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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994
Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny
ML20071Q2491994-07-31031 July 1994
Rev 3 to Shoreham Decommissioning Project Termination Survey Plan
ML20063D0261993-12-31031 December 1993
Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan
ML20059K1061993-08-25025 August 1993
Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny
ML20073E9171993-07-0707 July 1993
Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa
ML20063D0121993-04-30030 April 1993
Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan
ML20128P6781993-02-17017 February 1993
Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation
ML20128P6981993-02-0909 February 1993
Rev 1 to 67X001.10, Termination Survey Design
ML20128P6571993-02-0202 February 1993
Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure
ML20128P6661993-01-29029 January 1993
Rev 0 to 67X001.03, Termination Survey Quality Control
ML20128P7011993-01-19019 January 1993
Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations
ML20128P6941993-01-0808 January 1993
Rev 1 to 67X001.09, Termination Survey Background Assessment
ML20128P6831993-01-0808 January 1993
Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt
ML20128P6751993-01-0707 January 1993
Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt
ML20128P6701993-01-0606 January 1993
Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure
ML20127B8101993-01-0505 January 1993
Plan for Phased Decommissioning of Liquid Radwaste Sys
ML20125D5071992-12-14014 December 1992
Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements
ML20128P6881992-12-10010 December 1992
Rev 0 to 67X001.08, Survey Unit Classification Description
ML20128P7211992-10-31031 October 1992
Rev 0 to Shoreham Decommissioning Project Termination Survey Plan
ML20128P7151992-10-22022 October 1992
Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description
ML20128P6471992-10-0101 October 1992
Rev 0 to 67X001.01, Termination Survey History File Content & Preparation
ML20094M7681992-03-27027 March 1992
Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992
ML20086K0981991-12-0505 December 1991
Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel
ML20079N0681991-11-11011 November 1991
Excerpts from Shoreham Solid Waste Process Control Program
ML20079P3981991-10-31031 October 1991
Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively
ML20090A8321991-08-0707 August 1991
Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm
ML20082K9491991-05-31031 May 1991
Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual
ML20070H6191991-03-11011 March 1991
Proposed Tech Specs Removing License Condition 14 from License NPF-82
ML20070D4921991-02-26026 February 1991
Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls
ML20058E3051990-10-30030 October 1990
Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs
ML20059G3701990-08-30030 August 1990
Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation
ML20056B5081990-08-21021 August 1990
Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls
ML20058N5431990-08-10010 August 1990
Proposed Tech Specs Re Defueled SAR
ML20044A8011990-06-28028 June 1990
Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status
ML20006F4711990-02-20020 February 1990
Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural....
ML20006F4881990-02-20020 February 1990
Draft Odcm.
ML20064A3381990-01-31031 January 1990
Rev 15 to 4170002, Odcm
ML20005F2481990-01-0505 January 1990
Proposed Tech Specs Re Defueled Facility OL
SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989
Suppl 15 to Startup Rept for Period 890501-0801
ML20246N9731989-07-13013 July 1989
Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process
SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989
Suppl 14 to Startup Rept for Period 890201-0501
ML20246E5891989-04-30030 April 1989
Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company)
ML20246N4871989-01-31031 January 1989
Rev 14 to Offsite Dose Calculation Manual
SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988
Suppl 12 to Startup Rept for Period Aug-Nov 1988
SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988
Proposed Tech Spec Table 1.2, Operational Conditions
ML20235U9341988-09-13013 September 1988
Rev 5 to Solid Waste Process Control Program
SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988
Suppl 11 to Startup Rept for May-Aug 1988
ML20151D7141988-07-15015 July 1988
Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
1994-07-31
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994
Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny
ML20071Q2491994-07-31031 July 1994
Rev 3 to Shoreham Decommissioning Project Termination Survey Plan
ML20063D0261993-12-31031 December 1993
Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan
ML20059K1061993-08-25025 August 1993
Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny
ML20073E9171993-07-0707 July 1993
Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa
ML20063D0121993-04-30030 April 1993
Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan
ML20128P6781993-02-17017 February 1993
Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation
ML20128P6981993-02-0909 February 1993
Rev 1 to 67X001.10, Termination Survey Design
ML20128P6571993-02-0202 February 1993
Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure
ML20128P6661993-01-29029 January 1993
Rev 0 to 67X001.03, Termination Survey Quality Control
ML20128P7011993-01-19019 January 1993
Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations
ML20128P6941993-01-0808 January 1993
Rev 1 to 67X001.09, Termination Survey Background Assessment
ML20128P6831993-01-0808 January 1993
Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt
ML20128P6751993-01-0707 January 1993
Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt
ML20128P6701993-01-0606 January 1993
Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure
ML20127B8101993-01-0505 January 1993
Plan for Phased Decommissioning of Liquid Radwaste Sys
ML20128P6881992-12-10010 December 1992
Rev 0 to 67X001.08, Survey Unit Classification Description
ML20128P7211992-10-31031 October 1992
Rev 0 to Shoreham Decommissioning Project Termination Survey Plan
ML20128P7151992-10-22022 October 1992
Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description
ML20128P6471992-10-0101 October 1992
Rev 0 to 67X001.01, Termination Survey History File Content & Preparation
ML20094M7681992-03-27027 March 1992
Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992
ML20079N0681991-11-11011 November 1991
Excerpts from Shoreham Solid Waste Process Control Program
ML20090A8321991-08-0707 August 1991
Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm
ML20082K9491991-05-31031 May 1991
Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual
ML20006F4881990-02-20020 February 1990
Draft Odcm.
