W3P84-0735, Replaces Ltr Previously Issued as W3P84-0431 Re Activities & Commitments to Be Completed Prior to Fuel Load Due to Missing Page from Attachment.All Open Items to Be Completed by 840430.Anticipates Receipt of OL on Same Date: Difference between revisions

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{{#Wiki_filter:w e I OUISIANA f 44a octAnoNoe Staca P OW E F1 & L!G H T/ P o. ecx 6000
{{#Wiki_filter:w e
I OUISIANA f 44a octAnoNoe Staca P OW E F1 & L!G H T/ P o. ecx 6000
* NEW onLEANS. LOUIS!ANA 70174 + (504) 366 2345 E.$IVsS$
* NEW onLEANS. LOUIS!ANA 70174 + (504) 366 2345 E.$IVsS$
March 20, 1984 W3P84-0735 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
March 20, 1984 W3P84-0735 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 24: Line 27:


==Dear Sir:==
==Dear Sir:==
This letter was issued previously as W3P84-0431 but was missing a page of the Attachment and we are now issuing the entire letter which should replace the previous one.
This letter was issued previously as W3P84-0431 but was missing a page of the Attachment and we are now issuing the entire letter which should replace the previous one.
The construction and preoperational testing phases of Louisiana Power & Lic;ht 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 & Lic;ht Company's Waterford Steam Electric Station Unit 3 are nearing completion and final preparations for initial core loading are in progress.
A thorough assess'nent of project completion plans has been made and the baseline plant configuration to safely support initial fuel 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 syster.4 which LP&L intends to have constructed, tested, and trans-ferred from Construction /Startup to Plant Staff control prior to fuel load.
A thorough assess'nent of project completion plans has been made and the baseline plant configuration to safely support initial fuel 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 syster.4 which LP&L 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 "ill 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 "ill 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 given high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector 8403270154 840320                                                                     O PDR ADOCK 05000382 A                   PDR                                                             QDDk l l
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 given high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector 8403270154 840320 OQDDk PDR ADOCK 05000382 A
PDR l
l


4' LPage'2:
4' LPage'2:
W3P84-0735-13-A1.01.04 Lfor'Waterford 3.       We will continue to provide updated reports on a routine
W3P84-0735-13-A1.01.04 Lfor'Waterford 3.
                  ' 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 such they are tracked and receive frequent management reviews to ensure that they are completed
We will continue to provide updated reports on a routine
                . prior to their required-need.
' 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 such they are tracked and receive frequent management reviews to ensure that they are completed
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 H             date.
. prior to their required-need.
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 H
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, i
Very truly yours, i
K..W.. Cook
K..W.. Cook
                  .: Nuclear Support & Licensing Manager KWC/WAC/ch
.: Nuclear Support & Licensing Manager KWC/WAC/ch
          ,        . Attachment cc:     E.L. Blake, W.M.'Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson
. Attachment cc:
                            ~G.L. Constable l
E.L. Blake, W.M.'Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson
~G.L. Constable l
I-l
I-l
  -1 b:
-1 b:
E                                                                             . _ . . _ _ _ . . . _ . . _ . _ . _ - , _ . _ _ _ _ . . _ _ _ _ _ . _ . _
E
 
o ATTACHMENT I BAM Boric Acid Makeup HT Heat Tracing CVC Chemical and Volume Control
.BM Boron Management DC 125 Vdc Electrical Distribution 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 EGA Emergency Diesel Air EGC 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 CHW Chilled Water PAS-Post Accident Monitoring PRM Process Radiation Monitoring ARM Area Radiation Monitoring


    . o ATTACHMENT I BAM          Boric Acid Makeup HT            Heat Tracing CVC          Chemical and Volume Control
CB Cantainment Building CAR Containment Atmosphere Release CAP Containment Atmosphere Purge SP Sump Pumps EM Environmental Monitoring SM Seismic Monitoring RFR Refrigeration PAC Process Analog Control PPS Plant Protection System ESF Engineering Safety Features Actuation System HVC Control, Room HVAC HVR Reactor Auxiliary Building HVAC SS Site Security ENI Excore Nuclear Instrumentation IA Instrument Air IC Instrument Cabinets ANN Annunciators
        .BM            Boron Management DC            125 Vdc Electrical Distribution 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 EGA          Emergency Diesel Air EGC          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 CHW          Chilled Water PAS-          Post Accident Monitoring PRM          Process Radiation Monitoring ARM          Area Radiation Monitoring
.FHS Fuel Handling 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) i t.
3


CB          Cantainment Building CAR        Containment Atmosphere Release CAP        Containment Atmosphere Purge SP          Sump Pumps EM        Environmental Monitoring SM        Seismic Monitoring RFR        Refrigeration PAC        Process Analog Control PPS        Plant Protection System ESF        Engineering Safety Features Actuation System HVC        Control, Room HVAC HVR        Reactor Auxiliary Building HVAC SS          Site Security ENI        Excore Nuclear Instrumentation IA          Instrument Air IC          Instrument Cabinets ANN        Annunciators
c.
          .FHS        Fuel Handling 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  -
TW Trected Wster i
Primary Makeup (2) i t .                                                                  3
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 Caseous Waste Management INI In-cute Nuclear Instrumentation MNI.
: c. -.
Movable In-core Nuclear Instrumentation CDC Control Element Drive Cooling
TW         Trected Wster i
.PMC Plant Monitoring Computer CEC Control Element Assembly Calculator VLP Vibration and Loose Parts Monitroing LRT Leak Race Testing CED Control Element Drive Mechanism SVS Cable Vault a'nd Switchgear Ventilation SSL Secondary Sampling System CMP Communications Paging CMR Communications Radio CMS Communications Sound Powered Telephones CMT Communications Telephones CMU Condensate Makeup Storage AB Auxiliary Boiler (3)
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         Caseous Waste Management INI         In-cute 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 Race Testing CED         Control Element Drive Mechanism SVS         Cable Vault a'nd Switchgear Ventilation SSL         Secondary Sampling System CMP         Communications Paging CMR         Communications Radio CMS         Communications Sound Powered Telephones CMT         Communications Telephones CMU         Condensate Makeup Storage AB         Auxiliary Boiler (3)


