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| 9000 Florida W. P. STEWAR1, DIR ECTOR g{ POWER PRODUCTION c o m p arinu January 26, 1979 Mr. Robert W. Reid Chief, Operations Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555 | | 9000 Florida W. P. STEWAR1, DIR ECTOR g{ POWER PRODUCTION c o m p arinu January 26, 1979 Mr. Robert W. Reid Chief, Operations Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555 |
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| File: 3-0-3-a-3 7 9 0 2 0 2 0 J? 70 4 General Office 3201 Tnirty-fourtn street soutn . P O Box 14042, St. Petersburg, Fionda 33733 e 813-866-5151 | | File: 3-0-3-a-3 7 9 0 2 0 2 0 J? 70 4 General Office 3201 Tnirty-fourtn street soutn . P O Box 14042, St. Petersburg, Fionda 33733 e 813-866-5151 |
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| P | | P STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and corre ct to the best of his knowledge, information and belief. |
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| STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and corre ct to the best of his knowledge, information and belief. | |
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| LOM 3 LLOov W.P. Stewa rt Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January, 1979. | | LOM 3 LLOov W.P. Stewa rt Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January, 1979. |
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| File: 3-0-3-a-3 General Office 3201 Thirty-foum. street soutn . P O. Box 14042, st. Petersburg, Flanda 33733 813 - 866-5151 | | File: 3-0-3-a-3 General Office 3201 Thirty-foum. street soutn . P O. Box 14042, st. Petersburg, Flanda 33733 813 - 866-5151 |
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| | STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief. |
| e STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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| W.P. Stewart Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January,1979. | | W.P. Stewart Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January,1979. |
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| Notary g5sblic Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980 | | Notary g5sblic Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980 |
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| e | | e Question 23 - Prevention of Fire and Smoke Spread Describe the manner in which fire and smoke are prevented from spreading from area to area via the normal and emergency ventilation systems in all parts of the plant areas. Describe the location, actuation method and fire rating of dampers used for fire and smoke control in both air supply and return air systems. Describe the details of interlocks for ventilation system shutdown or mode change that can be utilized for ire and smoke control. |
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| Question 23 - Prevention of Fire and Smoke Spread Describe the manner in which fire and smoke are prevented from spreading from area to area via the normal and emergency ventilation systems in all parts of the plant areas. Describe the location, actuation method and fire rating of dampers used for fire and smoke control in both air supply and return air systems. Describe the details of interlocks for ventilation system shutdown or mode change that can be utilized for ire and smoke control. | |
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| See attached report. | | See attached report. |
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| 4 | | 4 Question 68 Provide information on the plant breathing air supply, per the requirements of Apper. dix A to BTP 9.5-1. |
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| Question 68 Provide information on the plant breathing air supply, per the requirements of Apper. dix A to BTP 9.5-1. | |
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| ===RESPONSE=== | | ===RESPONSE=== |
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| t | | 5.3.5.2 Auxiliary Building Ventilation The Auxiliary Building contains equipment and components which could be sources of airborne radioactivity as well as other equipment and components which would not. Its ventilation system is of the once-through type in which outside air is taken into the building and distributed to the various areas, then collected, filtered and dishearged to the outside. The flow diagram is shown in Figures 5-14 and 5-15. |
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| 4 5.3.5.2 Auxiliary Building Ventilation The Auxiliary Building contains equipment and components which could be sources of airborne radioactivity as well as other equipment and components
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| which would not. Its ventilation system is of the once-through type in which outside air is taken into the building and distributed to the various areas, then collected, filtered and dishearged to the outside. The flow diagram is shown in Figures 5-14 and 5-15. | |
| The Auxiliary Building ventilation supply consists of a supply system for each of the spent fuel pit and the fuel handling areas, along with a supply subsystem which supplies outside air to the other areas. The Auxiliary Building supply system consists of a particulate filter, two 50%-capacity fans, and ductwork. Outside air is drawn into the system and distributed to the various areas of the building. The fuel handling area supply subsystem consists of a particulate filter and a fan which brings in outside air. The spent fuel pit supply consists of two fans each of 100% | | The Auxiliary Building ventilation supply consists of a supply system for each of the spent fuel pit and the fuel handling areas, along with a supply subsystem which supplies outside air to the other areas. The Auxiliary Building supply system consists of a particulate filter, two 50%-capacity fans, and ductwork. Outside air is drawn into the system and distributed to the various areas of the building. The fuel handling area supply subsystem consists of a particulate filter and a fan which brings in outside air. The spent fuel pit supply consists of two fans each of 100% |
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| Supply air is heated or cooled as necessary, then distributed to the various areas of the complex. Air from those areas with recirculation capability is returned by Control Complex return fans. Powe r-ope rated dampers are provided to allow recirculation from the return fans to the WPS/hewWO4 (D7) | | Supply air is heated or cooled as necessary, then distributed to the various areas of the complex. Air from those areas with recirculation capability is returned by Control Complex return fans. Powe r-ope rated dampers are provided to allow recirculation from the return fans to the WPS/hewWO4 (D7) |
