Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R130 (HPCS Piping in Reactor Bldg)ML20195C852 |
Person / Time |
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Site: |
05000000 |
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Issue date: |
02/18/1986 |
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From: |
Andrie B, Helle M AFFILIATION NOT ASSIGNED |
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To: |
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Shared Package |
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ML20195C722 |
List: |
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References |
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FOIA-86-91 SVI-D51-T0289-B, SVI-D51-T0289-B-R02, SVI-D51-T289-B, SVI-D51-T289-B-R2, NUDOCS 8605300643 |
Download: ML20195C852 (13) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML20006A4211990-01-17017 January 1990 Proposed Tech Specs,Removing Certain cycle-specific Parameter for Relocation to Core Operating Limits Rept ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20011D3141989-12-21021 December 1989 Proposed Tech Specs Re Intervals for Surveillances ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20005G4221989-11-17017 November 1989 Proposed Tech Specs Re RCS Heatup Limitations ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML19327B4051989-10-19019 October 1989 Proposed Tech Specs,Authorizing Use of Vantage 5 Fuel & Combination of Vantage 5 Fuel & Present Optimized Fuel Assembly Core at Plant ML19325C6071989-10-0303 October 1989 Proposed Tech Specs Re Onsite Power Distribution ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML18153B8371989-07-24024 July 1989 Proposed Tech Specs Reflecting Composition of Station Nuclear Safety & Operating Committee Following Recent Assignment of superintendent-engineering Position at Stations.Tech Spec Pages Include 6.1-6,6-5 & 6-6 B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes1989-06-29029 June 1989 Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes ML20245H5671989-06-23023 June 1989 Proposed Tech Specs Revising Tech Spec Page 3.4.6.1, RCS Leak Detection Sys ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing B13256, Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual1989-05-25025 May 1989 Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual ML20247H2841989-05-22022 May 1989 Proposed Tech Specs Re Types of Absorber Matls in Control Rod Assemblies ML20245F2581989-04-25025 April 1989 Proposed Tech Specs Re Administrative Controls in High Radiation Area ML20245C2541989-04-0505 April 1989 Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear Stations ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20248G0051989-04-0303 April 1989 Proposed Tech Specs,Changing Tables 3.3-1 & 4.3-1,per Generic Ltr 85-09 for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments ML20247F1111989-03-23023 March 1989 Proposed Tech Specs,Adding 30-day Preliminary Special Rept as Well as 90-day Special Rept to Proposed Action 3.6.1.6.c & Tying Surveillance 4.6.1.6.1.d Re Tendon lift-off Stress to Action 3.6.1.6.a on Tendon lift-off Force B13098, Proposed Tech Specs Re Administrative Controls & Organizational Charts1989-03-13013 March 1989 Proposed Tech Specs Re Administrative Controls & Organizational Charts ML20246D2681989-03-0606 March 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements Re Control Room Ventilation Sys & Area Exhaust Filter Plenum Ventilation Sys ML20235J0671989-02-17017 February 1989 Proposed Tech Specs,Changing Administrative Controls Section 6.0 to Include Removal of Organizational Figures,Position Change from Radiation Chemistry Technician to Radiation Protection Technician,Per Generic Ltr 88-06 ML20247M8661989-02-0101 February 1989 Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 ML20247M8201989-02-0101 February 1989 Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2 ML20247M8741989-02-0101 February 1989 Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2 ML20196B7681988-11-28028 November 1988 Proposed Tech Spec 6.2.3 Re Safety Review Group ML20205H1671988-10-24024 October 1988 Revised Tech Specs Bases Page B 3/4 3-3 Re ESFAS Interlocks ML20155F0581988-10-0404 October 1988 Proposed Tech Specs Re Installation of Automatic Leakage Rate Detection Sys to Provide Continuous Pressure Testing of Containment Air Lock Door Seal Gaskets ML20155C1591988-09-28028 September 1988 Proposed Tech Specs Re Reactivity Control Sys,Movable Control Assemblies & Group Height ML20204J1391988-09-0707 September 1988 Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection ML20204J0391988-08-23023 August 1988 Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed ML20205A3521988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2528, Electrical Emergency ML20205A3181988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2525, Std Post-Trip Actions 1990-01-02
[Table view] Category:TEST REPORT
MONTHYEARML20246H9871988-04-30030 April 1988 Environ Qualification of Continental Wire & Cable Corp Instrumentation Cable Installed in Beaver Valley Power Station Unit 1 ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20215E4621986-11-30030 November 1986 Voltage Study for Split Group Bus Configuration ML20195C7791986-02-20020 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C7601986-02-20020 February 1986 Rev 1 to Seismic Instruments Channel Check ML20210T5271986-02-19019 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R140 (HPCS Pump Base Mat) ML20195C8941986-02-18018 February 1986 Rev 2 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R170 (Reactor Recirculation Piping Support) ML20195C8521986-02-18018 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R130 (HPCS Piping in Reactor Bldg) ML20195C7681986-02-18018 February 1986 Rev 1 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C8671986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R180 (HPCS Pump Base Mat) ML20195C8731986-02-17017 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R190 (RCIC Pump Base Mat). Related Documentation Encl ML20195C8601986-02-14014 February 1986 Rev 1 to Triaxial Response Spectrum Recorder Channel Calibr for D51-R160 (Reactor Bldg Foundation) ML20195C7391986-02-0707 February 1986 Rev 1 to Triaxial Time-History Accelerograph Channel Calibr ML20195C7521986-02-0707 February 1986 Rev 1 to Triaxial Seismic Switch Channel Calibr for D51-N150 ML20213G1521985-09-26026 September 1985 Sanitized Version of Test Program on Isolation Relays & Analog Signal Isolators for Use in Hope Creek Generating Station. W/Three Oversize Drawings ML20133N0211985-08-27027 August 1985 Electrical Cable Separation Verification Testing ML20099E6561985-02-18018 February 1985 Rev 1 to Reactor Vessel Cavity Seal Test Results,Catawba Nuclear Station,Units 1 & 2,McGuire Nuclear Station,Units 1 & 2 ML20112J7191985-02-0404 February 1985 Rev a to Qualification Rept for Model KDI-1000 High-Range Containment Area Radiation Detector & Mineral-Insulated Cable Sys ML20104A9601985-01-18018 January 1985 Reactor Vessel Cavity Seal Test Results ML20198E7441985-01-10010 January 1985 Test Rept for Full Flow Testing of 16,18 & 20-Inch Main Steam Safety Valve Vent Stacks for Yankee Atomic Electric Co ML20137Z8271984-11-30030 November 1984 Nuclear Component Qualification Test Rept Square D 9025-BCW-45 Thermal Switch ML20098F5441984-09-30030 September 1984 Rev 0 to Evaluation of Tests Performed on Energy Absorbing Matl for Pipe Whip Restraints ML20100N1091984-08-31031 August 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 8, Final Rept ML20094C1511984-07-12012 July 1984 Extension of Retainer Lifetime to 4 Cycles ML20094G7451984-04-30030 April 1984 Rev 1 to Evaluation of Energy Absorbing Matl for Pipe Whip Restraints