ML072780150
| ML072780150 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-065) |
| Issue date: | 10/04/2007 |
| From: | Gerald Bichof Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 06-0841B | |
| Download: ML072780150 (33) | |
Text
Dominion Nuclear Connecticut, Inc.
'iOOO Dominion Boulevard, Glen Allen, Virginia 2.1060 Weh Address: www.dom.com October 4, 2007 U.S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Serial No.
MPS LiclWDB Docket No.
License No.
06-0841B R1 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING INSTRUMENTATION TECHNICAL SPECIFICATION CHANGES Dominion Nuclear Connecticut, Inc. (DNC) submitted a proposed license amendment to modify the Technical Specification Action and Surveillance Requirements for instrumentation identified in Millstone Power Station Unit 2 Technical Specifications 3.3.1 and 3.3.2 on November 8, 2006 (Serial No. 06-0841).
DNC responded to a request for additional information (RAI) regarding this proposed change on May 4, 2007 (Serial No. 06-0841A).
During a conference call on August 21, 2007, the NRC requested additional information. The response to this RAI is provided in Attachment 1 to this letter. to the letter contains a calculation requested in the conference call.
The signatures of the individuals who prepared, reviewed, and approved the calculation have been removed for this docketed submittal. Attachment 3 provides revised marked up Technical Specification pages as discussed in the conference call.
The additional information provided in this letter does not affect the conclusions of the significant hazards consideration discussion in DNC's original submittal dated November 8, 2006.
In accordance with 10 CFR 50.91(b), a copy of this response is being provided to the State of Connecticut.
Serial No. 06-0841 B Docket No. 50-336 Response to Request for Additional Information Page 2 of 3 Should you have any questions about the information provided or require additional information, please contact Ms. Margaret A. Earle at (804) 273-2768.
Sincerely, Vice President - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald 1. Bischof, who is Vice President - Nuclear Engineering, of Dominion Nuclear Connecticut, Inc.
He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this LjT!;!day of 0t7In!v/1),2007.
My Commission Expires: -illr-'tJ d.~ ;Io;c -
VICKI L. HULL NoIary PublIc common..... of VII8INO laa e--tlllign
%RL-'I, 2IcUl Notary Public
Serial No. 06-0841 B Docket No. 50-336 Response to Request for Additional Information Page 3 of 3 Attachments:
- 1. Response to Request for Additional Information
- 2. Calculation ZPM_Drift-0426012, Rev 0, dated 9/14/07, "Zero Power Mode Drift Analysis in Support of LBDCR 06-MP2-036" 3.
Marked up Technical Specification Pages
Enclosure:
CD Containing MP2 Instrumentation Schematic Diagrams Document Components:
001 Schematic Diagram 25203-39047-Sh 1.pdf; 1,869,277 bytes; publicly available 002 Schematic Diagram 25203-39047-Sh 2.pdf; 2,036,912 bytes; publicly available 003 Schematic Diagram 25203-39047-Sh 10.pdf; 1,989,574 bytes; publicly available 004 Schematic Diagram 25203-39069-Sh 18.pdf; 1,175,779 bytes; publicly available 005 Schematic Diagram 25203-39069-Sh 19.pdf; 1,322,495 bytes; publicly available 006 Schematic Diagram 25203-39069-Sh 23C.pdf; 250,303 bytes; publicly available 007 Schematic Diagram 25203-39256-Sh 32.pdf; 201,156 bytes; publicly available 008 Schematic Diagram 25203-39256-Sh 58.pdf; 725,435 bytes; publicly available Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 Mr. J. D. Hughey NRC Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring & Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No. 06-0841 B Docket No. 50-336 ATTACHMENT 1 INSTRUMENTATION TECHNICAL SPECIFICATION CHANGES RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Serial No. 06-0841B Docket No. 50-336 Response to Request for Additional Information Page 1 of 4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION During a conference call on August 21,2007, the NRC requested additional information from Dominion Nuclear Connecticut, Inc. (DNC) regarding a proposed change to the Millstone Power Station Unit 2 (MPS2) instrumentation technical specifications.
The requested information is necessary in order for the NRC staff to complete its review.
The information requested is provided below.
NRC Question No.1.
The License Amendment Request (LAR), dated November 8, 2006, proposes to change the first sentence in Millstone 2 Technical Specification (TS), Surveillance Requirements (SR) 4.3.1.1.2 for Reactor Protective (RPS) Instrumentation and SR 4.3.2.1.2 for Engineered Safety Feature Actuation System (ESFAS) Instrumentation from "The logic for the bypass shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation" to "The bypass function and automatic bypass removal function shall be demonstrated OPERABLE during a CHANNEL FUNCTIONAL TEST once within 92 days prior to each reactor startup."
The Millstone 2, TS Table 4.3-1, Reactor Protective Instrumentation Surveillance Requirements, and TS Table 4.3-2 Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements, specify monthly CHANNEL FUNCTIONAL TEST for each Functional Unit.
Thus, the current wordings of SR 4.3.1.1.2 and SR 4.3.2.1.2 require monthly demonstration of the operability of the bypass channel logic.
The proposed TS change will effectively replace the bypass channel monthly CHANNEL FUNCTIONAL TEST by CHANNEL FUNCTIONAL TEST once within 92 days prior to each reactor startup.
It is stated in the LAR that the bases for the similar requirements contained in NUREG 1432 were reviewed and determined to be applicable to MPS2.
NUREG 1432, SR 3.3.1.7, specifies, "Once within 92 days prior to each reactor startup" for automatic bypass removal functions but not for bypass channels.
Provide justifications for extending SR for bypass channels from monthly to once within 92 days prior to each reactor startup.
It is also stated in the LAR, "The allowance to conduct this test within 92 days of startup is based on the reliability analysis presented in topical report CEN-327, "RPS/ESFAS Extended Test Interval Evaluation," which is referenced in NUREG 1432 and is applicable to MPS2." Provide justifications why this portion of NUREG CEN-327 is applicable to MPS2 and if necessary provide the schematic diagrams of the bypass and automatic bypass removal circuits.
Serial No. 06-0841 B Docket No. 50-336 Response to Request for Additional Information Page 2 of 4 ONC Response As discussed in the conference call on August 21,2007, the Reactor Protective System (RPS) Instrumentation and Engineered Safety Feature Actuation System (ESFAS)
Instrumentation contain both trip channel bypasses as well as operating bypasses. The trip channel bypasses will continue to be demonstrated operable through performance of the channel monthly CHANNEL FUNCTIONAL TEST required by SR 4.3.1.1.1 and SR 4.3.2.1.1. The operating bypass function and automatic bypass removal function of the operating bypasses will be demonstrated operable during a
CHANNEL FUNCTIONAL TEST once within 92 days prior to each reactor startup.