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| supply system or to exhaust all taturn air and to supply only outside air to the Control Complex. The outside air intake and discharge points are on the Control Complex roof, separated by a distance of more than forty feet. | | supply system or to exhaust all taturn air and to supply only outside air to the Control Complex. The outside air intake and discharge points are on the Control Complex roof, separated by a distance of more than forty feet. |
| The upper floor of the Control Complex has a relief fan system which exhausts ventilation air from this area to the atmosphere at a point on the roof well separated from the intake. | | The upper floor of the Control Complex has a relief fan system which exhausts ventilation air from this area to the atmosphere at a point on the roof well separated from the intake. |
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| Another P0C detector in the air inlet duct to the Control Complex closes a fire damper in the duct and initiates a control room alarm in the event that products of combustion are detected in the incoming air. | | Another P0C detector in the air inlet duct to the Control Complex closes a fire damper in the duct and initiates a control room alarm in the event that products of combustion are detected in the incoming air. |
| A products-of-combustion detector in the controlled access exhaust hood supply fan intake closes a damper in that duct on detection of fire, and initiates a control room alarm. | | A products-of-combustion detector in the controlled access exhaust hood supply fan intake closes a damper in that duct on detection of fire, and initiates a control room alarm. |
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| 4 5.3.5.4 Intermediate Building Ventilation System The Intermediate Building, which houses the emergency feedwater pumps, main steam isolation valves, and Reactor Building purge supply equipment, has a once-through ventilation system. Air is supplied by two 100%-capacity supply fans, first passing through a particulate filter. It passes first through the emergency feedwater pump room, then through the remainder of the Intermediate Building, and is exhausted by two 100%-capacity fans. | | 4 5.3.5.4 Intermediate Building Ventilation System The Intermediate Building, which houses the emergency feedwater pumps, main steam isolation valves, and Reactor Building purge supply equipment, has a once-through ventilation system. Air is supplied by two 100%-capacity supply fans, first passing through a particulate filter. It passes first through the emergency feedwater pump room, then through the remainder of the Intermediate Building, and is exhausted by two 100%-capacity fans. |
| There are fire dampers in the air intake and between the pump room and the remainder of the Intermediate Building. The fir damper in the air intake is closed automatically either by its fusible link or upon detection of high temperature by a temperature detector in the air intake. The dampers where the air leaves the pump room are closed by the dampers' fusible link or upon detection of high temperature in the pump room. A products-of-combustion detector is also provided in the pump room. The temperature and POC detectors also initiate control room alarms. | | There are fire dampers in the air intake and between the pump room and the remainder of the Intermediate Building. The fir damper in the air intake is closed automatically either by its fusible link or upon detection of high temperature by a temperature detector in the air intake. The dampers where the air leaves the pump room are closed by the dampers' fusible link or upon detection of high temperature in the pump room. A products-of-combustion detector is also provided in the pump room. The temperature and POC detectors also initiate control room alarms. |
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| Question 71 How of ten and by what means are "POC" interlocks tested for the reactor building purge supply and exhaust fans (Page 5-31)? | | Question 71 How of ten and by what means are "POC" interlocks tested for the reactor building purge supply and exhaust fans (Page 5-31)? |
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| Diesel Generator Control Room Smoke Detector Staff Concern The lower smoke detector located in the diesel generator | | Diesel Generator Control Room Smoke Detector Staff Concern The lower smoke detector located in the diesel generator |
| , control room is not effective in its present location. | | , control room is not effective in its present location. |
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| 4 SRP Station Ventilation Staff Concern Failure of exhaust ventilation in battery rooms could lead to build-up of explosive hydrogen concentrations. | | 4 SRP Station Ventilation Staff Concern Failure of exhaust ventilation in battery rooms could lead to build-up of explosive hydrogen concentrations. |
| Staff Position Relocate exhaust ducting to ceiling of battery room. Provide air flow monitoring on battery room exhaust by surveillance or alarm system. | | Staff Position Relocate exhaust ducting to ceiling of battery room. Provide air flow monitoring on battery room exhaust by surveillance or alarm system. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999
Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review
ML20217J5171999-10-13013 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed
3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
ML20212L0771999-10-0404 October 1999
Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii)
ML20217D6551999-10-0101 October 1999
Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025
ML20212J8481999-10-0101 October 1999
Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
ML20212F7251999-09-23023 September 1999
Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable
ML20212F7331999-09-23023 September 1999
Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
ML20212E6741999-09-21021 September 1999
Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
ML20212F3141999-09-13013 September 1999
Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations
ML20211L9081999-09-0303 September 1999
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3
ML20211Q7581999-09-0101 September 1999
Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20211G7111999-08-30030 August 1999
Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed
ML20211G7031999-08-30030 August 1999
Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
