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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
[Table view] |
Text
... -
MC-1 SP Number 44.403.10
. Revision O Ef f Date 9/ty/yf Signature Date Section Head /C A 8/ 4-t u a 7/23//3 ' TPC No. Date Eff Date Expr Quality Control , 7 >
Div. Mgr . [ 48 Plant Mgr. //~w 2I DRYWELL COOLER DRAIN FL0k' RATE FUNCTIONAL TEST 1.0 PURPOSE To provide a detailed instruction for station personnel to perfom a functional )
test of the Drywell Cooler Drain Flow Switches 1T47-FS029A and B to satisfy the requirements of Reference 11.1.
2.0 RESPONSIBILITY The I6C Engineer shall be responsible for ensuring the proper implementation of this procedure.
1 SR2-1021.400-6.421 m l
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JUL 241985 0603210192 860318 PDR ADOCK 05000322 P PDR
. 1
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3.0 DISCUSSION
, \ 3.1 Flow switches IT47-FS029A and B measure the volume of water condensed in
\ the Drywell by unit coolers IT47-UC017A and B. A high flow through these >
{ flow switches is indicative of high drywell humidity which may be the \
. i result of a primary nuclear process barrier leak. Alarms are provided on panel IH11*PNL-VC2 in the Main Control Room to provide early indication of g a small steam leak in the Primary Containment.
\
\ 3.2 Flow switches 1T47-FS029A and B are Magnetrol flow sensitive disk type
} instruments. Fluid flow displaces a piston and that movement is }
proportional to the rate of fluid flow. Magnetic interaction with the
{ piston stem actuates the alam switch.
3.3 The following annunciators, located on panel lHil*PNL-VC2, alarm during
/ the performance of this procedure:
l j Annunciator No. Description l
3055 (C-1 on 2B) DRYWELL UNIT CLR-17A FLOW HI 3056 (C-2 on 2B) DRYWELL UNIT CLR-17B FLOW HI 3.4 The fluid used in the performance of this procedure will eventually drain into the Drywell Floor Drain Tank, IG11*TK057. Because of this the following annunciators may alarm during the performance of this procedure:
Annunciator No. Description Location ,
0012 (D-7 on A7) DW FLOOR DRN TK lH11*PNL602 0423 (E-10 on 209C) RW SUMPS TROUBLE lHil*MCB01
( 4826 (A-2 on ZC) DRYWELL FLOOR DRAIN TK LEVEL HI IGil-PNL47
\
\
3.5 !
Table of Contents.
'N- 8.1 Functional Test of Flow Switch IT47-FS029A
\ 8.2 Functional Test of Flow Switch IT47-FS029B N-- _ - - -
4.0 PRECAUTIONS .
4.1 Steps indicated in this procedure for each instrument shall be performed in sequence.
l 4.2 The Watch Engineer shall be notified whenever a procedural step cannot be completed as stated, or if any other problem develops during the test.
l 4.3 The use of portable radio frequency generating communications equipment in the Main Control Room, Radwaste Control Room, Relay Room, Emergency Switchgear Room, and Diesel Generator Room is prohibited.
SP 44.403.10 Rev. O Page 2
- 5.0 *PREREOUISITES 5.1 Obtain approval to perform this procedure from the Watch Engineer in accordance with the Surveillance Program, SP 12.016.01.
5.2 Coordinate testing with the NSO.
5.3 Obtain an RWP, if required.
5.4 This procedure may be performed during all plant operating conditions.
However this procedure is not required to be performed when the Drywell is inerted.
6.0 LIMITATIONS AND ACTIONS 6.1 If the instrumentation being tested does not respond as specified in this procedure, then the LCOs of Reference 11.2 apply.
7.0 MATERIALS OR TEST EQUIPMENT 7.1 Polyethylene tubing (tygon) or equivalent.
7.2 Demineralized water source.
8.0 PROCEDURE INITIALS /DATE 8.1 Functional Test of Flow Switch IT47-FS029A.
8.1.1 Verify that all prerequisites have been satisfied.
7 8.1.2 Establish communications between flow switch IT47-FS029A, located on elevation 63 feet in the drywell, aid the main control room.
