W3P84-0431, Discusses Activities & Commitments to Be Completed Prior to Fuel Load.Listed Open Items Will Be Completed Prior to 840430: Difference between revisions

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LOUISIANA / i 2 OuAnO~oe sincer P O 'N E R & L I G H T/ P O BOX 6008 e NEW ORLEANS. LOUISIANA 7017A . (504) 366 2345 NEdYS                               March 8, 1984                     W3P84-0431 3-A1.01.04 Director of Nuclear Reactor Regulation Attention: Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
LOUISIANA / i 2 OuAnO~oe sincer P O 'N E R & L I G H T/ P O BOX 6008 e NEW ORLEANS. LOUISIANA 7017A. (504) 366 2345 NEdYS March 8, 1984 W3P84-0431 3-A1.01.04 Director of Nuclear Reactor Regulation Attention:
Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555


==SUBJECT:==
==SUBJECT:==
Line 23: Line 24:


==Dear Sir:==
==Dear Sir:==
The construction and preoperational testing phases of Louisiana Power & Light Company's Waterford Steam Electric Station Unit 3 are nearing completion and final preparations for initial core loading are in progress.
The construction and preoperational testing phases of Louisiana Power & Light Company's Waterford Steam Electric Station Unit 3 are nearing completion and final preparations for initial core loading are in progress.
A thorough assessment of project completion plans has been made and the baseline plant configuration to safely support initial t'ucl loading has been established using the FSAR, NRC Safety Evaluation Report and Supplements, and the Final Environmental Statement as guidance. Attachment I identifies
A thorough assessment of project completion plans has been made and the baseline plant configuration to safely support initial t'ucl loading has been established using the FSAR, NRC Safety Evaluation Report and Supplements, and the Final Environmental Statement as guidance. Attachment I identifies
Line 29: Line 29:
the plant systems which LP6L intends to have constructed, tested, and trans-ferred from Construction /Startup to Plant Staff control prior to fuel load.
the plant systems which LP6L intends to have constructed, tested, and trans-ferred from Construction /Startup to Plant Staff control prior to fuel load.
Systems which are required by Technical Specifications will be determined OPERABLE by satisfying the applicable Surveillance Requirements and will assure that fuel load and subsequent plant testing and operations will have no adverse impact on the health and well being of the general public and plant personnel.
Systems which are required by Technical Specifications will be determined OPERABLE by satisfying the applicable Surveillance Requirements and will assure that fuel load and subsequent plant testing and operations will have no adverse impact on the health and well being of the general public and plant personnel.
Licensing-related activities and commitments, which presently are not completed but are considered to be necessary for fuel load, have been identified and are being tracked to completion utilizing LP&L's Licensing Commitment Tracking System. The items contained on these reports receive on-going management review, are updated frequently, and are giver. high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector for Waterford 3. We will continue to provide updated reports on a reutine basis until Fuel Load. Additional items, not contained on the prior to fuel load reports, are considered requisite to criticality, low power physics testing, or power escalation sequence testing. As sach they are tracked and receive frequent management reviews to ensure that they are completed prior to their required need.
Licensing-related activities and commitments, which presently are not completed but are considered to be necessary for fuel load, have been identified and are being tracked to completion utilizing LP&L's Licensing Commitment Tracking System. The items contained on these reports receive on-going management review, are updated frequently, and are giver. high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector for Waterford 3.
                                                                                                                /
We will continue to provide updated reports on a reutine basis until Fuel Load. Additional items, not contained on the prior to fuel load reports, are considered requisite to criticality, low power physics testing, or power escalation sequence testing. As sach they are tracked and receive frequent management reviews to ensure that they are completed prior to their required need.
8403120168 840308 PDR ADOCK 05000382 A                     PDR m
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8403120168 840308 PDR ADOCK 05000382 A
PDR m
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                                                                                    't Mr. G. W. Knighten W3784-0431 Page Two it is LP&L's plan.to complete essentially all open items required prior to fuel load by not later than April 30, 1984. Thus it is expected that LP&L will be ready for receipt of the Operating License for Waterford 3 on that date.
't Mr. G. W. Knighten W3784-0431 Page Two it is LP&L's plan.to complete essentially all open items required prior to fuel load by not later than April 30, 1984. Thus it is expected that LP&L will be ready for receipt of the Operating License for Waterford 3 on that date.
If after your review of the attached information you have any questions or wish to discuss this matter further, please do not hesitate to contact me.
If after your review of the attached information you have any questions or wish to discuss this matter further, please do not hesitate to contact me.
Very truly yours, K. W. Cook                 ~,
Very truly yours, K. W. Cook
~,
Nuclear 92pport & Licensing Manager KWC/WAC/pco
Nuclear 92pport & Licensing Manager KWC/WAC/pco
        - cc.; E. L. Blake, W. M. Stevenson, G.- L. Constable, J. II. Wilson k
- cc.;
E. L. Blake, W. M. Stevenson, G.- L. Constable, J. II. Wilson k