Also as discussed in the conference call, the justification for extending the surveillance test interval for the operating bypasses from monthly to once within 92 days prior to each reactor startup is provided in the response to Question 2.
Copies of the applicable schematic diagrams of the operating bypasses and the automatic bypass removal circuits are provided on the enclosed compact disc.
These schematics show that the logic of the operating bypasses and the automatic bypass removal circuits are directly related to the RPS and ESFAS channels evaluated under CEN-327.
NRC Question No.2. to the LAR letter dated May 4,2007, refers to the Calculation PA79-219-00767GE, Rev 01.
This calculation does not provide the necessary information to conclude that the proposed changes to SR 4.3.1.1.2 and SR 4.3.2.1.2 will not have any adverse effect on plant safety, specifically the drift evaluation related to increasing the operability check for bypass channels from monthly to 92 days prior to each reactor startup.
The NRC letter dated November 6, 1989, "NRC Evaluation of CEOG Topical Report CEN-327, "RPS/ESFS Extended Test Interval Evaluation" states, The licensees must confirm that they have reviewed instrument drift information for each instrument channel involved and have determined that drift occurring in that channel over the period of extended STI will not cause the setpoint value to exceed the allowable value as calculated for that channel by their setpoint methodology.
Each licensee should have onsite records of the as-found and as-left values showing actual calculations and supporting data for planned future staff audits.
The records should consist of monthly data over a period of 2 to 3 years with the current plant-specific setpoint methodology used to derive the safety margins." Provide the drift evaluation to justify changing the CHANNEL FUNCTIONAL TEST frequency for the bypass channels from monthly to 92 days prior to each reactor startup.
Serial No. 06-0841 B Docket No. 50-336 Response to Request for Additional Information Page 3 of 4 DNC Response ONC Calculation ZPM_Orift-0426012, Rev 0, dated 9/14/07, "Zero Power Mode Drift Analysis in Support of LBOCR 06-MP2-036," is provided as Attachment 2.
This calculation confirms that the wide range neutron flux instrument rack drift occurring over the period of extended STI will not cause the Zero Power Mode (ZPM) operating bypass channel setpoint value to exceed the allowable value.
Accordingly, the wide range neutron flux ZPM bypass bistable trip upper limit will be set at less than or equal to 7.413E-05%.
This calculation concludes that the change of the CHANNEL FUNCTIONAL TEST frequency for the ZPM operating bypass channels from monthly to 92 days prior to each reactor startup is acceptable. Onsite records of the as-found and as-left values showing actual calculations and supporting data are available for staff audits. The records consist of monthly data over the period from January 2005 through July 2007.
The operating bypasses and their setpoints are not modeled in the plant safety analysis and are not considered analytical limits. The instrument uncertainty is used as a basis for establishing the setpoint value such that the setpoint value will remain below the allowable value over the period of the surveillance interval.
NRC Question No.3.
Does the Millstone Unit 2 control room currently have logarithmic displays or are they being added as a modification associated with this TS submittal?
DNC Response The Millstone Unit 2 control room currently has logarithmic displays.
NRC Question No.4.
Proposed ACTION 8.a appears to be internally inconsistent. The word "channel" should be "channels" as this ACTION applies to the condition of two inoperable automatic bypass removal channels.
DNC Response DNC concurs that proposed ACTION 8.a should read as follows:
Serial No. 06-0841 B Docket No. 50-336 Response to Request for Additional Information Page 4 of 4
- a. disable the bypass channels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or A revised insert reflecting this change is included in Attachment 3.
Question No.5.
Table 3.3-1, Table Notation (f) should be revised similar to the proposed change to Table Notation (a) to accurately reflect the parameter being measured by referring to logarithmic power instead of 'THERMAL POWER' and replacing '%RTP' with '%' where appropriate.
DNC Response DNC proposes changing Table 3.3-1, Table Notation (f) as follows:
Current (f) flT Power input to trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is ~
5% of RATED THERMAL POWER.
Proposed (f) flT Power input to trip may be bypassed when logarithmic power is < 1E-04%
and the bypass shall be capable of automatic removal whenever logarithmic power is < 1E-04%. Bypass shall be removed prior to raising logarithmic power to a value ~ 1E-04%.
The parameter used for the input to the flT trip input to the operating bypass for the affected functional unit (Le., Power Level -
High) is the associated wide range logarithmic nuclear instrumentation channel.
Accordingly, the discussion related to proposed changes 4 and 5, in Section 4.0, 'Technical Analysis,' of Attachment 1 to the November 8, 2006 submittal is also applicable to the above proposed change.
A revised marked up Technical Specification page and associated insert is included in.
Serial No. 06-0841 B Docket No. 50-336 ATTACHMENT 2 INSTRUMENTATION TECHNICAL SPECIFICATION CHANGES CALCULATION ZPM DRIFT-0426012, REV 0, DATED 9/14/07 ZERO POWER MODE DRIFT ANALYSIS IN SUPPORT OF LBDCR 06-MP2-036 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
Approved 11117/03 Effective__~1l,""12"""1",",/Q,,,,,3,-
CALCULATION TITLE PAGE Total Number of Pages: 22 TITLE ZPM DRIFT*04260I2 o
Zero Power Mode Drift Analysis in Support ofLBDCR 06-MP2-036 CALCULATION No.
Revision No.
NA N/A VENDOR CALCULATION No.
Revision No.
N/A VENDOR NAME NUCLEAR INDICATOR:
50.59 Evaluation or Screen Calc. Supports Calc. Supports Attached DCRlMMODIEE?
Other Process?
[gIeATl DRWQA DSBOQA DFPQA DATWSQA DNON-QA DYES I8lNO DYES I8lNO I81YES DNO INCORPORATES:
CCNNO:
AGAINST REV.
Ref. No.
.t LBDCR 06-MP2*036 Reference I Executive Summary II LBDCR 06-MP2-036 is proposing extending the surveillance requirement for the auto removal ofthe Zero Power Mode Bypass function from a monthly interval to once within 92 days ofa reactor startup. To support the proposed surveillance extension for the auto removal ofthe Zero Power Mode Bypass function, a detailed drift analysis is required to be perfonned. Existing calculation PA79-219-00767GE used a drift value of.08 decades for an assumed calibration interval of24 months. The drift analysis will verify that extending the existing monthly functional check to once within 92 days ofa reactor startup will not result in actual equipment drift beyond the assumed values within calculation PA79-219-00767GE. Also, this calculation detennines the upper trip setpoint limit for the auto removal of the Zero Power Mode Bypass function.