ML20210Q4511999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006
ML20210P0741999-08-0505 August 1999
Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
ML20210G8551999-07-27027 July 1999
Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209H5211999-07-16016 July 1999
Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review
ML20209G3231999-07-15015 July 1999
Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
ML20196L1261999-07-0707 July 1999
Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20196J4991999-07-0101 July 1999
Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
1999-09-03
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEAR3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999
Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed
3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999
Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made
3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999
Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment
3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999
Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331
3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999
Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46
3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999
Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)
3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999
Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief
3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999
Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals
ML20212C1351999-08-27027 August 1999
Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input
3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999
Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002
3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999
Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71
3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999
Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3
3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999
Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal
3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999
Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05
3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999
Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2
05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999
Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented
3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value
3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999
Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603
3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999
Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments
ML20209G3481999-07-15015 July 1999
Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon
3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999
Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl
3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999
Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl
3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999
Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl
3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999
Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730
3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999
Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held
3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999
Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21
3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999
Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3
ML20209C0811999-06-25025 June 1999
Forwards Overdue Controlled Document Transmittals for Listed Documents
3F0699-12, Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested1999-06-23023 June 1999
Provides Suppl Info for LAR 240,rev 0 & Pump Curve for EFP-3 to Facilitate Review,As Requested
3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999
Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl
3F0699-08, Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments1999-06-21021 June 1999
Provides Updated Info to Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Ltr Establishes No New Regulatory Commitments
3F0699-09, Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl1999-06-0404 June 1999
Forwards FPC 1998 Annual Financial Repts for Two Participating co-owners of Crystal River Unit 3.Financial Statements & Independent Auditors Repts for City of Alachua,Fl,Encl
3F0599-21, Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads1999-05-28028 May 1999
Submits Addendum to B&W Owners Group Topical Rept BAW-2346P, Rev 0.Addendum Includes Leak Rate Values Based on CR-3 Plant Specific Main Steam Line Break Tube Loads
3F0599-10, Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl1999-05-26026 May 1999
Submits Changes Made to Crystal River,Unit 3 Its,As Required by ITS 5.6.2.17.Encl Provides Revs to Plant ITS Bases That Will Update NRC Copies of Its.Instructions for Updating ITS, Encl
ML20207E4341999-05-25025 May 1999
Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft
3F0599-22, Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs1999-05-21021 May 1999
Forwards non-proprietary Version of B&Wog Topical Rept BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs
3F0599-18, Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM1999-05-14014 May 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3. Rept Is Submitted in Accordance with CR-3 ITS 5.7.1.1(b) & Section 6.6 of ODCM
3F0599-17, Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments1999-05-14014 May 1999
Submits Update Response to GL 97-06, Degradation of SG Internals. Ltr Establishes No New Regulatory Commitments
3F0599-07, Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 19781999-05-14014 May 1999
Submits Guarantee of Payment of Deferred Premiums for CR-3 in Accordance with 10CFR140.21.Internal Cash Flow Projection Was Prepared in Accordance with Suggested Format Outlined in Reg Guide 9.4 Dtd Sept 1978
3F0599-03, Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR1999-05-12012 May 1999
Provides Update Curves for Facility Pressure/Temp Limits Rept,Rev 2 & Updated Rev Bar ITS Pages Associated with LAR, in Response to NRC RAI Re Subject LAR
3F0599-05, Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl1999-05-12012 May 1999
Responds to 990402 RAI Re Third 10-year Interval ISI Program Plan Requests for Relief.Util Revised Relief Requests 98-010-II,98-003-PT,98-005-PT & 98-001-SS Based on Responses to Rai.Revised Relief Requests Encl
3F0599-08, Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments1999-05-0303 May 1999
