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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
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[x Reviewed /dOA Ener.: ~[ e ._
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P' ll.' d r- j s
Sp Number _ 35.122.01 Revision 1 Date Eff. y /f3 TPC TPC TPC SERVICE WATER PUMP ROTATING
.n ASSEMBLY REMOVAL AND INSTALLATION v\
1.0 PURPOSE To describe the the steps Service Water Pump.necessary to remove and reinstall the rotating assembly of 2.0 RESPONSIBILITY The Maintenance impleeentation of Engineer shall be responsible for ensuring the proper this procedure.
PPFIC21.3C3-6.421 Fi.P 03 2.0 ~
re r.e b d jm C' L .;;n[p.-
dIlv}idn..
m umem%
A
3.0' DISCUSSION 3.1 The service water pumps (IP41*P-003A/B/C/D) are 2 stage, vertical,
./ centrifugal wet-pit type pumps driven by individual electric motors. They 7 are located at El. 20 f t - f in. in the Screenwell. The punps take a (d auction on the intake canaI and discharge through strainers to supply cooling water to the turbine building closed loop cooling water, residual heat removal, and reactor building standby ventilation system. control room air conditioning and main ventilation chilled water chiller condensers, and the circulating water pump bearing and emergency diesel generator coolers . <1 3.2 '
The following procedures are provided to ensure proper maintenance of the service water pumps (excluding motors) and are intended to be used either as independent procedures or together:
_ Pare 8.1 Packing Replacement and Adjustment 3 8.2 Driver Removal 3
8.3 Driver Installation 4 8.4 Puep Rotating Element Disassembly and Reassembly 5 8.5 Returning the Pu=p to Service 6
4.0 PRECAUT10':S 4.1 Care should be taken when pump internals are exposed or when the screenwell pit is open to prevent foreign material from entering the pucp casing or '
screenwell pit and which could be left there after maintenance is complete.
4.2 After the service water pump is recoved from the screensell. the pump hole shouldthrough falling be covered the with wood (or suitable cover) to prevent personnel from opening.
4.3 Care on it.should be taken when lifting the pump to ensure that no strain is put Jerking or dropping the punp =ay effect pump align =ent. When lif ting the ensure thatpump and moving it from vertical to horizontal positions, bending of the there is adequate support for the bowls and colu=n to prevent pump.
5.0 PREREOUISITES 5.1 Faintenance Work Request 5.2 Station Eauipment Clearance Per=1t 5.3 laydown space for the motor and rotating element of the pump should be available around the screenwell building.
5.4 In order to disconnect and reconnect the pump column and bowl seismic restraints within the service water pit, the associated screenwell pit will have to be dewatered.
5.5 Equipeent Pumps. History Forn SPF31.f01.01-!.0D Vertical Centrifugal
<l
(- SP35.122.01 Rev. 1 Page 2
g .
5.6 Riggin:: cauip ent (crenas. slings, occ.) should be inspected to ensure that they are in a safe condition for use.
'm 1 5.7 Cleanliness requirenents shall be establist ed in accordance with SP 12.923.01, Station Housekeeci: z.
<1 6.0 LIMITATIONS AND ACTIONS 6.1 Allowable 11.1.
puap out of service time shall be in accordance with Reference 7.0 M_ATERIALS OR TEST EC"IP:ENT 7.1 Mobile crane capable of the following:
Lif t capacity - 12 tons with a radius of later ft.
Lif t height above screenwell roof - 32 f t.
7.2 Wire rope slings (matched) 7.3 Shackles 7.4 L%iversel dial indicator set 0-50-0 7.5 l Wood bloc.ks and materials on which to set the motor and pump parts during disassembly.
7.6 Two - 3 ton chain hoists 8.0 _ PROCEDURE Component ID No. Initials MWR/PM No.
Pu=p Serial No._ Motor Serial No.
Conducted by: Date 8.1 Packing Reelace ent and Adiustrent 8.1.1 Ensure the prerequisites of Section 5.0 have been met.
and the appropriate caterials cr test equiprent in Sectica 7.0 are available.
8.1.2 Replacerent of packing and adjustments should be performed in accordance with the Stuffing Box Assembly Section of Reference 11.2.
8.1.3 Coat the packing studs with a sc:all amount of grease or (DV SP35.122.01 Rev. 1 Page 3
lubriccnt citar caintcennco to prsvsnt the from becesing fculed er c:rred2d.
8.1.4
'g--) If no other naintenance is to be perforced and work has been recorded on the Equipment History fors, notify the Q Maintenance Foreeah that maintenance is complete.
8.2 Driver Renoval 8.2.1 Ensure the prerequisites of Section 5.0 have been met, and the appropriate materials or test equipment on Section 7.0 are available.
8.2.2 Remove the following electrical leads from the service water pump motor and tag them for identification and location during reassembly:
- 1. Motor power leads to main terminal box.
- 2. Power leads to space heater.
- 3. Bearing temperature detector leads.
4 Stator RTD leads.
- 5. Vibration monitor lead (s).