ML20138P4551984-04-19019 April 1984 Elcometer Adhesion Tests Nutec Concrete Coating Repair Sys 11S/1201/11S/1201 11S/1201/11/1201. Related Documentation Encl ML20100N1151984-03-31031 March 1984 Reactor Vessel Irradiation Surveillance Program Analysis of Capsule 18, Final Rept ML20090J5601984-03-23023 March 1984 Reactor Containment Bldg Integrated Leak Rate Test (Preoperational) ML20080B2691984-02-29029 February 1984 Diesel Generator Rocker Arm Lube Oil Temp Test Rept - SER Confirmatory Item 26 for Callaway & Item B.26 for Wolf Creek ML20080U4931984-01-31031 January 1984 Evaluation of Natural Circulation Cooldown Test Performed at San Onofre Nuclear Generating Station ML20086P0641983-12-0101 December 1983 Section 5.0, Startup Addenda, to Monthly Project Status Rept ML20080C5391983-10-15015 October 1983 Preliminary Rev 0 to Pre-Core Emergency & Auxiliary Feedwater Sys Test, Test Results Rept for 830503-0703 ML20080C5601983-10-0505 October 1983 Preliminary Rev 0 to Pre-Core Instrumentation Correlation, Test Results Rept for 830516-0701 ML20080C4511983-09-19019 September 1983 Preliminary Rev 0 to Pre-Core Chemical & Vol Control Sys Integrated Test, Test Results Rept for 830604-0704 ML20080C4341983-09-17017 September 1983 Draft 7 of Preliminary Rev 0 to Pre-Core Turbine Bypass Control Sys Test, Test Results Rept for 830601-0705 ML20080C4211983-09-14014 September 1983 Preliminary Rev 0 to Pre-Core Safety Injection Check Valve Test, Test Results Rept for 830602 ML20080C4781983-09-0707 September 1983 Preliminary Rev 0 to Main Steam Traps & Drain Valves Hot Functional Test, Test Results Rept for 830606-15 ML20134D3611983-08-30030 August 1983 Preoperational Test 2.58.11:Integrated Leak Rate Test ML20080C4671983-08-25025 August 1983 Preliminary Rev 0 to MSIV & Bypass Valves Hot Functional Test, Test Results Rept for 830602-0703 ML20080C4091983-08-25025 August 1983 Preliminary Rev 0 to Atmospheric Dump Valve Hot Functional Test, Test Results Rept for 830603-0822 ML20080C4851983-08-20020 August 1983 Preliminary Rev 0 to Pressurized Performance, Test Results Rept for 830603-17 ML20080C3951983-08-0101 August 1983 Preliminary Rev 1 to Steam Generator Blowdown Sys Test, Test Results Rept for 830611-15 ML20080C5201983-07-27027 July 1983 Preliminary Rev 0 to RCS Expansion Measurements, Test Results Rept for 830411-0715 ML20080C5061983-07-21021 July 1983 Preliminary Rev 0 to Main & Auxiliary Transformer Backfeed, Test Results Rept for 830420-0515 ML20080C4931983-06-14014 June 1983 Preliminary Rev 0 to Loose Parts & Vibration Monitoring Sys Hot Functional, Test Results Rept for 830506-0607 ML20073P9831983-03-31031 March 1983 Containment Recirculation Sump Hydraulic Performance, Snupps ML20195C6321982-12-22022 December 1982 Structural Response of Containment Structure,Shoreham Nuclear Power Station - Unit 1 During Structural Acceptance Test ML18142A0921982-10-31031 October 1982 Rev B to Nuclear Environ Qualification of Remote Multiplexer Unit Models MC170AD-Q2 & MC370AD-Q2 & Associated Pc Boards & Plug-In Modules. ML20063M6051982-09-0909 September 1982 Kuosheng Startup Test Rept,Reactor Internals Vibration Monitoring ML18047A3521982-05-31031 May 1982 Epri/Marshall Electric Motor Operated Valve (Block Valve), Interim Test Data Rept. 1988-04-30
[Table view] |
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g
, Attachment 1 OM7A: SVI-D51-T0289-3 Sheet 1 of 1 Page: 28 Rev.: 2 Triaxial Peak Accelerogra'ph Channel Calibration for D51-R130 ,.
(HPCS Piping in Reactor Building) '
Prerequisite Sign-Off Sheet Initials 4.0.3.a. Information tag for D51-R130 (DW-631-248) placed 3 on mounting location removed for performance of Lh SVI-D51-T0289-B. b
~tv 4.0.4 An RWP is in effect covering this instruction. N A 8. =d 4.0.5 Calibration Due Date is current on all test '
instruments.
v ,
b ,' ;.t
'LflSb Performed by: o //, a / / E A.16 Signature i % i afic,hu %a\s.