7 8.1.3 Inform the NSO of the intent to perform a functional test of flow switch IT47-FS029A. j 8.1.4 Record the present time. The time is recorded to help determine the length of time the instrument was out of service, j
Time 8.1.5 At the IT47-UC17A (CLC-6D) drip tray, locate the drain hole to the flow switch and insert about one foot of polyethylene tubing into the drain. Drain is inside the door adjacent to FNilA.
j 8.1.6 Connect the demineralized water source to the polyethylene tubing.
j 8.1.7 Verify that annunciator no. 3053 (C-1 on 2B),
DRYWELL UNIT CLR-17A FLOW HI, located on panel IH11*PNL-VC2, is clear.
/
SP 4).403.10 Rev. O Page 3
NOTE: Allow the flow sw!tch at least 3 minutes to respond to changes in flow.
. 8.1.8 Allow the demineralized water to flow into flow
.. switch IT47-FS029A until annunciator no. 3055 (C-1 on 2B), DRYWELL UNIT CLR-17A FLOW HI, located on panel lHil*PNL-VC2, alams. The flow should be at a rate sufficient enough to trip the flow switch.
(The flow switch should trip at approximately 1.3 CPM.) j 8.1.9 Isolate the demineralized water source. j 8.1.10 After at least three minutes verify annunciator no.
3055 (C-1 on 2B), DRYWELL UNIT CLR-17A FLOW HI, located on panel IH11*PNL-VC2, is clear. j 8.1.11 Disconnect the demineralized water source and the polyethylene tubing from the drip tray of IT47-UC17A (CLC-6D) . j 8.1.12 Record the present time. The time is recorded to help determine the length of time the instrument was out of service.
7 Time 8.1.13 Inform the NSO that testing of flow switch IT47-FS029A is complete. j 8.2 Functional Test of Flow Switch IT47-FS029B. ,
8.2.1 Verify that all prerequisites have been satisfied.
j 8.2.2 Establish communications bcts.r- f:. switch '
IT47-FS029B, located on ele h tion 63 feet in the drywell, and the main control room.
j 8.2.3 Inform the NSO of the intent to perform a functional test of flow switch IT47-FS029B. j 8.2.4 Record the present time. The time is recorded to help determine the length of time the instrument was cut of service.
j Time
.J 8.2.5 At the IT47-UC17B (CLC-7B) drip tray, ' locate the drain hole to the flow switch and insert about one foot of polyethylene tubing into the drain. Drain is inside the door adjacent to FN12A.
j SP 44.403.10 Rev. O Page 4
8.2.6 Connect the demineralized water source to the polyer.hylene tubing.
7 8.2.7 Verify that annunciator no. 3056 (C-2 on 2B),
'. DRYWELL UNIT CLR-17B FLOW HI, located on panel lHil*PNL-VC2, is clear.
f NOTE: Allow the flow switch at least 3 minutes to respond to changes in flow.
8.2.8 Allow the demineralized water to flow into flow switch IT47-FS029B until annunciator no. 3056 (C-2 on 2B), DRYWELL UNIT CLR-17B FLOW HI, located on panel IHil*PNL-VC2, alarms. The flow should be at a rate sufficient enough to trip the flow switch.
(The flow switch should trip at approximately 1.3 CPM.) 7 8.2.9 Isolate the demineralizd. water source.
f 8.2.10 After at least three minutes verify annunciator no.
3056 (C-2 on 2B), DRYWELL UNIT CLR-17B FLOW HI, located on panel 1H11*PNL-VC2, is clear.
7 8.2.11 Disconnect the demineralized water source and the polyethylene tubing from the drip tray of IT47-UC17B (CLC-7B). j 8.2.12 Record the present time. The time is recorded to help determine the length of time the instrument was out of service. j Time 8.2.13 Inform the NSO that testing of flow switch IT47-FS029B is complete.
f 9.0 ACCEPTANCE CRITERIA 9.1 The flow switches and annunciators trip and reset as noted in the procedure.
10.0 FINAL CONDITIONS 10.1 Submit all test results in accordance with the Surveillance Program, SP 12.016.01.
11.0 REFERENCES
11.1 Technical Specifications, Section 4.4.3.1.C.
11.2 Technical Specifications, Section 3.4.3.1.C.
SP 44.403.10 Rev. O Page 5 l
lg.
h 11.3 FB-23B, Flow Diagram System IT47 Primary Containment Air Cooling System.
, 11.4 ESK-10ANV03, S&W Elementary Diagram, lH11*PNL-VC2 Annunciators.
. 11.5 Magnetrol Flow Switch Instruction Manual, Model F503-A, SR2 No. 1472-1.
12.0 APPENDICES N/A 4
SP 44.403.10 Rev. O Page 6
.
