 1.3

-24.4 0.9 23.1 0

0.002

-0.008

-0.002 0.003

-0.006 0

0.002

-0.002 0.500 0.200

-0.200 7/11/94 outlier removed 0.2 0.5 0.8 3.3

-8.7 1.8

-21.6 1.2 3.3

-1.6

-15.15 6.15 0.005 0.003 0

-0.004

-0.001 0.004 0.01

-0.007 0.003

-0.001 0.005

-0.006 0

-0.001 0.001 0

0

-0.001 0.000

-0.400 0.400 0.000 0.300

-0.600 IRM 15 Interval 4/12/199417/11/1994 2/2/1995 3/1/1995 3/29/1996 1 7/25/1996 1 4/8/1997 1 4/27/1998 14/29/19981 4/6/1999 15/15/199919/29/1999 90 206 27 394 118 257 384 2

342 39 137 DC Amp Zero 1 Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts 8.17

-4.2

-1.14

-3.66 9.07

-7.77 1.5 0.5

-3.55 3.15 8.6 22.97

-10.8

-2.72

-8.08 36.33

-0.26 2

3.22

-11.33 10.11

-4.6 0.013

-0.001

-0.006

-0.001 0.01

-0.002 0.002

-0.006 0

-0.004 0.008 0.005 0.009

-0.007 0

0.008

-0.001

-0.002

-0.004 0.003 0.006

-0.003

-0.001 0

0 0.002

-0.002 0

0

-0.002 0.002 0

0

-0.30 0.13 0.34

-0.37 0.00 0.00

-1.00 0.00 0.10 0.20

-0.30 IRM 15 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 2/23/200012/26/20001 4/22/2001 1 5/6/2002 1 5/15/2002 1 12/6/2002 112/11/200213/11/200314/20/2003 147 3

421 379 9

205 5

90 40

-13.2 1.2 1

0.7 1.8 1.7

-1

-7.64 3.34

-35.3 2.6 5.1

-26.5 0.003

-0.001

-0.002

-0.006

-0.004 0.005 0

-0.007 0.001 0

-0.004 0.003 1.40

-1.00 0.40

-0.80 5

5.6

-2.4

-21.01 10.11 0

0.006

-0.001

-0.004 0.004 0.001 0.002

-0.001

-0.002 0.001 0.001

-0.002 0.001 0.001

-0.001

-0.60 0.80 0.20

-0.40 0.00

IRM 16 li4/12/1 Interval DC Amp Zero 1 Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts IRM 16 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 19417/11/19941 2/3/1995 1 3/2/1995 1 3/30/1996 1 7/25/1996 7 4/8/1997 l 4/27/1998 7 4/5/1999 14/29/199915/15/199912/24/2000 90 207 27 394 117 257 384 343 24 16 285 3.8

-2.87

-0.23 9.8

-7.5

-0.5 0

0.01

-0.01

-0.001 0.009

-0.008 0.002

-0.001 0

1.00

-0.80 0.95

-1.4 6.4

-5.4 1.1 17.66

-9.95

-8

-3.02

-4 0

-0.002 0.001

-1.15 34.6 0.7

-3.9

-31.3

-4.5 45.5

-21.3 0.011

-0.002

-0.001 0.002 0

-0.003

-0.009 0.008

-0.001

-0.009 0.004 0.012

-0.01 0.003 0

-0.001 0.001

-0.002 0.002

-0.002

-0.002 0.20

-0.20 0.00

-0.90 0.12 12/26/20001 5/1/2001 1 5/6/2002 1 5/15/2002 1 12/6/2002 112/11/20021 3/11 2

430 370 9

205 5

0.52 1.8 0.2 0.8

-0.2

-0.51 to 4/20/2003 40 1.8 1.8

-21.5 0.8 0.002

-0.003 0.005

-0.007

-0.002 0.015 0.003 0

0 0.38 0.00

-0.60 2.8

-1

-0.42

-0.18 5.96 0.007

-0.001

-0.002

-0.006 0.006

-0.009 0.002

-0.003 0.008

-0.008 0

0

-0.001 0

0.001

-0.40 1.00 0.00 0.14

-0.64 3/11/03 outlier removed 4/29/99 & 5/15/99 outliers removed IRM 17 Interval 14/12/199417/11/19941 2/3/1995 1 3/1/1995 l 3/30/1996 l 4/8/1997 1 4/27/199814/30/19981 4/6/1999 15/15/199919/29/199912/24/20001 90 207 26 395 374 384 3

341 39 137 148 DC Amp Zero I Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts 7.88

-6.35

-0.45 20.1

-15.87 2.83 0.004 0.01 0

0 0.014 0

-0.002 0.001

-0.002 0.0 0.1 1.4

-1 5.82

-9.82 0.9

-2.7 3.38

-6.46

-12.42

-9.3 10.58

-12.58 0.4 25.1 9.71

-18.15

-22.12

-0.013 0.014

-0.001

-0.005

-0.003 0.005 0.017

-0.007 0

0.004

-0.003 0.005

-0.001 0.004

-0.004

-0.002 0.004

-0.002 0

0.001 0.001

-0.002 0

-0.001

-1.0 1.0 0.0

-1.0 0.2

-0.7 0.7 0.4 IRM 17 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 12/25/200014/26/20011 5/6/2002 l 5/15/2002 l 12/6/2002 112/11/20021 3/12/2003 14/20/2003 1

426 375 9

205 5

91 39 1.4

-3.23 0.53 52.2 10.32

-31.4 0.003

-0.006 0.009 0

-0.002 0.005

-0.001 0.002 0

0.0 0.2

-0.8 1.2

-0.5

-0.5

-5.4 3.08 5.8

-2 3.7

-6.81 12.31

-0.003 0

0.001 0

0

-0.003 0

0.001

-0.001 0.002 0

0.001

-0.002 0.001

-0.001

-0.4 1.0 0.0 0.4

-0.4 COq

IRM 18 411/11 Interval DC Amp Zero I Drift mVDC DC Amp Zero 2 Drift mVDC Rod Block volts Upscale Trip volts IRM Downscale - Volts INOP Volts

)9417/11/19941 213/19951 3/1/1995 1 3/30/1996 1 7/25/1996 1 417/1997 1 4/27/1998 14/30/19981 4/6/1999 15/15/199919/29/1999 91 207 26 395 117 256 5.55

-1.05 5.52

-4.19 3

341 39 137 5.3 0.6

-5 1.27 1.27

-2.98 4.82 1.44 16

-8.8 14.96 3.37 17.25 6.04

-10.34 2.63

-6.63 6.1 2.73

-0.007 0.016

-0.002

-0.009 0.002 0.006 0.004

-0.008 0.005

-0.004 0.002

-0.002 0.006 0.009

-0.002 0.006

-0.004 0.007

-0.003

-0.004 0.008 0.001

-0.003 0.001 0

0.001 0

0

-0.001 0.001 0

0 0

-0.70

-0.07 1.59

-0.36

-0.36 0.36 0.00 0.00 0.10

-0.50 0.90 IRM 18 Interval DC Amp Zero 1 Drift DC Amp Zero 2 Drift Rod Block Upscale Trip IRM Downscale - Volts INOP 2124/200012/25/2000 4126/2001 1 517/2002 1 5/1512002 1 1216/2002 11211/200213/121200314/20/2003 148 1

426 376 8

205 5

91 39

-7.35

-0.72 1.92

-20.53

-2.9 11.4

-0.003

-0.009 0.003

-0.005

-0.018 0.011 0

0 0.001

-0.10

-1.50 1.30 1.4 0.3 0.26 3.04

-7.2 1.3

-17.1 3

-0.12

-0.08

-13.2 18.6 0.004 0.011

-0.012 0.001 0.005

-0.003 0.006

-0.003 0.001 0.001 0.005

-0.002

-0.001 0

-0.001' 0

0

-0.002 0.20

-0.50 0.45 0.55 0.15 0.25 Population Sample Sigma 95%

1st Outlier IRM Summary Count Mean Sigma Conf 1.96 Sigma

(+/-)

Amp Zero 1 mVdc 157 0.482 8.378 9.284 18.196 29.322 Amp Zero 2 mVdc 157

-0.463 17.279 19.148 37.530 60.477 Rod Block Volts 157 0.000 0.007 0.008 0.016 0.025 Upscale Trip Volts 157 0.000 0.006 0.006 0.012 0.019 IRM Downscale -Volts 157 0.000 0.001 0.002 J0.003 0.005 INOPTrip IVolts 157 0.061 0.912 1.011 1.981 3.193

Population IRM Summary After 1st Sample Sigma Outliers Count Mean Sigma

@95% Conf 1.96 Sigma Amp Zero 1

% Span 155 1-0.002%

0.058%

0.0639%0/

0.125%

Amp Zero 2

%Span 156 10.000% 0.162%

0.180%

0.353%

Rod Block

% Span 155 0.048%

0.551%

0.611%

1.197%

Upscale Trip

% Span 156 0.049%

0.531%

0.589%

1.154%

IRM Downscale - % Sp 157

-0.005%

0.137%

0.152%

0.297%

INOP Trip Volts 154 0.035 0.661 0.732 1.204 Population Max Cal Sample Sigma Interval -

IRM Summary - EXT Count Mean Sigma

@95% Conf 1.96 Sigma Days Amp Zero 1

% Span 60 0.001%

0.084%

0.100%

0.197%

1523 Amp Zero 2

% Span 60 0.009%

0.216%

0.257%

0.503%

1523 Rod Block 1% Span 40 0.118%

0.656%

0.819%

1.605%

1385 Upscale Trip

% Span 40 0.140% 1 0.607%

0.757%

1 1.484%

1385 IRM Downscale % Sp 40 1-0.020% 1 0.167% 1 0.208%

0.408%

1 1385 INOP Trip IVolts 35 0.152 0.852 1.082 2.121 1497 IRM-EXT Count Outliers Coverage Zero 1 60 1

-2 Zero 2 60 1

-1 INOP35 2

all Downscale 40 0

all Rod Block 40 0

all i Hi Trip 40 0

all

IRM Ampliflor Zero, Trips, and INOP Extended Calibration Interval Drift Analysis Extended Calibration Data for Amplifier Zero: (from IRMXXEXT Worksheets)

IRM 11 4/11/1994 7/11/1994 2/2/1995 7/24/1996 4/9/1997 4/30/1998 4/7/1999 2/24/2000 5/1/2001 5/8/2002 4/19/2003 DC Amplifer Zero Cal.

7.4.5 (AF-mVDC)

-2.00 9.10 2.10 10.20

-8.90

-8.80

-11.40 21.20 2.10

-9.40

-3.30 7.4.7 (AL-mVDC)

-2.00 9.10 2.10 10.20 0.20

-8.80 0.40

-2.60 2.10 0.00

-3.30 7.4.9 (AF-mVDC) 3.50 36.50

-18.10 28.30 29.30

-19.10 10.00 19.00 11.30

-3.00 10.00 7.4.11 (AL-mVDC) 3.50 3.00 0.00 5.00 1.20 2.90 1.00 1.90 0.00

-3.00 10.00 IRM 12 4/11/1994 2/2/1995 4/29/1998 4/7/1999 2/24/2000 5/8/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (AF-mVDC)

-2.20

-1.70 1.33

-0.80

-2.10

-1.40

-3.10 7.4.7 (AL-mVDC)

-2.20

-1.70 1.28

-0.80

-2.10

-1.40

-3.10 7.4.9 (AF-mVDC)

-18.00

-15.48

-11.50

-17.20

-23.70

-15.30

-4.60 7.4.11 (AL-mVDC)

-18.00 1.00

-11.50 0.80 3.40 0.10

-4.60 IRM 13 l4/12/1994 2/21995 7/24/1996 4/10/1997 4/8/1999 9/29/1999 4/30/2001 5/8/2002 12/6/2002 3/13/2003 4/20/2003 DC Amplifier Zero Cal.

l 7.4.5 (AF-mVDC) l

-2.00

-1.25 0.58

-1.55

-7.90

-6.00

-1.30 1.70 0.70 2.70 8.10 7.4.7 (AL-mVDC) l

-2.00

-1.25 0.58

-1.55

-7.90

-6.00

-1.30 1.70 0.70 2.70 8.10 7.4.9 (AF-mVDC) l -10.00

-16.50 26.24 12.84

-35.70

-24.10 21.60

-40.10 47.00 18.00

-75.40 7.4.11 (AL-mVDC) l -10.00 0.90 1.60 0.28 0.70 2.60 3.00 0.80 2.60 0.00 4.20 IRM 14 4/12/1994 7/11/1994 4/29/1998 5/8/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (AF-mVDC)

-1.50 66.00

-1.50

-2.70

-5.00 7.4.7 (AL-mVDC)

-1.50 0.10

-1.50

-2.70

-5.00 7.4.9 (AF-mVDC) 2.30 7.00

-15.70

-15.10

-4.80 7.4.11 (AL-mVDC) 2.30 7.00

-15.70 1.30

-4.80 IRM15 4/12/1994 7/11/1994 2/2/1995 7/25/1996 9/29/1999 2/23/2000 5/6/2002 5/15/2002 12/6/2002 3/11/2003 4/20/2003 DC Amplifier Zero Cal.