AITACHMENT I BAM         Boric Acid Makeup HT         Heat Tracing CVC       Chemical and Volume Control BM         Boron Management DC         125 Vdc Electrical Distributi n ID         Inverters and Distribution LVD         Low Voltage Distribution SSD         480 V Station Service Distribution 4kV         4.16 kV Electrical Distribution ST         Startup Transformers EG         Emergency Generators ECA         Emergency Diesel Air ECC         Emergency Diesel Cooling EGF         Emergency Diesel Fuel EGL         Emergency Diesel Lube Oil CC         Component Cooling Water ACC         Auxiliary Component Cooling Water FP         Fire Protection FPD         Fire Detection RC         Reactor Coolant SI         Safety Injection CS         Containment Spray M
AITACHMENT I BAM Boric Acid Makeup HT Heat Tracing CVC Chemical and Volume Control BM Boron Management DC 125 Vdc Electrical Distributi n ID Inverters and Distribution LVD Low Voltage Distribution SSD 480 V Station Service Distribution 4kV 4.16 kV Electrical Distribution ST Startup Transformers EG Emergency Generators ECA Emergency Diesel Air ECC Emergency Diesel Cooling EGF Emergency Diesel Fuel EGL Emergency Diesel Lube Oil CC Component Cooling Water ACC Auxiliary Component Cooling Water FP Fire Protection FPD Fire Detection RC Reactor Coolant SI Safety Injection CS Containment Spray M
          -CHW         Chilled Water PAS         Post Accident Monitoring PRM         Process Radiation Monitoring ARM         Area Radiation Monitoring k:.                                   _
-CHW Chilled Water PAS Post Accident Monitoring PRM Process Radiation Monitoring ARM Area Radiation Monitoring k:.


CB         Containment Building CAR       Containment 'tmosphere Release CAP       Contairment Atmosphere Purge SP         Sump Pumps EM         Environmental Monitoring SM         Seismic Menitoring RER       Refrigeration PAC       Process Analog Control PPS       Plant Protection System ESF       Engineering Safety Features Actuation System HVC       Control Room HVAC HVR       Reactor Auxiliary Building I;VAC SS         Site Security ENI'       Excore Nuclear Instrumentation
CB Containment Building CAR Containment 'tmosphere Release CAP Contairment Atmosphere Purge SP Sump Pumps EM Environmental Monitoring SM Seismic Menitoring RER Refrigeration PAC Process Analog Control PPS Plant Protection System ESF Engineering Safety Features Actuation System HVC Control Room HVAC HVR Reactor Auxiliary Building I;VAC SS Site Security ENI' Excore Nuclear Instrumentation
              .IA         Instrument Air IC         Instrument Cabinets ANN       Annunciators FHS       Fuel Handlinb and Storage HRA       Hydrogen Recombiners and Analyzers
.IA Instrument Air IC Instrument Cabinets ANN Annunciators FHS Fuel Handlinb and Storage HRA Hydrogen Recombiners and Analyzers
              .PSL       Primary Sampling System CTB       Constant Temperature Bath DFO       Diesel Fuel Oil CRN       Cranes SG         Steam Generators MS         Main Steam BD         Blowdown DW         Demineralized Water PMU.       Primary Makeup (2)
.PSL Primary Sampling System CTB Constant Temperature Bath DFO Diesel Fuel Oil CRN Cranes SG Steam Generators MS Main Steam BD Blowdown DW Demineralized Water PMU.
Primary Makeup (2)