ABC       Auxilicry Boiler Cond2nsste ABF       Auxiliary Boiler Fuel ABS       Auxiliary Boiler Steam AS       . Auxiliary Steam
ABC Auxilicry Boiler Cond2nsste ABF Auxiliary Boiler Fuel ABS Auxiliary Boiler Steam AS
                    - AE         Air Evacuation GS         Gland Steam
. Auxiliary Steam
                      'TC         Turbine Cooling CD         Condensate FW         Feedwater LOG         Turbine Generator Lube Oil LOF-       Feed Pump Lube Oil
- AE Air Evacuation GS Gland Steam
                      .7kV         6.9 kV Electrical Distribution EH.         Electro-hydraulic Fluid SO         Seal Oil NC         Nitrogen COL       Core Operating Limits Supervisory System CPC       Core Protection Calculator i
'TC Turbine Cooling CD Condensate FW Feedwater LOG Turbine Generator Lube Oil LOF-Feed Pump Lube Oil
RMC       Radia' tion Monitoring Computer EBA       Emergency Breathing Air MT         Main Transformer i
.7kV 6.9 kV Electrical Distribution EH.
Electro-hydraulic Fluid SO Seal Oil NC Nitrogen COL Core Operating Limits Supervisory System CPC Core Protection Calculator i
RMC Radia' tion Monitoring Computer EBA Emergency Breathing Air MT Main Transformer i
i _.
i _.
(4) r
(4) r
                                                                              ..}}
..}}

Latest revision as of 14:06, 13 December 2024

Replaces Ltr Previously Issued as W3P84-0431 Re Activities & Commitments to Be Completed Prior to Fuel Load Due to Missing Page from Attachment.All Open Items to Be Completed by 840430.Anticipates Receipt of OL on Same Date
ML20087L345
Person / Time
Site: Waterford Entergy icon.png
Issue date: 03/20/1984
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
W3P84-0735, W3P84-735, NUDOCS 8403270154
Download: ML20087L345 (6)


Text

w e

I OUISIANA f 44a octAnoNoe Staca P OW E F1 & L!G H T/ P o. ecx 6000

  • NEW onLEANS. LOUIS!ANA 70174 + (504) 366 2345 E.$IVsS$

March 20, 1984 W3P84-0735 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:

This letter was issued previously as W3P84-0431 but was missing a page of the Attachment and we are now issuing the entire letter which should replace the previous one.

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

A thorough assess'nent of project completion plans has been made and the baseline plant configuration to safely support initial fuel 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 syster.4 which LP&L 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 "ill 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 given high visibility throughout the Nuclear Operations organization. These reports have been provided to both the NRC Project Manager and Sr. Resident Inspector 8403270154 840320 OQDDk PDR ADOCK 05000382 A

PDR l

l

4' LPage'2:

W3P84-0735-13-A1.01.04 Lfor'Waterford 3.

We will continue to provide updated reports on a routine

' 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 such they are tracked and receive frequent management reviews to ensure that they are completed

. prior to their required-need.

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 H

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, i

K..W.. Cook

.: Nuclear Support & Licensing Manager KWC/WAC/ch

. Attachment cc:

E.L. Blake, W.M.'Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson

~G.L. Constable l

I-l

-1 b:

E

o ATTACHMENT I BAM Boric Acid Makeup HT Heat Tracing CVC Chemical and Volume Control

.BM Boron Management DC 125 Vdc Electrical Distribution 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 EGA Emergency Diesel Air EGC 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 CHW Chilled Water PAS-Post Accident Monitoring PRM Process Radiation Monitoring ARM Area Radiation Monitoring

CB Cantainment Building CAR Containment Atmosphere Release CAP Containment Atmosphere Purge SP Sump Pumps EM Environmental Monitoring SM Seismic Monitoring RFR Refrigeration PAC Process Analog Control PPS Plant Protection System ESF Engineering Safety Features Actuation System HVC Control, Room HVAC HVR Reactor Auxiliary Building HVAC SS Site Security ENI Excore Nuclear Instrumentation IA Instrument Air IC Instrument Cabinets ANN Annunciators

.FHS Fuel Handling 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) i t.

3

c.

TW Trected Wster i

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 Caseous Waste Management INI In-cute 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 Race Testing CED Control Element Drive Mechanism SVS Cable Vault a'nd Switchgear Ventilation SSL Secondary Sampling System CMP Communications Paging CMR Communications Radio CMS Communications Sound Powered Telephones CMT Communications Telephones CMU Condensate Makeup Storage AB Auxiliary Boiler (3)

ABC Auxilicry Boiler Cond2nsste 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 Distribution EH.

Electro-hydraulic Fluid SO Seal Oil NC Nitrogen COL Core Operating Limits Supervisory System CPC Core Protection Calculator i

RMC Radia' tion Monitoring Computer EBA Emergency Breathing Air MT Main Transformer i

i _.

(4) r

..