I I

I 7.4.5 (AF-mVDC)

-5.07 3.10

-1.10 3.17 5.60

-7.60

-4.70

-2.90

-1.20

-9.84

-6.50 7.4.7 (AL-mVDC)

-5.07 3.10

-1.10 3.17 5.60

-7.60

-4.70

-2.90

-1.20

-9.84

-6.50 7.4.9 (AF-mVDC) 0.63 23.60

-10.20 24.93

-1.90

-37.20

-18.90 5.00 10.60

-12.81 10.41 7.4.11 (AL-mVDC) 0.63 0.60

-0.60

-1.04

-1.90

-0.10 0.00 5.00 10.60 0.30 10.40 IRM16 4/12/199417/11/1994 7/25/1996 4/5/1999 l 5/15/1999 12/24/20001 5/1/2001 3/11/2003 4/20/2003 2DCAmplfierZeroCal.

7.4.5 (AF-mVDC)

-2.40 1.40 3.30 16.66

-18.00

-2.52

-0.20 36.10 1.90 7.4.7 (AL-mVDC)

-2.40 1.40 3.30

-0.05 l

0.50

-2.52 l

-0.20 0.10 1.90 7.4.9 (AF-mVDC) 2.40 12.20 21.80

-33.30 l

43.00

-21.30 l

-20.00 0.00 5.96 7.4.11 (AL-mVDC) 2.40

-0.80 1.20 2.00 l

0.00

-0.30

-2.00 0.00 5.96

IRM 17 4/12/1994 7/11/1994 2/3/1995 4/6/1999 2/24/2000 2/25/2000 5/6/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (AF-mVDC)

-4.58 3.30

-3.05

-10.30

-14.80

-13.40

-2.50

-4.62 7.4.7 (AL-mVDC)

-4.58 3.30

-3.05 0.70

-14.80 0.20

-2.50

-4.62 7.4.9 (AF-mVDC) 1.40 21.50

-14.47 16.80

-30.20 52.00

-21.90 13.00 7.4.11 (AL-mVDC) 1.40 1.40

-0.23 0.30

-0.20

-0.82 0.00 0.26 IRM 18 4/11/199417/11/1994 3/1/1995 7/25/1996 2/24/2000 5/7/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (AF-mVDC)

-3.70 1.60

-3.35 1.12

-4.60

-2.00

-4.30 7.4.7 (AL-mVDC)

-3.70 1.60

-3.35 1.12

-4.60

-2.00

-4.30 7.4.9 (AF-mVDC) 2.70 18.70 9.26 19.75

-19.70

-11.00 9.00 7.4.11 (AL-mVDC) 2.70 3.10

-0.87 0.30

-2.40 0.80 9.00 Zero Raw Drift data:

IRM 11 Interval 91 206 538 259 386 342 323 432 372 346 Zero 1 AF-AL 11.100

-7.000 8.100

-19.100

-9.000

-2.600 20.800 4.700

-11.500

-3.300 Zero 2 AF-AL 33.000

-21.100 28.300 24.300

-20.300 7.100 18.000 9.400

-3.000 13.000 IRM 12 Interval 297 1182 343 323 804 347 Zero I AF-AL 0.500 3.030

-2.080

-1.300 0.700

-1.700 Zero 2 AF-AL 2.520

-12.500

-5.700

-24.500

-18.700

-4.700 IRM 13 Interval 296 538 260 728 174 579 373 212 97 38 Zero 1 AF-AL 0.750 1.830

.2.130

-6.350 1.900 4.700 3.000

-1.000 2.000 5.400 Zero2AF-AL

-6.500 25.340 11.240

-35.980

-24.800 19.000

-43.100 46.200 15.400

-75.400 IRM 14 Interval 90 1388 1470 347 Zero I AF-AL 67.500

-1.600

-1.200

-2.300 Zero 2 AF-AL 4.700

-22.700 0.600

-6.100 IRM 15 Interval 90 206 539 1161 147 803 9

205 95 40 Zero 1 AF-AL 8.170

-4.200 4.270 2.430

-13.200 2.900 1.800 1.700

-8.640 3.340 Zero2AF-AL 22.970

-10.800 25.530

-0.860

-35.300

-18.800 5.000 5.600

-23.410 10.110 IRM 16 Interval 90 745 984 40 285 432 679 40 Zero 1 AF-AL 3.800 1.900 13.360

-17.950

-3.020 2.320 36.300 1.800 Zero 2 AF-AL 9.800 22.600

-34.500 41.000

-21.300

-19.700 2.000 5.960 IRM 17 Interval 90 207 1523 324 1

801 349 Zero I AF-AL 7.880

-6.350

-7.250

-15.500 1.400

-2.700

-2.120 Zero 2 AF-AL 20.100

-15.870 17.030

-30.500 52.200

-21.080 13.000 IRM 18 Interval 91 233 512 1309 803 348 Zero 1 AF-AL 5.300

-4.950 4.470

-5.720 2.600

-2.300 Zero 2 AF-AL 16.000 6.160 20.620

-20.000

-8.600 8.200

Interval Zero 1 AF-AL Zero 2 AF-AL Drift data ordered by increasing interval:

1 9

38 40 40 40 90 90 90 90 91 91 1.4 1.8 5.4 3.34

-17.95 1.8 8.17 3.8 7.88 11.1 5.3 52.2 5

10.11 41 5.96 4.7 22.97 9.8 20.1 33 16 Interval Zero 1 AF-AL Zero 2 AF-AL 95 97 147

-8.64 2

-13.2

-23.41 15.4

-35.3 174 1.9

-24.8 205 206 206 207 212 233 259 260 1.7

-7

-4.2

-6.35

-1

-4.95

-19.1

-2.13 5.6

-21.1

-10.8

-15.87 46.2 6.16 24.3 11.24 Interval Zero 1 AF-AL Zero 2 AF-AL 285 296

-3.02 0.75

-21.3

-6.5 297 0.5 2.52 323 20.8 18 323 324 342

-1.3

-15.5

-2.6

-24.5

-30.5 7.1 343 346 347 347 348

-2.08

-3.3

-1.7

-2.3

-2.3

-5.7 13

-4.7

-6.1 8.2 Interval Zero 1 AF-AL Zero 2 AF-AL 349 372

-2.12

-11.5 13

-3 373 386 3

-9

-43.1

-20.3 432 432 512 538 538 539 579 679 4.7 2.32 4.47 8.1 1.83 4.27 4.7 36.3 9.4

-19.7 20.62 28.3 25.34 25.53 19 2

Interval Zero 1 AF-AL Zero 2 AF-AL Interval Zero 1 AF-AL Zero 2 AF-AL 728 745 801 803

-6.35 1.9

-2.7 2.9

-35.98 22.6

-21.08

-18.8 803 804 984 1161 1182 1309 1388 1470 2.6 0.7 13.36 2.43 3.03

-5.72

-1.6

-1.2

-8.6

-18.7

-34.5

-0.86

-12.5

-20

-22.7 0.6 1523

-7.25 17.03 Population Sample Sigma 95%

1.96 Outlier -

IRM Summary Count Mean Sigma Conf Sigma 3.09*sigma Amp Zero 1 mVDC 61 1.241 12.014 14.300 28.028 37.123 Amp Zero 2 mVDC 61

-0.390 23.503 27.976 54.833 72.625 Population Sample Sigma 95%

1.96 IRM Summary - After 1 st Outlier Count Mean Sigma Conf Sigma Amp Zero I mVDC 60 0.1365 8.434 10.039 19.676 Amp Zero 2 mVDC 60 0.860 21.559 25.662 50.298 Population IRM Summary - After 1st Outlier in %

Sample Sigma 95%

1.96 Span Count Mean Sigma Conf Sigma j Amp Zero 1

% Span 60 0.001%

0.084%

0.100%

0.197% J Amp Zero 2

% Span 60 0.009%

0.216%

0.257%

0.503% I NN=-outlier

DC Amplifier Zero Drift 60 40 -

20 aO' E

-20 -60 I

MU I

U M.

U0

• Zero 1 Drift l e Zero 2 Drift

'00 20 0

500 1000 1500 Calibration Interval Days

Extended Interval Trip Calibration Data:

IRM 11 14/11/1994 4/9/1997 9/2811999 5/15/2002 4/19/2003 4/11/1994 2/2)1995 2128/1995 4/26/1998 4/29/2001 3/13/2003 4/20/2003 Upscale & Downscale Trli Cal.

IRM 12 7.6.7 a. (%)

107.50 107.50 110.00 110.00 107.50 110.00 109.00 108.00 107.50 107.50 107.50 107.50

b. (VDC) 0.864 0.850 0.861 0.867 0.855 0.867 0.865 0.858 0.857 0.857 0.857 0.857 7.6.8 a. (%)

107.50 107.50 110.00 110.00 107.50 110.00 107.50 108.00 107.50 107.50 107.50 107.50

b. (VDC) 0.864 0.850 0.861 0.858 0.855 0.867 0.855 0.858 0.857 0.857 0.857 0.857 7.6.9 a. (%)

118.00 117.50 120.00 120.00 117.50 117.50 119.00 120.00 120.00 117.50 117.50 117.50

b. (VDC) 0.944 0.940 0.940 0.937 0.935 0.940 0.944 0.952 0.947 0.945 0.937 0.937 7.6.10 a. (%)

118.00 117.50 120.00 120.00 117.50 117.50 118.00 118.00 120.00 117.50 117.50 117.50

b. (VDC) 0.944 0.940 0.940 0.937 0.935 0.940 0.943 0.941 0.947 0.945 0.937 0.937 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.063 0.060 0.063 0.062 0.063 0.062 0.063 0.062 0.063 0.063 0.062 0.062 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.063 0.060 0.063 0.062 0.063 0.062 0.063 0.063 0.063 0.063 0.062 0.062 IRM 13 14/12/1994 7/11/1994 4/26/1998 2/25/2000 12/6/2002 4/20/2003 4/12/1994 7/11/1994 3/3/1995 4/29/1998 5/1/2001 4/20/2003 Upscale & Downscale Trip Cal.

l IRM 14 7.6.7 a. (%)

107.50 107.50 107.50 110.00 110.00 110.00 110.00 107.50 118.00 107.50 107.50 110.00

b. (VDC) 0.860 0.860 0.864 0.868 0.864 0.862 0.865 0.863 0.858 0.866 0.860 0.867 7.6.8 a. (%)

107.50 107.50 107.50 110.00 110.00 110.00 110.00 107.50 118.00 107.50 107.50 110.00

b. (VDC) 0.860 0.860 0.864 0.868 0.864 0.862 0.865 0.863 0.860 0.866 0.860 0.867 7.6.9 a. (%)

117.50 117.50 117.50 120.00 117.50 120.00 117.50 117.50 118.00 117.50 1 117.50 117.50

b. (VDC) 0.931 0.940 0.946 0.948 0.944 0.942 0.936 0.940 0.939 0.932 0.930 0.934 7.6.10 a. (%)

117.50 117.50 117.50 120.00 117.50 120.00 117.50 117.50 118.00 117.50 117.50 117.50

b. (VDC) 0.931 0.940 0.946 0.948 0.944 0.942 0.936 0.940 0.939 0.932 0.930 0.934 7.6.11 a. (%)

7.500 7.500 7.500 5.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.065 0.068 0.060 0.059 0.059 0.058 0.061 0.061 0.061 0.061 0.060 0.059 7.6.12 a. (%)

7.500 7.500 7.500 5.000 7.500 7.500 1

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.065 0.060 0.060 0.059 0.059 0.058 0.061 0.061 l

0.061 l

0.061 l

0.060 0.059 IRM 15 14/12/1994 7/25/1996 4/6/1999 4/22/2001 12/11/2002 4/20/2003 4/12/1994 7/25/1996 5/15/1999 5/6/2002 3/11/2003 4/20/2003 Upscale & Downscale Trip Cal.

