|
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18151A6641999-08-0606 August 1999 Rev 0 to Surry Unit 2 Cycle 16 Startup Physics Tests Rept. ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18151A5511999-02-10010 February 1999 to NE-1187, Surry Unit 1,Cycle 16 Startup Physics Tests Rept. ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML20249B9911998-05-0606 May 1998 Analysis of Capsule X Virginia Power Surry Unit 1 Reactor Vessel Matl Surveillance Program. W/Evaluation of Surry Unit 1 Surveillance Capsule X Results & Response to NRC RAI Re GL 92-01,rev 1,suppl 1 ML18151A1931998-05-0404 May 1998 Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program. ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20199B0711998-01-0505 January 1998 Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18150A4661997-12-16016 December 1997 ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2 ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18150A4641997-10-27027 October 1997 Risk-Informed ISI (RI-ISI) Pilot Program Submittal. ML18151A3911997-10-16016 October 1997 Rev 8 to VPAP-2103, Odcm. ML18151A7231997-08-0707 August 1997 Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products. ML20210J5031997-07-31031 July 1997 Rev 0 to NE-1132, Surry Unit 1,Cycle 15 Startup Physics Tests Rept ML18150A4441997-06-0909 June 1997 Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003. ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18151A9761996-08-13013 August 1996 Cycle 14 Startup Physics Test Rept. W/960830 Ltr ML20134J9861996-07-30030 July 1996 /Unit 2 Fuel Assembly Insp Program ML18152A4701996-06-13013 June 1996 Cycle 13 Control Rod Performance Test Results. ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18152A0571995-12-20020 December 1995 Startup Physics Test Rept,Surry Unit 1,Cycle 14. W/960111 Ltr ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18151A6421995-08-0101 August 1995 Change 3 to Rev 0 to Third Interval IST Program ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML20083C9951995-05-0808 May 1995 Rev 0 to Surry Unit 2,Cycle 13 Startup Physics Tests Rept ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing Zirlo Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating 1999-08-06
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18151A1931998-05-0404 May 1998 Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program. ML18150A4661997-12-16016 December 1997 ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2 ML18150A4641997-10-27027 October 1997 Risk-Informed ISI (RI-ISI) Pilot Program Submittal. ML18151A3911997-10-16016 October 1997 Rev 8 to VPAP-2103, Odcm. ML18151A7231997-08-0707 August 1997 Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products. ML18150A4441997-06-0909 June 1997 Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003. ML20134J9861996-07-30030 July 1996 /Unit 2 Fuel Assembly Insp Program ML18151A6421995-08-0101 August 1995 Change 3 to Rev 0 to Third Interval IST Program ML20076F8341994-08-0404 August 1994 Rev 0,Change 1 to Surry Unit 2 Third Interval IST Program ML18151A2451994-07-31031 July 1994 ISI Program,Interval 3,940510-040509, for Surry Power Station,Unit 2,rev 1 ML18151A2101994-07-31031 July 1994 ISI Program,Interval 3,931014-031013, Rev 1 ML18151A9011994-03-0303 March 1994 ISI Program Interval 3,940510- 040509, Rev 0 ML18151A1651993-04-30030 April 1993 Rev 0 to Surry Power Station Unit 1 ISI Program Interval 3 931014-031013. ML18151A6411992-03-19019 March 1992 Rev 5 to Surry Power Station,Unit 1,Inservice Testing Program Plan for Pumps & Valves,Second Insp Interval 821222-921222. ML18151A3711992-03-19019 March 1992 Rev 3 to Surry Power Station,Unit 2 Inservice Testing Program Plan for Pumps & Valves,Second Insp Interval 821222-921222. ML20079L2091991-09-22022 September 1991 Rev 2 to Station Administrative Procedure VPAP-0805, MOV Program, Upgrading Procedure to Acup Format ML20092M9061991-09-0101 September 1991 Rev 2 to VPAP-2103, Odcm ML18151A4121991-09-0101 September 1991 Rev 2 to VPAP-2103, Odcm. ML18151A6551990-11-14014 November 1990 Revised Corporate Emergency Plan Implementing Procedures, Including Rev 0 to CPIP-1.0,CPIP-2.0,CPIP-2.1,CPIP-2.2, CPIP-2.3,CPIP-2.4,CPIP-2.5,CPIP-2.6,CPIP-3.0,CPIP-3.1 & CPIP-3.2 ML20006C0571990-01-18018 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. ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. 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 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. 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. ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. 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 ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. 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 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 ML18152A5231989-04-19019 April 1989 Rev 0 to Motor-Operated Valve Action Plan. 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 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 ML18152A2911988-10-19019 October 1988 Major Milestones Description of Issue Approach to Resolution. 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 ML20205A6651988-08-0303 August 1988 Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal 1998-05-04
[Table view] |
Text
VA!.~.~!~.~ INSTRUMENTATION
- ELECJRONICS P.O. Box 9025
- 8626 Wilbur Avenue Northridge, California 91328 Telephone (213) 886-8488 Telex 65-1303 REMOTE MULTIPLEXER DOC. #466 INTEGRATED FUNCTIONAL TEST PROCEDURE I. PURPOSE:
The purpose of this test is to demonstrate that the MC170AD-Q2 Remote Multiplexer unit and associated equipment remains func-tionally operational or does not degrade the connected input circuitry in the event of a failure. This test will be performed while the equipment is subjected to the following tests:
a) Safe Shutdown Seismic Event b) Extreme Temperature/Humidity Environmental Test SEISMIC TEST A. PRE-REQUISITES:
- 1) All equipment to be tested shall have completed all irradi-ation and aging requirements.