Initials Date
- r TEMPORARY CHANGE Atta:h c.-t 2 #d OH7A: SV!-D51-70289-B l Shee: '. :f 10 Page g of j Page: 29 Rev.: 2 Triaxial Peak Accelerotrarh Channel 7 !
Calibration for D51-R130 (HPCS Piping in Reactor Building)
Data Sheet SECTION 5.1.1 Initials Supervising Operator notified of channel 2.
inope ability a d Action Statement 3.3.7.2.a.
Time Date
- 3. Exterior of D51-R130 (DW-631-248) inspected; any discrepancies found are noted _in comments section and Supervising Operator notified.
- 5. Record plates are removed and zero lines coincide. N
- 6. Calibration set of record plates installed. >#.
- 8. Recorder D51-R130 removed. Y
. 11. Interior of D51.Jt130 inspected; any discre-pancies found are noted in comments section ,
and Unit Supervisor notified.
Section 5.1.2
- 6. AS FOUND vertical displacement 0. b IN. b\
7.a. 2 = 2 = M g/IN. M vertical displacement 0.gy IN l
Vertical Sensitivity TttJ AS AS
()OQ STEP FOUND LEIT ALLOWABLE VALUE
$ 5.1.2.7.b. 6.'br/ IN N/A / p g g/IN M
! $ 5.1.'6.7.b, N/A b'/IN a /4 .
m/IN fM
- 8. Independently verify the calculation in stop 7.a..
, ,. . Independent Verifier: MVI
$ Denotes Technical Specification requirement.
- D hSl-$l30 G 5 erset r e W574t hed TU UT ATran[
b5I-tl\ [ "'" NurcIO
TEMPORARY CHANGE Attachment 2 (Cont.) 8 OM7A: SVI-D51 70289-8 Sheet : of 10 -
Page: 30 Page 3 of 1 ,
Rev.: 2 .
SECTION 5.1. 2 (Cont.) .
Initials 4 r.
14 'AS FOUND longitudinal displacement O.L i I3 IN. MA 15.a. 2 = 3 = RO g/IN. b longitudinal displacement 0.Mb !N Longitudinal Sensitivity TM AS AS 0g} STEP FOUND LEFT ALLOWABLE VALUE
$ 5.1.2.15.b. Wi/IN N/A gg g/IN lb
\w 9 to
$ 4 5.1.6.15.b. N/A r/IN /.5" /4 t/IN 1M
- 16. Independently verify the calculation,in step 15.a. O Independent Verifier: f[
. 22. AS FOUND transverse displacement O.\LN IN. M 23.a. '2 = 2 = i3 A g/IN. Ulh transverse displacement 0 1% IN Transverse Sensitivity T('N AS AS STEP FOUND LEFT ALLOWABLE VALUE COQ $ 5.1.2.23.b. 6 N/IN N/A /J.y g/IN N h to
$ 5.1.6.23.b. N/A g/IN st X.5",# st/IN 24 Independently verify the calculation in step 23.a.
i Independent Verifier:
Section 5.1.3
! 6. Calibration record plated pulled out 3/64 inches. b 10.a. AS FOUND maximum overshoot displacement 0.0 %IN. 1AM 10.b. AS FOUND saximum displacement 0.AN. b N
. 10.c. AS FOUND maximum overshoot displacement 0.0%IN.
10.d. AS FOUND saximum displacement 0.\9IN. MM
{ $ Denotes Technical Specification requirement.
i :
TEMPORARY CHANGE Attachment 2 (Cont.) ON7A: SVI-D51 T0289-8 Sheet 3 of 10 # Page: 31 Page 'l of 1 Rev.: 2
)
SECTION 5.1.3.(Cont.) Initials j 11.a. (step 10.a. ) = maximum overshoot displacement =
(step 10.b.) eaximum displacement 0.0% IN = lh x 100% = 6 % N 0 330 IN (step 10.c. ) = maximum overshoot displacement =
(step 10.d.) maximum displacement
- 0. 0% IN = .13 x 100% = 13 % k@
0.\q\ IN
$ 11.b. AS FOUND overshoot percentages O % MM n % h%
- 12. Independently verify the calculations in step 11.a. g-Independent Verifier: (U>C, M
$ 13. (Overshoot percentare + Overshoot percentage) =
2
( O %+ 0 %) = O % M 2
- 14. Independently verify the calculation in step 13. .