I___IIRM 16 1

1 1

7.6.7 a. (%)

108.00 110.00 110.00 110.00 110.00 107.50 107.50 110.00 110.00 107.50 107.50 107.50

b. (VDC) 0.859 0.872 0.866 0.870 0.869 0.869 0.860 0.871 0.867 0.862 0.860 0.866 7.6.8 a. (%)

108.00 110.00 110.00 110.00 110.00 107.50 107.50 110.00 110.00 107.50 107.50 107.50

b. (VDC) 0.857 0.872 0.866 0.870 0.869 0.869 0.860 0.871 0.867 0.862 0.860 0.866 7.6.9 a. (%)

118.00 120.00 120.00 120.00 120.00 117.50 120.00 120.00 120.00 120.00 120.00 120.00

b. (VDC) 0.935 0.950 0.946 0.950 0.945 0.944 0.942 0.948 0.944 0.953 0.951 0.943 7.6.10 a. (%)

118.00 120.00 120.00 120.00 120.00 117.50 120.00 120.00 120.00 120.00 120.00 120.00

b. (VDC) 0.935 0.950 0.946 0.950 0.945 0.944 0.942 0.948 0.944 0.953 0.951 0.943 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.065 0.064 0.064 0.061 0.064 0.064 0.058 0.060 0.058 0.059 0.058 0.058 7.6.12 a. (%)

1 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 1 7.500 7.500 7.500 7.500

b. (VDC) l 0.065 0.064 0.064 0.061 0.064 0.064 0.058 0.060 l 0.058 0.059 0.057 0.058

IRM 17 14/12/1994 3/1/1995 4/30/1998 4/26/2001 3/12/2003 4/20/2003 4/11/1994 2/3/1995 3/1/1995 4/27/1998 4/26/2001 4/20/2003 Upscale & Downscale Tri Cal.

IRM 18 7.6.7 a. (%)

107.00 108.00 107.50 107.50 107.50 110.00 108.00 109.00 107.50 107.50 107.50 107.50

b. (VDC) 0.856 0.870 0.855 0.864 0.871 0.871 0.867 0.876 0.864 0.867 0.853 0.859 7.6.8 a. (%)

107.00 107.50 107.50 107.50 107.50 110.00 108.00 107.00 107.50 107.50 107.50 107.50

b. (VDC) 0.856 0.860 0.855 0.864 0.871 0.871 0.867 0.866 0.864 0.867 0.853 0.859 7.6.9 a. (%)

118.00 118.00 117.50 117.50 117.50 120.00 119.00 118.00 119.00 117.50 117.50 120.00

b. (VDC) 0.934 0.948 0.943 0.938 0.940 0.942 0.942 0.946 0.955 0.951 0.941 0.949 7.6.10 a. (%)

118.00 117.50 117.50 117.50 117.50 120.00 119.00 118.00 118.00 117.50 117.50 120.00

b. (VDC) 0.934 0.937 0.943 0.938 0.940 0.942 0.942 0.946 0.944 0.951 0.941 0.949 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 6.500 6.500 60.000 7.500 7.500 7.500

b. (VDC) 0.060 0.057 0.063 0.062 0.062 0.061 0.060 0.058 0.058 0.063 0.065 0.061 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 6.500 6.500 70.000 7.500 7.500 7.500

b. (VDC) 0.060 0.060 0.063 0.062 0.062 0.061 1

0.060 0.058 0.063 0.063 0.065 0.061 Interval Rod Block Upscale Trip Downscale Trip Interval Rod Block Upscale Trip Downscale Trip Interval Rod Block Upscale Trip Downscale Trip Trip Raw Drift Values In % Span as calculated based on trip voltages:

1094 902 960 339 297 26 1153

-1.400%

1.100%

0.600%

-0.300%

-0.200%

0.300%

-0.100%

-0.400%

0.000%

-0.300%

-0.200%

0.400%

0.900%

0.600%

-0.300%

0.300%

-0.100%

0.100%

0.100%

-0.100%

0.000%

670 1015 135 90 235 1153 1098 0.400%

-0.400%

-0.200%

-0.200%

-0.500%

0.600%

-0.600%

0.200%

-0.400%

• 0.200%

0.400%

-0.100%

-0.700%

-0.200%

-0.100%

0.000%

-0.100%

0.000%

0.000%

0.000%

-0.100%

130 835 1024 1087 309 40 323 0.000%

1.100%

-0.400%

-0.500%

-0.200%

0.600%

1.400%

-0.100%

0.600%

-0.400%

0.900%

-0.200%

-0.800%

1.400%

0.000%

0.200%

-0.200%

0.100%

-0.100%

0.100%

-0.300%

1099 683 38 90 1385 0.000%

0.000%

0.000%

0.000%

0.400%

-0.200%

-0.800%

0.000%

0.900%

0.600%

0.000%

-0.100%

0.000%

0.300%

0.000%

719 835 985 747 598 0.700%

1.500%

-0.600%

0.400%

-0.100%

0.400%

1.500%

-0.400%

0.400%

-0.500%

-0.100%

-0.100%

0.000%

-0.300%

0.300%

1156 1092 685 39 298

-0.500%

0.900%

0.700%

0.000%

0.900%

0.600%

-0.500%

0.200%

0.200%

0.400%

0.300%

-0.100%

0.000%

-0.100%

-0.200%

Interval Rod Block Upscale Trip Downscale Trip 26 1153 1095 724

-0.200%

0.300%

-1.400%

0.600%

0.900%

0.700%

-1.000%

0.800%

0.000%

0.000%

0.200%

-0.400%

Population Sample Sigma 95%

1.96 Outier-IRM Trip EXT Drift Count Mean Sigma Conf Sigma 2.87'sigma Rod Block Upscale Trip Downscale Trip

% Span 1

40 0.118%

1 0.656%

l 0.819%

1 1.605% T 1.884%

Therearenooutliersinthedatall

% Span 40 0.140%

1 0.607%

1 0.757%

1 1.484% 1 1.876%

% Span 40 1 -0.020%

1 0.167%

1 0.208%

1 0.408% 1 0.515%

IRM Trip Drift 2.0%

1.5%

V 1.0%

a 0.5%

hU 0.0%

0.

CX -0.5%

-1.0%

-1.5%

-2.0%

• Rod Block

• Upscale Trip A Downscale Trip 0

500 1000 Calibration Interval Days 1500

Extended Calibration Data for INOP Trip:

IRM 11 14/11/1994 7/24/1996 4/7/1999 5/1/2001 4/19/2003 4/11/1994 4/9/1997 4/7/1999 4/29/2001 4/20/2003 HV Power SuDPlV & Inop Trip IRM 12 7.5.4 (VDC) 75.00 75.00 75.00 79.60 80.00 76.00 75.00 75.00 81.26 80.00

b. (VDC) 75.00 75.00 80.00 79.60 80.00 76.00 75.00 80.00 81.26 80.00 IRM 13 14/12/19941 3/3/1995 3/29/1996 4/8/1999 5/8/2002 4/20/2003 4/12/1994 7/11/1994 4/9/1997 4/8/1999 5/1/2001 4/20/2003 HV Power SuPDIv & lnoD Trip IRM 14 1

7.5.4 (VDC) 75.00 79.29 79.00 76.00 81.00 81.00 74.00 73.90 75.00 75.00 81.00 80.70

b. (VDC) 75.00 76.03 75.00 80.00 81.00 81.00 74.00 75.10 75.00 79.50 81.00 80.70 IRM 15 14/12/199417/25/1996 4/29/1998 l 4/6/1999 5/6/2002 4/20/2003 4/12/1994 7/25/1996 4/5/1999 5/1/2001 4/20/2003 HV Power Supply & Inop Trig J

IRM 16 1 1

1 1

1 7.5.4 (VDC) 75.20 75.00 74.00 1

75.10 79.60 79.60 75.00 75.20 74.10 80.00 79.50

b. (VDC) 75.20 1 75.00 75.00 1

79.70 79.60 79.60 75.00 75.20 79.80 80.00 79.50 IRM 17 14/12/19941 3/1/1995 4/6/1999 1 4/26/2001 4/20/2003 4/11/1994 3/1/1995 4/27/1998 4/6/1999 4/26/2001 4/20/2003 HV Power Supply & Inop Trip I

I l

IRM 18 I

I I

I I

7.5.4 (VDC) 75.00 76.50 1 74.20 1

81.20 81.00 75.60 76.42 75.00 75.10 80.30 81.40

b. (VDC) 75.00 75.00 80.70 81.20 81.00 75.60 75.36 75.00 80.20 80.30 81.40 Interval Inop Trip Interval Inop Trip Interval Inop Trip Raw Drift Data in Volts:

724 835 987 755 1.100 0.000 0.000

-0.400 1126 347 90 1003 1.000 0.000

-0.100

-0.100 835 984 757 719 0.200

-1.100 0.200

-0.500 718 1094 728 753 721 325 392 1105 0.400

-1.000 0.000 1.260

-1.260 l

2.970 1.000 729 754 719 835 643 342 1126 349 0.000 1.500

-0.300

-0.200

-1.000 0.100

-0.100 0.000 323 1497 751 724 324 1153 344 751 1.500

-0.800 0.500

-0.200 0.820

-0.360 0.100 0.100 Population I

I Sample Sigma 95%

1.96 Outlier -

IRM Trip Count Mean Sigma Conf Sigma 2.87*sigmal INOPI np Volts 36 1

0.267 1

1.087 1

1.380 1 2.706 1

3.118 ououtlier Population I

Sample Sigma 95%

1.96 IRM Trip After 1 st Outlier C

Count Mean Sigma Conf Sigma_l INOP Trip Volts 35 1

0.152 T 0.85-2T 1 1082~ 1 2.1211 Cll

IRM INOP Trip EXT Drift 3.500 3.000 2.500 2.000 1.500 C. 4_

£*

LI 1.UUU 0.500 0

0.000 _

{

An isnn

• INOP TRIP

-1.000

-1.500 9

0 500 1000 1500 2000 Calibration Interval Days

Intermediate Range Monitor Calibration Data All Data TOLERANCES 4/11/1994 7/11/1994 2/2/1995 2/28/1995 3/28/1996 7/24/1996 4/9/1997 4/27/1998 4/30/1998 417/1999 IRM 11 DC Amplifier Zero Cal.

l 7.4.5 (AF-mVDC) 0.0 (-20.0 to 20.0)

-2.000 9.100 2.100 l0.500

-12.700 10.200

-8.900

-9.100

-8.800

-11.400 7.4.7 (AL-mVDC) 0.0 (-20.0 to 20.0)

-2.000 9.100 2.100

-0.500

-12.700 10.200 0.200

-9.100

-8.800 0.400 7.4.9 (AF-mVDC) 0.0 (-20.0 to 20.0) 3.500 36.500

-18.100

-7.200

-9.400 28.300 29.300

.18.900

-19.100 10.000 7.4.11 (AL-mVDC) 0.0 (-20.0 to 20.0) 3.500 3.000 0.000

-7.200 9.400 5.000 1.200

-18.900 2.900 1.000 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Inop Trip I.