Forwards Licensee Clarification of Info Provided in Amend 171 Re post-LOCA Boron Dilution Precipitation Prevention.Ltr Establishes No New Regulatory Commitments
3F0599-09, Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 19981999-05-0101 May 1999
Forwards Crystal River Unit 3 Radioactive Effluent Release Rept - 1998 & Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997. Licensee Informs That ODCM & PCP Were Not Revised During 1998
3F0499-24, Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent1999-04-30030 April 1999
Forwards Summary of Proposed Changes to Crystal River,Unit 3 NPDES Permit,That Are Being Submitted to Florida Dept of Environ Protection.Proposed Change Will Allow Use of Scale Inhibitor,Biocides & Foam Control Agent
3F0499-09, Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 9907301999-04-30030 April 1999
Forwards FPC Annual Financial Rept & Annual Financial Repts for Eight of Ten Participating co-owners of Crystal River Unit 3 Nuclear Station.Outstanding Annual Financial Rept Will Be Submitted by 990730
3F0499-23, Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements1999-04-23023 April 1999
Submits Repts Required by App B,Environ Protection Plan,Of Crystal River,Unit 3 Operating License.Fl Dept of Environ Protection Has Provided Clarification Re Ph Monitoring Requirements
3F0499-18, Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl1999-04-20020 April 1999
Informs of Recent Senior Management Change at Fpc,Which Will Not Affect Std Recipients of Incoming NRC Correspondence. Updated Util Mailing List,Encl
3F0499-05, Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin1999-04-16016 April 1999
Forwards Rev 19 to Radiological Emergency Response Plan. Changes to Plan Marked with Vertical Bars in Left Margin
3F0499-08, Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 19981999-04-16016 April 1999
Forwards FPC Annual ITS Dose Rept for Period Jan-Dec 1998. Rept Provides person-rem Radiation Exposures,According to Work & Job Function,At CR-3 for Period Jan-Dec 1998
1999-09-27
[Table view]
Category:UTILITY TO NRC
MONTHYEAR3F0990-11, Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-141990-09-20020 September 1990
Forwards Final Status Update Re Design & Operations Verification for Instrument Air Sys Per Generic Ltr 88-14
3F0990-05, Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams1990-09-14014 September 1990
Forwards 1990 Inservice Insp Summary Rept. Rept Contains Owners Data Rept,Data Summary Sections for Class 1,2 & 3 Components,Rept for Repair & Replacements & Listing of Exams
3F0990-08, Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure1990-09-13013 September 1990
Forwards Response to Violations Noted in Insp Rept 50-302/90-23.Corrective Actions:Training Session Conducted to Stress Importance of Attachments Being Part of Work Package When Required by Procedure
3F0890-23, Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls1990-08-30030 August 1990
Discusses Decommissioning Financial Assurance Rept Dtd 900726.Amount Util Collecting Exceeds Amount Necessary Based on NRC Formula & Does Not Include Estimated Cost of Removal & Disposal of Nonradioactive Structures & Matls
ML20028G8251990-08-29029 August 1990
Advises That Supplemental Response to Insp Rept 50-302/89-18 Will Be Submitted by 901030
ML20059G1721990-08-24024 August 1990
Submits Info Re Change in Operator License Status.Re Rawls & Wa Stephenson Senior Reactor Licenses Should Be Terminated, Effective 900817 Due to Reassignment from Position Requiring Licenses
3F0890-15, Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 19901990-08-23023 August 1990
Forwards Fitness for Duty Program Performance Data for Period of Jan-Jun 1990
3F0890-21, Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm1990-08-23023 August 1990
Forwards Semiannual Radioactive Release Rept Jan-June 1990 for Crystal River Unit 3 & Rev 15 to Crystal River Unit 3 Odcm
ML20059A0031990-08-16016 August 1990
Responds to NRC 900613 Request for Addl Info Re Util 871222 Response to Violations Noted in Insp Rept 50-302/87-30
3F0890-03, Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 31990-08-16016 August 1990
Forwards Rev 11 to Inservice Insp - Pump & Valve Program, Crystal River Unit 3
3F0890-10, Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events1990-08-16016 August 1990
Advises That Util Completed Mods to Comply w/10CFR50.62 Requirements Re Reduction of Risk from ATWS Events
3F0890-05, Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 1741990-08-10010 August 1990
Forwards Addl Info Re Response to Mode 3 Loca,Per 900711 Request,Providing Background of Factors Considered During Evaluation of Tech Spec Change Request 174
ML20058L2001990-08-0202 August 1990
Provides Current Status of Reg Guide 1.97 Activities. Pressurizer Heater Status & Main Steam Safety/Relief Valve Position Indications Completed
3F0790-10, Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals1990-07-18018 July 1990
Forwards Justification for Continued Operation Re Emergency Diesel Generator Block Loading Voltage Dips.Util Will Install Higher Accuracy Relays to Improve on Accuracy & Repeatability of Load Intervals
3F0790-06, Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-81990-07-12012 July 1990
Forwards Rev 1 to Cycle 8 Core Operating Limits Rept, Correcting Typo in Note 1 of Figures 1-8 & Note 2 of Figures 1,2 & 4-8
ML20055D5561990-06-29029 June 1990
Forwards 890505 & s to Be Placed in Plant File
3F0690-15, Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-171990-06-29029 June 1990
Informs That Tech Spec Actions Identified in Util Addressed as Part of Tech Spec Improvement Program,Per 900518 Request for Programmed Enhancements for Generic Ltr 88-17
3F0690-22, Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)1990-06-27027 June 1990
Forwards Annual Financial Repts for 1989 for Orlando Utils Commission & Cities of Bushnell,Leesburg,Ocala & Tallahassee,Per 10CFR50.71(b)
3F0690-19, Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array1990-06-25025 June 1990
Responds to Deviations Noted in Insp Rept 50-302/90-15. Corrective Actions:All Reg Guide 1.97 Category 1 Instruments on Main Control Board Marked & Engineered Safeguards Matrix Indicating Lights Arranged in Unique Array
ML20043H5781990-06-21021 June 1990
Responds to Generic Ltr 89-06, Spds. All Open Issues Identified in NRC SER & Plant SPDS Satisfies NUREG-0737, Item I.D.2 & Suppl 1
ML20044A6121990-06-21021 June 1990
Forwards Payment of Civil Penalty,Per NRC 900524 Order Based on Findings in Insp Rept 50-302/89-09
ML20043J0221990-06-21021 June 1990
Submits Info in Support of Tech Spec Change Request 175,Rev 1,Suppl 1 Re Spent Fuel Pool Storage Capacity at Plant
ML20043H4151990-06-21021 June 1990
Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions.