Independent Verifier:
o vt Vertical Damping g 51TP AS FOUND AS I. EFT AILOWABLE VAI.UE CcQ JS 13% Overshoot 3 5.1.3.15. 55 % N/A_ = 55% Damping
.M 05% overshoot 8
$ 5.1.5.15. N/A $$%
= 70% Dampinz W# $
- 21. Calibration record plated pulled out 3/64 inches, b 25.a. AS FdUND saximum overshoot displacement 0.OIIN2 h 25.b. AS FOUND saximum displacement 0.80IN. @%
25.c. AS FOUND maxlaus overshoot displacement 0.0 MIN. M 25.d. AS FOUND maximum displacement 0. MIN. Il@
$ D'enotes Technical Specification requirement.
v ,----,,-,,_,,,..-,.,.,-,--.----.--.,,,._--,--_.--.-n ,-. ,-.e ,- - . - . , - - -- --
TEMPORARY CHANGE Attachment 2 (Cont.)
Sheet - of 10
- M OM7A: SVI-D51-T0289-8 Page d of 7 Page: 32 Rev.: 2 SECTION 3.1.3 (Cont.) Initials 26.a. (step 25.a.) = maximum overshoot displacement =
(step 25.b.) maximum displaceoent O. OM IN 0 10(0 IN
. I'3 x 100% = A % IM (step 25.c.) = maximum overshoot displacement
(step 25.d.) maximum displacement O.OF IN
- 0. gtf IN
= .10 x 100: = 10 : M
- 26. b. AS FOUND overshoot percentages b % IAF3 10 % 1,#
- 27. Independently verify the a lculations in Independent Verifier-I
$ 28. (Overshoot percentaxe + Overshoot percentane) = _
2
( O x+ lo x) = D x WAW 2
- 29. Independently verify the calculations in i
.. step 28.
Independent Verifier: O Ydf f
Longitudinal Damping ICN AS AS ETEP FOUND I. EFT ALLOVABLE VALUE
'sv
$ 5.1.3.30. Ste x N/A * =,13% Overshoot 55x DampinS to W
.Ds .05% Overshoot
$ 5.1.5.31. N/A SL% = 70% Dampinz N
- 36. Calibration record plated pulled out 3/64 inches. b 40.a. AS FOUND maximum overshoot displacement 0.@IN. 1W 40.b. AS FOUND saximum displacement 0.\M IN. 8 N
.40.c. AS FOUND maximum overshoot d'isplacement 0. MIN. %O 40.d. AS FOUND maximum displacement 0.\btN. hM
$ Denotes Technical Specification requirement.
TEMPORARY CHANGE Attachment 2 (Cont.) #b ON7A: SVI-D51-T0289-8 Sheet 5 of 10 page 6 et ? Page: 33 Rev.: 2 SECTION 5.1.3 (Cont.) Initials 41.a. (step 40.a.) =maximumovershootdisplacebent =
(step 40.b.) maximum displatement 0 Odd IN = ,(\ x 100; = M % [M
- 0. \C(\ IN (step 40.c.) = maximum overshoot displacement =
(step 40.d.) maximum displacement O. OM IN = .O x 100% = 0 % M8
- 0. (cf IN ,
S 41.b. AS FOUND overshoot percentages l\ % l\.b i3 % fMW
- 42. Independently verify the calculation,s in step 41.a. _
Independent Verifier:
$ 43. (Overshoot percentage + Overshoot percentage) =
2
( b %+ b %) = Q % N 2
- 44. Independently vocify the calcul'ation in step 43.
Independent Verifier:
7 Transverse Damping TCM AS .AS STEP FOUND LEFT AI, LOVABLE VALUE
,W 13% Overshoot
$ 5.1.3.45. 8e % N/A = 55% Damping b i
9 .