7.5.2 (VDC) 100 (97 to 103) 100.000 100.100 99.720 100.160 100.000 99.800 100.000 100.000 100.000 100.000 7.5.4 (VDC) 75 (73 to 77) 75.000 75.000 75.500 75.680 76.000 75.000 76.000 76.000 75.000 75.000 7.5.5 (NIA) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 75.000 75.000 75.500 75.680 76.000 75.000 76.000 76.000 75.000 80.000 7.5.7 (VDC) 100 (97 to 103) 100.000 100.000 100.210 100.100 100.000 99.900 100.000 100.000 100.000 100.000 Upscale & Downscale Trio Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 110.000 110.000 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.864 0.861 0.860 0.873 0.847 0.853 0.850 0.850 0.854 0.870 7.6.8 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 110.000 110.000 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.864 0.861 0.860 0.873 0.847 0.853 0.850 0.850 0.854 0.870 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 117.500 117.500 120.000 117.500 117.500 117.500 117.500 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.944 0.940 0.940 0.951 0.930 0.935 0.940 0.940 0.933 0.934 7.6.10 a. (%)

117.5 (115.0 to 120.0) 118.000 117.500 117.500 120.000 117.500 117.500 117.500 117.500 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.944 0.940 0.940 0.951 0.930 0.935 0.940 0.940 0.933 0.934 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.063 0.062 0.062 0.063 0.062 0.060 0.062 0.062 0.063 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.063 0.062 0.062 0.063 0.062 0.062 0.060 0.062 0.062 0.063

All Data TOLERANCES 5/15/1999 9/28/1999 2V24/2000 2/25/2000 5/1/2001 5/8/2002 5/15/2002 12/5/2002 12/12/2002 3/13/2003 4/19/2003 IRM 11 DC AmplIfier Zero Cal.

7.4.5 (AF-mVDC) 0.0 (-20.0 to 20.0) 4.100

-1.200 21.200 0.100 2.100

-9.400 0.500 2.800 1.900

-6.100

-3.300 7.4.7 (AL-mVDC) 0.0 (-20.0 to 20.0) 4.100

-1.200

-2.600 0.100 2.100 0.000 0.500 2.800 1.900

-6.100

-3.300 7.4.9 (AF-mVDC) 0.0 (-20.0 to 20.0) 14.800 8.500 19.000 10.000 11.300

-3.000

-4.000 2.800 1.900 2.100 10.000 7.4.11 (AL-mVDC) 0.0 (-20.0 to 20.0) 14.800 8.500 1.900 10.000 0.000

-3.000

-4.000 2.800 1.900 2.100 10.000 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a 0.000 n/a n/a n/a n/a n/a n/a HV Power Supply & Inop T ID 7.5.2 (VDC) 100 (97 to 103) 100.000 100.200 100.200 100.200 99.820 100.200 100.000 100.000 100.000 99.930 100.000 7.5.4 (VDC) 75 (73 to 77) 79.000 79.000 79.500 80.000 79.600 79.600 79.400 80.000 80.000 79.650 80.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 79.00 79.000 79.500 80.000 79.600 79.600 79.400 80.000 80.000 79.650 80.000 7.5.7 (VDC) 100 (97 to 103) 99.950 100.000 100.200 100.000 99.980 100.000 100.000 100.000 100.000 99.970 100.000 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 109.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.871 0.861 0.862 0.862 0.859 0.870 0.867 0.867 0.863 0.866 0.855 7.6.8 a. (%)

107.5(105.0to110.0) 109.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.871 0.861 0.862 0.862 0.859 0.870 0.858 0.867 0.863 0.866 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 120.000 117.500 117.500 117.500 120.000 117.500 120.000 119.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.940 0.937 0.939 0.931 0.937 0.937 0.933 0.942 0.944 0.935 7.6.10 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 120.000 117.500 117.500 117.500 120.000 117.500 120.000 119.000

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.940 0.937 0.939 0.931 0.937 0.937 0.933 0.942 0.944 7.6.11 a. (%)

7.5(6.5 to 8.5) 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.063 0.063 0.061 0.063 0.062 0.063 0.062 0.063 0.063 0.062 0.063 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.063 0.063 0.061 0.063 0.062 0.063 0.062 0.063 0.063 0.062 0.063

Intermediate Range Monitor Extended Calibration IRM 11 Extended Data Extended Data l

4/11/1994 7/11/1994 2/2/1995 7/24/1996 4/9/1997 4/30/1998 4/7/1999 2/24/2000 5/1/2001 5/8/2002 4/19/2003 DC Amplifier Zero Cal.

l 7.4.5 (AF-mVDC)

-2.000 9.100 2.100 10.200

-8.900

-8.800

-11.400 21.200 2.100

-9.400

-3.300 7.4.7 (AL-mVDC)

-2.000 9.100 2.100 10.200 0.200

-8.800 0.400

-2.600 2.100 0.000

-3.300 7.4.9 (AF-mVDC) 3.500 36.500

-18.100 28.300 29.300

-19.100 10.000 19.000 11.300

-3.000 10.000 7.4.11 (AL-mVDC) 3.500 3.000 0.000 5.000 1.200 2.900 1.000 1.900 0.000

-3.000 10.000 4/11/1994 4/9/1997 9/28/1999 5/15/2002 4/19/2003 Upscale & Downscal Trip Cal.

l 7.6.7 a. (%)

107.500 107.500 110.000 110.000 107.500

b. (VDC) 0.864 0.850 0.861 0.867 0.855 7.6.8 a. (%)

107.500 107.500 110.000 110.000 107.500

b. (VDC) 0.864 0.850 0.861 0.858 0.855 7.6.9 a.l()

118.000 117.500 120.000 120.000 117.500

b. (VDC) 0.944 0.940 0.940 0.937 0.935 7.6.10 a. (%)

118.000 117.500 120.000 120.000 117.500

b. (VDC) 0.944 0.940 0.940 0.937 0.935 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.063 0.060 0.063 0.062 0.063 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.063 0.060 0.063 0.062 0.063 4/11/1994 7/24/1996 4/7/1999 5/1/2001 4/19/2003 HV Power Supplv & Inop Trip j

7.5.4 (VDC) 75.000 75.000 75.000 79.600 80.000

b. (VDC) 75.000 75.000 80.000 79.600 80.000

Intermediate Range Monitor Calibration All Data TOLERANCES 4/11/1994 7/111/1994 2/2/1995 2/28/1995 3/28/1996 7/24/1996 4/9/1997 4/26/1998 4/29/1998 41/71999 IRM12 12 1

1 T__

DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-2.200 3.500

-1.700

-2.240

-4.100 6.200 0.340 0.900 1.330

-0.800 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-2.200 3.500

-1.700

-2.240

-4.100 6.200 0.340 0.900 1.280

-0.800 7.4.9 (mVDC) 0.0 (-20.0 to 20.0)

-18.000 0.200

-15.480

-0.610

-5.000 8.500

-0.360

-12.000

-11.500

-17.200 7.4.11 (mVDC) 0.0 (-20.0 to 20.0)

-18.000 0.200 1.000 0.610

-5.000 8.500

.0.360

-12.000

-11.500 0.800 77.4.15 (%)

O.(not on eg to2.5/)7 50.0001 0.000l 0.000l 0.000 0.000 0.000 0.000 0.0

°°°°0 l

°° 0°°° 7.4.16 (%

0.0O(notonpegto2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply Inop Trip o I

I

__TI

_T_

7.5.2 (VDC) 100 (97 to 103) 99.700 99.900 100.170 99.710 100.000 100.000 100.000 99.000 100.000 100.000 7.5.4 (VDC) 75 (73 to 77) 76.000 75.200 75.560 75.950 76.000 75.200 75.000 76.000 75.100 75.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 76.000 75.200 75.560 75.950 76.000 75.200 75.000 76.000 75.100 80.000 7.5.7 (VDC) 100 (97 to 103) 100.000 100.000 99.770 100.000 100.000 100.000 100.000 100.000 100.000 100.000 Upscale & Downseale TriP Cal.

T I

I_

TIII_

7.6.7 a. (%)

107.5(105.0 to 110.0) 110.000 107.500 109.000 108.000 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.863 0.865 0.858 0.854 0.862 0.861 0.857 0.856 0.861 7.6.8 a. (%)

107.5 (105.0 to 110.0) 110.000 107.500 107.500 108.000 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.863 0.855 0.858 0.854 0.862 0.861 0.857 0.856 0.861 7.6.9 a. (%)

117.5 (115.0 to 120.0) 117.500 117.500 119.000 120.000 117.500 117.500 117.500 120.000 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.940 0.942 0.944 0.952 0.939 0.944 0.940 0.947 0.944 0.941 7.6.10 a. (%)

117.5(115.0to120.0) 117.500 117.500 118.000 118.000 117.500 117.500 117.500 120.000 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.940 0.942 0.943 0.941 0.939 0.944 0.940 0.947 0.944 0.941 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.062 0.063 0.063 0.062 0.065 0.063 0.063 0.063 0.064 0.062 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.062 0.063 0.063 0.063 0.065 0.063 0.063 0.063 0.064 0.062

All Data TOLERANCES 5/15/1999 9/28/1999 2/24/2000 2/25/2000 4/29/2001 5/8/2002 5/15/2002 12/5/2002 12112/2002 3/13/2003 4/20/2003 IRM 12 l

DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0) 1.700 6.800

-2.100

-1.900

-0.890

-1.400 0.000 0.000 0.000

-4.670

-3.100 7.4.7 (mVDC) 0.0 (-20.0 to 20.0) 1.700 6.800

-2.100

-1.900

-0.890

-1.400 0.000 0.000 0.000

-4.670

-3.100 7.4.9 (mVDC) 0.0 (-20.n to 20.0) 11.250 1.000

-23.700 4.700 5.200

-15.300 0.000 5.100 0.000 07.400 4.600 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 11.250 1.000 3.400 4.700 5.200 0.100 0.000 5.100 0.000

-7.400

-4.600 7.4.15 (%)

0.0 (nOt On Pe0 to 2.5%)

1.250 1.000 3.400 4.700 5.200 0.100 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on Peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power SUPplV & InoP TriP D

7.5.2 (VDC) 100 (97 to 103) 100.400 99.000 100.000 98.900 99.860 100.000 99.400 100.000 99.780 100.000 100.000 7.5.4 (VDC) 75(73 to 77) 80.000 81.000 80.000 80.600 81.260 80.500 80.000 81.000 81.300 80.300 80.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 80.000 81.000 80.000 80.600 81.260 80.500 80.000 81.000 81.300 80.300 80.000 7.5.7 (VDC) 100 (97 to 103) 100.000 100.000 100.000 100.000 100.200 100.000 100.000 100.000 100.100 100.000 100.000 UPscale & Downsc le Trip Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 108.000 107.500 110.000 107.500 107.500 107.500 107.500 107.500 110.000 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.861 0.856 0.857 0.860 0.857 0.856 0.857 0.862 0.861 0.857 0.857 7.6.8 a. (%)

107.5(105.0 to 110.0) 108.000 107.500 110.000 107.500 107.500 107.500 107.500 107.500 110.000 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.861 0.856 0.857 0.860 0.857 0.856 0.857 0.862 0.861 0.857 0.857 7.6.9 a. (%)

117.5 (115.0to 120.0) 118.000 117.500 120.000 117.500 117.500 120.000 120.000 117.500 120.000 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.946 0.948 0.940 0.945 0.947 0.947 0.942 0.940 0.937 0.937 7.6.10 a. (%)

117.5 (115.0 to 120.0) 118.000 117.500 120.000 117.500 117.500 120.000 120.000 117.500 120.000 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.946 0.948 0.940 0.945 0.947 0.947 0.942 0.940 0.937 0.937 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.063 0.061 0.064 0.063 0.063 0.063 0.062 0.063 0.063 0.062 0.062 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 tO 0.068) 0.063 0.061 0.064 0.063 0.063 0.063 0.062 0.063 0.063 0.062 0.062

Intermediate Range Monitor Extended Calibration IRM 12 Extended Data Extended Data l

4/11/1994 2/2/1995 4/29/1998 4/7/1999 2/24/2000 5/8/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (mVDC)

-2.200

-1.700 1.330

-0.800

-2.100

-1.400

-3.100 7.4.7 (mVDC)

-2.200

-1.700 1.280

-0.800

-2.100

-1.400

-3.100 7.4.9 (mVDC)

-18.000

-15.480

-11.500

-17.200

-23.700

-15.300

-4.600 7.4.11 (mVDC)

-18.000 1.000

-11.500 0.800 3.400 0.100

-4.600 4/11/1994 2l201995 2128/1995 4/26/1998 4/29/2001 3/13/2003 4/20/2003 Upscale & Downscale Trip Cal.

l l

l l

7.6.7 a.