3F0690-18, Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error1990-06-20020 June 1990
Responds to Violations Noted in Insp Rept 50-302/90-09. Corrective Action:Temporary Lettering Placed on Index Plates for Consistency W/Previous Markings Immediately Following Discovery of Error
ML20043H2901990-06-15015 June 1990
Forwards Results of Refuel 7 once-through Steam Generator (OTSG) Eddy Current Insp,Per Tech Spec Section 4.4.5.5.Eight Defective Tubes & Two Administratively Plugged Tubes in OTSG a Resulted from Review of Insp Data
ML20044A0641990-06-13013 June 1990
Forwards Rev 5 to Physical Security Plan,Replacing Currently Approved Rev 4 W/Amends.Rev Withheld (Ref 10CFR73.21)
ML20043G2271990-06-12012 June 1990
Suppls 900604 Ltr Describing How Control Room Habitability Dose Would Be Adversely Affected by Elimination of Reactor Bldg Flood Vol Unless Overly Conservative Failure Postulations Also Changed.Quarterly Updates to Be Provided
ML20043G3711990-06-12012 June 1990
Forwards 1990 Internal Cash Flow Projection for Plant Which Updates Utils Utilization of Alternative (E)
ML20043G2361990-06-12012 June 1990
Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated
ML20043F1601990-06-0404 June 1990
Provides Supplemental Info on Reactor Bldg Flooding,Per Util 900517 Ltr Describing Resolution Plan Being Pursued.Util Has Limited Vol of Water Contributed by Borated Water Storage Tank & Sodium Hydroxide Tank to Flood Level
ML20043C8721990-05-31031 May 1990
Forwards Rev 0 to Crystal River Unit 3 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.1.7
ML20043B8431990-05-24024 May 1990
Describes Alternative Testing of Reactor Bldg Spray Suction Valves BSV-1 & BSV-8,per Generic Ltr 89-04.At Least One Valve Will Be Disassembled & Inspected During Each Refueling Outage Using Alternate Insp Method
ML20043B2771990-05-18018 May 1990
Advises of Mod to Original Commitment & Plans to Store Seal Ring in Original Storage Location During Plant Operations, Per 790606 Ltr.Mod Minimizes Personnel Exposure & Enhances Seal Plate Leak Tightness Due to Less Handling
ML20043B0321990-05-17017 May 1990
Provides Details of Resolution Util Will Pursue Re Reactor Bldg Flooding Detailed in Encl LER 90-005.Mod Will Be Installed to Add Alarm in Main Control Room to Indicate When Flood Level Reaches Point & Operator Action Begins
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20042G7681990-05-10010 May 1990
Submits Unsatisfactory Performance Testing Incident Repts, Per 10CFR26, Fitness for Duty. Results of Three Positive Blind Test Samples Certified to Contain No Drugs
ML20043A4931990-05-10010 May 1990
Forwards Executed Amend 8 to Indemnity Agreement B-54
ML20042G2101990-05-0707 May 1990
Provides Notice of MW Kirk Permanent Reassignment from Position & Requests Termination of Senior Reactor Operator License 20481-1,effective 900505
ML20042E8611990-04-26026 April 1990
Forwards Annual Financial Repts for Six Participating Owners of Plant
ML20012F2941990-03-30030 March 1990
Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11
ML20042D8321990-03-30030 March 1990
Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained
ML20012E2041990-03-23023 March 1990
Requests Temporary Waiver of Compliance Granted on Tech Spec 3.9.8.2 Re DHR Power Source Requirements
ML20012D9471990-03-21021 March 1990
Requests Approval of Capsule Withdrawal Schedule in Table 3-19 of BAW-1543,Rev 3, Master Integrated Reactor Vessel Surveillance Program to Allow Plant Refuel 7 Outage Plans to Continue on Schedule.Changes Needing NRC Approval Listed
ML20012D7371990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Resolution of USI A-47. Util Will Implement Appropriate Sys to Protect Against Overfill Concerns
ML20012C4501990-03-13013 March 1990
Forwards Listing of Insurance Policies in Place for Plant as of 900225
ML20012B4821990-03-0707 March 1990
Forwards Inservice Insp Pump & Valve Program Relief Request V-371 Proposing Alternate Acceptance Criteria Requirements for IWP-4150 for Fluctuations in Hydraulic Instrument Readings
ML20012B3651990-03-0101 March 1990
Lists Five Addl Drugs Included in 10CFR26 Re fitness-for- Duty Testing Program.Specimens Identified as Positive on Initial Screening Will Be Confirmed Using Gas Chromatography or Mass Spectrometry at Listed cut-off Levels
ML20012A4041990-02-27027 February 1990
Forwards 1989 Annual Rept of Personnel Exposure in Accordance w/10CFR20.407 & Tech Spec 6.9.1.5.(a) & Annual Rept of Facility Changes,Tests & Experiments in Accordance w/10CFR50.59
ML20006G1731990-02-23023 February 1990
Advises That Util Voluntarily Agrees to Participate in Emergency Response Data Sys Proposed in Generic Ltr 89-15
ML20011F2411990-02-21021 February 1990
Provides Followup on & Documents Discussion in 900116 Meeting Re Emergency Diesel Generator Loading
1990-09-20
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9000 Florida W. P. STEWAR1, DIR ECTOR g{ POWER PRODUCTION c o m p arinu January 26, 1979 Mr. Robert W. Reid Chief, Operations Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
On January 9,1979, Florida Power Corporation submitted responses and a schedule for responses to the NRC's letters of November 14, 1978, November 21, 1978 and December 20, 1978. As indicated in the letter, responses to nine (9) questions and concerns were scheduled for January 19, 1979.
Enclosed you will find responses to the following:
Enclosure 2 - Questions 23, 30, 56, 68, 71, 73 Enclosure 3 - SRP 25 Enclosure 4 - SRP's 9, 20 Should you or members of your staff wish to discuss our responses to these NRC concerns, please contact this office.
Very truly yours, FLORI A POWER CORPORAT ON
- ( QLD M W. P. Stewart Enclosure WPS/hewWO4 (D7)
File: 3-0-3-a-3 7 9 0 2 0 2 0 J? 70 4 General Office 3201 Tnirty-fourtn street soutn . P O Box 14042, St. Petersburg, Fionda 33733 e 813-866-5151
P STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and corre ct to the best of his knowledge, information and belief.