TW         Treated Water CW         Circulating Water TSW       Traveling Screens and Wash EFW       Emergency Feedwater CCS       Containment Cooling System ANP       Annulus Negative Pressure CVR       Containment Vacuum Relief SBV       Shield Building Ventilation RCC       Reactor Cavity Cooling LWM       Liquid Waste Management GWM       Gaseous Waste Management INI       In-core Nuclear Instrumentation MNI       Movable In-core Nuclear Instrumentation
TW Treated Water CW Circulating Water TSW Traveling Screens and Wash EFW Emergency Feedwater CCS Containment Cooling System ANP Annulus Negative Pressure CVR Containment Vacuum Relief SBV Shield Building Ventilation RCC Reactor Cavity Cooling LWM Liquid Waste Management GWM Gaseous Waste Management INI In-core Nuclear Instrumentation MNI Movable In-core Nuclear Instrumentation
                  .CDC       Control Element Drive Cooling PMC       Plant Monitoring Computer CEC       Control Element Assembly Calculator VLP       Vibration and Loose Parts Monitroing LRT       Leak Rate Testing CSD       Control Element Drive Mechanism SVS       Cable Vault and Switchgear Ventilation SSL       Seconoary Sampling System CMP       Communications Paging CMR       Communications Radio CMS       Communications Sound Powered telephones CMT       Communications Telephones CMU       Condensate Makeup Storage AB         Auxiliary Boiler (3) g -   -    -  -. . .                                _.
.CDC Control Element Drive Cooling PMC Plant Monitoring Computer CEC Control Element Assembly Calculator VLP Vibration and Loose Parts Monitroing LRT Leak Rate Testing CSD Control Element Drive Mechanism SVS Cable Vault and Switchgear Ventilation SSL Seconoary Sampling System CMP Communications Paging CMR Communications Radio CMS Communications Sound Powered telephones CMT Communications Telephones CMU Condensate Makeup Storage AB Auxiliary Boiler (3) g -


f*
f*
ABC           Auxiliary Boiler Condensate ABF           Auxiliary Boiler Fuel ABS           Auxiliary Boiler Steam AS             Auxiliary Steam               .
ABC Auxiliary Boiler Condensate ABF Auxiliary Boiler Fuel ABS Auxiliary Boiler Steam AS Auxiliary Steam AE Air Evacuation
AE             Air Evacuation
. GS Gland Steam TC Turbine Cooling CD Condensate FW Feedwater LOG Turbine Generator Lube Oil LOF Feed Pump Lube Oil 7kV 6.9 kV Electrical Distributica EH Electro-hydraulic Fluid 50 3eal Oil NG Nitrogen COL Core Operating Limits Supervisory System CPC Core Protection Calculator RMC Radiation Monitoring Computet
                        . GS             Gland Steam TC             Turbine Cooling CD             Condensate FW             Feedwater LOG           Turbine Generator Lube Oil LOF           Feed Pump Lube Oil 7kV           6.9 kV Electrical Distributica EH             Electro-hydraulic Fluid 50             3eal Oil NG             Nitrogen COL           Core Operating Limits Supervisory System CPC           Core Protection Calculator RMC           Radiation Monitoring Computet
' EBA.
                        ' EBA.           Emergency Breathing Air MT             Main Transformer 4
Emergency Breathing Air MT Main Transformer 4
(4)-
(4)-
                                  ._                                _.      .}}
.}}

Latest revision as of 08:17, 14 December 2024

Discusses Activities & Commitments to Be Completed Prior to Fuel Load.Listed Open Items Will Be Completed Prior to 840430
ML20081C187
Person / Time
Site: Waterford Entergy icon.png
Issue date: 03/08/1984
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
W3P84-0431, W3P84-431, NUDOCS 8403120168
Download: ML20081C187 (6)


Text

,

LOUISIANA / i 2 OuAnO~oe sincer P O 'N E R & L I G H T/ P O BOX 6008 e NEW ORLEANS. LOUISIANA 7017A. (504) 366 2345 NEdYS March 8, 1984 W3P84-0431 3-A1.01.04 Director of Nuclear Reactor Regulation Attention:

Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

Waterford SES Unit 3 Docket No. 50-382 Activities and Commitments to be Completed Prior to Fuel Load

Dear Sir:

The construction and preoperational testing phases of Louisiana Power & Light Company's Waterford Steam Electric Station Unit 3 are nearing completion and final preparations for initial core loading are in progress.

A thorough assessment of project completion plans has been made and the baseline plant configuration to safely support initial t'ucl loading has been established using the FSAR, NRC Safety Evaluation Report and Supplements, and the Final Environmental Statement as guidance. Attachment I identifies

(

the plant systems which LP6L intends to have constructed, tested, and trans-ferred from Construction /Startup to Plant Staff control prior to fuel load.

Systems which are required by Technical Specifications will be determined OPERABLE by satisfying the applicable Surveillance Requirements and will assure that fuel load and subsequent plant testing and operations will have no adverse impact on the health and well being of the general public and plant personnel.