110.000 109.000 108.000 107.500 107.500 107.500 107.500

b. (VDC) 0.867 0.865 0.858 0.857 0.857 0.857 0.857 7.6.8 a. (%)

110.000 107.500 108.000 107.500 107.500 107.500 107.500

b. (VDC) 0.867 0.855 0.858 0.857 0.857 0.857 0.857 7.6.9 a. (%)

117.500 119.000 120.000 120.000 117.500 117.500 117.500

b. (VDC) 0.940 0.944 0.952 0.947 0.945 0.937 0.937 7.6.10 a. (%)

117.500 118.000 118.000 120.000 117.500 117.500 l 117.500

b. (VDC) 0.940 0.943 0.941 0.947 0.945 0.937 0.937 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.062 0.063 0.062 0.063 0.063 0.062 0.062 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.062 0.063 0.063 0.063 0.063 0.062 0.062 l

4/11/1994 4/9/1997 4/7/1999 4/29/2001 4/20/2003 HV Power Supplv & Inop Trip I

I I

7.5.4 VC 76.000 75.000 75.000 81.260 80.000

b. VC 76.000 75.000 80.000 81.260 80.000

Intermediate Range Monitor Calibration All Data TOLERANCES 4/12/1994 7/11/1994 2/2/1995 3/3/1995 3/29/1996 7/24/1996 4/10/1997 4/26/1998 4/29/1998 4/8/1999 IRM 13 DC AmplIfier Zero Cal.

7.4.5 (mVDC) 0.0 (.20.0 to 20.0)

-2.000 2.000

-1.250

-0.390

-5.100 0.580

-1.550

-8.860

-8.800

-7.900 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-2.000 2.000

-1.250

-0.390

-5.100 0.580

-1.550

-8.860

.8.800

-7.900 7.4.9 (mVDC) 0.0 (-20.0 to 20.0)

-10.000 11.000

-16.500 2.260

-18.600 26.240 12.840 3.520 8.500

-35.700 7.4.11 (mVDC) 0.0 (-20.0 to 20.0)

-10.000 11.000 0.900 2.260

-18.600 1.600 0.280 3.520 8.500 0.700 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Inop TriD 7.5.2 (VDC) 100 (97 to 103) 99.900 100.200 99.870 104.400 99.000 100.000 100.000 100.240 100.000 100.000 7.5.4 (VDC) 75 (73 to 77) 75.000 74.400 74.800 79.290 79.000 75.000 75.000 74.760 75.000 76.000 7.5.5 (N/A) j n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) l 75 (73 to 77) 75.000 74.400 74.800 76.030 75.000 75.000 75.000 74.760 75.000 80.000 7.5.7 (VDC) 100(97 to 103) 100.000 100.000 100.200 100.630 100.000 100.000 100.000 99.950 100.000 100.000 Upscale & Downsea le Trip Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 109.000 109.000 110.000 110.000 110.000 107.500 110.000 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.860 0.860 0.860 0.862 0.866 0.864 0.864 0.864 0.863 7.6.8 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 109.000 109.000 110.000 110.000 110.000 107.500 110.000 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.860 0.860 0.860 0.862 0.866 0.864 0.864 0.864 0.863 7.6.9 a. (%)

117.5 (115.0 to 120.0) 117.500 117.500 117.500 118.000 117.500 120.000 120.000 117.500 120.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.931 0.940 0.943 0.941 0.940 0.948 0.946 0.946 0.946 0.945 7.6.10 a. (%)

117.5(115.0 to 120.0) 117.500 117.500 117.500 118.000 117.500 120.000 120.000 117.500 120.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.931 0.940 0.943 0.941 0.940 0.948 0.946 0.946 0.946 0.945 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.065 0.068 0.057 0.061 0.060 0.060 0.058 0.060 0.060 0.058 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.065 0.060 0.057 0.061 0.060 0.060 0.058 0.060 0.060 0.058

I TOLERANCES 5t15/1999 9/29/1999 2125/2000 4/30/2001 5/8/2002 5/15/2002 12/6/2002 12/12/2002 3/13/2003 4/20/2003 IRM 13 l

DC Amplifier Zero Cal.

7.4.5 (mVDC) 0 0.0 (-20.0 to 20.0)

-4.500

-6.000

-13.500

-1.300 1.700 0.000 0.700 0.600 2.700 8.100 7.4.7 (mVDC) l 0.0 (.20.0 to 20.0)

• 4.500

-6.000

-13.500

-1.300 1.700 0.000 0.700 0.600 2.700 8.100 7.4.9 (mVDC) 0.0 (-20.0 to 20.0)

-4.000

-24.100 5.500 21.600

-40.100 0.000 47.000 3.000 18.000

-75.400 7.4.11 (mVDC) 0.0 (-20.0 to 20.0)

-4.000 2.600 5.500 3.000 0.800 0.000 2.600 3.000 0.000 4.200 7.4.15(%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16(%)

0.0 (not on peg to 2.5%)

n/a n/a n/a 0.000 n/a n/a n/a n/a n/a n/a HV Power Supply & Inop Trip 7.5.2 (VDC) 100 (97 to 103) 100.400 99.900 100.000 100.280 100.000 100.000 99.000 100.000 100.000 100.000 7.5.4 (VDC) 75(73 to 77) 80.300 79.400 80.200 81.700 81.000 81.000 80.000 80.000 81.000 81.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75(73 to 77) 80.300 79.400 80.200 81.700 81.000 81.000 80.000 80.000 81.000 81.000 7.5.7 (VDC) 100 (97 to 103) 100.000 100.100 100.000 100.000 100.000 100.000 100.000 100.000 99.970 100.000 Upscale & Downsc IQ Trip Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 108.000 107.500 110.000 110.000 110.000 107.500 110.000 110.000 110.000 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.810 0.865 0.868 0.860 0.864 0.863 0.864 0.865 0.866 0.862 7.6.8 a. (%)

107.5 (105.0 to 110.0) 108.000 107.500 110.000 110.000 110.000 107.500 110.000 110.000 110.000 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.861 0.865 0.868 0.860 0.864 0.863 0.864 0.865 0.866 0.862 7.6.9 a. (%)

117.5(115.0 to 120.0) 118.000 120.000 120.000 120.000 120.000 120.000 117.500 120.000 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.945 0.948 0.946 0.944 0.944 0.944 0.945 0.946 0.942 7.6.10 a. (%)

117.5(115.0 to 120.0) 118.000 120.000 120.000 120.000 120.000 120.000 117.500 120.000 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.945 0.948 0.946 0.944 0.944 0.944 0.945 0.946 0.942 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 5.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.059 0.059 0.059 0.059 0.058 0.057 0.059 0.059 0.058 0.058 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 5.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.059 0.059 0.059 0.059 0.058 0.057 0.059 0.059 0.058 0.058

Intermediate Range Monitor Extended Calibration IRM 13 Extended Data Extended Data l

4/1211994 2/2/1995 7/24/1996 4/10/1997 4/8/1999 9/29/1999 4/30/2001 5/8/2002 12/6/2002 3/13/2003 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (mVDC)

-2.000

-1.250 0.580

-1.550

-7.900

-6.000

-1.300 1.700 0.700 2.700 8.100 7.4.7 (mVDC)

-2.000

-1.250 0.580

-1.550

-7.900

-6.000

-1.300 1.700 0.700 2.700 8.100 7.4.9 (mVDC)

-10.000

-16.500 26.240 12.840

-35.700

-24.100 21.600

-40.100 47.000 18.000

-75.400 7.4.11 (mVDC)

-10.000 0.900 1.600 0.280 0.700 2.600 3.000 0.800 2.600 0.000 4.200 4/12/1994 7/11/1994 4/26/1998 2/25/2000 12/6/2002 4/20/2003 Upscale & Downscal Trip Cal.

__ll

_l 7.6.7 a. (%)

107.500 107.500 107.500 110.000 110.000 110.000

b. (VDC) 0.860 0.860 0.864 0.868 0.864 0.862 7.6.8 a. (%)

107.500 107.500 107.500 110.000 110.000 110.000

b. (VDC) 0.860 0.860 0.864 0.868 0.864 0.862 7.6.9 a.

117.500 117.500 117.500 120.000 117.500 120.000

b. (VDC) 0.931 0.940 0.946 0.948 0.944 0.942 7.6.10 a. (%)

117.500 117.500 117.500 120.000 117.500 120.000

b. (VDC) 0.931 0.940 0.946 0.948 0.944 0.942 7.6.11 a. (%)

7.500 7.500 7.500 5.000 7.500 7.500

b. (VDC) 0.065 0.068 0.060 0.059 0.059 0.058 7.6.12 a. (%)

7.500 7.500 7.500 5.000 1 7.500 7.500

b. (VDC) 0.065 0.060 0.060 0.059 l

0.059 l

0.058 1

4/12/1994 3/3/1995 3/29/1996 4/8/1999 5/8/2002 4/20/2003 HV Power Supplv & Inop TriD 7.5.4 (VDC) 75.000 79.290 79.000 76.000 81.000 81.000

b. (VDC) 75.000 76.030 75.000 80.000 81.000 81.000

Intermediate Range Monitor Calibration All Data TOLERANCES 4/12/1994 7/11/1994 2/2/1995 3/3/1995 3/29/1996 7/25/1996 4/9/1997 4/27/1998 4/29/1998 4/8/1999 IRM 14 DC Ampllfier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-1.500 66.000

-3.600

-5.030

-6.400 2.930

-2.500

-1.300

-1.500

-3.100 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-1.500 0.100

-3.600

-5.030

-6.400 2.930

-2.500

-1.300

-1.500

-3.100 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 2.300 7.000

-5.500

-9.800

-13.600 8.310 3.200

-13.100

-15.700

-14.500 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 2.300 7.000

-5.500

.9.800

-13.600 8.310 32.000

.13.100

-15.700

-14.500 7.4.15(%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16(%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a 0.000 n/a n/a n/a HV Power SupplV & Inop Trip 7.5.2 (VDC) 100 (97 to 103) 100.000 100.200 99.960 99.870 100.000 100.000 100.000 100.150 100.000 100.000 7.5.4 (VDC) 75 (73 to 77) 74.000 73.900 75.700 76.310 76.000 75.000 75.000 75.000 75.000 75.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 74.000 75.100 75.700 76.310 76.000 75.000 75.000 75.000 75.000 79.500 7.5.7 (VDC) 100 (97 to 103) 100.000 100.000 99.940 99.930 100.000 100.000 100.000 99.940 100.000 100.000 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 110.000 107.500 107.500 118.000 105.000 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.865 0.863 0.860 0.858 0.857 0.862 0.868 0.870 0.866 0.861 7.6.8 a. (%)

107.5(105.0 to 110.0) 110.000 107.500 107.500 118.000 105.000 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.865 0.863 0.860 0.860 0.857 0.862 0.868 0.870 0.866 0.861 7.6.9 a. (%)

117.5(115.0 to 120.0) 117.500 117.500 117.500 118.000 117.500 120.000 117.500 117.500 117.500 117.500

b. (VDC) 0.940(0.920 to 0.960) 0.936 0.940 0.940 0.939 0.937 0.940 0.945 0.930 0.932 0.936 7.6.10 a. (%)

