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| issue date = 06/02/2010
| issue date = 06/02/2010
| title = Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
| title = Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
| author name = Kuntz R F
| author name = Kuntz R
| author affiliation = NRC/NRR/DLR/RPB2
| author affiliation = NRC/NRR/DLR/RPB2
| addressee name = Franke J
| addressee name = Franke J
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:June 2, 2010 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B) ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708  
{{#Wiki_filter:June 2, 2010 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)  
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)


==Dear Mr. Franke:==
==Dear Mr. Franke:==


By letter dated December 16, 2009, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail at robert.kuntz@nrc.gov. Sincerely, /RA/
By letter dated December 16, 2009, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302  
Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail at robert.kuntz@nrc.gov.
Sincerely,
                                              /RA/
Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302


==Enclosure:==
==Enclosure:==
As stated cc w/encl:  See next page 


ML101410512 OFFICE PM:RPB2:DLR LA:DLR BC:DLR:RARB BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz IKing GShukla DWrona RKuntz DATE 06/01/10 05/27/10 06/01/10 06/02/10 06/02/10 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 RAI 3.2.1.47-1
As stated cc w/encl: See next page


===Background===
ML101410512 OFFICE    PM:RPB2:DLR    LA:DLR  BC:DLR:RARB      BC:RPB2:DLR          PM:RPB2:DLR NAME      RKuntz          IKing    GShukla          DWrona                RKuntz DATE      06/01/10        05/27/10 06/01/10          06/02/10              06/02/10
: Crystal River Unit 3 Nuclear Generating Plant (CR-3) license renewal application (LRA) Table 3.2.1 item 47 states that "This items is not applicable to CR-3. Cast austenitic stainless steel (CASS) valves associated with engineered safety feature (ESF) Systems are inside Class 1 boundaries and evaluated with reactor coolant system components (see Table 3.1.1, Item 3.5.1-55)."
Issue: Standard Review Plan (SRP) Table 3.2.1 item 47 states that CASS piping, piping components, and piping elements exposed to treated borated water > 250 oC are subject to aging effects of loss of fracture toughness due to thermal aging embrittlement and recommends managing the aging effect with the Thermal Aging Embrittlement of CASS Program. LRA Tables 3.2.2-2 "Engineered Safety Features - Summary of Aging Management Evaluation - Core Flood System" and 3.2.2-3 "Engineered Safety Features - Summary of Aging Management Evaluation - Decay Heat Removal System" contain aging management reviews (AMRs) for CASS piping, piping components, and piping elements. The aging effect of loss of fracture toughness due to thermal embrittlement is managed by the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD. This is consistent with SRP Table 3.1.1 item 55, which recommends aging management specifically for CASS Class 1 pump casings and valve bodies and bonnets exposed to reactor coolant >250 oC. Request: Provide a list of component types covered by the above AMRs in the Core Flood System and Decay Heat Removal System. For components other than Class 1 pump casings and valve bodies and bonnets provide justification for managing the loss of fracture toughness due to thermal embrittlement using the ASME Section XI, Inservice Inspection, Subsection IWB, IWC, and IWD Program in lieu of the Thermal Aging Embrittlement of CASS Program.
RAI 3.31.53-1


===
REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 RAI 3.2.1.47-1
Background===
:  The GALL Report Table 3, line items 53 and 54 indicate that steel or stainless steel piping, piping components, and piping elements exposed to condensation should be managed by the Compressed Air Monitoring Program. The GALL AMP XI.M24, "Compressed Air Monitoring Program" includes recommendations for the management of aging effects through visual inspection and for preventive maintenance including air quality checks and performance monitoring. Specifically, the "Monitoring and Trending" element of the GALL Report Compressed Air Monitoring Program recommends testing to verify proper operation of the compressed air system by comparing measured system performance values with specified performance limits as part of the aging management program.
Issue:  The applicant indicates in the LRA that the GALL Report Table 3, line items 53 and 54 are not applicable to CR-3. As a result, the applicant has not developed a Compressed Air Monitoring Program consistent with the GALL guidance to manage steel or stainless steel piping, piping components, and piping elements exposed to condensation. The LRA indicates that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is used to manage corrosion of internal surfaces of compressed air systems that might be subject to internal condensation. Although the applicant's Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program addresses the detection of age-related degradation products on the internal surfaces of system piping and ducting, it does not include preventive maintenance activities as recommended by the GALL Report for the Compressed Air Monitoring Program.
Request:  1. Clarify which specific table 2 line items are credited to manage loss of material for steel compressed air system piping, piping components, and piping elements exposed to internal condensation.
: 2. Describe how performance monitoring and air quality considerations recommended by                        the GALL AMP XI.M24, "Compressed Air Monitoring Program" are included in the selected AMP for managing the materials, environments, and aging effects that are significant to the plant compressed air system.
Letter to Jon Franke from Robert Kuntz dated June 2, 2010