Installation Verification o Calculation represents the installed configuration and appro~ed licensing condition (Calculation ofRecord) o NfA does not affect plant configuration (e.g., study, hypothetical analysis, etc.)
PreparerlDesigner Engineer: (Print and Sign)
Date:
Date:
Date:
Date:
Date: ~II 'lIb 7 Date:
Discipline:
Discipline:
~
-~-~--~
Engineering Approver:
- Interdiscipline Reviewer:
N/A Independent Reviewer:
A rovals Preparer: S FE I
[
1_
DCM 05-1 A Rev. 011
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P_a_g_e_l_o_f_l
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Approved 9/22/04 Effective 9/27104
~I-PassPort DATABASE INPUTs Page 2
Calculation Number:
ZPM_DRIFT*04260I2 Revision:
0 Vendor Calculation Number/Other:
N/A Revision:
N/A CCN#
N/A Calc Voided:
DYes
[gJ No Superseded By:
NIA Supersedes Calc:
N/A Discipline (Up to 10)
I,N Unit Project Reference Component Id Computer Code Rev. No.1 (Ml,M2,M3)
(EWA, OCR or MMOD)
Level No.
M2 N/A WR-LOG-A Microsoft Excel 9.0 WR-LOG-B WR-LOG-C WR-LOG-D I
MELCODES*
Structure System Component Reference Calculation Rev CCN No.
N/A
- The codes required must be alpha codes designed for structure, system and component.
NOTE: Avoid multiple item references on a line, e.g., LT 1210 A-D reauires four senarate lines.
Reference Drawing Sheet Rev.No.
NIA Comments:
Referenced By Calculation Impact Impact AR Reference/Calc Change Ref.
Y N
N/A DCM OS-OOIB Rev 009-01 Page I of I (j
Section & Title Calculation No. ZPM_DRIFT-04260I2, Rev. 0 TABLE OF CONTENTS COVER PAGE PASSPORT DATABASE INPUTS TABLE OF CONTENTS 1.0 PURPOSE 2.0
SUMMARY
OF RESULTS
3.0 REFERENCES
/DESIGN INPUTS 4.0 ASSUMPTIONS 5.0 METHOD OF CALCULATION 6.0 BODY OF CALCULATION 7.0 DESIGN VERIFICATION 8.0 AITACHMENTS Appendix A - Historical Surveillance Data - WR-LOG~A,B,C & D DCM Fonn 5-1C DeM Fonn 5-1 D TOTAL 2
3 4
4 5
6 7
8 14 AI-A5 A6&7 A8 22pgs Page 3 of 14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 1.0 PURPOSE The purpose ofthis calculation is to estimate 92 day drift values for the auto removal ofthe Zero Power Mode Bypass function. LBDeR 06-MP2-036 is proposing extending the surveillance requirement for the auto removal ofthe Zero Power Mode Bypass function from a monthly interval to once within 92 days ofa plant startup. To support the proposed surveillance extension for the auto removal ofthe Zero Power Mode Bypass function, a detailed drift analysis is required to be performed. Existing calculation PA79-219-00767GE used a drift value of.08 decades for an assumed calibration interval of24 months. The drift analysis will verify that extending the existing monthly functional check to once within 92 days ofa plant startup will not result in actual equipment drift beyond the assumed values within calculation PA79-219-00767GE. This calculation shall also determine the upper trip setpoint limit for the auto removal ofthe Zero Power Mode Bypass function.
2.0
SUMMARY
OF RESULTS The bounding values ofdrift for a 92 day surveillance requirement, derived from historical calibration data for Wide Range Nuclear Instrumentation WR-LOG-A, WR-LOG-B, WR-LOG-C and WR-LOG-D is Bound = +/- 0.0269 decades This value is less than the+/- 0.08 decades drift tenn used in calculation PA79-219-00767GE Revision 1. This value is conservative given none ofthe four instruments required any readjustment during the period oftime between January 2005 and July of 2007.
The upper trip setpoint limit is 7.413Xl0-5 % power. The setpoint must be left below this value based on the Technical Specification Allowable Value of 1.OX10-4 %
power.
Page 4 of 14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 3.0 DESIGN INPUTS & REFERENCES 3.1 Design Inputs 3.1.1 SP-M2-EE-0003, Rev 0, Guidelinesfor Impact Evaluation of24-Month Fuel Cycle on Technical Specification Surveillancesfor Millstone Unit 2 3.1.2 Surveillance Procedure SP2403GA "RPS Channel "A" Bistable Trip Test" Rev 2 Chg 5 3.1.3 Surveillance Procedure SP2403GB "RPS Channel "B" Bistable Trip Test" Rev 2 Chg 5 3.1.4 Surveillance Procedure SP2403GC "RPS Channel "C" Bistable Trip Test" Rev 2 Chg 6 3.1.5 Surveillance Procedure SP2403GD "RPS Channel "D" Bistable Trip Test" Rev 2 Chg 6 3.1.6 Surveillance Procedure SP2401 BB1 "Channel "A" Wide Range Monitor Start-up Functional Test" Rev 1 Chg 3.
3.1.7 Surveillance Procedure SP2401BB2 "Channel "B" Wide Range Monitor Start-up Functional Test" Rev 1 Chg 4.
3.1.8 Surveillance Procedure SP240lBB3 "Channel "C" Wide Range Monitor Start-up Functional Test" Rev 1 Chg 4.
3.1.9 Surveillance Procedure SP240IBB4 "Channel "D" Wide Range Monitor Start-up Functional Test" Rev 1 Chg 5.
3.1.10 Surveillance Procedure SP2401 BCl "Channel "A" Wide Range Monitor Calibration" Rev 1 Chg3.
3.1.11 Surveillance Procedure SP2401BC2 "Channel "B" Wide Range Monitor Calibration" Rev 1 Chg4.
3.1.12 Surveillance Procedure SP2401BC3 "Channel "c" Wide Range Monitor Calibration" Rev 1 Chg3.
3.1.13 Surveillance Procedure SP2401BC4 "Channel "D" Wide Range Monitor Calibration" Rev 1 Chg6.
3.1.14 Calculation PA97-219-00676GE Rev 1, Millstone Unit 2 Wide Range Neutron Flux Channel Loop Uncertainty.
3.1.15 DOE Research and Development Report No. WAPD-TM-1292, February 1981.
Statisticsfor Nuclear Engineers and Scientists Part 1: Basic Statistical Inference.
3.1.16 American National Standard N15.15-1974, Assessment ofthe Assumption ofNormality (Employing Individual Observed Values)
Page 5 of 14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 4.0 ASSUMPTIONS 4.1.1 The data derived from the surveillance procedures constitute a random sample ofthe population ofpossible values ofdrift from like instruments.