117.5(115.0 to 120.0) 117.500 117.500 117.500 118.000 117.500 120.000 117.500 117.500 117.500 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.936 0.940 0.940 0.939 0.937 0.940 0.945 0.930 0.932 0.936 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.061 0.061 0.060 0.061 0.060 0.061 0.060 0.060 0.061 0.058 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.061 0.061 0.060 0.061 0.060 0.061 0.060 0.060 0.061 0.058

All Data TOLERANCES 5/15/1999 9/29/1999 212412000 2/2512000 511/2001 51812002 5/15/2002 12/6/2002 12112/2002 3114/2003 4/20/2003 IR M 14_

D~C Amplifer Zero Cal.__

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-0.990 4.100

-4.500

-4.200

-2.900

-2.700

-2.200

-1.400 1.900

-6.800

-5.000 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-0.990 4.100

-4.500

-4.200

-2.900

-2.700

-2.200

-1.400 1.900

-6.800

-5.000 7.4.9 (mVDC) 0.0 (-20.0 to 20.0)

-8.500 6.900

-17.500

-16.600 6.500

-15.100 2.500 5.800 4.200

.10.950

-4.800 7.4.11 (MVDC) 0.0 (-20.0 to 20.0)

-8.500 6.900

-1 7.500

-16.600 6.500 1.300 2.500 5.800 4.200

-10.950

-4.800 7.4.15 ()0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 ()0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Inop Trip 7.5.2 (VDC) 100 (97 to 103) 99.950 100.000 100.100 100.000 100.000 99.910 100.000 100.000 100.000 99.930 99.800 7.5.4 (VDC) 75 (73 to 77) 80.700 80.500 81.000 81.200 81.000 81.000 80.600 81.000 81.000 81.300 80.700 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 80.700 80.500 81.000 81.200 81.000 81.000 80.600 81.000 81.000 81.300 80.700 7.5.7 (VDC) 100 (97 to 103) 100.200 100.100 100.000 100.000 100.000 100.000 100.000 100.000 100.000 100.050 100.000 U~pscale & Downscale Trip Cal._____________________

7.6.7 a. (%)

107.5 (105.0 to 1 10.0) 108.000 110.000 110.000 110.000 107.500 107.500 107.500 107.500 110.000 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.866 0.866 0.866 0.868 0.860 0.865 0.868 0.868 0.864 0.863 0.867 7.6.8 a. (%)

107.5 (105.0 to 11 0.0) 108.000 110.000 110.000 110.000 107.500 107.500 107.500 107.500 110.000 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.866 0.866 0.866 0.868 0.860 0.865 0.868 0.868 0.864 0.863 0.867 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 117.500 117.500 117.500 120.000 117.500 117.500 117.500 119.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.935 0.933 0.936 0.930 0.940 0.933 0.936 0.935 0.940 0.934 7.6.1 0 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 117.500 1117.500 117.500 120.000 117.500 117.500 117.500 119.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.935 0.933 0.936 0.930 0.940 10.933 0.936 0.935 0.940 0.934 7.6.11 a. (%)

7.5 (6.5 to 8.5 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500-7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.060 0.060 0.060 0.062 0.060 0.060 0.059 0.060 1

0.060 0.060 0.059 7.56.(6.5. to)8.5) 7.500 7.500 7.500 7.500

.0 7.500 7.500 7.500 7.500 7.500 7.500 lb. (VDC) 0.060 (0.052 to 0.068) 0.060 0.060 0.060 0.062

.6 0.060 0.059 0.060 1

0.060 0.060

.5

Intermediate Range Monitor Extended Calibration IRM 14 Extended Data Extended Data l

4/12/1994 17/11/1994 4/29/1998 5/812002 4/20/2003 DC Amplifier Zero Cal.

7 1

1 l

I 7.4.5 (mVDC)

-1.500 J 66.000

-1.500

-2.700

-5.000 7.4.7 (mVDC) l 1.500 l

0.100

-1.500

-2.700

-5.000 7.4.9 (mVDC) l 2.300 l

7.000

-15.700

-15.100

-4.800 7.4.11 (mVDC) l 2.300 l

7.000

-15.700 1.300

-4.800 4112/1994 7/11/1994 3/3/1995 4/29/1998 5/1/2001 4/20/2003 Upscale & Downsc ale Trip Cal.

7.6.7 a. (%)

110.000 107.500 118.000 107.500 107.500 110.000

b. (VDC) 0.865 0.863 0.858 0.866 0.860 0.867 7.6.8 a. (%)

110.000 107.500 118.000 107.500 107.500 110.000

b. (VDC) 0.865 0.863 0.860 0.866 0.860 0.867 7.6.9 a. (%)

117.500 117.500 118.000 117.500 117.500 117.500

b. (VDC) 0.936 0.940 0.939 0.932 0.930 0.934 7.6.10 a. (%)

117.500 117.500 118.000 117.500 117.500 117.500

b. (VDC) 0.936 0.940 0.939 0.932 0.930 0.934 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.061 0.061 0.061 0.061 0.060 0.059 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.061 0.061 0.061 0.061 0.060 0.059 l

4/12/1994 7/11/1994 4/9/1997 14/8/1999 5/1/2001 14/20/2003 HV Power Supply &l no Trip l

l l

1 7.5.4 (VDC) 74.000 73.900 75.000 7 75.000 81.000 80.700

b. (VDC) 74.000 75.100 75.000 79.500 81.000 l 80.700

Intermediate Range Monitor Calibration All Data TOLERANCES 4/12/1994 7/11/1994 2/2/1995 3/1/1995 3/29/1996 7/25/1996 4/8/1997 4/27/1998 4/29/1998 4/6/1999 IRM 15 DC Amplifier Zero Cal.

l 7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-5.070 3.100

-1.100

• 2.240

-5.900 3.170

-4.600

-3.100

-2.600

-6.150 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-5.070 3.100

-1.100

_2.240

-5.900 3.170

-4.600

-3.100

-2.600

-6.150 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 0.630 23.600

-10.200

-3.320

-11.400 24.930

-1.300 0.700 3.920

-7.410 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 0.630 0.600

-0.600

-3.320

-11.400

-1.040

-1.300 0.700 3.920

-7.410 7.4.15 (%)

0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Ino Trip T

I I_

I__T_

7.5.2 (VDC) 100(97 to 103) 100.000 100.200 99.850 100.240 100.000 100.000 100.000 100.000 100.000 99.840 7.5.4 (VDC) j 75 (73 to 77) 75.200 74.900 75.030 75.370 75.000 75.000 75.000 74.000 74.000 75.100 7.5.5 (N/A) l n/a n/a nla n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 75.200 74.900 75.030 75.370 75.000 75.000 75.000 74.000 75.000 79.700 7.5.7 (VDC) 100 (97 to 103) 100.200 100.000 100.090 99.990 100.000 100.000 100.000 100.000 100.000 100.000 Upscale & Downscale Ip Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 108.000 107.000 107.500 107.500 107.500 110.000 107.500 110.000 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.859 0.870 0.869 0.863 0.862 0.872 0.870 0.872 0.866 0.866 7.6.8 a. (%)

107.5 (105.0 to 110.0) 108.000 107.000 107.500 107.500 107.500 110.000 107.500 110.000 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.857 0.870 0.869 0.863 0.862 0.872 0.870 0.872 0.866 0.866 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 117.000 117.500 117.500 117.500 120.000 117.500 120.000 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.935 0.940 0.949 0.942 0.942 0.950 0.949 0.947 0.943 0.946 7.6.10 a. (%)

117.5(115.0 to 120.0) 118.000 117.000 117.500 117.500 117.500 120.000 117.500 120.000 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.935 0.940 0.949 0.942 0.942 0.950 0.949 0.947 0.943 0.946 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.065 0.064 0.064 0.064 0.066 0.064 0.064 0.064 0.062 0.064 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.065 0.064 0.064 0.064 0.066 0.064 0.064 0.064 0.062 0.064

All Data TOLERANCES 5/15/1999 9/29/1999 2V23/2000 2/2612000 4/22/2001 5/6/2002 5/15/2002 12/6/2002 12/11/2002 3/11/2003 4/20/2003 IRM 15 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-3.000 5.600

-7.600

-6.400

-5.400

-4.700

-2.900

-1.200

-2.200

-9.840

-6.50 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-3.000 5.600

-7.600

-6.400

-5.400

-4.700

-2.900

-1.200

-2.200

-9.840

-6.50 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 2.700

-1.900

-37.200 2.500 7.600

-18.900 5.000 10.600 8.200

-12.810 10.41 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 2.700

-1.900

-0.100 2.500 7.600 0.000 5.000 10.600 8.200 0.300 10.40 7.4.15(%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16(%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Inc p Trio 7.5.2 (VDC) 100 (97 to 103) 99.770 100.000 99.900 100.000 99.880 99.700 100.000 99.800 100.000 99.800 99.90 7.5.4 (VDC) l 75(73 to 77) 79.900 79.600 81.000 80.000 80.400 79.600 79.000 79.800 80.000 79.600 79.60 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC)

I 75(73 to 77) 79.900 79.600 81.000 80.000 80.400 79.600 79.000 79.800 80.000 79.600 79.60 7.5.7 (VDC) l 100 (97 to 103) 100.000 100.000 100.000 100.000 99.970 100.100 100.000 100.000 100.000 100.000 100.00 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 107.500 110.000 110.000 110.000 110.000 107.500 107.500 107.500 110.000 110.000 107.50

b. (VDC) 0.860 (0.840 to 0.880) 0.862 0.870 0.873 0.872 0.870 0.864 0.864 0.870 0.869 0.865 0.869 7.6.8 a. (%)

107.5(105.0to110.0) 107.500 110.000 110.000 110.000 110.000 107.500 107.500 107.500 110.000 110.000 107.50

b. (VDC) 0.860 (0.840 to 0.880) 0.862 0.870 0.873 0.872 0.870 0.864 0.864 0.870 0.869 0.865 0.869 7.6.9 a. (%)

117.5(115.0 to 120.0) 120.000 120.000 117.500 120.000 120.000 120.000 117.500 120.000 120.000 120.000 117.50

b. (VDC) 0.940(0.920 to 0.960) 0.952 0.949 0.945 0.950 0.950 0.943 0.944 0.946 0.945 0.943 0.944 7.6.10 a. (%)

117.5(115.0 to 120.0) 120.000 120.000 117.500 120.000 120.000 120.000 117.500 120.000 120.000 120.000 117.50

b. (VDC) 0.940(0.920 to 0.960) 0.952 0.949 0.945 0.950 0.950 0.943 0.944 0.946 0.945 0.943 0.944 7.6.11 a. (%)

7.5(6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.064 0.064 0.065 0.065 0.061 0.064 0.065 0.063 0.064 0.065 0.064 7.6.12 a. (%)

7.5(6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.064 0.064 0.065 0.065 0.061 0.064 0.065 0.063 0.064 0.065 0.064

Intermediate Range Monitor Extended Calibration IRM 15 Extended Data Extended D, DC Amplifle 7.4.5 (mVD(

Cta 1

4/12/1994 7/11/19941 2/2/1995 7/25/1996 9/29/1999 2/ 23/2000 5/6/2002 5/15/2002 12/612002 3/11/2003 4/20/2003 4r Zero Cal.

7/I.

