|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History ML20216G8091998-04-10010 April 1998 Safety Evaluation Accepting Resolution of Crystal River Restart Issues Related to USI A-46 Program ML20199A1441998-01-0909 January 1998 Safety Evaluation Accepting Relief Request for Delayed Implementation of 10CFR50.55a,until 971231 or Plant Restart, Whichever Occurs First ML20199D0561997-11-14014 November 1997 Safety Evaluation Approving Ampacity Derating Test Results for Crystal River,Unit 3 Related to GL 92-08, Thermo-Lag 330-1 Fire Barriers ML20212C3751997-10-16016 October 1997 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20217D7561997-10-0101 October 1997 Safety Evaluation Concluding That Testing of Ingersoll-Dresser Pump Model 8HN194 at Test Facility Demonstrates That Crystal River Decay Heat Pumps of Same Model Can Operate at Flows of 100 Gpm for 30 Days ML20138J0151997-05-0505 May 1997 Safety Evaluation Approving Request for Relief 95-050,Rev 1, for Plant,Unit 3 ML20138E4411997-04-30030 April 1997 Safety Evaluation on ASME Code Case N-509 for Crystal River Nuclear Plant,Unit 3 ML20140F3771997-04-28028 April 1997 Safety Evaluation Supporting Staff Evaluation of Plant, Unit 3 Nuclear Generating Plant IPE ML20134B7091997-01-29029 January 1997 SER Accepting Fire Barrier Sys Relied by Licensee to Meet NRC Fire Protection Requirements for Following Raceway Types & Sizes ML20133N6511997-01-22022 January 1997 Safety Evaluation Accepting Licensee Request to Use Code Case N-524 as Alternative to ASME Code Section XI for Plant ML20149M6801997-01-17017 January 1997 Safety Evaluation Accepting Licensee 960807 Results of Analyses Re Operability Evaluation of Main Steam Sys W/Bent Rod Hangers at Plant ML20133D3471997-01-0606 January 1997 Safety Evaluation Supporting Amend 155 to License DPR-72 ML20058P1981993-12-16016 December 1993 Safety Evaluation Accepting Ground Response Spectra Utilized & Approaches Used in Development of Floor Response Spectra for Resolution of USI A-46 ML20138D5941993-02-0909 February 1993 Safety Evaluation Granting Relief from Repair Requirements of ASME Code Section XI in Order to Perform Temporary Noncode Repair to 18 Inch Portion of Nuclear Closed Cycle Cooling Sys ML20126F7811992-12-22022 December 1992 Safety Evaluation to Confirm Granting of Request for Relief from ASME Code Repair Requirements Nuclear Closed Cycle Cooling Sys ML20056B5341990-08-23023 August 1990 Safety Evaluation Re Station Blackout.Recommends That Util Reevaluate Areas of Nonconformance W/Station Blackout Guidance Identified in Evaluation.Subj to Acceptable Resolution of NRC Recommendations,Issue Remains Open ML20055E5141990-07-0202 July 1990 Safety Evaluation Re Util 831104 & 840731 Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20245F6561989-06-22022 June 1989 Safety Evaluation Supporting Amend 118 to License DPR-72 ML20245D3001989-06-14014 June 1989 Safety Evaluation Concluding That Licensee Meets NRC Position on Item 4.5.2 of Generic Ltr 83-28,based on Finding That Facility Will Be Designed to Permit on-line Functional Testing of Reactor Trip Sys,Including Stated Testing ML20247D4951989-05-19019 May 1989 Safety Evaluation Re TMI Action Item II.K.3.31 Concerning plant-specific Calculations to Show Compliance w/10CFR50.46 ML20245A6161989-04-19019 April 1989 Safety Evaluation Supporting Util 890210 Final ATWS Design Description ML20155F2641988-10-0606 October 1988 Safety Evaluation Supporting Relief from Inservice Testing Program ML20154A7421988-04-29029 April 1988 Evaluation of Auxiliary Feedwater Sys Reliability (Generic Issue 124).Licensee Should Consider Listed Addl Recommendations for Improved Plant Performance & Auxiliary Feedwater Sys Challenge Rate Reduction ML20234D5221987-06-16016 June 1987 Safety Evaluation Re Conformance to Reg Guide 1.97 ML20214Q7731987-05-29029 May 1987 Ser:Pump & Valve Inservice Testing Program,Crystal River Nuclear Power Station,Unit 3,for Remainder of First 10-Yr Interval ML20214M1781987-05-26026 May 1987 Safety Evaluation Granting Util 860324 & 870114 Requests for Relief from Certain Requirements of ASME Code Section XI & to Use ANSI N45.2.6-1978 in Lieu of ASME Code Requirement of ANSI N45.2.6-1973 