4.1.2 The electronics installed in the Wide Range Monitors are typical ofall electronics ofthe same manufacturer and model numbers. Therefore, data may be pooled without further analysis.
4.1.3 It is important to note that none ofthe instruments required recalibration. In tenns of real drift, none ofthe affected instrument channels drifted beyond 0.0269 decades from the period ofJanuary 2005 to July of2007. However, for purposes of added conservatism, each successive calibration interval was assumed as a unique data point with no credit for non-adjustment ofthe instrument setpoint.
Page 6 of 14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 5.0 METHOD OF CALCULATION In order to calculate bounding drift values for a 92 day surveillance interval, the methods ofReference 3.1.1 were employed. Plant historical data were tabulated and analyzed.
Historical surveillance test and calibration data was collected for the applicable instrumentation and entered into an Excel'spreadsheet. Statistical analysis ofthe data was performed using various functions within Excel'.
A linear regression analysis ofthe data was performed to determine if drift is time dependent. The data were tested for normality, and estimates ofthe bounding values of drift were determined using the methods for normal distributions. Scatter plots and histograms were prepared to assist in visualization ofthe data.
5.1 Instrument Block Diagram Figure I is a diagram ofa typical Wide Range Nuclear Instrumentation channel. The scope ofdrift analysis in this calculation pertains to the Zero Power Mode Bypass bistable. The current setpoint for the Zero Power Mode Bypass removal function is 9.4 X 10-5 % reactor power.
Indicator Preamplifier CJ-----
Fission Chamber
I I-------~
ZPM Bistable output to RPS Signal Processor Figure 1; Wide Range Instrumentation Channel Block Diagram 5.2 Zero Power Mode Bistable Calibration/Functional Check The identified surveillance procedures (References 3.1.2 through 3.1.13) verify the bistable trip setting of the Zero Power Mode Bypass. The setpoint is verified to fall within an acceptance range of7.1 X 10.5 to 1.2 X 10-4 % reactor power.
From the completed surveillance tests, drift values can be typically obtained by subtracting "as-found" surveillance values from the "as-left" values from the preceding surveillance test. The drift values obtained are for the period of time between the two surveillance dates. The twelve surveillance procedures effectively verify the Zero Power Page 7 of14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 Mode Bypass bistable setting using the same methodology. As a result, the calibration interval for each channel will be based on the period oftime between each successive instrument check, whether it was verified through the calibration surveillance, functional test surveillance or the bistable trip test surveillance procedure.
5.3 Input Data The historical calibration data in the Appendix constitute the input data for this calculation.
The data was derived from surveillance records which were completed over the period from January of2005 to July of2007. The associated workorders have been identified for each completed surveillance.
5.4 Spreadsheet Calculations Microsoft Excel', version 9.0, for Windows 2000 was used to perform the statistical calculations and prepare the scatter plots and histograms for this calculation. The function, AVERAGE, was used to calculate the sample mean, the function, STDEV, was used to calculated the sample standard deviation and the functions, SLOPE and INTERCEPT, were used to calculate the slope and intercept ofthe best-fit straight line for the regression analyses.
The computations performed to the full precision of Excel'are presented in this calculation rounded to two decimal places in most cases. Verification by hand calculator using the rounded values may result in slightly different results due to round-offerrors.
6.0 BODY OF CALCULATION
- 6. I Drift Analysis The identified surveillance procedures simulate an input signal through operation ofa potentiometer on the Wide Range Nuclear Instrumentation drawers. The "as-found" and "as-left" were observed on the displays and recorded. The loop drift was then determined by subtracting the "as-left" values from the "as-found" values.
Page 8 of14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 6,2 Historical Data Compilation No Days Drift (Dec)
No Days Drift (Dec)
No Days Drift (Dec)
No Days Drift (Dec) 1 1
-0.0269 39 15 0.0000 77 28 0,0000 115 36 0.0000 2
3
-0.0269 40 15 0.0000 78 28 0,0000 116 37 0,0000 3
4
-0.0269 41 15 0.0000 79 28 0,0000 117 37 0,0000 4
7
-0.0269 42 16 0.0000 80 28 0.0000 118 38 0,0000 5
9
-0,0269 43 17 0,0000 81 28 0.0000 119 38 0.0000 6
13
-0,0269 44 17 0.0000 82 28 0.0000 120 38 0.0000 7
15
-0.0269 45 17 0.0000 83 28 0.0000 121 38 0.0000 8
15
-0,0269 46 17 0.0000 84 28 0.0000 122 38 0.0000 9
15
-0.0269 47 19 0.0000 85 28 0.0000 123 38 0.0000 10 19
-0.0269 48 19 0.0000 86 28 0.0000 124 38 0.0000 11 25
-0.0269 49 19 0.0000 87 28 0.0000 125 42 0.0000 12 28
-0,0269 50 19 0.0000 88 28 0.0000 126 42 0,0000 13 28
-0.0269 51 19 0.0000 89 28 0.0000 127 42 0.0000 14 34
-0.0269 52 19 0.0000 90 28 0,0000 128 42 0.0000 15 0
0.0000 53 19 0,0000 91 28 0.0000 129 51 0.0000 16 1
0.0000 54 19 0.0000 92 28 0.0000 130 51 0.0000 17 1
0.0000 55 19 0.0000 93 29 0.0000 131 51 0.0000 18 1
0.0000 56 20 0,0000 94 29 0.0000 132 55 0.0000 19 1
0.0000 57 21 0.0000 95 29 0.0000 133 64 0.0000 20 1
0.0000 58 21 0.0000 96 31 0.0000 134 64 0.0000 21 2
0.0000 59 21 0.0000 97 31 0.0000 135 64 0.0000 22 2
0.0000 60 21 0.0000 98 31 0.0000 136 64 0.0000 23 3
0.0000 61 22 0.0000 99 31 0.0000 137 1
0.0269 24 4
0.0000 62 22 0.0000 100 31 0.0000 138 4
0.0269 25 7
0.0000 63 23 0.0000 101 31 0.0000 139 7
0.0269 26 7
0.0000 64 23 0.0000 102 31 0.0000 140 15 0.0269 27 7
0.0000 65 23 0.0000 103 31 0.0000 141 18 0.0269 28 7
0.0000 66 23 0.0000 104 31 0.0000 142 20 0.0269 29 9
0.0000 67 25 0.0000 105 31 0.0000 143 21 0.0269 30 11 0,0000 68 27 0.0000 106 31 0.0000 144 28 0.0269 31 11 0.0000 69 27 0,0000 107 33 0.0000 145 28 0.0269 32 11 0.0000 70 27 0.0000 108 33 0.0000 146 33 0.0269 33 13 0.0000 71 27 0.0000 109 33 0.0000 147 33 0.0269 34 15 0.0000 72 27 0.0000 110 33 0.0000 148 37 0.0269 35 15 0.0000 73 27 0,0000 111 33 0.0000 149 37 0.0269 36 15 0.0000 74 27 0.0000 112 34 0.0000 150 41 0.0269 37 15 0.0000 75 28 0.0000 113 34 0.0000 38 15 0.0000 76 28 0.0000 114 34 0.0000 Table 1: WR-Log AID Drift Data Table 1 presents the results ofthe drift detennination, described above. The drift data are in order of increasing values ofdrift.
