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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20236S4081998-07-0101 July 1998 Safety Evaluation Supporting Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively ML20248L1961998-06-0808 June 1998 Safety Evaluation Supporting Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20216E4701998-03-0909 March 1998 Safety Evaluation Approving Exemption from Updated FSAR Requirements of 10CFR50.71(e)(4) for Sequoyah Nuclear Plant,Units 1 & 2 ML20203K6811998-02-20020 February 1998 Safety Evaluation Supporting Amends 231 & 221 to Licenses DPR-77 & DPR-79,respectively ML20198P9171998-01-13013 January 1998 Safety Evaluation Supporting Amend 230 to License DPR-77 ML20217D7881997-09-29029 September 1997 Safety Evaluation Supporting Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively ML20211G2061997-09-23023 September 1997 Safety Evaluation Supporting Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively ML20210J5951997-08-12012 August 1997 Safety Evaluation Supporting Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively ML20151L7981997-07-14014 July 1997 Safety Evaluation Supporting Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively ML20148S0581997-07-0101 July 1997 Safety Evaluation Supporting Amends 225 & 216 to Licenses DPR-77 & DPR-79,respectively ML20140F0311997-06-10010 June 1997 Safety Evaluation Supporting Amends 224 & 215 to Licenses DPR-77 & DPR-79,respectively ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20137Y8911997-04-21021 April 1997 Safety Evaluation Supporting Amends 223 & 214 to Licenses DPR-77 & DPR-79,respectively ML20101M5761996-04-0303 April 1996 Safety Evaluation Supporting Amend 211 to License DPR-79 ML20100N5711996-03-0404 March 1996 Safety Evaluation Supporting Amends 220 & 210 to Licenses DPR-77 & DPR-79,respectively ML20097D4191996-02-0707 February 1996 Safety Evaluation Supporting Amends 218 & 208 to Licenses NPF-77 & NPF-79,respectively ML20095F9891995-12-11011 December 1995 Safety Evaluation Supporting Amends 216 & 206 to Licenses DPR-77 & DPR-79,respectively ML20094N5341995-11-21021 November 1995 Safety Evaluation Supporting Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively ML20094D2451995-10-30030 October 1995 Safety Evaluation Supporting Amend 204 to License DPR-79 ML20093E1191995-10-11011 October 1995 Safety Evaluation Supporting Amend 214 to License DPR-77 ML20093B9471995-10-0404 October 1995 Safety Evaluation Supporting Amends 213 & 203 to Licenses DPR-77 & DPR-79,respectively ML20092N0711995-10-0202 October 1995 Safety Evaluation Supporting Amends 212 & 202 to Licenses DPR-77 & DPR-79,respectively ML20092H0811995-09-15015 September 1995 Safety Evaluation Supporting Amends 211 & 201 to Licenses DPR-77 & DPR-79,respectively ML20092G7071995-09-13013 September 1995 Safety Evaluation Supporting Amends 210 & 200 to Licenses DPR-77 & DPR-79 ML20087L4671995-08-22022 August 1995 Safety Evaluation Supporting Amends 207 & 197 to Licenses DPR-77 & DPR-79,respectively ML20086C2861995-06-29029 June 1995 Safety Evaluation Supporting Amends 205 & 195 to Licenses DPR-77 & DPR-79,respectively ML20085G5811995-06-13013 June 1995 Safety Evaluation Supporting Amends 203 & 193 to Licenses DPR-77 & DPR-79,respectively ML20085G5091995-06-13013 June 1995 Safety Evaluation Supporting Amends 202 & 192 to Licenses DPR-77 & DPR-79,respectively ML20083L1931995-05-10010 May 1995 Safety Evaluation Supporting Amends 198 & 189 to Licenses DPR-77 & DPR-79,respectively ML20087J3291995-04-28028 April 1995 Safety Evaluation Supporting Amends 197 & 188 to Licenses DPR-77 & DPR-79,respectively ML20082E4291995-04-0404 April 1995 Safety Evaluation Supporting Amends 196 & 187 to Licenses DPR-77 & DPR-79,respectively ML20078M8441995-02-0909 February 1995 Safety Evaluation Supporting Amends 195 & 186 to Licenses DPR-77 & DPR-79,respectively 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively 05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
1999-09-30
[Table view] |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 30eeH001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.195 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO.186 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SE000YAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 i
1.0 INTRODUCTION
By application dated December 16, 1994, and supplemented by letter dated January 19, 1995, the Tennessee Valley Authority (the licensee) proposed an amendment to the Technical Specifications (TS) for Sequoyah Nuclear Plant (SQN) Units 1 and 2.
The requested changes would replace the surveillance requirement (SR) to accelerate the diesel to 900 rpm within 10 seconds with a similar requirement to accelerate the diesel generator to 60 1.2 Hz within 10 seconds.