ML20064A3381990-01-31031 January 1990
Rev 15 to 4170002, Odcm
ML20246N4871989-01-31031 January 1989
Rev 14 to Offsite Dose Calculation Manual
ML20235U9341988-09-13013 September 1988
Rev 5 to Solid Waste Process Control Program
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
ML20151D5931988-07-13013 July 1988
Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
ML20151D5621988-07-13013 July 1988
Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization
ML20151D6971988-06-20020 June 1988
Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl
ML20151D6281988-06-10010 June 1988
Rev 1 to Procedure 3.04, Developing Written Tests
ML20151D6481988-06-10010 June 1988
Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan
ML20151D6791988-06-10010 June 1988
Rev 2 to Procedure 8.01, Simulator Exam Evaluation
ML20151D6581988-06-10010 June 1988
Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests
ML20151D5821988-05-11011 May 1988
Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding
ML20151D4981988-05-11011 May 1988
Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control
ML20151D5691988-05-11011 May 1988
Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling
ML20151D6041988-05-11011 May 1988
Rev 0 to Plant-Specific Technical Guideline 12, Figure
ML20151D5481988-05-11011 May 1988
Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control
ML20151D4471988-05-11011 May 1988
Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control
ML20151D4251988-05-11011 May 1988
Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control
ML20151D5971988-05-11011 May 1988
Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding
ML20151D4901988-05-11011 May 1988
Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control
ML20196A9081988-01-25025 January 1988
Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing
ML20196A9601988-01-25025 January 1988
Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1
ML20196A9911988-01-25025 January 1988
Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1
ML20196A9471988-01-25025 January 1988
Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1
1994-07-31
[Table view] |
Text
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SP Ntuaber 44.662.92 Revision: 9 Date Eff.:8/18/82 TPC TPC TPC LOOSE PARTS MONITORING SYSTEM FUNCTIONAL CHECK 1.0 PURPOSE To provide detailed instructions necessary to perform a functional check of the Loose Parts Monitoring (LPM) System required by Reference 11.5.
2.0 RESPONSIBILITY The I&C Engineer shall be responsible f or insuring the proper implementation of the procedure. .
PPF 1021.499-6.421
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3.0 DISCUSSION 3.1 The Loose Parts Monitoring (LPM) System is supplied by Technology for Energy Corporation (TEC) to detect impact noises in the reactor pressure vessel.
3.2 The LPM System contains four channels which monitor acoustical signals.
Each channel consists of an accelerometer, charge converter, differential transducer amplifier and an impact detector.
3.3 Two channels monitor the feeduster vessel nozzles. The other two channels ~
monitor two control rod drive housings.
~
3.4 Also included in the system are control module, annunciator module, audio monitor / simulator, power monitor, and tape recorder.
3.5 All equipment is prefixed with 1B21 and located in IB21-FNL-252 unless otherwise noted.
4.0 PRECAUTIONS 4.1 Steps indicated in this procedure shall be performed in sequence.
4.2 The Watch Engineer shall be notified whenever a procedural step can not be completed as stated.
4.3 The LPM System may still receive alerts from the reactor pressure vessel.
If att alert is received, allow the system to reset automatically.
5.0 PREREQUISITES 5.1 Obtain permission and written approval of the Watch Engineer in accordance with the station surveillance program.
5.2 The LPM System is in its normal operating configuration as described in Step 8.1.1 of Reference 11.4.
5.3 Verify that the revision number and date on this station procedure are the same as the revision number and date on the statior. procedure in the Control Room master file.
5.4 The reactor is not required to be in any special condition (Condition 9) -
prior to performance of this test. However, suf ficient background noise must be present.
6.0 LIMITATIONS AND ACTIONS N/A 7.0 MATERIALS OR TEST EQUIPMENT N/A SP 44.662.02 Rev. 9 8/18/82 Page 2
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8.0 PROCEDURE INITIALS 8.1 Verify that all prerequisites of Section 5.0 have been completed.
8.2 Initial System Verification 8.2.1 Verify the LED's on EI-502, signifying vl5V, -15V, +5V,
+30V available, are illuminated.
8.2.2 Verify the OVL LED's on VBF-148A, 148B, 149A, and 1498 are indicating green.
8.2.3 Verify the STATUS LED's on VBD-148A, 148B, 149A and 149B are indicating green.
8.2.4 Verify the ALARM LED on VRA-502 is OFF.
8.2.5 Depress the Display Test Switch on VBI-502. Verify all segments of the Voltmeter Display LED on VB1-502 illuminate.
8.3 Sensor Functional Check 8.3.1 Place the Channel Select Switch on VBM-502 to channel 1 (2, 3, 4). Verify the background noise is audible.