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LOM 3 LLOov W.P. Stewa rt Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January, 1979.
CM4 ' Notary Pulflic Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980
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3 4sh})33 W. P. STEWAR T. DIR ECTOR gf POWER PRODUCTION consonario, January 26, 1979 Mr. Robert W. Reid Chief, Operations Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
On January 9,1979, Florida Power Corporation submitted responses and a schedule for responses to the NRC's letters of November 14, 1978, November 21, 1978 and December 20, 1978. As indicated in tha letter, responses to nine (9) questions and concerns were scheduled for January 19, 1979.
Enclosed you will find responses to the following:
Enclosure 2 - Questions 23, 30, 56, 68, 71, 73 Enclosure 3 - SRP 25 Enclosure 4 - SRP's 9, 20 Should you or members of your staff wish to discuss our responses to these NRC concerns, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION H
k.'. i hD0 W. P. Stewart Enclosure WPS/hewWO4 (D7)
File: 3-0-3-a-3 General Office 3201 Thirty-foum. street soutn . P O. Box 14042, st. Petersburg, Flanda 33733 813 - 866-5151
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STATE OF FLORIDA COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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W.P. Stewart Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 26th day of January,1979.
Notary g5sblic Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980
e Question 23 - Prevention of Fire and Smoke Spread Describe the manner in which fire and smoke are prevented from spreading from area to area via the normal and emergency ventilation systems in all parts of the plant areas. Describe the location, actuation method and fire rating of dampers used for fire and smoke control in both air supply and return air systems. Describe the details of interlocks for ventilation system shutdown or mode change that can be utilized for ire and smoke control.
RESPONSE
The ventilation systems are described in the Florida Power Corporation submittal entitled Fire Protection Program Review, June 1977, pages 5-29 through 5-36. As discussed therein, the ventilation systems for the auxiliary building and the intermediate building operate only in a once through mode. Smoke removed from any area in those buildings by the ventilation system will be exhausted to the outside, not spread within the building. Air from the turbine building, which is also ventilated in the once through mode , is exhausted to the outside via ventilators, louvers, and windows. The control complex ventilation system switches to a once through mode upon detection of smoke in the ducts, or under manual control. Rated fire dampers in ventilation ducts penetrating fire walls in the control complex also assist in preventing the spread of smoke and fire within the control complex.
Question 30 - Fire Suppression System Design Provide the design data for all automatic suppression systems (both existing and proposed) including such items as design densities, soak times, power supplies and associated alarms. Identify areas of noncompliance with appropriate NFPA standards.
RESPONSE
The requested information is given for existing systems in section 5.3.3 of the Florida Power Corporation submittal entitled Fire Protection Program Review, June 1977, with the following additional information: design densities are 0.25 gpm/sqf t for the deluge system for the transformers, turbine lube oil piping and reservoirs, hydrogen seal unit, and main feedwater pumps. Soak time for maintenance of a 5% halon concentration in the cable spreading room for a 20 minute time period was demonstrated by preoperational test. As of this date Florida Power Corporation has not committed to install any additional automatic suppression systems at CR 3.
Should any automatic fire suppression system be required to resolve the outstanding concerns expressed by your staf f, FPC will supply the information required by Question 30 at that time.
Question 56 When will the results of the planned cable fire tests be provided (Page 5-9)?
RESPONSE
See attached report.
4 Question 68 Provide information on the plant breathing air supply, per the requirements of Apper. dix A to BTP 9.5-1.
RESPONSE
5.3.5 Ventilation There are separate ventilation systems for the Reactor Building, the Auxiliary Building, the Control Comples, the Intermediate Building, the Turbine Building, the Diesel Generator Building, and the Fire Service Pump House. These systems are discussed individually in the follcwing sections.
5.3.5.1 Reactor Building Ventilation System The flow diagram of Reactor Building ventilation systems is ahown in Figure 5-14. The ventilation systems (1) cool and recirculate air in the Reactor Building, and (2) provide capability of purging the building by exhausting air from it to the outside through the plant vent and supplying outside air into the building. The Reactor Building air is cooled and recirculated by three fan-cooler units (two normally operating) which draw air from various locations in the building, discharging it into the large open space above the operating floor. Emergency cooling of the Reactor Building is performed using the same equipment. Under post-accident emergency conditions, the units will operate at reduced speed. The fan motors are two-speed , pipe-ve. tilated units with air-to-water heat exchangers. They are capable of operation under accident conditions of 281*F and 68.3 psia.
Local area ventilation is provided for the operating floor by booster fans which supply air through supply ducts. Two booster fans (one normally operating) also supply air to the steam generator compartments. Cool air to the reactor cavity is supplied by one of two 100%-capacity fan-cooler units. There are twelve exhaust fans to exhaust air from the control-rod-drive shroud area.
The purge system provides mear.s for the reduction of concentrations of airborne radioactivity in the Reactor Building. It is operated only as required. The system is designed to remove up to 50,000 cfm air from the Reactor Building and supply an equal amount of outside air. Roughing, absolute, and charcoal filters are provided in the purge exhaust to remove radioactive particulates and iodine from the air prior to discharge.