6.3 Tests for Outliers There were no suspected outliers in the results. Therefore, this test was not perfonned and no data points were removed from the sample population.
Page 9 of 14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 6.4 Data Plots The scatter plots and histograms, Figures 2 and 3, provide a graphical presentation ofthe drift data. These graphs were created using Excel'.
WR-LOG-A1D Drift Data 0.0300 ***....
0.0200 0' 0.0100 OIl "C
C'll Col 0.0000 III
..............-.r
~
10 20 30 40 50 60
/0
~...
0
-0.0100
-0.0200
-o.0300.l---------------------....-J Surveillance Interval (days)
Figure 2: Scatter Plot - WR-LOG-ND Drift Data A visual inspection of the scatter plot indicates no apparent connection between the magnitude and the duration ofthe surveillance interval. A linear regression analysis ofthe data will confirm or deny the visual observation that the magnitude ofdrift is not dependent on the duration between surveillances.
WR-LOG*A!B/C/D 16,-.------------------------------,
14 12
>. 10 uI:!l 8
0" CIl.t 6
4 2
0-1----
-0.0269 Drift (decades)
Figure 3: Histogram - WR-LOG-ND Drift Data 0.0269 Page 10 of 14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 The histogram does not appear to be from a normal distribution. A D' Test shall confirm or deny the normality ofthe drift data.
6.5 Tests for Normality Due to the sample population being greater than 50 data points, the D' Test was performed. (Reference 3.1.16).
D'Test First, T was computed using the following formula:
II
[
n+l~
T::::I i--
I
- =1 2
where:
n is the number ofvalues in the sample Xi represents the values in the sample arranged in increasing order Then the D' test statistic was calculated:
where:
S2 :::: (n-l )S2 and S2 is the unbiased estimate of the population variance The mean and standard deviation calculate as follows:
- Ix.
Mean X =__
1 n
where:
Standard deviation = s::::
(Xi - X)
(n-I)
Xi represents the values in the sample arranged in increasing order n is the number ofvalues in the sample Using Excel, the standard deviation, s, calculates to 0.01166 and the mean is 0.0.
Therefore, the variance S2 calculates to 1.3596E-4.
Page 11 of 14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 Using the above fonnula, with n is equal to150 data samples, S2== (150-1)1.3596E-4== 0.0203 The test statistic, D' was then compared to the critical values from Table 5 ofReference 3.1.16 at a significance level, a== 0.02 (P =0.01 and 0.99).
The results, calculated by Excel', are:
T = 51.218 51.218 Therefore, D'==
== 359.82
.J0.0203 From Reference 3.1.16, the critical values are 505.6 at P = 0.01 and 526.4 at P== 0.99. The test statistic, D', does not lie between the critical values, so the hypothesis ofa normal distribution is rejected at a =0.02.
6.6 Bounding Values ofDrift For a non-nonnal distribution, the proportion of the population exceeding assumed bounds can be determined from Reference 3.1.1.
P _
(x + I)Fa:12~2(X+l).2(II-X) u-(n - x) + (x + l)FaI2;2(X+I),2(II-X)
Assumed upper and lower bounds (pass/fail criterion) are selected as +/- 0.0269 decades.
Then, X== 0, and the above equation becomes:
pu =
F;,.02S;2.1S0 150+ F;,.02S;2.300
_3_._78_1_ = 0.025 150+3.781 Thus, 97.5% ofthe population will lie within a bound of+/- 0.269 decades.
It is important to note here that none ofthe instruments required recalibration. Therefore, in tenns ofreal drift, none of the affected instrument channels drifted beyond 0.0269 decades from the period ofJanuary 2005 to July of2007. However, for purposes of added conservatism, each successive calibration interval was assumed as a unique data point with no credit for non-adjustment ofthe instrument setpoint.
6.7 Linear Regression Analysis ofDrift As stated earlier, examination ofthe scatter plot shows no apparent time dependency in the drift. Linear regression analyses ofthe absolute values of the data, performed by Excel'using the SLOPE and INTERCEPT functions, provide the slope and intercept of the best-fit straight line.
Page 12 of 14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 Slope = -1.486X10-4 Intercept =0.0086 The negative slope ofthe regression line for the drift data confinn that the drift does not increase with time. This is further supported by the fact that the instrument channels in question did not require any readjustment for the identified surveillances from January 2005 to July 2007. Further, the Zero Power Mode Bypass auto removal setpoint for instrument channels WR-LOG-C and WR-LOG-D did not move at all from the period of in question.
Therefore, based on the above results, the bounding values ofdrift for a 92 day surveillance interval for the Zero Power Mode bypass auto removal function is +/- 0.0269 decades.
Bound = +/- 0.0269 decades This value is less than the +/- 0.08 decades drift term assumed in calculation PA79-219-00767GE Revision 1 (Reference 3.1.14).
6.8 Setpoint Derivation The 1X 10-4 % reactor power Tech Spec value is considered an allowable value and not an analytical limit. The Zero Power Mode bypass setpoint is not modeled in the plant safety analysis and is not considered an analytical limit. For purposes ofthis calculation, the upper triP. setpoint limit shall be calculated by subtracting from the allowable value of l.OXIO
% reactor power the root ofthe sum ofthe squares ofthe expected errors which would be seen during the calibration process. The expected uncertainty terms include Rack Drift (RD), Rack Calibration Accuracy (RCAzp) associated with the Zero Power Mode Function and Measurement and Test Equipment (MTE). These terms have been derived from calculation PA79-219-00767GE Revision 1 (Reference 3.1.14). They are as follow:
RCAzp = +/- 0.10 decades RD = +/- 0.08 decades It is important to note this drift value is much more conservative that the expected drift term calculated within this calculation. (+/- 0.0269 decades).