.05% Over oot
$ 5.1.5.47. N/A $b% = 70% Dampin t M
$ Denotes Technical Specification requirement.
Attachment 2 (Cont.) OH7A: SVI-D51-T0289-8 Sheet 6 of 10 Page: 34 Rev.: 2 SECTION 5.1.4 Initials r
Scriber Preload AS AS STEP FOUND LEFT ALLOWABLE VALUE f
$ 4.a. *g(o) IN 0.052 IN *
'OW)IN to
$ 9.a. O.082 IN
$ 4.b. ,00) IN IN 0.052 IN
$ 9.b. O.082 IN * [$
$ 4.c. ,0 IN
,h IN 0.052 IN
$ 9.c. 0.082 IN
- N SECTION 5.1.5 1.a. Damping Adjustment made (Vertical) M
- 6. Calibration record plated pulled out 3/64 inches. ulA 10.a. AS LEFT maximum overshoot displacement O. IN. u\A ,
10.b. AS LEFT maximum displacement O. IN. u\A 10.c. AS LEIT maximum overshoot displacement O. IN. UlA .
10.d. AS LEFT maximum displacement O. IN. pM 11.a. (step 10.a.) = maximum overshoot disp 1a' cement =
(step 10.b.) maximum displacement
- 0. IN = x 100% = % nM
- 0. IN (step 10.c.) = maximum overshoot displacement =
(step 10.d.) maximum displacement
- 0. IN = x 100% = % Wh
- 0. IN
$ 11.b. AS LEIT overshoot percentages % alA
% oh
- The maximum step on scriber preload gauge is equal to
.052 inches and the minimum step is equal to .082 inches.
$ Denotes Technical Specification requirement.
L
Attachment 2 (Cont.) DH7A: SVI-D51-T0289-3 4 Sheet 7 of 10 Page: 35 Rev.: 2 SECTION 5.1.5 (Cont. ) Initials r
l' Independently verify the calculations in step 5.1.5.a.
Independent Verifier: ,(n
$ 13. (Cvershoot percentage + Overshoot percentage) =
2
( %+ tl = % ulA 2
14 Independently verify the calculation in step 5.1.5.13.
Independent Verifier: n\A 17.a. Damping Adjustment made (Longitudinal). idA
- 22. Calibration record plated pulled out 3/64 .
inches. wh 26.a. AS LEFT maximum overshoot displacement O. IN. u\A 26.b. AS LEFT maximum displacement O. IN. a)%
26.c. AS LEFT maximum overshoot displacement O. IN. __ukA f
26.d. AS LEFT maximum displacement O. IN. uk\
27.a. (step 26.a.) = maximum overshoot displacement =
(step 26.b.) maximum displacement O. IN = x 100% = % t\A
- 0. IN (step 26.c.) = maximum overshoot displacement =
(step 26.d.) maximum displacement O. IN = x 100% = % A]'. A
- 0. IN
$ 27.b. AS LEFT overshoot percentages % o\9
% utA
- 28. Independently verify the calculations in step 5.1.5.27.a.
Independent Verifier: u\A
$ Denotes Technical Specification requirement.
1 l
. j Attachment 2 (Cont.) OM7A: SVI-D51-T0289-B f Sheet 3 of 10 Page: 56 I
Rev.: 2 SECTION 5.1.5 (Cont.) Initials c
$ 29. (Overshoot percentage + Overshoot percentane) =
2
( %+ %) = % mlA 2
- 30. Independently verify the calculations in step 5.1.5.29.
Independent Verifier: w\A 33.a. Damping Adjustment made (Transverse). m y%
- 38. Calibration record plated pulled out 3/64 inches. AIA 42.a. AS LEFT maximum overshoot displacement O. IN. ylA 42.b. AS LEFT maximum displacement O. IN. em 42.c. AS LEFT maximum overshoot displacement O. IN. uw 42.d. AS LEFT maximum displacement O. IN. 4h 43.a. (step 42.a.) = maximum overshoot displacement =
(step 42.b.) maximum displacement
- 0. IN = x 100% = % &A%
- 0. IN (step 42.c.) = maximum overshoot displacement =
(step 42.d.) maximum displacement O. IN = x 100% = % a V%
- 0. IN
$ 43.b. AS LEFT overshoot percentages % dh
% A li
- 44. Independently verify the calculations in step 5.1.5.43.a.