I 5//20 160 4 /2 ___0.2__0 C)

-5.070 3.100

-1.100 3.170 5.600

-7.600

-4.700 I -2.900 I -1.200 I

-9.540 I -5.500 I

7.4.7 (mVDC)

-5.070 3.100

-1.1001 3.170 1 5.6001

-7.600

-4.700

-2.900

-1.200

.9.840

-6.500 7.4.9 (mVDC) f 0.630 j 23.600

-10.200 24.930

-1.900 i-37.200

.18.900 5.000 10.600

-12.810 10.410 7.4.11 (mVDC) 0.630 j

0.600

-0.600

-1.040

-1.900

-0.100 0.000 5.000 10.600 0.300 10.400 4/12/1994 7/25/1996 4/6/1999 4/22/2001 12/11/2002 4/20/2003 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

108.000 110.000 110.000 110.000 110.000 107.500

b. (VDC) 0.859 0.872 0.866 0.870 0.869 0.869 7.6.8 a. (%)

108.000 110.000 110.000 110.000 110.000 107.500

b. (VDC) 0.857 0.872 0.866 0.870 0.869 0.869 7.6.9 a. (%)

118.000 120.000 120.000 120.000 120.000 117.500

b. (VDC) 0.935 0.950 0.946 0.950 0.945 0.944 7.6.10 a. (%)

118.000 120.000 120.000 120.000 120.000 117.500

b. (VDC) 0.935 0.950 0.946 0.950 0.945 0.944 7.6.11 a. %

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.065 0.064 0.064 0.061 0.064 0.064 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.065 0.064 0.064 0.061 0.064 0.064

[

4/12/1994 I7/25/1996 4/29/1998 4/6/1999 5/6/2002 I4/20/2003

[HV Power SupplV & Inop TrIp I

I I

I I

I

[7.5.4 (VD 75.200 75.000 J 74.000 75.100 79.600 79.600

[b.

DC 75.200 75.000 75.000 79.700 79.600 79.600

Intermediate Range Monitor Calibration All Data TOLERANCES 4/1211994 7/11/1994 2/3/1995 3/2/1995 3/30/1996 7/25/1996 4/8/1997 4/27/1998 4/5/1999 4/29/1999 IRM 16 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-2.400 1.400

-1.470

-1.700

-3.100 3.300

-2.100

-1.000 16.660

-10.000 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-2.400 1.400

-1.470

-1.700

-3.100 3.300

-2.100

-1.000

-0.050

-10.000 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 2.400 12.200

-8.300

-8.800

-12.800 21.800 1.900

-2.000

-33.300

-2.500 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 2.400

-0.800

-8.300

-8.800

-12.800 1.200 1.900

-2.000 2.000

-2.500 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power SupplY & I op Trip 7.5.2 (VDC) 100 (97 to 103) 99.900 100.100 99.750 99.820 100.000 99.900 100.000 100.000 100.060 100.000 7.5.4 (VDC) 75 (73 to 77) 75.000 76.000 75.200 76.150 75.000 75.200 75.000 75.000 74.100 75.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 75.000 76.000 75.200 76.150 75.000 75.200 75.000 75.000 79.800 75.000 7.5.7 (VDC) 100 (97 to 103) 100.100 100.000 100.100 100.020 100.000 100.100 100.000 100.000 100.000 100.000 Upscale & Downscale Trin Cal.

7.6.7 a. (%)

107.5 (105.0 to 1 10.0) 107.500 107.500 110.000 107.500 110.000 110.000 107.500 110.000 110.000 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.860 0.870 0.860 0.860 0.871 0.869 0.868 0.870 0.870 7.6.8 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 110.000 107.500 110.000 110.000 107.500 110.000 110.000 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.860 0.870 0.860 0.860 0.871 0.869 0.868 0.870 0.870 7.6.9 a. (%)

117.5 (115.0 to 120.0) 120.000 119.000 120.000 119.000 120.000 120.000 117.500 117.500 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.941 0.950 0.942 0.940 0.948 0.947 0.938 0.942 0.954 7.6.10 a. (%)

117.5 (115.0 to 120.0) 120.000 119.000 120.000 119.000 120.000 120.000 117.500 117.500 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.941 0.950 0.942 0.940 0.948 0.947 0.938 0.942 0.954 7.6.11 a. (%)

7.5(6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.058 0.060 0.059 0.059 0.060 0.060 0.059 0.060 0.058 0.060 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.058 0.060 0.059 0.059 0.060 0.060 0.059 0.060 0.058 0.060

TOLERANCES 5/15/1999 2/24/2000 2/26/2000 5/1/2001 5/6/2002 5/15/2002 12/612002 12/11/2002 3/11/2003 4/20/2003 IRM 16 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-18.000

-2.520

-2.000

-0.200 0.000 0.800 0.600 0.090 36.100 1.900 7.4.7 (mVDC) 0.0 (-20.0 to 20.0) 0.500

-2.520

-2.000

-0.200 0.000 0.800 0.600 0.090 0.100 1.900 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 43.000

-21.300 1.500

-20.000

-1.200 1.600 0.600 0.180 0.000 5.960 7.4.11 (mVDC) l 0.0 (-20.0 to 20.0) 0.000

-0.300 1.500

-2.000

-1.200 1.600 0.600 0.180 0.000 5.960 7.4.15 (%)

T 0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

Too(not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Inop Trip 7.5.2 (VDC) 100(97 to 103) 99.980 100.120 100.000 100.000 100.000 100.000 100.100 100.000 99.950 100.000 7.5.4 (VDC) j 75 (73 to 77) 79.500 79.620 80.000 80.000 79.400 79.000 80.000 80.000 80.140 79.500 7.5.5 (N/A) i n/a n/a n/a n/a n/a n/a n/a n/a nla n/a

b. (VDC) l 75 (73 to 77) 79.500 79.620 80.000 80.000 79.400 79.000 80.000 80.000 80.140 79.500 7.5.7 (VDC) 100 (97 to 103) 100.000 100.170 100.000 100.000 100.000 100.000 100.000 100.000 99.960 100.000 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 110.000 107.500 110.000 107.500 107.500 110.000 110.000 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.858 0.860 0.857 0.862 0.869 0.868 0.866 0.860 0.866 7.6.8 a. (%)

107.5(105.0 to 110.0) 110.000 107.500 110.000 107.500 107.500 110.000 110.000 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.858 0.860 0.857 0.862 0.869 0.868 0.866 0.860 0.866 7.6.9 a. (%)

117.5 (115.0 to 120.0) 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.944 0.947 0.940 0.938 0.953 0.944 0.946 0.943 0.951 0.943 7.6.10 a. (%)

117.5(115.0 to 120.0) 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.944 0.947 0.940 0.938 0.953 0.944 0.946 0.943 0.951 0.943 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.058 0.056 0.059 0.059 0.059 0.059 0.059 0.058 0.058 0.058 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7 7.500

.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.058 0.056 0.059 0.059 0.059 0.059 0.059 0.058 0.057 0.058

Intermediate Range Monitor Extended Calibration IRM 16 Extended Data Extended Data 1

4/12/1994 7/11/1994 7/25/1996 4/5/1999 5/15/1999 2/24/2000 5/1/2001 3/11/2003 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (mVDC)

-2.400 1.400 3.300 16.660

-18.000

-2.520

-0.200 36.100 1.900 7.4.7 (mVDC)

-2.400 1.400 3.300

-0.050 0.500

-2.520

-0.200 0.100 1.900 7.4.9 (mVDC) 2.400 12.200 21.800

-33.300 43.000

-21.300

-20.000 0.000 5.960 7.4.11 (mVDC) 2.400

-0.800 1.200 2.000 0.000

-0.300

-2.000 0.000 5.960 1

4/12/1994 7/25/1996 5/15/1999 5/6/2002 3/11/2003 4/20/2003 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.500 110.000 110.000 107.500 107.500 107.500

b. (VDC) 0.860 0.871 0.867 0.862 0.860 0.866 7.6.8 a. (

107.500 110.000 110.000 107.500 107.500 107.500

b. (VDC) 0.860 0.871 0.867 0.862 0.860 0.866 7.6.9 a. (%)

120.000 120.000 120.000 120.000 120.000 120.000

b. (VDC) 0.942 0.948 0.944 0.953 0.951 0.943 7.6.10 a. (%)

120.000 120.000 120.000 120.000 120.000 120.000

b. (VDC) 0.942 0.948 0.944 0.953 0.951 0.943 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.058 0.060 0.058 0.059 0.058 0.058 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.058 0.060 0.058 0.059 0.057 0.058 I

4/12/1994 7/25/1996 4/5/1999 5/1/2001 4/20/2003 HV Power SupplV & Inop Trip I

7.5.4 (VDC) 75.000 75.200 74.100 80.000 79.500

b. (VDC) 75.000 75.200 79.800 80.000 79.500

Intermediate Range Monitor Calibration All Data TOLERANCES 4/12/1994 7/11/1994 2/3/1995 3/1/1995 3/30/1996 4/8/1997 4/27/1998 4/30/1998 4/6/1999 5/15/1999 IRM 17 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-4.580 3.300

-3.050

-3.500

-4.500 1.320

-8.500

-7.600

-10.300 4.080 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-4.580 3.300

-3.050

-3.500

-4.500 1.320

-8.500

-7.600 0.700 4.080 7.4.9 (mVDC) 0.0 (.20.0 to 20.0) 1.400 21.500

-14.470 2.600

-6.700 3.880

-8.700

-8.300 16.800 10.010 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 1.400 1.400

-0.230 2.600

-6.700 3.880

-8.700

-8.300 0.300 10.070 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power SuppIY & Ino TriD i

7.5.2 (VDC) 100 (97 to 103) 100.100 100.100 100.100 100.190 100.000 100.000 100.000 100.000 99.880 99.900 7.5.4 (VDC) 75 (73 to 77) 75.000 75.000 75.110 76.500 74.000 75.000 75.000 74.000 74.200 79.990 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 75.000 75.000 75.110 75.000 74.000 75.000 75.000 74.000 80.700 79.990 7.5.7 (VDC) 100 (97 to 103) 100.100 100.000 100.070 99.980 100.000 100.000 100.000 100.000 100.000 99.970 Upscale & Downscale TrIp Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 107.000 107.000 108.000 108.000 105.000 107.500 107.500 107.500 107.500 106.000

b. (VDC) 0.860 (0.840 to 0.880) 0.856 0.860 0.870 0.870 0.847 0.861 0.860 0.855 0.852 0.857 7.6.8 a. I%)

107.5 (105.0 to 110.0) 107.000 107.000 108.000 107.500 105.000 107.500 107.500 107.500 107.500 106.000

b. (VDC) 0.860 (0.840 to 0.880) 0.856 0.860 0.870 0.860 0.847 0.861 0.860 0.855 0.852 0.857 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 117.500 118.000 118.000 117.500 117.500 117.500 117.500 120.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.934 0.948 0.948 0.937 0.941 0.938 0.943 0.942 0.946 7.6.1 0 a. (%)

117.5 (115.0 to 120.0) 118.000 117.500 118.000 117.500 117.500 117.500 117.500 117.500 120.000 117.500

b. (VDC) 0.940 (0.920 to 0.960) 0.934 0.934 0.948 0.937 0.937 0.941 0.938 0.943 0.942 0.946 7.6.11 a. (%)

7.5(6.5 to 8.5) 7.500 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.060 0.058 0.059 0.057 0.064 0.062 0.062 0.063 0.064 0.062 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.060 0.058 0.059 0.060 0.064 0.062 0.062 0.063 0.064 0.062

All Data TOLERANCES 9/29/1999 2/24/2000 2/25/2000 4/26/2001 5/6/2002 5/15/2002 12/6/2002 12/11/2002 3/12/2003 4/20/2003 IRM 17 DC Amplifier Zero Cal..