MTE =+/- 0.01 decades Total Expected Uncertainty during perfonnance ofthe Zero Power Mode Bypass function surveillance would be calculated as follows:
Page 13 of14
Calculation No. ZPM_DRIFT-0426012, Rev. 0 SVenur = +/- ~(.I 0)2 + (.08)2 +(.01)2 =+/- 0.13 decades The Allowable Value for the Zero Power Mode Bypass function is again I.OXI 0.
4 %
reactor power. In tenns ofdecades, I.OXI 0-4 equates to the following:
Log(1.0XlO,4) = -4 These instruments have 10 decades ranging from 10'8 to 102. In terms of logarithmic function:
Log(lO'8) = -8 Log(102) = 2 In terms of log, this span ranges from -8 to 2. To detennine the up-per trip setpoint limit, 0.13 decade must be subtracted from logarithmic value of I.OXI O~ which is -4.
Upper trip setpoint limit equals 0.13 = -4.13 decades.
In tenus of% reactor power, -4.13 decades equals 10-4*13 or 7.413XlO-5 % power.
Figure 4 below provides a simplified diagram ofthe upper trip setpoint derivation.
Allowable Value l.OXlO-4 (-4 log) 1 SVerror = -0.13 decades or log
7.413XlO'5 (-4.13 log)
As-found
{
As-left trip
Actual field setpoint setpoint band Figure 4: Upper Trip Setpoint Derivation 7.0 DESIGN VERIFICAnON Design verification was done by means ofa full design review in accordance with Design Control Manual, Chapters 4 and 5. A copy of the Calculation Review Comment and Resolution Fonn is included as an attachment.
Page 14 of 14
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 Appendix Historical Surveillance Data WR-LOG-A, WR-LOG-B, WR-LOG-C & WR-LOG-D Page Al
~LOG-A Surveillance Data I Calculation No. ZPM_DRlFT-0426012, Rev. 0 Surveillance Completion AS FOUND AS LEFT DRIFT AS FOUND AS LEFT DRIFT Absoulte Procedure Work Order Date
% Power
% Power (Log)
Decades Decades Decades DAYS Drift SP2401GA M20702383 07/19/2007 1.00E-04 1.00E-04
-4.0000
-4.0000 SP24018C1 M2OS00025 07/16/2007 9AOE-05 9.40E-05
-6.00E-06
-4.0269
-4.0269
-0.0269 3
0.0269 SP2401GA M20701671 06/2812007 1.00E-04 1.00E-04 6.00E-OS
-4.0000
-4.0000 0.0269 18 0.0269 SP2401GA M20700842 06/0712007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 21 0.0000 SP2401GA M20700061 05/04/2007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 34 0.0000 SP2401GA M20609438 03/27/2007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 38 0.0000 SP2401GA M20607927 02/27/2007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 28 0.0000 SP2401GA M20607014 02/0212007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 25 0.0000 SP2401GA M20606247 01/1612007 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 17 0.0000 SP2401GA M20605502 12/05/2006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 42 0.0000 SP2401BB1 M20504175 11/16/2006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 19 0.0000 SP2401GA M20604755 1111512006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 1
0.0000 SP2401GA M20603026 09/1212006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 64 0.0000 SP2401GA M20602006 08115/2006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 28 0.0000 SP2401GA M20601062 07118/2006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 28 0.0000 SP2401GA M20600096 06/2012006 9.40E-05 9AOE-05
-6.00E-06
-4.0269
-4.0269
-0.0269 28 0.0269 SP2401GA M20512070 06/05/2006 1.00E-04 1.00E-04 6.00E-OS
-4.0000
-4.0000 0.0269 15 0.0269 SP2401GA M20511380 05/0812006 9.40E-05 9AOE-05
-6.00E-06
-4.0269
-4.0269
-0.0269 28 0.0269 SP24018B1 M20602053 04/05/2006 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 33 0.0269 SP2401GA M20510621 03/29/2006 1.00E-04 1.00E*04 O.OOE+OO
-4.0000
-4.0000 0.0000 7
0.0000 SP2401GA M20S09769 03/06/2006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 23 0.0000 SP2401BB1 M20402580 02/2312006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 11 0.0000 SP2401BC1 M20406730 02114/2006 9AOE-05 9.40E-05
-6.00E-06
-4.0269
-4.0269
-0.0269 9
0.0269 SP2401GA M20509024 02/07/2006 1.00E-Q4 1.00E-04 6.00E-OB
-4.0000
-4.0000 0.0269 7
0.0269 SP2401GA M20508223 01/0512006 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 33 0.0000 SP2401GA M20507476 12109/2005 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 27 0.0000 SP2401GA M20506707 11/08/2005 1.00E*04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 31 0.0000 SP2401GA M20505140 10/20/2005 9AOE-05 9.40E-05
-6.00E-06
-4.0269
-4.0269
-0.0269 19 0.0269 SP2401GA M20503476 09/13/2005 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 37 0.0269 SP2401GA M20502597 08/29/2005 9.40E-05 9AOE-05
-6.00E-06
-4.0269
-4.0269
-0.0269 15 0.0269 SP2401GA M20501552 08/01/2005 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 28 0.0269 SP2401GA M20500102 06/2412005 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 38 0.0000 SP2401GA M20412412 05/2412005 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 31 0.0000 SP2401GA M20411407 05/23/2005 9.40E-OS 9.40E-OS
-6.00E-06
-4.0269
-4.0269
-0.0269 1
0.0269 SP2401BB1 M20314121 05119/2005 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 4
0.0269 SP2401GA M20410435 03/29/2005 1.00E-04 1.00E-04 O.OOE+OO
-4.0000
-4.0000 0.0000 51 0.0000 SP2401GA M20409365 03/14/2005 9.40E-05 9.40E-05
-6.00E-06
-4.0269
-4.0269
-0.0269 15 0.0269 SP2401GA M20408330 02/14/2005 9.40E-05 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GA M20407340 01/04/2005 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 41 0.0269 PageA2
I WR-LOG-B Surveillance Data I Calculation No. ZPM_DRIFT-04260I2, Rev. 0 Surveillance Completion AS FOUND AS LEFT DRIFT AS FOUND AS LEFT DRIFT Absoulte Procedure Work Order Date
% Power
% Power (Log)
Decades Decades Decades DAYS Drift SP2401GB M20702384 07/1912007 9AOE-OS S.40E-OS 4.0269 4.0269 SP2401BC2 M20512632 06/2812007 SAOE-OS SAOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 21 0.0000 SP2401GB M20701672 06/2812007 9AOE-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 0
0.0000 SP2401GB M20700843 06/0712007 1.00E-04 1.00E-04 6.00E-06
-4.0000 4.0000 0.0269 21 0.0269 SP2401GB M20700062 05/04/2007 9.40E-05 9.40E-OS
-6.00E-06
-4.0269
-4.0269