- 2) All equipment shall have been tested per applicable compo-nent acceptance test procedtn"es.
- 3) The equipment shall be configured and motmted per Figures 1 and 2 with actual motmting methods recorded.
- 4) Amplifier inputs and outputs shall be adjusted per Table 1.
- 5) Amplifier inputs and outputs shall be connected to a PO.f recorder.
- 6) All test and recording equipment checked and calibrated.
B. PROCEDURE:
- 1) Prior to energizing the seismic table, record a minim.tun of 120 sec. of data.
- 2) While recording data, energize the seismic table and increase to required frequency and amplitude.
- 3) Maintain seismic table at required frequency and amplitude for required ti.me specified by tester and approved by Validyne Engineering Corporation engineer.
- 4) De-energize the seismic table per tester's procedures. Record data during this time.
- 5) After de-energizing the seismic table, record a minim.tun of 120 sec. of data from the test tmit.
- 6) Reproduce the recorded PCM data through Digital-to-Analog Converters (DAC's) onto an analog strip chart recorder.
Analyze each channel (32) of data for irregularities, such as amplitude increases, decreases, noise and distortion.
Use a DVM and/or scope to supplement the recorder, if necessary. Data transmitted via both fiber optic and balanced line shall be analyzed.
II. SEISMIC TEST (Continued)
B. PROCEDURE: (Continued)
- 7) Reproduce the recorded input signals and analyze for ampli-tude changes, noise, distortion, etc.
( . III. EXTREME TEMPERATURE/HUMIDITY TEST A. PRE-REQUISITE:
- 1) All equipment to be qualified shall have completed required irradiation, aging and seismic testing.
- 2) All equipment shall have been tested per applicable component acceptance test procedure.
- 3) All equipment shall be configured per Figure 1.
- 4) Module inputs and outputs adjusted per Table 1.
- 5) Equipment supply voltage adjusted for a nominal 115 VAC, 60 Hz.
- 6) Equip_ment to be tes*ted shall be installed in a suitable environ-mental chamber.
B: PROCEDURE:
- 1) Prior to energizing the environmental chamber, record the input and output data for 120 sec.
- 2) .While recording data, vary the input supply voltage to the equip-ment under test +/-10%. Hold each extreme for 120 sec.
- 3) Increase temperature and humidity to required levels(l73°F and 95% R.H.) and soak equipment for a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 4) Record signal input and data outputs for minimum of 5 minutes.
- 5) While recording data, vary the input supply voltage +/-10% of the nominal 115 VAC. Hold each extreme for a minimum of 120 sec.
- 6) Secure environmental chamber per tester's procedures.
( ~ III. EXTREME TEMPERATURE/HUMIDITY TEST (Continued)
B. PROCEDURE: (Continued)
- 7) Reproduce recorded data thru DAC's onto strip chart recorders and analyze for amplitude changes, noise, distortion, etc.
DVM's and scopes will be required to supplement the recorder.
- 8) Compare the data taken at temperature to pre-test data.
IV. ACCEPTANCE/FAILURE CRITERIA:
( A. FUNCTIONAL OPERATION:
- 1) Functional operation failure is defined as output data signal variation which exceeds published manufacturer's specification.
During seismic tests, the sample dropout error rate shall not exceed 3 dropouts per 0.15 second period. The calibration shift after seismic tests shall not exceed 0.5% of full scale.
During extreme temperature, the thermal effects shall not exceed the following:
Zero Shift: +/-100 microvolts/°F referred to signal conditioning input Span Shift: +/-0.005%/°F (percent of range)
- 2) Signal variation which exceeds specification and is not directly traceable to a module or input signal shall constitute a module case failure.
