|
---|
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 ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations 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 ML20247M8741989-02-0101 February 1989 Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2 ML20247M8661989-02-0101 February 1989 Rev to 1BEP-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 ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 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 ML20205A3831988-08-0303 August 1988 Rev 5 to Emergency Operating Procedure EOP 2534, Steam Generator Tube Rupture ML20205A3341988-08-0303 August 1988 Rev 2 to Emergency Operating Procedure EOP 2526, Reactor Trip Recovery 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] |
Text
Jg K And L. I l_ /./ c-INSTRLCT!!>e10.
CATA PACKAC.E C3VER SHEET
,,,. ms.1 m, SVI- d f/- To 2F9 -A 1tDes1 CAL IPECIFICAT196(1) OR CDet!TEWT(S)
- 4. 3. 7, 7. /
t/. 3. '7. 2. 2 _
rd 4.3.7,2-I rm,, 2. s r
TEST PERFORMANCE TEST AS$1GC010. raa' de IF A/ t' # !- 7[ @. 0740 DATE AND TIME
- AUTMIRIZATION TO STARY PREREQUI51TES: ,,4,'/N e/vf f, RATIONS 11 $UPERVISOR DATE A@ T](
AUTM)RIZAT10N TO $1 AR1 1E$1: I A1 / 7 f./ p f '()
SJ'ERv15ING OPERATOR DATE A@ 1]ME ACTUAL PLANT CDOITIONS 1 2 3 A 5 (Circle One)hrchdQ CC>etNTS INSTRUCTION CODPLf f!f. 4 FLLL PARTIAL _
TECH. SPEC. ActtP1ANCE CRITERI A ACCEPTABLE LMACCEPTAALE N/A OTPER DATA CRITERIA ACCEPTAaiL h thACCEPTABLE D HiA TC(5) IN EFFECT DWING PERf0RMANCE CETICIENCl[$ b Wa8 D h N WM aN (N/A if none)
- 4 M cm # Issao LCo ENTEREo TM witw0 e WRITTEN PtarompCR's SIONATuRE - '
O bli 2./nfw /0 y i.
oATE Ape T14
~}(()/g g, g 3 ortmAT10N5 WIT $UPERvl50R m[ s sHiri strERvis0R / < e / '
M[/ l 2b (Required IIf Tech, spec. Acceptance Criteria t set.other ase mark N/A) ' DATE APC T!*
l Co+ENTS: dhr NN Y(3.DbS4 i
TEST RESULTS REVIEW (8,.4.J. /- L g J A y ,,j g l
sysitH ENctwER/ f _ j, ..
f w
' d r, / (m%WV
~
REFONSISLE SECTION KVIEWER l l' - >
-. ',) ' DATE APO TIE ca. guts. . . _ _ _ _ .
I SLAVEILLAPCE CDOCINATOR 8605300543 860321 /
PDR FOIA '
HIATT86-91 PDR f
Attachment 1 ON7&: SVI-D51-70289-A
, Sheet 1 of 1 Page: 22 Rev.: 1 Triaxial Peak Accelerograph Channel Calibrat ion for D51-R120 g (Reactor Recirculation Pump)
Prerequisite Sign-Off Sheet Initials 1
4.0.3.a. Information tag for D51-R120 (DW-583-145) p 4eed on mounting location removed for performance of SVI-D51-T0289-A.
_h %
4.0.4 An RWP is in effect covering this instruct wr. bW
/// mpe-4.0.5 Calibration due date is current on all test instruments.
_}h Performed by: _
a / b / Sl17 fd,
- / /
'- g ~S ignature Initials
/
Date 4
9
, , _ , - . -r
9 Attachment 2 OM7A: 5VI-D51-70289-A Sheet 1 of 11 Page: 23 Rev.: 1 Triaxial Peak Accelerograph Channel Calibration for D51-R120 *
(Reactor Recirculation Purrp) I Data Sheet Section 5.1.1 Initials
- 2. Supert sing Operator notified of channel inoperab211ty and Action Statement 3.3.7.2.a.
< Aco / 2/nl1 '
d4W T2me Date
- 3. Exterior of D51-R120 (DV-SS3-145) inspected; any discrepancies found are noted in comments NN section and Supervising Operator notified.
- 5. Record plates are removed and zero lines coincide. 1M
- 6. Calibration set of record plates installed. NM-
- 8. Recorder D51-R120 removed. b
- 11. Interior of D51-R120 inspected; any discre-pancies found are noted in comments section and Supervising Operator notified. M Section 5.1.2
- 6. AS FOUND vertical displacement 0.0% IN. .@
7.a. 2 = 2' = ) M g/IN. n@
vertical displacement 0.g IN.