The Reactor Building purge exhaust duct contains detectors for products of combustion, temperature and radioactivity. Upon detection of either products of combustion or excessive temperature, the Reactor Building purge fan is stopped by an interlock, and an alarm sounded in the control room.
Interlocks are provided to close the purge exhaust valves in the event of excessive particulate, gaseous or iodine activity. The Reactor Building purge supply air is filtered and monitored for combustible gases and products of combution. Detection of either causes the purge supply fans to stop and sounds a control room alarm. Purge system fans, filters and instrumentation are located outside the containment.
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5.3.5.2 Auxiliary Building Ventilation The Auxiliary Building contains equipment and components which could be sources of airborne radioactivity as well as other equipment and components which would not. Its ventilation system is of the once-through type in which outside air is taken into the building and distributed to the various areas, then collected, filtered and dishearged to the outside. The flow diagram is shown in Figures 5-14 and 5-15.
The Auxiliary Building ventilation supply consists of a supply system for each of the spent fuel pit and the fuel handling areas, along with a supply subsystem which supplies outside air to the other areas. The Auxiliary Building supply system consists of a particulate filter, two 50%-capacity fans, and ductwork. Outside air is drawn into the system and distributed to the various areas of the building. The fuel handling area supply subsystem consists of a particulate filter and a fan which brings in outside air. The spent fuel pit supply consists of two fans each of 100%
capacity.
Within the Auxiliary Building, there are subsystems to cool air within the building and direct it into the compartments containing the spent fuel coolant pumps and the decay heat closed cycle cooling water pumps. There is also a small fan to recirculata air in the area containing the airlock which provides personnel access to the Reactor Building.
The Auxiliary Building main exhaust subsystem consists of ductwork to collect air from the various compartments and areas throughout the building, particulate, absolute and charcoal filters and four exhaust fans each of 50% capacity. Exhaust air from the controlled access area of the Control Complex (el. 95') is handled by this subsystem.
All air from the Auxiliary Building ventilation system is filtered by the particulate and charcoal filters, then exhausted to the atmosphere through the plant vent from a point near the top of the cylindrical section of the containment. Intakes to the system are located on the sides of the Auxiliary Building.
5.3.5.3 Control Complex The Control Complex is divided for purposes of ventilation into two zones, the controlled access area (el. 95') and the remainder of the building.
The flow diagram is shown in Figure 5-16. Except for the controlled access area and the top floor of the Control Complex (which contains the ventilation equipment for the complex), the Control Complex ventilation is of the recirculating type, but may be converted to once-through by operation of dampers. Air is supplied to the various areas by either the normal duty supply units or the emergency supply subsystem. The normal duty units consist of particulate filters and fans, while particulate
. filters, absolute filters, and charcoal filters, and fans make up the emergency supply subsystem.
Supply air is heated or cooled as necessary, then distributed to the various areas of the complex. Air from those areas with recirculation capability is returned by Control Complex return fans. Powe r-ope rated dampers are provided to allow recirculation from the return fans to the WPS/hewWO4 (D7)
supply system or to exhaust all taturn air and to supply only outside air to the Control Complex. The outside air intake and discharge points are on the Control Complex roof, separated by a distance of more than forty feet.
The upper floor of the Control Complex has a relief fan system which exhausts ventilation air from this area to the atmosphere at a point on the roof well separated from the intake.
The controlled access area (parts of which may contain radioactivity) receives air from the Control Complex supply system. Air is also supplied to the exhaust and sample hoods from the Turbine Building by a supply fan.
Air from the controlled access area is collected and directed by exhaust fans to the Auxiliary Building exhaust system for filtering and discharge.
The Control Complex is equipped with UL-approved, three-hour-rated fire dampers to isolate the various areas. Closure of these dampers is initiated by a fusible link upon the occurrence of high temperature at the dampe r. These dampers are also arranged to be automatically closed by products-of-combustion and/or temperature detectors, as descried in Section 5.3.3.1 and Table 5-3. Upon actuation of one of these detectors, an electric circuit is closed, melting the fusible link of its associated damper, thereby allowing it to close. Rooms are isolated by automatic closure of dampers in the supply and return air ducts upon detection of fire by a detector either in the room or in the return air duct. A control room alarm is also initiated. All dampers in the cable spreading room ducts are also automatically closed in the event the Halon system is initated.
The Control Complex ventilation system normally operates in the recirculation mode (except for the controlled access area) with outside air supplied as required to make up for the air exhausted from the controlled access area. If an engineered safeguards signal occurs, dampers are actuated to stop the supply of air to the controlled access area and place the remainder of the Control Complex in a full recirculation mode. Upon detection of radioactivity in the Control Complex atmosphere exceeding a present level, an emergency supply unit is started and the normal duty units stopped and isolated. This routes the supply air through the HEPA and charcoal filters in the supply units prior to its return to the Control Complex arecs.
A POC detector in the return air system automatically changes the system to once-through, exhausting all return air to the outside. A control room alarm is also initiated.
Another P0C detector in the air inlet duct to the Control Complex closes a fire damper in the duct and initiates a control room alarm in the event that products of combustion are detected in the incoming air.
A products-of-combustion detector in the controlled access exhaust hood supply fan intake closes a damper in that duct on detection of fire, and initiates a control room alarm.
