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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 ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 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
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I SP Number 23.662.01 Revision: 9 Date Eff.:8/6/82 TPC TPC TPC LOOSE PARTS MONITORING SYSTEM 1.0 PURPOSE To provide detailed instructions to Station Operating Personnel for operation of the Loose Parts Monitoring System.
i l 2.0 RESPONSIBILITY i
The Operating Engineer shall be responsible for insuring the proper implementation of this procedure.
PPF 1021.299-6.421 p -_
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3.0 DISCUSSION .
3.1 The Loose Parts Monitoring (LPM) System is designed to detect, process, annunciate, alarm and record information induced by acoustical / mechanical vibrations associated with loose parts impacting within the reactor primary cooling system.
3.2 The Looss Parts Monitoring System consists of four monitoring channels.
A channel generates an alert signal when an impact generates a voltage greater than the preset threshold voltage. When the number of alerts in e given time interval (e.g. 4 alert signals in a 5 second period) is exceeded, an alarm will sound and the system's tape recorder will automatically record the loose part signals. .
3.3 The LPM System also generates an audio amplified signal to provide a means - -
of listening to the output signal of a selected channel.
NOTE: 1. All Loose Parts Monitoring System component identification numbers are preceded with the system number 1B21 unless otherwise specified.
- 2. All control switches and indicating lights are located on 1821-PNL-252 unless otherwise specified.
3.A The following procedures are provided for the operation of the 13ose Parts Monitoring System:
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8.1 Normal Performance 8.1.1 System Startup 3 8.1.2 System Shutdown .3 8.2 Abnormal Performance Inhibiting the Loose Part Monitor Alarm 4 8.2.1 Alarm Response Procedure 4 8.2.2 Appendix 12.1 Loose Parts Monitoring Prerequisite Checklist SPF23.662.01-1 Appendix 12.2 Breaker Lineup Checklist, Loose Parts Monitoring System SPF 23.662.01-5 4.0 PRECAUTIONS 4.1 An alarm resulting from the loose part monitoring system is considered a ~
warning. Therefore, no action with respect to reactor operation should be based solely on the information obtained from the Loose Parts Monitoring System.
5.0 PREREQUISITES .
5.1 Prerequisited are delineated on the Prerequisite Checklist, SPF 23.662.01-1.
SP 23.662.01 Rev. 0 8/6/82 Page 2 J
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k 1 6.0 LIMITATIONS AND ACTIONS , i
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6.1 Technical Specifications 6.1.1 In Power Operation or Startup (CONDITIONS I and 2), the LCO of Reference 11.1 shall apply.
6.2 Operating Limits N/A 7.0 kTERIALSORTESTEQUIPMENT N/A ,
8.0 PROCEDURE 8.1 Normal Performance 8.1.1 System Startup _
8.1.1.1 Verify the Prerequisite Checklist is completed and signed.
8.1.1.2 On the Audio Monitor Module (1439D), select each of channels 1 through 4 and listen for impact noises and channel response.
6.1.1.3 On the Control Module (1433C), reset all alarms by momentarily depressing the RESET switch.
e 8.1.1.4 On the Control Module (1433C), place the Deliberate Plant Maneuver Detector inhibit (DPMD INH) switch to the AUIO position.
8.1.2 System Shutdown NOTE: The Loose Parts Monitorin,, System will normally be kept operating at all times. In plant conditions when the LPM System is.not required to be fully operational, the alarm output should be inhibited in accordance with Section 8.2.1 to preclude undue operator attention to spurious LPM alarms.
8.1.2.1 On the Control Module (1433C), place the Deliberate Plant -
Maneuver Detector Innibit (DPMD INH) switch to the MANUAL position.
SP 23.662.91 Rev. 9 8/6/82 Page 3
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8.2 Abnormai Performance ,
8.2.1 Inhibiting a Loose Part Monitor Alarm NOIE: False alert signals may be generated from certain plant anneuvers
< such as control rod stepping, reactor trips, pump starts, etc. The alert level alarm any be temporarily overriden as specified below in order to make allowances for alert signals caused by plant anneuvers.