ML20211N2661987-02-19019 February 1987 Evaluation of Licensee Response to Insp Rept 50-302/86-12. Procedure AI-401 Found to Be Inadequate & Resulted in Restatement of Violation 2.Design Error Could Cause Loss of RHR Ability ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20211B5521987-02-0909 February 1987 Safety Evaluation Re Rev 7 to Offsite Dose Calculation Manual (ODCM) & Rev 0 to Process Control Program (Pcp).Odcm & PCP Acceptable Refs for Use W/Tech Specs for Assuring Compliance w/10CFR20 & 50,App a & I ML20209H7051987-01-16016 January 1987 Safety Evaluation of Util 831104,840116 & 0731 Responses to Generic Ltr 83-28,Item 4.4 Re safety-related Maint & Test Procedures for Diverse Reactor Trip Feature.Responses Acceptable ML20207Q6451987-01-0909 January 1987 Safety Evaluation Supporting Util 831104,840116 & 0731 Responses to Generic Ltr 83-28,Item 4.4 Re Maint & Test Procedures for Silicon Controlled Rectifiers ML20214N1941986-09-0404 September 1986 Safety Evaluation Supporting Licensee 860117 Response to 10CFR50.61 Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20205T5301986-06-0909 June 1986 SER Supporting Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability ML20211D6251986-06-0909 June 1986 SER Supporting Responses to Generic Ltr 81-21 Re Natural Circulation Cooldown ML20210R9531986-05-0202 May 1986 SER Supporting Util Response to IE Bulletin 80-11 Re Masonry Wall design.Safety-related Masonry Walls Will Withstand Specified Design Load Conditions W/O Impairment of Wall Integrity.Technical Evaluation Rept Encl ML20133Q1271985-10-24024 October 1985 SER Re Generic Ltr 83-28,Item 1.1 Post-Trip Review Program Description & Procedure. Util 831104 Response to Generic Ltr 83-28 Does Not Meet Guidelines for post-trip Review. Acceptable Responses Required ML20135F8871985-09-11011 September 1985 SER Re Control Complex Dedicated Cooling Sys for post-fire Alternate Shutdown Capability.Design of Control Complex Dedicated Cooling Sys Meets Requirements of Section III.G.3 & Iii.L of 10CFR50 App R & Acceptable ML20135G1051985-09-0909 September 1985 SER Supporting Licensee Response to Items 3.1.1,3.1.2,3.2.1, 3.2.2,4.1 & 4.5.1 of Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20135E6131985-09-0606 September 1985 SER Re Licensee Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability).Licensee Program for Data Retention Conforms to Guidelines of Section Ii.D & Acceptable ML20214J2911979-12-20020 December 1979 Safety Evaluation Re Preliminary Design for safety-grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Turbine Trip 1999-09-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
[Table view] |
Text
. - ~ _ - - - - . - - - . - _- - . _ - . - . - - . . - - - - --. - . - - - -
, p+2nsg i g k
- UNITED STATES 1 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3008H001 g...../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT FOR ESAS SURVEILLANCE :
CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302
1.0 INTRODUCTION
By letter dated September 23, 1996, the Florida Power Corporation (FPC or the licensee) proposed changes to the Crystal River Unit 3 (CR3) Technical
, Specifications (TS). The proposed changes involve deleting a note in the l
Surveillance Requirement (SR) for the Engineered Safeguard Actuation System (ESAS) Automatic Actuation Logic. The NOTE in the TS SR 3.3.7.1 states: "When ,
an ESAS automatic actuation logic matrix is placed in an inoperable status l l solely for performance of this Surveillance, entry into associated Conditions
! and Required Actions may be delayed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provided the associated
! ES [ Engineered Safeguards) function is maintained." The CR3 design of ESAS l is such that when the automatic actuation logic for a particular ES function is placed in " test," the associated components for either the "A" or "B" ES train are blocked from actuation in response to a valid automatic or manual actuation. Thus, the NOTE does not provide the relief intended and is not ;
required. Therefore, the licensee proposes to delete the note, and enter into applicable TS Conditions during the performance of the ESAS test and bypassing of the associated ES function.
