Letter Sequence Other |
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Results
Other: 3F0198-29, Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation, 3F0198-35, Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes, 3F0298-02, Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163, 3F1197-45, Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos, 3F1197-54, Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in, 3F1297-27, Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA, 3F1297-32, Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal, 3F1297-38, Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon, 3F1297-47, Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl, ML20199B738, ML20203C390
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MONTHYEARIR 05000302/19970071997-07-0707 July 1997
Insp Rept 50-302/97-07 on 970504-0607.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support Re self-assessment Rept on Health Physics & Radiation Control Areas Access Control Program
Project stage: Request
ML20216J9101997-09-10010 September 1997
Forwards Request for Addl Info Re Submitting Emergency Operating Procedures W/Proposed Changes to Reflect TS Change Request Number 210 Relating to Mitigation of Small Break Loss of Coolant Accidents & Design Basis Changes
Project stage: RAI
ML20199B4421997-11-0505 November 1997
Forwards Request for Addl Info Re License Amend Submittal & 970925 Re FPC Approach for Addressing Certain SBLOCA Scenarios
Project stage: RAI
ML20199B7381997-11-15015 November 1997
Provides Response to 971105 RAI Re TS Change Request Notice 210,proposing Amends to License DPR-72.List of Commitments Made in Submittal Encl
Project stage: Other
ML20199E3951997-11-19019 November 1997
Forwards Request for Addl Info Re Emergency Operating Procedures Tech Specs Change Request Notice 210.Questions Pertain to Operator Actions Described in Eops,Involving Mitigation of Certain Small Break LOCA Scenarios
Project stage: Request
3F1197-45, Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos1997-11-21021 November 1997
Submits Rev 1 to TS Change Request Notice 210,which Proposes Amends to OL DPR-72.Rev Addresses Changes Resulting from NRC Review of TS Change Request Notice 210.Rev Involves Additional Restrictions,Editorial Clarifications & Typos
Project stage: Other
3F1197-54, Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in1997-11-21021 November 1997
Forwards Copy of Proposed Rev 5 to EOP-8, LOCA Cooldown, as Committed in
Project stage: Other
ML20202E5671997-11-26026 November 1997
Forwards Request for Addl Info Re Amend Submittal ,supplemented by Submitting Approach for Addressing Certain SBLOCA Scenarios
Project stage: RAI
ML20202D4161997-11-26026 November 1997
Mod Outage Integrated Verification Team Rept
Project stage: Request
05000302/LER-1997-039, Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed1997-12-0303 December 1997
Corrected Page 1 to LER 97-039-00,adding Rept Date in Block 7.On 971108,unqualified Matl Discovered Left in Reactor Bldg During Const.Caused by Personnel Error.Polystyrene Permanently Installed
Project stage: Request
3F1297-27, Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA1997-12-0303 December 1997
Forwards Response to 971126 RAI Re TS Change Request 210, Which Addresses Design & Licensing Basis Changes Primarily Involving Plant Systems Used to Mitigate Consequences of Certain Small Break LOCA
Project stage: Other
3F1297-32, Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal1997-12-0505 December 1997
Provides NRC Requested Clarification Re Use of HPI Flow Throttling TS Change Request Notice 210.No New Commitments Made in Submittal
Project stage: Other
ML20203C3901997-12-0505 December 1997
Requests Addl Info Re 970614 License Amend,Suplemented on 970925,1119,1121 & 1203,re FPC Approach for Addressing Certain SBLOCA Scenarios
Project stage: Other
3F1297-38, Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon1997-12-11011 December 1997
Forwards Addl Info on Validations of Proposed Emergency Operating Procedures Containing Operator Actions Related to TS Change Request 210,per 971203 Telcon
Project stage: Other
3F1297-47, Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl1997-12-24024 December 1997
Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl
Project stage: Other
3F0198-29, Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation1998-01-15015 January 1998
Informs That Util in Conjunction W/Framatome Technologies Inc,Completed Confirmation Which Includes Consideration of SG Tube Plugging Levels Specific for CR-3.Util Verified That LOCA Analyses of Record Does Not Require Manual Actuation
Project stage: Other
3F0198-35, Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes1998-01-22022 January 1998
Forwards Complete Updated TS & Bases Pages to TS Change Request Notice 210 Submitted on 970614.Updated Pages Reflect Changes Identified in Licensee ,Correction of Typo & Addition of Footnotes
Project stage: Other
3F0298-02, Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 1631998-02-20020 February 1998
Forwards Status of Requirements Stated in SE Submitted W/ License Amend 163.Status of SE Requirements Do Not Invalidate or Alter Any Conclusions,Or Basis of Any Conclusion,Supporting TS Issued in License Amend 163
Project stage: Other
1997-12-24
[Table View] |
Text
_ -_____- - _ - ____ _
-Mr. Roy A. Anderson December 5, 1997 f
Senior Vice Pr sident i
Nucle r Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION -
LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 210, SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA)
SUBMITTAL (TAC NO. M98991)
Dest Mr. Anderson:
The purpose of this letter is to request additional information (RAl) relating to your license amendment submittal dated June 14,1997, as supplemented by letters dated September 25, November 19, November 21, and December 3,1997, regarding Florida Power Corporation's (FPC's) approach for addressing certain SBLOCA scenarios. Specifically, the amendment requested a Technical Specification change to support operation with hardware changes involving the Emergency Feedwater System, the High Pressure injection System, and the Emergency Diesel Generators and review and approval of FPC's integrated design and operating strategies to resolve unreviewed safety questions identified by the U.S Nuclear Regulatory Commission and FPC. The enclosure provides the details for the i. quested information.