-0.0269 34 0.0259 SP2401GB M20609439 03/27/2007 9.40E-05 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 38 0.0000 SP2401GB M20607928 02127/2007 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 28 0.0269 SP2401GB M20607015 0210212007 9.40E-05 9AOE-05
-6.00E-06
-4.0269
-4.0269
-0.0269 25 0.0269 SP2401GB M20606248 01/16/2007 9.40E-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 17 0.0000 SP2401GB M20605S03 1210S12006 9AOE-05 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 42 0.0000 SP2401BB2 M20S04176 11/1612006 9.40E-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 19 0.0000 SP2401GB M20604756 11/1S12006 9.40E-05 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 1
0.0000 SP2401GB M20603027 09/1212006 9.40E-05 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 64 0.0000 SP2401GB M20602007 08/1S12006 9.40E-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GB M20601063 07/1812006 9.40E-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GB M20600097 06/2012006 9.40E-05 9.40E-05 O.OOE+OO
-4.0269 4.0269 0.0000 28 0.0000 SP2401GB M20512071 06/05/2006 9.40E-OS 9.40E-D5 O.OOE+OO
-4.0269
-4.0269 0.0000 15 0.0000 SP2401GB M20S11381 05/0812006 9.40E-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401BB2 M20602052 04/05/2006 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 33 0.0269 SP2401GB M20510622 03129/2006 9.40E-OS 9AOE*OS
-6.00E-DS
-4.0269
-4.0269
-0.0269 7
0.0269 SP2401GB M20509770 03/06/2006 9.40E-OS 9AOE-CS O.OOE+OO
-4.0269
-4.0269 0.0000 23 0.0000 SP2401BB2 M20402581 02123/2006 9.40E-QS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 11 0.0000 SP2401GB M20509025 02/0712006 9.40E-QS 9.40E-Q5 O.OOE+OO
-4.0269
-4.0269 0.0000 16 0.0000 SP2401BC2 M20406595 01/18/2006 1.00E-04 1.00E-04 6.00E-Q6
-4.0000
-4.0000 0.0269 20 0.0269 SP2401GB M20508224 01/05/2006 9.40E-OS 9.40E-OS
-6.00E-06 4.0269
-4.0269
-0.0269 13 0.0269 SP2401GB M20507477 12109/2005 9.40E-OS 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 27 0.0000 SP2401GB M20506708 11/08/2005 9.40E-OS 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 SP2401GB M20505141 10120/2005 9.40E-QS 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 19 0.0000 SP2401GB M20S03477 09/13/2005 1.00E-04 1.00E-04 6.00E-OS
-4.0000
-4.0000 0.0269 37 0.0269 SP2401GB M20502S98 08129/2005 9.40E-05 9.40E-OS
-B.00E-06
-4.0269
-4.0269
-0.0269 15 0.0269 SP2401GB M20S01553 08/01/2005 9.40E-CS 9.40E-DS O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GB M20S00103 06/29/2005 9.40E-05 9.40E-Q5 O.OOE+OO
-4,0269
-4.0269 0.0000 33 0.0000 SP2401GB M20412413 05/24/2005 9.40E-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 36 0.0000 SP2401GB M20411408 05/23/2005 1.00E-04 1.00E-04 6.00E-06
-4.0000
-4.0000 0.0269 1
0.0269 SP2401BB2 M20314122 05/19/2005 9AOE-OS 9AOE-OS
-6.00E-06
-4.0269
-4.0269
-0.0269 4
0.0269 SP2401GB M20410436 03/2912005 9AOE-OS 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 51 0.0000 SP2401GB M20409366 03/14/2005 9.40E-OS 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 15 0.0000 SP2401GB M20408331 021141200S 9.40E-05 9.40E-OS O,OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GB M20407341 01/14/2005 9.40E-OS 9.40E-05 O,OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 Page A3
Calculation No. ZPM_DRIFT-04260I2, Rev. 0 I WR-LOG-C Surveillance Data I Surveillance Completion AS FOUND AS LEFT DRIFT AS FOUND AS LEFT DRIFT Absoulte Procedure Work Order Date
% Power
% Power (Log)
Decades Decades
~cades DAYS Drift SP2401GC M20702385 07119/2007 9.40E~b5 9AOE-DS
-4.0269
-4.0269 SP2401BC3 M20600413 07/17/2007 9AOE-05 9ADE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 2
0.0000 SP2401GC M20701673 06/2812007 9.40E-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 19 0.0000 SP2401GC M20700844 06/0712007 9AOE-05 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 21 0.0000 SP2401GC M20700063 05/0412007 9.40E-05 9AOE-OS O.ODE+OO
-4.0269
-4.0269 0.0000 34 0.0000 SP2401GC M20609440 03127/2007 9ADE-05 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 38 0.0000 SP2401GC M20607929 03/05/2007 9AOE-05 9.40E-DS O.OOE+OO
-4.0269
-4.0269 0.0000 22 0.0000 SP2401GC M20607016 0210212007 9.40E-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 SP2401GC M20606249 01/1612007 9ADE-05 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 17 0.0000 SP2401GC M20605S04 1210512006 9.40E-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 42 0.0000 SP2401BB3 M20504177 1111612006 9AOE-05 9AOE-05 O.oOE+OO
-4.0269
-4.0269 0.0000 19 0.0000 SP2401GC M20604757 11/1512006 9.40E-05 9.40E-oS O.OOE+OO
-4.0269
-4.0269 0.0000 1
0.0000 SP2401GC M20603028 09/1212006 9AoE-OS 9AoE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 64 0.0000 SP2401GC M20602008 08/1412006 9.40E-05 9.40E*OS O.OOE+OO
-4.0269
-4.0269 0.0000 29 0.0000 SP2401GC M20601064 07/18/2006 9.40E-D5 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 27 0.0000 SP2401GC M20600098 0612012006 9AOE-OS 9.40E~05 O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GC M20512072 0610512006 9AOE-05 9.40E-DS O.OOE+OO
-4.0269
-4.0269 0.0000 15 0.0000 SP2401GC M20511382 05/0812006 9.40E~05 9.40E*OS O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401BB3 M20602051 04/0512006 9AOE-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 33 0.0000 SP2401GC M20S10623 0312912006 9AOE-05 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 7
0.0000 SP2401GC M20509771 03/06/2006 9AOE-OS S.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 23 0.0000 SP2401BB3 M20402S82 02123/2006 9.40E-DS 9.40e-DS O.OOE+OO
-4.0269
-4.0269 0.0000 11 0.0000 SP2401BC3 M20407114 0211412006 9AOE-OS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 9
0.0000 SP2401GC M20509026 02/07/2006 9.40E-05 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 7
0.0000 SP2401GC M2050822S 01/05/2006 9AOE-OS 9AOE-QS O.OOE+OO
-4.0269
-4.0269 0.0000 33 0.0000 SP2401GC M20S07478 12/09/2005 9AOE*05 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 27 0.0000 SP2401GC M20506709 11/081200S 9AOE-05 S.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 SP2401GC M2050S142 10/20/2005 9AOE-05 9.40E~05 O.OOE+OO
-4.0269