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4 5.3.5.4 Intermediate Building Ventilation System The Intermediate Building, which houses the emergency feedwater pumps, main steam isolation valves, and Reactor Building purge supply equipment, has a once-through ventilation system. Air is supplied by two 100%-capacity supply fans, first passing through a particulate filter. It passes first through the emergency feedwater pump room, then through the remainder of the Intermediate Building, and is exhausted by two 100%-capacity fans.
There are fire dampers in the air intake and between the pump room and the remainder of the Intermediate Building. The fir damper in the air intake is closed automatically either by its fusible link or upon detection of high temperature by a temperature detector in the air intake. The dampers where the air leaves the pump room are closed by the dampers' fusible link or upon detection of high temperature in the pump room. A products-of-combustion detector is also provided in the pump room. The temperature and POC detectors also initiate control room alarms.
5.3.5.5 Turbine Building The Turbine Building has nine supply fans, with fire dampers located in the intakes. Each damper automatically closes upon high temperature in its fan discharge, or by the fusible link in the damper. Turbine Building air is exhausted through gravity ventilators, windows and wall louvers.
Thermavent gravity roof dampers are provided for the Turbine Building roof.
The dampers are equipped with 160*F fusible links.
The Turbine Building switchgear rooms are equipped with a recirculating ventilation system. It consists of two 100%-air-handling units consisting of filters, cooling coils, and fans. The air handling units are connected by ductwork to the switchgear rooms. Supply and return ducts are equipped with fire dampers which close on detection of high return air temperature.
Products-of-combustion detectors are also located in the return air ducts.
Both POC and temperature detectors sound control room alarms.
5.3.5.6 Diesel Generator Rooms Each diesel generator room has two 100%-capacity fans which supply air to the room. The air exhausts through wall louvers. A separate fan circulates air between the diesel control room and the diesel generator room. Fire dampers are provided between each diesel generator room and its control room. A products-of-combustion detector closes the mampers on detection of fire and initiates a control room alarm.
5.3.5.7 Fire Service Pump House The Fire Service Pump House has two 100%-capacity supply fans with a particulate filter which supply outside air. A products-of-combustion detector initiates a control room alarm in the event of fire.
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Question 71 How of ten and by what means are "POC" interlocks tested for the reactor building purge supply and exhaust fans (Page 5-31)?
RESPONSE
The product of combustion interlocks are tested semiannually. The procedure of this check is outlined in Surveillance Procedure 190 of 3/30/78.
Question 73 Verify that the tGrbine building is a free standing building in that it will not affect the control complex or intermediate building by its structural f ailure due to a fire in the turbine building.
RESPONSE
The turbine building was designed and constructed as a free standing structure. It is joined to the control complex and the intermediate building will not af fect the control complex or the intermediate building.
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4 SRP-25 -
Diesel Generator Control Room Smoke Detector Staff Concern The lower smoke detector located in the diesel generator
, control room is not effective in its present location.
Staff Position Relocate the smoke detector to high bay in diesel generator control room (s).
RESPONSE
POC's in the emergency diesel generator control rooms will be relocated by 4/79. Ref: WR#4433.
SRP-9 -
Control Room Kitchenette Staff Concern The control room kitchenette is located in a safety-related area and presents an unprotected fire hazard.
Staff Postion Remove stove, kitchen equipment and kitchen cabinets from behind control panels.
RESPONSE
Electric stove and oven in the control room were disconnected 12/7/78, WR #4148. Cabinets on order PR
- 740-4587; completion expected by 4/79.
WPS/hewWO4 (D7)
4 SRP Station Ventilation Staff Concern Failure of exhaust ventilation in battery rooms could lead to build-up of explosive hydrogen concentrations.
Staff Position Relocate exhaust ducting to ceiling of battery room. Provide air flow monitoring on battery room exhaust by surveillance or alarm system.
RESPONSE
The batteries are of a type which has a very low hydrogen production rate when under charge. The potential ef fects of loss of ventilation in the battery room has been addressed in the Crystal River Unit 3 Final Safety Analysis Report, Section 8.2.2.6. The FSAR states:
"The Battery chargers normally supply the d-c system load and the float charge to the batteries. The chargers are also capable of supplying a 24-hour equalize charge. The chargers are supplied with a high/ low voltage alarm relay to monitor the d-c system. The high alarm point is set at 137 vde to protect against battery overcharging during normal operation.
" Battery Hydrogen Evolution was calculated under worst case conditions of the battery rooms at a temperature of 77'F and the batteries being overcharged at the high voltage alarm point of 2.35 volts per cell.
The results are as follows:
"1. Under the condition that the battery rooms were completely sealed from outside air it was found that it would require 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> to produce sufficient Hydrogen in the rooms to yield an explosive mixture (four percent by volume). This calculation was completed for comparison basis only as this condition is abnormal to plant ope ration.
"2. Under the condition that the control complex air handling system is in the emergency recirculation mode as described in Section 9.7.2.7.h with 0 percent outside air admission it was found that it would require 6500 hours0.0752 days <br />1.806 hours <br />0.0107 weeks <br />0.00247 months <br /> to produce sufficient Hydrogen in the control complex to yield an explosive mixture (four percent by volume)."
Because of the long time required to build up a flammable concentra-tion of hydrogen, and the surveillance program which requires periodic visits to each battery room, it is concluded that a ventilation flow alarm is not justified.
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