Independent Verifier: alg
$ 45. (Overshoot percentane + Overshoot percentare) =
2
( %+ %) = % al*
2
$ Denotes Technical Specification requirement.
(
I
\
i TEMPORARY CH ANGE Attach ent 2 (Cont.) #
Sheet : st 10 OM7A: SVI-D51 TC289-8 p g, 7 of 7 Page: 37 Rev.: 2 SECTION 5.i.5 (Cont.) r Initials
- 46. Independently verify the calculation in step 5.1.5.45.
Independent Verifier: otA SECTION 5.1.6 s
- 6. AS LEFT vertical displacement 0.IM IN.- M 7.a. 2 =
vertical displacement 2
0.13\ IN
= R g/IN. J$rl
- 8. Independently verify the calculation in step 5.1.6.7.a.
Independent Verifier: _s 14 AS LETT longitudinal displacement 0.149 IN.
15.a. 2 = 2 = \4.0 g/IN. b longit.udinal displacement 0143IN
- 16. Independently verify the calculation in s tep 5.1.6.15a. .
Independent Verifier
- 22. AS LEFT transverse displacement 0.'l44 IN. b 23.b. AS LEFT transverse acceleration sensitivity transposed to data table on Attachment 2. Mk I
- 24. Independently verify the calculation in step 5.1.6.23.a. ~
Independent Verifier:
SECTION 5.1.7 '
4 Calibration record plates installed. _f
- 6. D51-R130 re-installed per installation drawings.
h
- 7. Independent Verification: D51-R130 re-installed. hl 7tg
- 8. 50 D51-R130 mount".ug screw torqued to -e IN LBS.
J
$ Denotes Technical Specification requirement.
l
Attachment 2 (Cont.) OH7A: SV.1-D51-T0289-3 Sheet 10 of 10 Page: 34 Rev.: 2 SECTION 5.1.7 (Cont.)
Initials
- 9. Independent Verificatiorr: mounting screw torqued.
Nhk
- 10. The calibration record plates removed and operational record plates are installed. _M h
- 12. Supervising Operator notified of channel operability. 14 0 Time
/ .) 'nli late N
Section 4.0 TEST INSTRUMENTS MPL NUMBER CAL DATE CAL DUE DATE INT Scriber Preload Gauge L?C-VCf/2/7/ 2 ff 3/24f Rf kU' ggw Magnifier $70-V04FT h w/L k b Microscope L70- Vv1gT kh b & k'
- Microscope L70-)/oVS/f h4 h Torque Wrench th@706 1/ZLfy'f 2/2t/gb ' g dhh COMME!frS:
Performed By: an ) / hh /
2, [
f M / 1h / 9llbffu 4 Independent Verifier: I M./ */ NN / "I//f,/JL N fbb
/ / c s ,
8 Signature Initials Date
$ Denotes Technical Specification requirement.
l O
Attachment 3 OM7A: SVI-D51-70289-3
,' Sheet 1 of 1 Page: 39 - IAST Rev.: 2 System Restoration Checklist r
Title:
Triaxial Peak Accelerographs Channel Calibration for D51-R130 (HPCS Piping in Reactor Building)
Verified By: .. ,_, , .% h <' !? [b Ylhd/ N$ / XfAn elr//w Signature / Initials Date INITIALS LOCATION COMPONENT REQUIRED FIRST SECOND REMARKS MPL OR NAME POSITION VERIF VERIF DW-631-248 Access plugs installe'd and co'ver on f d
( D51-R130 '
Longitudinal j, access set r#
DW-631-248 screw on D51-R130 installed COMMEhTS: OL 8 5 [n s~D t IfU Ib
,. DW/SVI117/H/cp
.