==SUBJECT:==
==Background:==
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
DISTRIBUTION
:  HARD COPY: DLR RF E-MAIL: PUBLIC  RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource --------------------------------------- RKuntz EKeegan AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI Crystal River Unit 3 Nuclear Generating  Plant  cc:    Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A) Florida Power Corporation P.O. Box 14042 St. Petersburg, FL  33733-4042


Mr. James W. Holt Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, FL  32399-1741 
Crystal River Unit 3 Nuclear Generating Plant (CR-3) license renewal application (LRA) Table 3.2.1 item 47 states that This items is not applicable to CR-3. Cast austenitic stainless steel (CASS) valves associated with engineered safety feature (ESF) Systems are inside Class 1 boundaries and evaluated with reactor coolant system components (see Table 3.1.1, Item 3.5.1-55).
Issue:
Standard Review Plan (SRP) Table 3.2.1 item 47 states that CASS piping, piping components, and piping elements exposed to treated borated water > 250oC are subject to aging effects of loss of fracture toughness due to thermal aging embrittlement and recommends managing the aging effect with the Thermal Aging Embrittlement of CASS Program. LRA Tables 3.2.2-2 Engineered Safety Features - Summary of Aging Management Evaluation - Core Flood System and 3.2.2-3 Engineered Safety Features - Summary of Aging Management Evaluation
- Decay Heat Removal System contain aging management reviews (AMRs) for CASS piping, piping components, and piping elements. The aging effect of loss of fracture toughness due to thermal embrittlement is managed by the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD. This is consistent with SRP Table 3.1.1 item 55, which recommends aging management specifically for CASS Class 1 pump casings and valve bodies and bonnets exposed to reactor coolant >250oC.
Request:
Provide a list of component types covered by the above AMRs in the Core Flood System and Decay Heat Removal System. For components other than Class 1 pump casings and valve bodies and bonnets provide justification for managing the loss of fracture toughness due to thermal embrittlement using the ASME Section XI, Inservice Inspection, Subsection IWB, IWC, and IWD Program in lieu of the Thermal Aging Embrittlement of CASS Program.
RAI 3.31.53-1


Attorney General Department of Legal Affairs The Capitol Tallahassee, FL  32304
==Background:==


Mr. Ruben D. Almaguer, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL  32399-2100
The GALL Report Table 3, line items 53 and 54 indicate that steel or stainless steel piping, piping components, and piping elements exposed to condensation should be managed by the Compressed Air Monitoring Program. The GALL AMP XI.M24, Compressed Air Monitoring Program includes recommendations for the management of aging effects through visual ENCLOSURE


Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, FL  34450-4245 Mr. Stephen J. Cahill Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708
inspection and for preventive maintenance including air quality checks and performance monitoring. Specifically, the Monitoring and Trending element of the GALL Report Compressed Air Monitoring Program recommends testing to verify proper operation of the compressed air system by comparing measured system performance values with specified performance limits as part of the aging management program.
Issue:
The applicant indicates in the LRA that the GALL Report Table 3, line items 53 and 54 are not applicable to CR-3. As a result, the applicant has not developed a Compressed Air Monitoring Program consistent with the GALL guidance to manage steel or stainless steel piping, piping components, and piping elements exposed to condensation. The LRA indicates that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is used to manage corrosion of internal surfaces of compressed air systems that might be subject to internal condensation. Although the applicants Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program addresses the detection of age-related degradation products on the internal surfaces of system piping and ducting, it does not include preventive maintenance activities as recommended by the GALL Report for the Compressed Air Monitoring Program.
Request:
: 1. Clarify which specific table 2 line items are credited to manage loss of material for steel compressed air system piping, piping components, and piping elements exposed to internal condensation.
: 2. Describe how performance monitoring and air quality considerations recommended by the GALL AMP XI.M24, Compressed Air Monitoring Program are included in the selected AMP for managing the materials, environments, and aging effects that are significant to the plant compressed air system.