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-2.380

-14.800

-13.400

-3.030

-2.500

-1.300

-1.800

-2.300

-7.700

-4.620 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-2.380

-14.800 0.200

-3.030

-2.500

-1.300

-1.800

-2.300

-7.700

-4.620 7.4.9 (mVDC) 0.0 (-20.0 to 20.0)

-8.080

-30.200 52.000 9.500

-21.900 5.800 3.800 7.500 0.690 13.000 7.4.11 (mVDC) 0.0 (-20.0 to 20.0)

-8.080

-0.200

-0.820 9.500 0.000 5.800 3.800 7.500 0.690 0.260 7.4.15 i%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 i%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power SuppyI & Ingo Trip 7.5.2 (VDC) 100 (97 to 103) 99.710 100.200 100.000 100.100 99.810 100.000 100.000 100.000 100.000 100.100 7.5.4 (VDC) 75 (73 to 77) 80.670 81.030 81.000 81.200 80.400 80.000 81.000 81.000 81.400 81.000 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 80.670 81.030 81.000 81.200 80.400 80.000 81.000 81.000 81.400 81.000 7.5.7 (VDC) 100 (97 to 103) 100.010 100.030 100.000 100.000 100.000 100.000 100.000 100.000 100.100 100.000 Upscale & Downscale Trip Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 107.500 107.500 107.500 107.500 110.000 107.500 107.500 107.500 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.874 0.867 0.870 0.864 0.873 0.870 0.870 0.871 0.871 0.871 7.6.8 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 107.500 107.500 110.000 107.500 107.500 107.500 107.500 110.000

b. (VDC) 0.860 (0.840 to 0.880) 0.874 0.867 0.870 0.864 0.873 0.870 0.870 0.871 0.871 0.871 7.6.9 a. (%)

117.5 (115.0 to 120.0) 117.500 120.000 117.500 117.500 117.500 117.500 117.500 117.500 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.940 0.940 0.938 0.943 0.940 0.940 0.941 0.940 0.942 7.6.10 a. (%)

117.5 (115.0 to 120.0) 117.500 120.000 117.500 117.500 117.500 117.500 117.500 117.500 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.940 0.940 0.938 0.943 0.940 0.940 0.941 0.940 0.942 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.062 0.061 0.060 0.062 0.062 0.062 0.063 0.061 0.062 0.061 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.062 0.061 0.060 0.062 0.062 0.062 0.063 0.061 0.062 0.061

Intermediate Range Monitor Extended Calibration IRM 17 Extended Data Extended Data l

4/12/1994 7/11/1994 2/3/1995 4/6/1999 2/24/2000 2/25/2000 5/6/2002 4/20/2003 DC Amplifier Zero Cal.

7.4.5 (mVDC) 4.580 3.300

-3.050

-10.300

-14.800

-13.400

-2.500

-4.620 7.4.7 (mVDC) 4.580 3.300

-3.050 0.700

-14.800 0.200

-2.500

-4.620 7.4.9 (mVDC) 1.400 21.500

-14.470 16.800

-30.200 52.000

-21.900 13.000 7.4.11 (mVDC) 1.400 1.400

-0.230 0.300

-0.200

-0.820 0.000 0.260 4/12/1994 3/1/1995 4/30/1998 4/26/2001 3/12/2003 4/20/2003 Upscale & Downsca o Trip Cal.

7.6.7 a. (%)

107.000 108.000 107.500 107.500 107.500 110.000

b. (VDC) 0.856 0.870 0.855 0.864 0.871 0.871 7.6.8 a. (%)

107.000 107.500 107.500 107.500 107.500 110.000

b. (VDC) 0.856 0.860 0.855 0.864 0.871 0.871 7.6.9 a. (%)

118.000 118.000 117.500 117.500 117.500 120.000

b. (VDC) 0.934 0.948 0.943 0.938 0.940 0.942 7.6.10 a. (%)

118.000 117.500 117.500 117.500 117.500 120.000

b. (VDC) 0.934 0.937 0.943 0.938 0.940 0.942 7.6.11 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 0.057 0.063 0.062 0.062 0.061 7.6.12 a. (%)

7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 0.060 0.063 0.062 0.062 0.061 l

4/12/1994 J 3/1/1995 J 4/6/1999 4/26/2001 4/20/2003 HV Power Supply & Inop Trip l

l 7.5.4 (VDC) 75.000 76.500 74.200 81.200 81.000

b. (VDC) 75.000 75.000 80.700 81.200 81.000

Intermediate Range Monitor Calibration All Data TOLERANCES 4/11/1994 7/11/1994 2/3/1995 3/1/1995 3/30/1996 7/25/1996 4/7/1997 4/27/1998 4/30/1998 4/6/1999 IRM 18 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0)

-3.700 1.600 2.200

-3.350

-4.400 1.120

-3.070

-1.800

-0.530

-3.510 7.4.7 (mVDC) 0.0 (-20.0 to 20.0)

-3.700 1.600 2.200

-3.350

-4.400 1.120

-3.070

-1.800

-0.530

-3.510 7.4.9 (mVDC) 0.0 (-20.0 to 20.0) 2.700 18.700

-5.700 9.260 2.500 19.750 6.340 4.000

-1.370

-8.000 7.4.11 (mVDC) 0.0 (-20.0 to 20.0) 2.700 3.100

-5.700

-0.870 2.500 0.300 6.340

-4.000

-1.370

-8.000 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Supply & Int TriD 7.5.2 (VDC) 100 (97 to 103) 99.800 100.200 99.700 99.930 100.000 99.820 100.000 100.000 100.000 99.860 7.5.4 (VDC) 75 (73 to 77) 75.600 74.900 74.830 76.420 75.000 74.640 75.000 75.000 75.000 75.100 7.5.5 (N/A) n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 75.600 74.900 74.830 75.360 75.000 74.640 75.000 75.000 75.000 80.200 7.5.7 (VDC) 100 (97 to 103) 100.200 100.200 100.020 99.960 100.000 100.000 100.000 100.000 100.000 100.020 Upscale & Downscale TrID Cal.

7.6.7 a. (%)

107.5 (105.0 to 110.0) 108.000 107.500 109.000 107.500 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.860 0.876 0.864 0.855 0.857 0.863 0.867 0.859 0.864 7.6.8 a. (%)

107.5(105.0 to 110.0) 108.000 107.500 107.000 107.500 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.867 0.860 0.866 0.864 0.855 0.857 0.863 0.867 0.859 0.864 7.6.9 a. (%)

117.5(115.0 to 120.0) 119.000 117.000 118.000 119.000 117.500 120.000 117.500 117.500 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.940 0.946 0.955 0.942 0.948 0.944 0.951 0.948 0.944 7.6.10 a. (%)

117.5 (115.0 to 120.0) 119.000 117.000 118.000 118.000 117.500 120.000 117.500 117.500 117.500 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.942 0.940 0.946 0.944 0.942 0.948 0.944 0.951 0.948 0.944 7.6.11 a. (%)

7.5 (6.5 to 8.5) 6.500 7.000 6.500 60.000 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.060 0.057 0.058 0.058 0.064 0.064 0.064 0.063 0.064 0.064 7.6.12 a. (%)

7.5 (6.5 to 8.5) 6.500 7.000 6.500 70.000 7.500 7.500 7.500 7.500 7.500 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.060 0.057 0.058 0.063 0.064 0.064 0.064 0.063 0.064 0.064

All Data TOLERANCES 5/15/1999 9/29/1999 2/24/2000 2/25/2000 4/26/2001 5/7/2002 5115/2002 12/6/2002 12/11/2002 3112/2003 4/20/2003 IRM 18 DC Amplifier Zero Cal.

7.4.5 (mVDC) 0.0 (-20.0 to 20.0) 1.310 2.750

-4.600

-5.320

-3.400

-2.000

-1.700

-1.440 1.600

-5.600

-4.300 7.4.7 (mVDC) 0.0 (-20.0 to 20.0) 1.310 2.750

-4.600

-5.320

-3.400

-2.000

-1.700

-1.440 1.600

-5.600

-4.300 7.4.9 (mVDC) 0.0 (.20.0 to 20.0)

-1.900 0.830

-19.700

-5.300 6.100

-11.000 3.800 3.680 3.600

-9.600 9.000 7.4.11 (mVDC) 0.0 (-20.0 to 20.0)

-1.900 0.830

-2.400

-5.300 6.100 0.800 3.800 3.680 3.600

-9.600 9.000 7.4.15 (%)

0.0 (not on peg to 2.5%)

0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.4.16 (%)

0.0 (not on peg to 2.5%)

n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a n/a HV Power Suppyv & Ino j Trip 7.5.2 (VDC) 100 (97 to 103) 99.960 100.000 100.100 100.000 99.780 100.000 100.000 99.550 100.000 99.780 100.000 7.5.4 (VDC) 75 (73 to 77) 79.700 80.600 80.500 79.000 80.300 80.500 80.000 80.450 81.000 81.150 81.400 7.5.5 (N/A) n/a n/a n/a n/a rn/a n/a n/a n/a n/a n/a n/a

b. (VDC) 75 (73 to 77) 79.700 80.600 80.500 79.000 80.300 80.500 80.000 80.450 81.000 81.150 81.400 7.5.7 (VDC) 100 (97 to 103) 99.990 100.200 100.000 100.000 100.020 100.000 101.000 100.000 100.000 99.970 100.000 Upscale & Downscale TrIP Cal.

7.6.7 a. (%)

107.5(105.0 to 110.0) 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.862 0.859 0.850 0.853 0.857 0.868 0.856 0.857 0.862 0.859 7.6.8 a. (%)

107.5 (105.0 to 110.0) 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500 107.500

b. (VDC) 0.860 (0.840 to 0.880) 0.860 0.862 0.859 0.850 0.853 0.857 0.868 0.856 0.857 0.862 0.859 7.6.9 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 120.000 120.000 117.500 120.000 117.500 117.500 117.500 119.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.952 0.953 0.948 0.930 0.941 0.947 0.944 0.945 0.946 0.951 0.949 7.6.10 a. (%)

117.5 (115.0 to 120.0) 118.000 120.000 120.000 120.000 117.500 120.000 117.500 117.500 117.500 119.000 120.000

b. (VDC) 0.940 (0.920 to 0.960) 0.952 0.953 0.948 0.930 0.941 0.947 0.944 0.945 0.946 0.951 0.949 7.6.11 a. (%)

7.5 (6.5 to 8.5) 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 8.000 7.500

b. (VDC) 0.060(0.052 to 0.068) 0.064 0.064 0.064 0.064 0.065 0.064 0.064 0.063 0.063 0.063 0.061 7.6.12 a. (%)

7.5 (6.5 to 8.5) 7.000 7.500 7.500 7.500 7.500 7.500 7.500 7.500 7.500 8.000 7.500

b. (VDC) 0.060 (0.052 to 0.068) 0.064 0.064 0.064 0.064 0.065 0.064 0.064 0.063 0.063 0.063 0.06 1

intermediate Range Monitor Extended Calibration IRM 18 Extended Data Extended Data 4/11/1994 71/1/1994 311/1995l7/25/1996l2/24/2000 5/7/2002 4/20/2003 DC Amplifier Zero Cal.

l -3.350 1.120

_ -4.600 l

7.4.5 (mVDC)

-3.700 1.600

-3.350 1.120

-4.600

-2.000 l -4.300 7.4.7 (mVDC)

-3.700 1.600

-3.350 1.120

-4.600

-2.000 7

-4.300 7.4.9 (mVDC) 2.700 18.700 9.260 19.750

-19.700

-11.000 J9.000 7.4.11 (mVDC) 2.700 3.100

-0.870 0.300

-2.400 0.800 9 2000 l

4/11/1994 2/3/1995 3/1/1995 4/27/1998 4/26/2001 4/20/2003 UJscale & Downscale T Ip Cal.

i 7.6.7 a. (%)

108.000 109.000 107.500 107.500 107.500 107.500

b. (VDC) 0.867 0.876 0.864 0.867 0.853 0.859 7.6.8 a. (%)

108.000 107.000 107.500 107.500 107.500 107.500

b. (VDC) 0.867 0.866 0.864 0.867 0.853 0.859 7.6.9 a. (%)

119.000 118.000 119.000 117.500 117.500 120.000

b. (VDC) 0.942 0.946 0.955 0.951 0.941 0.949 7.6.10 a. (%)

119.000 118.000 118.000 117.500 117.500 120.000

b. (VDC) 0.942 0.946 0.944 0.951 0.941 0.949 7.6.11 a. (%)

6.500 6.500 60.000 7.500 7.500 7.500

b. (VDC) 0.060 0.058 0.058 0.063 0.065 0.061 7.6.12 a. %

6.500 6.500 70.000 7.500 7.500 7.500

b. (VDC) 0.060 0.058 0.063 0.063 0.065 0.061 4/11/1994 3/1/1995 4/27/1998V 4/6/1999 14/26/2001 4/20/20031 HV Power Supplv & Inog TriD I

I _

7.5.4 (VDC) 75.600 76.420 75.000 75.100 1 80.300 81.400

b. (VDC) 75.600 75.360 75.000 80.200 l 80.300 81.400