Vertical Sensitivity AS AS STEP TO'3 D LETT ALLOVABLE VALUE 5 5.1.2.7.b. @ i/IN. N/A 11.23 g/IN. M to 5 5.1.6.7.b. N/A 3/IN. 12.17 g/IN. *
- 6. Independently verify the calculation in step 7.a.
Independent Verifier
%^
5 Denotes Technical Specification requirement.
Attachment 2 (Cont.) OH7A: SVI-D51-T0289-A Sheet 2 of 11 Page: 24 Rev.: 1 Section 5.1.2 (Cont.) Initials r
14 AS FOUND longitudinal displacement 0. 061 IN. _ fMW=
15.a. 2 longitudinal displacement
= 1. - S,0 g/IN. k 0 <y511N Longitudinal Sensitivity AS AS STEP FOUND LEFT ALLOVABLE VALUE
$ 5.1.2.15.b. blg/IN. N/A 10.66 g/1N. (kDY<'
to
$ S.1.6.15.b N/A g/IN. 11.5' n'IN. 4
- 16. Independently verify the calculation in step 15.a.
Independent Verifier
- 22. AS FOUND transverse displacement 0.10$ IN. _)4 23.a. 2 = 2 - R 0 g/IN. RAnp<
transverse displacement 0.pyfIN.
Transverse Sensitivity AS AS STEP FOUND LEFT ALLOVABLE VALUE
$ 5.1.2.23.b. (d'g/IN. N/A 9.89 g/IN. _kN3hr
. .to
$ 5.1.6.23.b. N/A g/IN. 10.71 g/IN. 4
- 24. Independently verify the calculation in step 23a.
Independent Verifier /
M Section 5.1.3
- 6. Calibration record plated pulled out 3/64 inches'. 4 10.a. AS FOUND maximum overshoot displacement O. IN. 4 10.b. AS FOUND maximum displacement O. IN. M 10.c. AS FOUND maximum overshoot displacement O. A IN.
10.d. AS FOUND maximum displacement O. IN. if i Denotes Technical Specification requirement.
._. . . _ - .. - =
Attachment 2 (Cont.) ON7A: SV1-D51-TC289-A
. Sheet 3 of 11 Page: 25 Rev.: 1 Section 5.1.3.(Cont.) Initials r
11.a. (step 10.a.) = maximum overshoot displacement =
(step 10.b.) maximum d2splacement 4
- 0. IN. = x 100% = %
- 0. IN.
(step 10.c.) = maximum overshoot displacement =
(step 10.d.) maximum displacement
- 0. IN. = x 100% = % Y
- 0. IN.
$ 11.b. AS FOUND oversheet percentages % A L r
- 12. Independently verify the calculations in Independent Verifier
$ 13. (Overshoot percentage + Overshoot percentage) =
2
( t+ t) = *
. k 2
- 14. Independently verify the calculation in step 13.
Independent Verifier
- Vertical Damping AS AS STEP FOUND LEFT ALLOWABLE VALUE 13% Overshoot
$ 5.1.3.15. % N/A = 55% Damping
$ 5.1.5.15. N/A % = 70'. Damping *
- 21. Calibration record plated pulled out 3/64 inches, k' 25.a. AS FOUND maximum overshoot displacement O. IN. A 25.b. AS FOUND maximum displacement O. IN. >
25.c. AS FOUND maximum overshoot displacement O. IN. r 25.d. AS FOUND maximum displacement O. IN. *
$ Denotes Technical Specification requirement.
Attachment 2 (Cont.) OH7A: SVI-D51-70289 A Sheet 4 of 11 Page: 26 Rev.: 1 Section 5,.1.3 (Cont.) Initials r
26.a. (step 25.a.) = maximum overshoot displacement =
(step 25.b.) maximum displacement O. IN. = x 100*. = * 'E
- 0. IN.
(step 25.c.) = maximum overshoot displacement =
(step 25.d.) maximum displacement O. IN. = x 100% = t Y
- 0. IN.
$ 26.b. AS FOUND overshoot percentages t
- 27. Independently verify the calculations in step 26a.
Independent Verifier *
$ 28. (Overshoot percentage + Overshoot percentage) =
2 g
( *+ *)=
2
- 29. Independently verify the calculations in step 28. k~
Independent Verifier Longitudinal Damping AS AS STEP FOUND LEFT ALLOk'ABLE VALUE 13% Overshoot
$ 5.1.3.30. % N/A = $5% Damping #
to 5*. Overshoot
$ 5.1.5.30. N/A % = 70% Damping k
- 36. Calibration record plated pulled out 3/64 inches.