Mr. Daniel R. Westcott Supervisor, Licensing & Regulatory  Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL  34428-6708
Letter to Jon Franke from Robert Kuntz dated June 2, 2010


Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL  34428
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource
---------------------------------------
RKuntz EKeegan AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI


Mr. Jack E. Huegel Manager, Nuclear Oversight Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708  
Crystal River Unit 3 Nuclear Generating Plant cc:
Mr. R. Alexander Glenn                  Mr. Daniel R. Westcott Associate General Counsel (MAC-BT15A)  Supervisor, Licensing & Regulatory Florida Power Corporation                Programs P.O. Box 14042                          Crystal River Nuclear Plant St. Petersburg, FL 33733-4042          15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. James W. Holt Plant General Manager                  Senior Resident Inspector Crystal River Nuclear Plant (NA2C)      Crystal River Unit 3 15760 W. Power Line Street              U.S. Nuclear Regulatory Commission Crystal River, FL 34428-6708            6745 N. Tallahassee Road Crystal River, FL 34428 Mr. William A. Passetti, Chief Department of Health                    Mr. Jack E. Huegel Bureau of Radiation Control            Manager, Nuclear Oversight 2020 Capital Circle, SE, Bin #C21      Crystal River Nuclear Plant (NA2C)
Tallahassee, FL 32399-1741              15760 W. Power Line Street Crystal River, FL 34428-6708 Attorney General Department of Legal Affairs            Mr. David T. Conley The Capitol                            Associate General Counsel II - Legal Dept.
Tallahassee, FL 32304                  Progress Energy Service Company, LLC P.O. Box 1551 Mr. Ruben D. Almaguer, Director        Raleigh, NC 27602-1551 Division of Emergency Preparedness Department of Community Affairs        Mr. Michael P. Heath 2740 Centerview Drive                  Supervisor, License Renewal Tallahassee, FL 32399-2100              Progress Energy 8470 River Road, 2E Chairman                                Southport, NC 28461 Board of County Commissioners Citrus County                          Mr. Mark Rigsby 110 North Apopka Avenue                Manager, Support Services - Nuclear Inverness, FL 34450-4245                Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Stephen J. Cahill                  Crystal River, FL 34428-6708 Engineering Manager Crystal River Nuclear Plant (NA2C)      Mr. Robert J. Duncan II 15760 W. Power Line Street              Vice President, Nuclear Operations Crystal River, FL 34428-6708            Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551


Mr. David T. Conley Associate General Counsel II - Legal Dept. Progress Energy Service Company, LLC P.O. Box 1551 Raleigh, NC  27602-1551 Mr. Michael P. Heath Supervisor, License Renewal Progress Energy 8470 River Road, 2E Southport, NC  28461 Mr. Mark Rigsby Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, FL  34428-6708 Mr. Robert J. Duncan II Vice President, Nuclear Operations Progress Energy P.O. Box 1551 Raleigh, NC  27602-1551 Crystal River Unit 3 Nuclear Generating   Plant cc:   Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551}}
Crystal River Unit 3 Nuclear Generating Plant cc:
Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551}}

Latest revision as of 17:52, 13 November 2019

Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML101410512
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/02/2010
From: Robert Kuntz
License Renewal Projects Branch 2
To: Franke J
Florida Power Corp
Robert Kuntz, 415-3733 DLR/NRR
References
TAC ME0274
Download: ML101410512 (7)


Text

June 2, 2010 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

Dear Mr. Franke:

By letter dated December 16, 2009, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or by e-mail at robert.kuntz@nrc.gov.

Sincerely,

/RA/

Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

As stated cc w/encl: See next page

ML101410512 OFFICE PM:RPB2:DLR LA:DLR BC:DLR:RARB BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz IKing GShukla DWrona RKuntz DATE 06/01/10 05/27/10 06/01/10 06/02/10 06/02/10

REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 RAI 3.2.1.47-1

Background:

Crystal River Unit 3 Nuclear Generating Plant (CR-3) license renewal application (LRA) Table 3.2.1 item 47 states that This items is not applicable to CR-3. Cast austenitic stainless steel (CASS) valves associated with engineered safety feature (ESF) Systems are inside Class 1 boundaries and evaluated with reactor coolant system components (see Table 3.1.1, Item 3.5.1-55).

Issue:

Standard Review Plan (SRP) Table 3.2.1 item 47 states that CASS piping, piping components, and piping elements exposed to treated borated water > 250oC are subject to aging effects of loss of fracture toughness due to thermal aging embrittlement and recommends managing the aging effect with the Thermal Aging Embrittlement of CASS Program. LRA Tables 3.2.2-2 Engineered Safety Features - Summary of Aging Management Evaluation - Core Flood System and 3.2.2-3 Engineered Safety Features - Summary of Aging Management Evaluation

- Decay Heat Removal System contain aging management reviews (AMRs) for CASS piping, piping components, and piping elements. The aging effect of loss of fracture toughness due to thermal embrittlement is managed by the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD. This is consistent with SRP Table 3.1.1 item 55, which recommends aging management specifically for CASS Class 1 pump casings and valve bodies and bonnets exposed to reactor coolant >250oC.