8.2.3 Disconnect the motor ground cable.
8.2.4 Record the "As Found" pu=p coupling clearance between the pump-end adjusting nut and the motor driving half and disconnect the pu=p coupling. Record "As Found"
.- alignment data on the Equip:ent History Form.
8.2.5 Remove the bolts attaching the motor to the motor support head and any align =ent pins that may be installed.
8.2.6 Attach rigging to the lifting lugs mounted on the top of the motor housing, and re=ove the motor frc= the support head.
8.2.7 Set the motor in an upright position on suitable blocking.
CAUTION:
The motor shaft extends 7 in. below the mounting surface. Ensure that blocking is hi hF enough to prevent damage to the shaft.
8.3 Driver Installation 8.3.1 Replace motor on the support head in accordance with the sections of Reference 11.2 which cover motor installation SP35.122.01 Rev. 1
(. Page 4
" ---*---r- -- -
c cnd ccupling instellation.
8.3.2 Reconnect and alien the punp coupling in accordance viht Reference 11.2 sections which cover the flanned coupling and aligneent. Record final alighnent data on the Equipment History Form.
8.3.3 Replace the following electrical leads on the service water punp. Ensure proper replacement of leads by matching tags:
- 1. Motor power leads to the main terminal box.
- 2. Power leads to the space heater.
- 3. Bearing temperature detector leads.
- 4. Stator RTD leads.
- 5. Vibration monitor lead (s) 8.3.4 Replace the motor ground cable.
8.3.5 Check for proper power lead placement using a motor rotation tester. Rearrange leads for proper rotation if necessary.
8.3.6 Notify the Maintenance Fore =an or his assigned alternate that all work is co=pleted and that Section 8.5 may be conducted.
8.4 Puno Rotatine Elenent Disassenb1v and Reassenbly
()N 8.4.1 Ensure prerequisites of Section 5.0 have been met, and k ,)
m the appropriate caterials or test equipcent in Sectin 7.0 are available.
8.4.2 The service water pump motor has been recoved in accordance with Section 8.2.
8.4.3 Disconnect the discharge and seal water piping.
8.4.4 With the screenwell dewatered. re=ove the seismic restraints on the pu=p pipe column and bowls.
8.4.5 Renove pu=p from the screenwell pit and locate in laydown area for further disassembly per Reference 11.2.
8.4.6 After the pump has been renoved, the pdep mounting plate opening should be covered to prevent equipment and/or debris from entering the screenwell pit and adequate personnel safety precautions taken.
8.4.7 Disassenble the pu=p and rotating element in accordance with the appropriate sections of Reference 11.2. Record the "As-Found" conditions on the Maintenance History SP35.122.91 Rev. 1 Pare 5
~,-~.,wm .
e F2rm.
8.4.8 Conduct necessary rework to.the pump parts and or replace
()
parts as required. If necessary, perform repairs in accordance with SP 31.017.91. Soeeisi Rerairs and Testine.
8.4.9 Reassemble the pump rotating assembly and pump case in accordance with Reference 11.2.
8.4.10 Reinstall pump into the screenwell pit reassemble the stuffing box and replace the pump motor per 8.3.
- 8.4.11 Replace the seisnic restraints on the pump pipe column and bowls and reconnect the discharge and seal wate rpiping.
8.4.12 Af ter the pump and motor have been reinstalled and the Equipment History Form is completed, notify the Maintenance Forenan that Seciton 8.5 may be conducted.
8.5 Returninz the Pump to Service 8.5.1 Check the screenwell pit clear of foreirn material if dewatered or the pump was removed.
8.5.2 Check the cotor thrust bearing oil levels and fill to the proper level, if required.
8.5.3 Turn the puep shaft by hand, using a strap wrench, to
) ensure freedom of rotation.
(
8.5.4 Check that the motor housing ventilatin ports are clear.
l I
1 SP35.122.01 Rev. 1 Page 6
8.5.5
, Return the scracnwell pit to its normal cpercting !
c:nditien.
8.5.6 Monentarily energize motor to check direction of g( - rotation.
Switch motor leads if necessary to achieve proper direction of rotation.
8.5.7 Check the pump packing gland and adjust for proper leakoff after the pump is operating. ,
9.0 ACCEPTANCE CRITERIA 9.1 Measured clearances are within the following limits:
- 1. Coupling Aligneent = .002"
- 2. Pump and Motor Float = 1/2 total float
- 3. Wear Ring Clearances = .625" max.
- 4. Shaft Runout = .9005" per ft.
10.0 FINAL CONDITIONS 10.1 Remove tools, rigging, and trash from the work area.
10.2 Equipment History Form and procedure submitted to Maintenance Engineer for review and filing in accordance with SP 31.002.01, Maintenance Record System.
<1 10.3 Statien equipment clearance tags removed.
10.4 Maintenance Engineer Review Date
11.0 REFERENCES
11.1 Technical Specifications, 5/21/76. Section 3.7.1 11.2 Binghan-Williatette Company, Type VM Size 16 x 26c, Multi-STaza Vertical Pu=ps, Wet Pit VCM & VTM. Installation, Operation, and Maintenance Procedures. File Code IP41.110.
<l 12.0 APPENDICES N/A SP35.122.91 Rev. 1 (0 Page 7
)