8.3.2 Repeat Step 8.3.1 for channel 2, 3, and 4.
8.3.3 Place the Setpoint Monitor Select Switch on VBD-148A (148B, 149A, and 149B) to the "BKCD" position. Record the voltmeter reading of VBI-502 on Data Sheet 1, Appendix 12.1.
8.3.4 Place the Setpoint Monitor Select Switch on VBD-148A (148B, 149A, and 149B) to the " THRESH 0LD" position.
Record the voltmeter reading of. VB1-502 on Data Sheet 1, l
Appendix 12.1.
NOTE: The magnitude of Background and Threshold voltages should be approximately equal. The Threshold voltage will be shown as a negative ,
quantity.
8.3.5 Repeat Steps 8.3.3 and 8.3.4 for VBD-148B,149A, and 149B.
8.4 Simulator Functional Check 8.4.1 Place the Simulator Enable / Disable Switch on VBM-502 to the " ENABLE" position.
! SP 44.662.02 Rev. 0 8/18/82 Page 3 l
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_ _m 8.4.2 Depress the Simulator-lapact Switch on VBM-592 to the "lMPACT" position momentarily. Verify the following:
a) The status LED's on VBD-148A, 148B, 149A, and 149B are illuminated red.
b) The f$rst alert display on VBC-592 displays the first alert channel. Bacord the channel number on Data Sheet 1 Appendix 12.1.
c) The alarm LED on VBA-592 is illuminated. ,
d) The Control Room Annunciator Alarms. . _.
e) VBR-592 is in a forward / record mode.
8.4.3 After approxiantely one minute stop VBR-582 by depressing the "STOP" button.
8.4.4 Rewind VBR-592 to the point where the footage counter reads ~0000". Play the section just recorded.
8.4.5 Place the " METER" selector switch of VBR-592 to the " REP' position for each of the four channels, one channel at a time. Verify the following:
a) VBR-592 did record the signals from VBM-502 on each of the four channels.
b) The s'ignals as seen on the monitor meter of VBR-592 are approximately + 5 db on each of the four channels.
8.4.6 Depress the system reset switch on VBC-592 while l
simultaneously placing the Simulator Enable / Disable I
Switch on VBM-592 to the " DISABLE" position.
9.0 ACCEPTANCE CRITERLA 9.1 The sensors are functioning properly as demonstrated in Section 8.3.
! 9.2 The LPM System is functioning properly as demonstrated in Section 8.4. -
f 10.0 FINAL CONDITIONS I
l 10.1 Submit all test results in accordance with the station surveillance l program.
10.2 Upon completion of this procedure, the system is ready for operation.
Leave the Loose Parts Monitoring System in a normal operating configuration powered with no alarms - or as directed by the Watch Engineer. 4 SP 44.662.02 Rev. 0 8/18/82 Page 4 I
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11.0 REFERENCES
11.1 Shoreham FSAR 14.1.8.4 11.2 TEC Assembly Drawings 111699 92-7.81-15A thru 31A.
11.3 TEC Operations and Maintenance Manual #39963-91 T937.419 91 11.4 SP 23.662.01, Loose Parts Monitoring System 11.5 Technical Specification, Section 3/4.3.7.12 12.0 APPENDICES 12.1 Data Sheet 1, SPF 44.662.92-1 12.2 Equipment Numbers and Channel Designation l
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SP 44.662.92 Rev. 9 8/18/82 Page 5
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APPEND 1X 12.1 Page 1 of 1 DATA SHEET 1 Procedure Step .
V 8.3.3 Background Voltage of VBD-148A V -
Background Voltage of VBD-148B Background Voltage of VBD-149A V- --
V Background Voltage of VBD-149B Threshold Voltage of VBD-148A V 8.3.4 V
Threshold Voltage of VBD-148B Threshold Voltage of VBD-149A V Threshold Voltage of VBD-149B V 8.4.2 B) First Alert Channel SPF 44.662.92-1 Rev. 9 SP 44.662.02 Rev. 9 8/18/82 Page 6
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s APPENDIX 12.2 Page 1 of 1 EQUIPMENT NUMBERS AND CHANNEL DESIGNATION NOTE: All equipment numbers are prefixed by 1821.
CHANNEL #
1 2 3 4 -
Model i VBE-148A VBE-148B VBE-149A VBE-149B Endevco 2273AMI Sensor VBT-148A VBT-148B VBT-149A VBT-149B TEC-500 Chu ge Converter VBF-148A VBF-148B VBF-149A VBF-149B TEC-932 Differential Transducer Amplifier VBD-148A VBD-148B VBD-149A VBD-149B TEC-1432 Impact Detector TEC-1433C Control Module VBC-502 TEC-133C Annunciator Module VBA-502 TEC-1439 Audio Monitor / Simulator VBM-502 TEC-913 Power Supply Monitor El-502 TEC-142 Alert Setpoint Monitor VBI-502 TEC-146 Tape Rec. Interf ace VBS-502 Racal Tape Recorder VBR-502 TEC-141 AC Power Distrib. Junc. Box E/S-252 SP 44.662 02 Rev. 0 8/18/82 Page 7
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