We request your response as soon as possible so that we can schedule our review effort consistent with your restart plan if you have any questions, please call me at (301) 415-1471.
Sincerely,
/S/
L. Raghavan, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/II Docket No. 50-302
Enclosure:
RAI cc w/ enclosure: See next page Distribution Docket File W. Lefave T. Marsh
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- g NUCLEAR REGULATORY COMMISSION W ASHINGToN, D.C. 2066H001 49*****,d December 5,1997 Mr. Roy A. Anderson Senior Vice President Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION -
LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 210, SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA)
SUBMITTAL (TAC NO. M98991)
Dear Mr. Anderson:
The purpose of this letter is to request additional Iriformation (RAI) relating to your license amendment submittal dated June 14,1997, as aupplemented by letters dated September 25, November 19, November 21, and December 3,1997, regarding Florida Power Corporation's (FPC's) approach for addressing certain SBLOCA scenarios. Specifically, the amendment requested a Technical Specification change to support operation with hardware changes involving the Emergency Feedwater System, the High Pressure Injection System, and the Emergency Diesel Generators and review and approval of FPC's integrated design and operating strategies to resolve unreviewed safety questions identified by the U.S Nuclear Regulatory Commission and FPC. The enclosure provides the details for the requested information.
We request your response as soon as possible so that we can schedule our review effort consistent with your rectart plan. If you have any questions, please call me at (301) 415-1471.
Since'ely,
.- J L. Raghavan, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor ReOulatiu Docket No. 50-302
Enclosure:
RAI cc w/ enclosure: See next page
I e
i n
Mr. Roy A. Anderson CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Corporate Counsel Mr. Robert E. Grazio, Director Florica Power Corporation Nuclear Regulatory Affairs (SA2A)
MAC-ASA Florida Power Corporation P.O. Box 14042 Crystal River Energy Complex St. Petersburg, Florida 33733-4042 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Charles G. Pardee, Director Nuclear Plant Operations (NA20)
Senior Resident Inspector Florida Power Corporation Crystal River Unit 3 Crystal River Energy Complex U.S. Nuclear Regulatory Commission 15760 W. Power Line Street 6745 N. Tallahassee Road Crystal River, Florida 34428-6708 Crystal River, Florida 34428 Mr. Bruce J. Hickle, Director Mr. John P. Cowan Director, Restart (NA2C)
Vice President, Nuclear Production Florida Power Corporation (NA2E)
Crystal River Energy Complex Florida Powtr Corporation 15760 W. Power Line Street Crystal Piver Energy Complex Crystal River, Florida 34428-6708 15760 W. Power Line Street Crystal R',ver, Florida 34428-6708 Mr. Robert B. Borsum Framatome Technologies Inc.
Mr. James S. B:umstark 1700 Rockville Pike, Suite 525 Director, Quality Programs (SA2C)
Rockville, Maryland 20852 Florida Power Corporation Crystal River Energy Complex Mr. Bill Passetti 15760 W. Power Line Street Office of Radiation Control Crystal River, Florida 34428-6708 Department of Health and Rehabilitative Services Regional Administrator, Region 11 1317 Winewood Blvd.
U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Attorney General Department of Legal Affairs Mr. Kerry Landis The Capitol U.S. Nuclear Regulatory Commission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245
s REQUEST FOR ADDITIONALjNFORMATION - LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 210. SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA) SUBMITTAL 1.
The response to question 1 in the November 19,1997 submittal indicates that flow throttling of the high pressure injection (HPI) pumps has been approved by the U.S.
Nuclear Regulatory Commission. This is important because the Crystal River Unit 3 (CR3)
HPl system throttling is performed every time the suction path is aligned to the low pressure injection. A review of the references provided (November 16,1980 NRC SER, and May 23,1980 submittal) indicate that HPI throttling is allowed only when there is adequate subcooling to prevent pressurizer overfilling. Because it appears that HPI throttling has cnly been approved if there is adequate subcooling, please describe the conditions where HPl throttling is necessary or required by the procedures with the current system and if HPl throttling could occur when there may not be adequate subcooling, provide a justification why this is acceptable.
Enclosure
_