8.2.1.1 Before the plant maneuver, place the DPMD INHIBIT switch in the MANAUAL position.
8.2.1.2 Record time LPM system inhibited and reason.
8.2.1.3 Return the DPMD INHIBIT switch t'o the AUTOo p'sitiori.~
8.2.1.4 Record time that the system was restored to normal.
8.2.2 Alarm Response Proceduce 8.2.2.1 The following Alarm Response Procedure is associated with this procedure:
ARP (Later) RPV I4ose Part Alara 9.0 ACCEPTANCE CRITERIA None 10.0 FINAL CONDITIONS . :.
10.1 Ensure all documentation has been completed and signed.
11.0 REFERENCES
11.1 Technical Specifications, Section 3/4.3.7.11 11.2 TEC Leose Parts Detection Program Manual File Code T937.419.91 i 12.0 APPENDICES 12.1 Loose Parts Monitoring Prerequisite Checklist, SPF 23.662.91-1 12.2 Breaker Lineup Checklist, loose Parts Monitoring System, SPF 23.662.91-5 SP 23.662.01 Rev. 9 8/6/82 Page 4 l
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. . Page 1 of 1 1 DOSE PARTS N)NITORING Signature Initials Time Date Authorisation for Start (Watch Engineer) .
Initiated by Cempleted by ,
Reviewed by __
(Watch Engineer)
Step No. Procedure Initials
- 1. Tagging Log and Lifted 14 ads and Jumpers Log reviewed.
- 2. Distribution pat.s1 ID11-PNL-N2 energized.
- 3. System Component Power Supply Checklist (SPF 23.662.91-5) completed.
- 4. On the back of PNL-252, turn the main frame power switch ON.
- 5. On Power Monitor Module (913) turn the AC power switch ON and ensure all 4 power supply status indicators are illuminated.
- 6. On the Control Module (1433C), verify the auto reset period select switch is in the ENABLE position.
- 7. On the Annunciator Alarm Module (133C) verify the alarm inhibit indicator is extinguished.
- 8. On the Audio Monitor Module (1439D) verify that:
.1 Volume Control Set at 9 o' clock position.
.2 Channel Select Switch on 1
.3 Simulator status LED is extinguisbG -
- 9. On the Tape Recorder Interface Module (146) verify that:
.1 Start select switch in ENABLE position
.2 Tape speed select set at 7.5 ips
- 10. Verify that tape recorder has sufficient tape and counter reset to 99@9 SPF 23.662.91-1 Rev. 9 SP 23.662.91 Rev. 9 8/6/82 Page 5
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- APPENDIX 12.2 Page 1 of 1
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BREAKER LINEUP CHECKLIST IDOSE PARTS MDNITORING SYSTEM BREAKER REQU1 RED NUMBER DESCRIPTION POSITION INITIALS COMPUTER ROOM - WEST WALL -
ID11-PNL-N2 f6 LOOSE PARTS MONITORING SYSTEM POWER CLOSED - - -
i SPF 23.662.91-5 Rev. 9 i
SP 23.662.01 Rev. 9 8/6/82 Page 6
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EffcetiveDefe n/11/a? Damal Number) r,a m, . m Qanel Sub-Section)
RFV LOOSE PARTS MONTT0 RING , _
1321-VBE-148A, 3 Instr. No. 1B21-VBE-149A. B Set Point Trip 4 alerts /5 seconds Raset Manual "3SSIBLE CAUSE 130EDIATE ACTION 1.0 Loose Part. 1.1 Audibly monitor the first alert channel and then the remaining channels at FNL-252 1.2 Verify tape recorder running.
1.3 Notify STA.
2.0 Noises generated by plant 2.1 Audiblymonitorfirstal'rI' e transient or maneuver. channel and then the remaining channela at FNL-252.
2.2 If no impact noises are heard,
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reset the system and stop the tape recorder.
l 0 . 2.3 Increase the gain on all channels 4 by one step. (NOTE: This may artifically trigger the system).
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- 2.4 If no impact noises are heard, l return gain settings to normal and return system to standby.
SUBSEQUENT ACTION 1.1 Evaluate the short term safety significance of the detected loose parts by observing parameters such as offgas radiation levels, jet pump operability. CRD operability, LFRM levels.
1.2 Notify the Reactor Engineer so that the long term safety significance of the loose part can be evaluated.
2.1 If repeated false alerts occur, initiate a Maintenance Work Request for I&C to adjust alert criteria.
REFERENCES SP 23.662 91
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