Licensing-related activities and commitments, which presently are not completed but are considered to be necessary for fuel load, have been identified and are being tracked to completion utilizing LP&L's Licensing Commitment Tracking System. The items contained on these reports receive on-going management review, are updated frequently, and are giver. high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector for Waterford 3.

We will continue to provide updated reports on a reutine basis until Fuel Load. Additional items, not contained on the prior to fuel load reports, are considered requisite to criticality, low power physics testing, or power escalation sequence testing. As sach they are tracked and receive frequent management reviews to ensure that they are completed prior to their required need.

/

8403120168 840308 PDR ADOCK 05000382 A

PDR m

i

.m

't Mr. G. W. Knighten W3784-0431 Page Two it is LP&L's plan.to complete essentially all open items required prior to fuel load by not later than April 30, 1984. Thus it is expected that LP&L will be ready for receipt of the Operating License for Waterford 3 on that date.

If after your review of the attached information you have any questions or wish to discuss this matter further, please do not hesitate to contact me.

Very truly yours, K. W. Cook

~,

Nuclear 92pport & Licensing Manager KWC/WAC/pco

- cc.;

E. L. Blake, W. M. Stevenson, G.- L. Constable, J. II. Wilson k

AITACHMENT I BAM Boric Acid Makeup HT Heat Tracing CVC Chemical and Volume Control BM Boron Management DC 125 Vdc Electrical Distributi n ID Inverters and Distribution LVD Low Voltage Distribution SSD 480 V Station Service Distribution 4kV 4.16 kV Electrical Distribution ST Startup Transformers EG Emergency Generators ECA Emergency Diesel Air ECC Emergency Diesel Cooling EGF Emergency Diesel Fuel EGL Emergency Diesel Lube Oil CC Component Cooling Water ACC Auxiliary Component Cooling Water FP Fire Protection FPD Fire Detection RC Reactor Coolant SI Safety Injection CS Containment Spray M

-CHW Chilled Water PAS Post Accident Monitoring PRM Process Radiation Monitoring ARM Area Radiation Monitoring k:.

CB Containment Building CAR Containment 'tmosphere Release CAP Contairment Atmosphere Purge SP Sump Pumps EM Environmental Monitoring SM Seismic Menitoring RER Refrigeration PAC Process Analog Control PPS Plant Protection System ESF Engineering Safety Features Actuation System HVC Control Room HVAC HVR Reactor Auxiliary Building I;VAC SS Site Security ENI' Excore Nuclear Instrumentation

.IA Instrument Air IC Instrument Cabinets ANN Annunciators FHS Fuel Handlinb and Storage HRA Hydrogen Recombiners and Analyzers

.PSL Primary Sampling System CTB Constant Temperature Bath DFO Diesel Fuel Oil CRN Cranes SG Steam Generators MS Main Steam BD Blowdown DW Demineralized Water PMU.

Primary Makeup (2)

TW Treated Water CW Circulating Water TSW Traveling Screens and Wash EFW Emergency Feedwater CCS Containment Cooling System ANP Annulus Negative Pressure CVR Containment Vacuum Relief SBV Shield Building Ventilation RCC Reactor Cavity Cooling LWM Liquid Waste Management GWM Gaseous Waste Management INI In-core Nuclear Instrumentation MNI Movable In-core Nuclear Instrumentation

.CDC Control Element Drive Cooling PMC Plant Monitoring Computer CEC Control Element Assembly Calculator VLP Vibration and Loose Parts Monitroing LRT Leak Rate Testing CSD Control Element Drive Mechanism SVS Cable Vault and Switchgear Ventilation SSL Seconoary Sampling System CMP Communications Paging CMR Communications Radio CMS Communications Sound Powered telephones CMT Communications Telephones CMU Condensate Makeup Storage AB Auxiliary Boiler (3) g -

f*

ABC Auxiliary Boiler Condensate ABF Auxiliary Boiler Fuel ABS Auxiliary Boiler Steam AS Auxiliary Steam AE Air Evacuation

. GS Gland Steam TC Turbine Cooling CD Condensate FW Feedwater LOG Turbine Generator Lube Oil LOF Feed Pump Lube Oil 7kV 6.9 kV Electrical Distributica EH Electro-hydraulic Fluid 50 3eal Oil NG Nitrogen COL Core Operating Limits Supervisory System CPC Core Protection Calculator RMC Radiation Monitoring Computet

' EBA.

Emergency Breathing Air MT Main Transformer 4

(4)-

.