- 40.a. AS FOUND maximum overshoot displacement 0. IN. I' 40.b. AS FOUND maximum displacement 0. IN. #
40.c. AS FOUND maximum overshoot displacement O. IN.
40.d. AS FOUND maximum displacement O. #
IN.
$ Denotes Technical Spec ification requirement.
Attachment 2 (Cont.) OH7A: SVI-D51-70289-A Sheet 5 of,11 Page: 27 Rev.: 1 Sect ion 5.1.3 (Cont . ) Initials 41.a. (st er 40.a. ) = masimum overshoot displacement =
(ster -0.b. ) maximum displacement Jh
- 0. IN. = x 100% = %
- 0. IN.
(st el -0. c. ) = maximum overshoot displacement =
(stey *0.d.) maximum displacement O. IN. =
- 0. IN.
$ 41.b. AS FJ JS.*1 overshoot percentages % *
. 4
- 42. Ind(pendently verify the calculations in ster -1.a.
Independent Verifier *
$ 43. (Overshoot percentage + Overshoot percentage) =
2
( %+ *)=
2 44 Independently verify the calculation in
- step 43.
Independent Verifier Y Transverse Damping AS AS STEP FOUND LEFT ALLOWABLE VALUE 13% Overshoot 5 5.1.3.45. % N/A = 55% Damping h to 5% Overshoot
$ 5.1.5.45. N/A % = 70% Damping #
$ Denotes Technical Specification requirement.
Attachment 2 (Cont.) OH7A: SVI-D51-T0289-A Sheet 6 of 11 Page: 28 Rev.: 1 Section 3.1.4 Initials Scriber Preload AS AS STEP TOUND LETT ALLOk'ABLE VALUE
$ a.a. IN. IN. 0.052 IN. Y to
$ 6.a. 0.082 IN.
- 5 4.b. IN. IN, 0.052 IN. Y to
$ 6.h. 0.082 IN. 4
$ 4.c. IN. IN. 0.052 IN.
$ 6.c. 0.082 IN. V Section 5.1.5
- 6. Calibration record plated pulled out 3/64 inches. k 10.a. AS LEFT maximum overshoot displacement O. IN. Yr 10.b. AS LEFT maximum displacement 0. IN. A 10.c. AS LEFT maximum overshoot displacement O. IN. +
10.d. AS LEFT maximum displacement 0. IN. M-11.a. (step 10.a.) = maximum overshoot displacement =
(step 10.b.) maximum displacement O. IN. = x 100% = .
% 3r
- 0. IN.
(step 10.c.) = maximum overshoot displacement =
(step 10.d.) maximum displacement O. IN. = x 100% = % Y
- 0. IN.
$ 11.b. AS LEFT overshoot percentages % F
% k
- 12. Independently verify the calculations in step 5.1.5.a.
Independent Verifier M
$ Denotes Technical Specification reqsirement.
Attachment 2 (Cont.) OM7A: SVI-D51-70289-A Sheet 7 of 11 Page: 29 Rev.: 1 Section 5.1.5 (Cont.) Initials
$ 13. (Overshoot pereertage + Overshoot percentage) =
2
( %+ %) = % Y 2
- 14. Independently verify the calculation in Independent Verifier s 15. AS LEFT maximu Overshoot percentage trans-posed to data table on Attachment 2. *
- 21. Calibration reecrd plated pulled out 3/64 inches. A 25.a. AS LEFT maximur overshoot displacement O. IN. Y-25 b. AS LEFT maximum displacement O. IN.
- 25.c. AS LEFT maximue overshoot displacement O. IN. #
25.d. AS LEFT maximum displacement 0. IN. e 26.a. (step 25.a.) = maximum overshoot displacement =
(step 25.b.) maximum displacement O. IN. = x 100% = %
- 0. IN.
(step 25.c.) = maximum overshoot displacement =
(step 25.d.) maximum displacement O. IN. = x 100% = % k
- 0. IN.
$ 26.b. AS LEFT overshoot percentages % k
% v
- 27. Independently verify the calculations in step 5.1.5.26.a.
Independent Verifier *'
$ 28. (Overshoot percentane + Overshoot percentage) =
2 9
, ( %+ %J a %
2
$ Denotes Technical Specification requirement.
Attachment 2 (Cont.) OM7A: SVI-D51-T026.9eA
. Sheet 4 of 11 Page: 30 Rev.: 1 Section 5.1.5 (Cont.) _ Initials r
- 29. Independently verify the calculations in Independent Verifier 5 30. 'AS LEFT maximum overshoot percentage trans-posed to data table on Attachment 2. *
- 36. Calibration record plated pulled out 3/64 inches. 'I 40.a. AS LEFT maximum overshoot displacement O. IN. A 40.b. AS LEFT maximum displacement O. IN. 4 40.c. AS LEFT maximum overshoot displacement O. IN.