- 3) A closely related failure in two or more modules of the same type shall constitute a generic design failure of that module type.
B. FAIL-SAFE:
- 1) A failure in the Remote Multiplexer unit or associated equipment which directly degrades below an acceptable level an input signal shall constitute a failure of that piece of equipment.
(.
- v. TEST REPORTS Test Reports for Seismic and Extreme Temperature/Humidity Tests will be issued after all data has been analyzed.
All data recorded during each test shall be transcribed to hard copy under appropriate QC witness and included as part of each Test Report *
-~
DATA SHEET 1 Page 1 AMP
_f . NO. TYPE SERIAL NUMBER INPlIT OUTPUI'
- 1. TC292 QE425-1 +10 mV +8.0 VDC (OV.l.Il + ovout)
- 2. CD173 QE428-22 IV P-P ;\.;\ 15V P-P CM249 55422 30 HZ (OV.l.Il + ovout)
- 3. JC177 QE429-1 +5 VDC +5 VDC
- 4. TC292 QE425-2 +10 mV +9.50 VDC (OVin+ ovout) *
- 5. BA332 QE419-1-C +10 VDC +7.50 VDC (OV. + ov m out)
- 6. PC202 QE427-1 . +10 VDC +7.00 VDC (OV. + ov I
I
.~k, m out)
I
- 7. PT174 Q9702-l 249//11808 +5.380 VDC
- 8. CD173 QE538-1 lV P-P N 18V P-P (4-ann input)
CM249 55423 30 Hz (OV. + ov m out)
- 9. D1325 QE424-1 1,2,3,4 = 23 VDC +9.375 VDC (All OFF + -9. 375V)
- 10. D1325 QE424-2 1,2,4 = 23 VDC +6.375 VDC 3 = ov (All OFF + -9.375V)
- 11. D1325 QE424-3 1,3 = 120 VAC +3.125 VDC 2,4 = ov (All OFF + -9.375V)
- 12. CD173 QE538-2 lV P-Pj\/\ 16V P-P (4-ann input)
CM249 55420 30 Hz (OV in+ ovout)
- 13. PT174 Q9702-2 261 + 10n +8.738 C.
- 14. PC202 QE427-2 +10 VDC 9.50 VDC (OV in+ ovout)
DATA SHEET 1 Page 2 AMP i H. NO. TYPE SERIAL NUMBER ' INPUT OUTPUI'
- 15. BA332 QE419-2 lV P-P f'v" 17V P~P 30 Hz \ (OV. + ovout) in
- 16. BA332 QE419-341-C lV P-P;v, 14V P-P (OV. + ovout) 30 Hz ' in
- 17. PC202 QE427-100 1V P-P 30 Hz 1
'V'\\ 19V P-P (OV. + ovout) in
- 18. PT174 QE426-143 10 n +150 n 3.118 VDC
- 19. CD173 Q428-21 lV P-P/'* :\ lOV P-P (4 Hi)
CM249 55421 30 Hz . \ (OV. + ov in out)
- 20. TC292 QE506-l +10 mV +9.00 VDC (OV.in + ovout)
I~ 21. TC292 QE506-2 +10 mV +7.00 VDC (OV.in + OVOUt)
- 22. PT174 QE-507-1-E) 249 g I I 1180 Q +5.387
- 23. DI325 QE424-4 1,2,3,4 = 23 VDC +9.375 VDC (All OFF + -9. 375V)
- 24. DI325 QE424-5 1,2,3,4 = 2~ VDC +9.375 VDC (All OFF + -9.375V)
- 25. JC177 QE429-2 +5 VDC +5 VDC
- 26. N/A +7 .5 *VDC Jumper J103 Pin B-7 to A-13
- 27. N/A +9.0 VDC Jumper J103 Pin B-8 to Pin B-12
- 28. N/A -7.5 VDC Jumper Jl03 Pin A-7
.. to' Pin A-12
-(
.. 29. N/A . -9.0 VDC Jumper Jl03 Pin A-8 f"n Pi TI R- 11 30 *. N/A s voe Jumper J103 Pin B-20 f"n p;,, A-11
- 31. N/A 7.75 voe Jumper J103 Pin B-13 f"n Pin B-ln
r-----------------. ----------------~
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- OS D
REPORT OF COMPLIANCE Procedure Number:
Procedure Rev:
Validyne Order No:
Addendum:
This report is certification that testing operations contained in the above procedure were completely and carefully conducted on this day of
, 19 , and were witnessed by the undersigned.
~ :J To the best of my knowledge, the above statement is true~ and correct.
(Signature) (Date)
(Title) (Organization)
(Signature) (Date)
(Title) (Organization)