1 j 2.0 DISCUSSION The channel functional test for the ESAS automatic actuation logic is performed by an ES function. While the actuation matrices are tested, the ES 1 function is bypassed. When "one or more automatic actuation logic matrices !
inoperable," TS 3.3.7.1, Condition A, requires to place the associated '
component (s) in the ES configuration or declare them inoperable within l 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. However, during an ESAS Surveillance and the ESAS automatic actuation !
logic matrix is placed in an inoperable status solely for performance of the surveillance, a NOTE in TS SR 3.3.7.1 provides relief from the TS 3.3.7.1 Required Actions. The NOTE allows up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for entry into associated Conditions and Required Actions may be delayed, provided the associated ES function is maintained.
The CR3 system design and testing method are such that while the three ES l functions (high pressure injection, low pressure injection, and reactor l building isolation and cooling) are tested, the associated end devices, will '
. not respond to either an automatic or manuai actuation of the ESAS function.
! Thus the CR3 system design and testing method could not maintain the associated ES function and, therefore, could not utilize the intended relief '
I in the NOTE for delaying the required actions for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. When performing the Surveillance, the licensee proposes to declare automatic actuation logic matrices inoperable and, accordingly, to enter the TS 3.3.7.1, ENCLOSURE 9701090150 970106 PDR ADOCK 05000302 P PDR
l i
2 Required Action to restore the ES configuration within the allowed I hour time. The licensee states that I hour is adequate to complete testing of the l individual test gr~ups, including the time needed to assess potential l equipment failures. In the event of a failure of an individual ES actuation I
matrix, the affected equipment would be placed in the ES configuration or declared inoperable until repaired while the remaining matrices are returned to an OPERABLE configuration. The proposed TS is consistent with the required action for TS 3.3.7.1 and therefore, deleting the NOTE in SR 3.3.7.1 is acceptable.
3.0 STATE CONSULTATION
l Based upon the written notice of the proposed amendments, the Florida State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defineri in 10 CFR Part 20 and changes the surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released l offsite, and that there is no significant increase in individual or cumulative l occupational radiation exposure. The Comission has previously issued a l proposed finding that the amendments involve no significant hazards l consideration, and there has been no public coment on such finding (61 FR 55034). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR El.22(c)(9). Pursuant to l 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
l
5.0 CONCLUSION
Based on review of the proposed changes as discussed above, the staff has concluded that the proposed TS changes to delete the NOTE to Surveillance Requirements 3.3.7.1 are acceptable.
The Comission has concluded, based on the considerations discussed above, that. (1) there is reasonable assurance that the health and safety of the ,
public will not be endangered by operation in the proposed manner, (2) such i activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principle Contributor: Sang Rhow, HICB i
Date: January 6, 1996 i
)
. o
- Mr. Percy M. Beard, Jr. CRYSTAL RIVER UNIT NO. 3 ;
Florida Power Corporation GENERATING PLANT l 1
l l cc:
l Mr. R. Alexander Glenn Chairman l Corporate Counsel Board of County Commissioners l Florida Power Corporation Citrus County l MAC-ASA 110 North Apopka Avenue l P.O. Box 14042 Iverness, Florida 34450-4245 St. Petersburg, Florida 33733-4042 l Mr. Larry C. Kelley, Director
! Mr. Bruce J. Hickle, Director Nuclear Operations Site Support Nuclear Plant Operations (kA2C) (SA2A)
Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 l Mr. Robert B. Borsum Senior Resident Inspector i B&W Nuclear Technologies Crystal River Unit 3 ,
1700 Rockville Pike, Suite 525 U.S. Nuclear Regulatory Commission l Rockville, Maryland 20852 6745 N. Tallahassee Road Crystal River, Florida 34428 l
, Mr. Bill Passetti l Office of Radiation Control Mr. Gary Boldt Department of Health and Vice President - Nuclear Production Rehabilitative Services Florida Power Corporation 1317 Winewood Blvd. Crystal River Energy Complex Tallahassee, Florida 32399-0700 15760 W. Power Line Street Crystal River, Florida 34428-6708
, Attorney General l Department of Legal Affairs Regional Administrator, Region II j The Capitol U.S. Nuclear Regulatory Commission l
Tallahassee, Florida 32304 101 Marietta Street N.W., Suite 2900 l Atlanta, Georgia 30323 Mr. Joe Myers, Director Division of Emergency Preparedness Mr. Kerry Landis Department of Community Affairs U.S. Nuclear Regulatory Commission 2740 Centerview Drive 101 Marietta Street, N.W. Suite 2900 Tallahassee, Florida 32399-2100 Atlanta, Georgia 30323-0199
-. ,