- 40.d. AS LEFT maximum displacement O. IN.
- 41.a. (step 40.a.) = maximum overshoot displacement =
(step 40.b.) maximum displacement O. IN. = x 100% = Af
- 0. IN.
(step 40.c.) = maximum overshoot displacement =
(step 40.d.) maximum displacement O. IN. = x 100% = 4"
- 0. IN.
$ 41.b. AS LEFT overshoot percentages % 6
% k
- 42. Independently verify the calculations in step 5.1.5,41.a.
Independent Verifier 4r
$ 43. (Overshoot percentage + Overshoot percentage) =
2 &
( %+ %) = %
2
- 44. Independently verify the calculation in step 5.1.5.43.
Independent Verifier k~
i l
$ Denotes Technical Specification requirement.
l a
~
L4 1
Attachment 2 (Cont.) OM7A: SVI-D51-70289-A Sheet 9 of 11 Page: 31 Fev.: 1 Section 5.1.5 (Cont.) Initials
?
$ 45. AS LETT maxieum overshoot percentage trans-posed to data table on Attachment 2.
- 6. AS LEFT vertical displacement O. IN.
7.a. = 2 = g/IN. Y vertical d:splacement O. IN
$ 7.b. AS LEFT vertical acceleration sensitivity transposed te data table on Attachment 2. k
- 8. Independent ly verify the calculation in step 5.1.6.7.a.
Independent Verifier *
- 14. AS LEFT longitudinal displacement O. IN. I 15.a. 2 = 2 = g/IN. 4r longitudinal displacement O. IN.
$ 15.b. AS LEFT longitudinal acceleration sensitivity transposed to data table on Attachment 2. b
- 16. Independently verify the calculation in step 5.1.6.15a.
Independent Verifier 4
- 22. AS LEFT transverse displacement O. IN. 4
$ 23.a. 2 = 2 = g/IN. At transverse displacement O. IN.
23.b. AS LEFT transverse acceleration sensitivity transposed to data table on Attachment 2. **
- 24. Independently verify the calculation in step 5.1.6.23.a.
Independent Verifier V
$ Denotes Technical Specification requirement.
p
~
Attechnent 2 (Conte) ON7A: SVI-D51-70269-A Sheet 10 of il Page: 32 Rev : 1 Section 5.1,7 Initials 4 .. Ca71bration record plates installed. j
- 6. D$1-R120 re-inst.A led per installation drawingt.
7 ,.
Indeper. dent Veej ficaticso; D51-R120 re instelled. 4
- 4. D51-R120 heunting screw torqued tc .23 IN.I.BS. E'
'9 . Indtpsndent \erification; snounting screw Aprqued. 4 P
10 The calibrot$on record plates removed and op3rotional record plates are installed. *
- 12. Supervising Dperator notified of channel operability. /_
- Time Date Sectica 4.0 TEST INSTRUMENTS MPL NUMBER CAL lDATE CAL DUE DATE Ih7 Scriber Preload Gauge Clo-i(AbhT 9lNM _3)3tl% Njle Magnifier UK)-V041,5 JA AtM & ,
Microscope L~)O-VO411 dA 4.,% _b Microscope L*)D- VOtT N M/L ml,& _ _
M_ ,_ _
Torque Vrench L')O*d M I t {.DIL 2 /'a% % _Jl/4d2r 4 - Denotes Technical $pecification requitemen.ts
%_ __m
4 Attachment 2 (Cont.) ON7A: SVI-D51-70289-A
-+
Sheet 11 of 11 Page: 33 Rev.: 1 C0!!!!ENTS: r Performed By: Ns jhhb f y/$ f z/f7)g w.-
O
/ h / 2f/TfPS Independent
,gh,<
g Yetiiier* /k, c. , , m L eb / l T fl7 ff A .
_n Signature
/ kW / D\Qlx Initials Daie 4
5 Denotes Technical Spe:ification requirement.
a
, Attachment 3 OM7A: SVI-D51-T0289-A Sheet 1 of 1 Page: 34 - LAST Rev.: 1 System Restoration Checklist e
Title:
Triaxial Peak Accelerographs Channel Calibration for D51-R120 (Reactor Recirculation Pump)
Verified By:
Signature / Initials Date INITIALS LOCATION C0!!PONENT REQUIRED FIRST SECOND REMARKS MPL OR NAME POSITION VERIF VERIF Dk*-563-145 Access plugs Installed and cover on g
- D51-R120 W Y C0!DIENTS: b k b E O d A)O dQ k d e_5 O rd ko br Od. edbdn oma - a a.c da m ,A.
r Dw'/SVI30/A/cp