-4.0269 0.0000 19 0.0000 SP2401GC M20503478 09/1312005 9.40E-DS 9AOE-D5 O.OOE+OO
-4.0269
-4.0269 0.0000 37 0.0000 SP2401GC M20S02599 08/2912005 9.40E-05 9.40E~05 O.OOE+OO
-4.0269
-4.0269 0.0000 15 0.0000 SP2401GC M20501554 08/01/2005 9AOE-OS 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GC M20500104 0612412005 9.40E~05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 38 0.0000 SP2401GC M20412414 05/24/2005 9AOE-OS 9.40E*OS O.OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 SP2401GC M20411409 05/23/2005 9.40E-oS 9AOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 1
0.0000 SP2401BB3 M20314123 05/1912005 9AOE-05 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 4
0.0000 SP2401GC M20410437 03/2912005 9.40E-05 S.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 51 0.0000 SP2401GC M20409367 03/14/200S 9AOE-05 9AOE-05 O.OOE+OO
-4.0269
-4.0269 0.0000 15 0.0000 SP2401GC M20408332 02/14/2005 9.40E-DS 9.40E-05 O.OOE+OO
-4.0269
-4.0269 0.0000 28 0.0000 SP2401GC M20407342 01/14/2005 9AOE-05 9.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 31 0.0000 PageA4
Calculation No. ZPM_DRIFT-0426012, Rev. 0 I WR-LOG-D Surveillance Data I Surveillance Completion AS FOUND AS LEFT DRIFT AS FOUND AS LEFT DRIFT Absoulte Procedure Work Order Date
% Power
% Power (Log)
Decades Decades Decades DAYS Drift SP2401GO M20702386 07/1912007 9AOE-05 9.40E-QS
-4.0269
-4.0269 SP2401GD M20701674 06/2812007 9AOE-OS S.40E-OS O.OOE+OO
-4.0269
-4.0269 0.0000 21 0.0000 SP2401BC4 M20S12601 06/2612007 9.40E-05 SAOE-OS O.OOE+OO
-4.0269
-4.0269 0.0000 2
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Serial No. 06-0841 B Docket No. 50-336 ATTACHMENT 3 INSTRUMENTATION TECHNICAL SPECIFICATION CHANGES MARKED UP TECHNICAL SPECIFICATION PAGES DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
TABLE 3.3-1 (Continued)
TABLE NOTATION ECh16,~
With the protective system trip breakers in the closed position and the CEA drive system capable ofCEA withdrawal.
~------~------=--==-----~-:------:--:-:-----,...--.~
(a) rip may be bypassed below 5% ofRATED THERMAL POWER; bypass shall be
..__ \\
~
~t.. automatically removed when THERMAL POWER is ~ 5% oeRATED THERMAL PO~
- rl'-'~:'I"T f V
(b) Trip may be manually bypassed when steam generatorpressure is < 800 psia and all CEAs are fully inserted; bypass shall be automatically removed when steam generator pressure is ~ 800 psia.
(c) Trip maybe bypassed below ]5% ofRATED TIIERMAL POWER; bypass shall be automatically removed when TIIERMAL POWER is ~ 15% ofRATED THERMAL POWER (d) Trip does not need to be OPERABLE ifall the control rod drive mechanisms are de-energized f/
or ifthe RCS boron concentration is greater than or equal to the refueling concentration of tv Specification 3.9.1.
(e) DELETED
.....J2---
(f) ~T Power input to trip may be bypassed below 5% ofRATED THERMAL POWER; bypass"\\
(;;:;-_.,.,
shall be automatically removed when THERMAL POWER is ~ 5% ofRATED THERMAL I
(:t; ~P~O~WE~R~.
l
~/
ACTION STATEMENTS ACTION I -
With the number ofchannels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> andlor open the protective system trip breakers.
ACTION 2 -
With the number ofOPERABLE channels one less than the Total Number of Channels. operation may continue provided the following conditions are satisfied:
a.
The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status. or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable. and the appropriate actions are taken for the affected functional units.
c.
The Minimum Channels OPERABLE requirement is met; however. one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
provided one ofthe inoperable channels is placed in the tripped condition.
MILLSTONE - UNIT 2 3/43-4 Amendment No.9. 38. ::':;;, if6, -H9, ~.m, ~.
Reissued by NRC Letter dated September 27,ifor
Serial No. 06-0841A Docket No. 50-336 Insert C Trip may be bypassed when logarithmic power is < 1E-04% and the bypass shall be capable of automatic removal whenever logarithmic power is < 1E-04%.
Bypass shall be removed prior to raising logarithmic power to a value ~ 1E-04%.
Insert G 11T Power input to trip may be bypassed when logarithmic power is < 1E-04% and the bypass shall be capable of automatic removal whenever logarithmic power is < 1E-04%.
Bypass shall be removed prior to raising logarithmic power to a value ~ 1E-04%.
ACTION 3 -
NOT USED TABLE 3.3-1 (Continued)
ACTION STATEMENTS (1iarCh 16, 2006-;-
ACTION 4 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, immediately verify compliance with the
,~
SHUTDOWN MARGIN requirements of Specification 3.1.1.1, and at least once (J) per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter.
ACTION 5 -
With the number ofchannels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 homs or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 6 -
With the Ilumber ofchannels OPERABLE one less than required by th~ Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MILLSTONE - UNIT 2 Amendment No. ~, ~,(lfr
Serial No. 06-0841A Docket No. 50-336 Insert 0 ACTION 7 -
With one automatic bypass removal channel inoperable for one or more functions, either
- a. disable the bypass channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or
- b. place the affected trip units in bypass or trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and either
- 1. restore the bypass removal channel and affected trip units to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or
- 2. place the affected trip units in trip within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
ACTION 8 -
With two automatic bypass removal channels inoperable for one or more functions, either
- a. disable the bypass channels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or
- b. place one affected trip unit in bypass and place the other in trip for each affected trip function, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and restore one automatic bypass removal channel and the associated trip unit to OPERABLE status for each affected trip function, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.