Request:

Provide a list of component types covered by the above AMRs in the Core Flood System and Decay Heat Removal System. For components other than Class 1 pump casings and valve bodies and bonnets provide justification for managing the loss of fracture toughness due to thermal embrittlement using the ASME Section XI, Inservice Inspection, Subsection IWB, IWC, and IWD Program in lieu of the Thermal Aging Embrittlement of CASS Program.

RAI 3.31.53-1

Background:

The GALL Report Table 3, line items 53 and 54 indicate that steel or stainless steel piping, piping components, and piping elements exposed to condensation should be managed by the Compressed Air Monitoring Program. The GALL AMP XI.M24, Compressed Air Monitoring Program includes recommendations for the management of aging effects through visual ENCLOSURE

inspection and for preventive maintenance including air quality checks and performance monitoring. Specifically, the Monitoring and Trending element of the GALL Report Compressed Air Monitoring Program recommends testing to verify proper operation of the compressed air system by comparing measured system performance values with specified performance limits as part of the aging management program.

Issue:

The applicant indicates in the LRA that the GALL Report Table 3, line items 53 and 54 are not applicable to CR-3. As a result, the applicant has not developed a Compressed Air Monitoring Program consistent with the GALL guidance to manage steel or stainless steel piping, piping components, and piping elements exposed to condensation. The LRA indicates that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is used to manage corrosion of internal surfaces of compressed air systems that might be subject to internal condensation. Although the applicants Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program addresses the detection of age-related degradation products on the internal surfaces of system piping and ducting, it does not include preventive maintenance activities as recommended by the GALL Report for the Compressed Air Monitoring Program.

Request:

1. Clarify which specific table 2 line items are credited to manage loss of material for steel compressed air system piping, piping components, and piping elements exposed to internal condensation.
2. Describe how performance monitoring and air quality considerations recommended by the GALL AMP XI.M24, Compressed Air Monitoring Program are included in the selected AMP for managing the materials, environments, and aging effects that are significant to the plant compressed air system.

Letter to Jon Franke from Robert Kuntz dated June 2, 2010

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT, LICENSE RENEWAL APPLICATION (TAC NO. ME0274)

DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource


RKuntz EKeegan AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI

Crystal River Unit 3 Nuclear Generating Plant cc:

Mr. R. Alexander Glenn Mr. Daniel R. Westcott Associate General Counsel (MAC-BT15A) Supervisor, Licensing & Regulatory Florida Power Corporation Programs P.O. Box 14042 Crystal River Nuclear Plant St. Petersburg, FL 33733-4042 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. James W. Holt Plant General Manager Senior Resident Inspector Crystal River Nuclear Plant (NA2C) Crystal River Unit 3 15760 W. Power Line Street U.S. Nuclear Regulatory Commission Crystal River, FL 34428-6708 6745 N. Tallahassee Road Crystal River, FL 34428 Mr. William A. Passetti, Chief Department of Health Mr. Jack E. Huegel Bureau of Radiation Control Manager, Nuclear Oversight 2020 Capital Circle, SE, Bin #C21 Crystal River Nuclear Plant (NA2C)

Tallahassee, FL 32399-1741 15760 W. Power Line Street Crystal River, FL 34428-6708 Attorney General Department of Legal Affairs Mr. David T. Conley The Capitol Associate General Counsel II - Legal Dept.

Tallahassee, FL 32304 Progress Energy Service Company, LLC P.O. Box 1551 Mr. Ruben D. Almaguer, Director Raleigh, NC 27602-1551 Division of Emergency Preparedness Department of Community Affairs Mr. Michael P. Heath 2740 Centerview Drive Supervisor, License Renewal Tallahassee, FL 32399-2100 Progress Energy 8470 River Road, 2E Chairman Southport, NC 28461 Board of County Commissioners Citrus County Mr. Mark Rigsby 110 North Apopka Avenue Manager, Support Services - Nuclear Inverness, FL 34450-4245 Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Mr. Stephen J. Cahill Crystal River, FL 34428-6708 Engineering Manager Crystal River Nuclear Plant (NA2C) Mr. Robert J. Duncan II 15760 W. Power Line Street Vice President, Nuclear Operations Crystal River, FL 34428-6708 Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551

Crystal River Unit 3 Nuclear Generating Plant cc:

Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551