It would also delete the "during shutdown" requirement associated with performance of the diesel generator 10-year interdependence surveillance test.
The supplemental letter supplied amplifying information that did not affect the original no significant hazards consideration determination.
2.0 EVALVATION SR 4.8.1.1.2.a.4 requires that each diesel generator be started at least once 1
per 184 days to verify acceleration to at least 900 rpm in less than or equal to 10 seconds.
In addition, the SR requires verification that the generator voltage and frequency is 6900 690 volts and 60 1.2 Hz within 10 seconds after the start signal. The requested change would delete the requirement to verify that the diesel accelerates to at least 900 rpm. The SR would continue to require that the diesel generator test be conducted at least once per 184 days to verify that the diesel achieves generator voltage and frequency of 6900 1690 volts and 60 i 1.2 Hz in less than or equal to 10 seconds.
SR 4.8.1.1.2.e requires that the diesel generators be started simultaneously during shutdown at least once per 10 years or after any modifications which could affect diesel generator interdependence, to verify that the diesel generators accelerate to at least 900 rpm in less than or equal to 10 seconds.
The requested change would delete the requirement that the surveillance be performed during shutdown.
The new SR 4.8.1.1.2.e would require that the i
diesel generators be started simultaneously at least once per 10 years or 9502140417 950209 PDR ADOCK 05000327 ENCLOSURE P
PDR
after any modifications which could affect diesel generator interdependence to verify that each diesel generator achieves 6900 690 volts and 60 1.2 Hz in less than or equal to 10 seconds.
In justification of their request to remove / replace the 900 rpm requirement in SRs 4.8.1.1.2.a.4 and 4.8.1.1.2.e, the licensee documented by letter dated December 16, 1994, that the removal / replacement does not change the intent of the surveillance.
The 60 1.2 Hz frequency requirement is the same as the 900 rpm speed limit requirement.
The frequency requirement satisfies the speed limit requirement to ensure that the diesel generator is ready to accept accident loads. Therefore, no relaxation of the technical specification requirement is realized by implementing the requested change.
In addition, the requested change is consistent with the Standard Technical Specifications.
In justification of their request to delete "during shutdown" from SR 4.8.1.1.2.e, the licensee documented by letter dated December 16, 1994, that the deletion would not alter the intent of this surveillance.
The deletion is consistent with the Standard Technical Specifications.
With the exception that all diesel generators are started simultaneously, TVA further indicated, in supplemental information provided by letter dated January 19, 1995, and by discussions, that the surveillance (i.e., simultaneous start of all diesel generators during shutdown once per 10 years or after modifications), is the same as the surveillance which requires diesel generator start during normal plant operation every 30 days.
TVA indicated that independence between the diesel generators and the offsite and onsite distribution systems is maintained during the 10-year test. The diesel generators are capable of responding, in accordance with design basis requirements, to a loss of offsite power signal and/or accident signal during the 10-year test.
Failure of one or more diesel generators during the surveillance will not cause a design basis accident or plant condition which would necessitate the use of diesel generators.
Therefore, the deletion of "during shutdown" does not alter the intent of the surveillance.
The staff concludes that the requested changes do not alter the requirements included in SRs 4.8.1.1.2.a.4 and 4.8.1.1.2.e.
The requested changes are, therefore, acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR j
Part 20 and changes a surveillance requirement.
The NRC staff has determined that the amendment tavolves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a i
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proposed finding that the amendment involves no significant hazards consideration,-and there has been no public comment on such finding (59 FR 67350). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission 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 activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: John L. Knox Dated:
February 9, 1995 i
1 i
- Mr. 01'iver D. Kingsley, Jr.
SEQU0YAH NUCLEAR PLANT
' Tennessee Valley Authority.
4 CC:
Mr. O. J. Zeringue, Sr. Vice President TVA Representative Nuclear Operations Tennessee Valley Authority Tennessee Valley Authority 11921 Rockville Pike 3B Lookout Place Suite 402 1101 Market Street Rockville, MD 20852 Chattanooga, TN 37402-2801 Regional Administrator Dr. Mark O. Medford, Vice President U.S. Nuclear Regulatory Commission Engineering & Technical Services Region II Tennessee Valley Authority 101 Marietta Street, NW., Suite 2900 3B Lookout Place Atlanta, GA 30323 1101 Market Street Chattanooga, TN 37402-2801 Mr. William E. Holland Senior Resident Inspector Mr. D. E. Nunn, Vice President Sequoyah Nuclear Plant New Plant Completion U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road 3B Lookout Place Soddy Daisy, TN 37379 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael H. Mobley, Director Division of Radiological Health Site Vice President 3rd Floor, L and C Annex Sequoyah Nuclear Plant.
401 Church Street Tennessee Valley Authority Nashville, TN 37243-1532 P.O. Box 2000 Soddy Daisy, TN 37379 County Judge Hamilton County Courthouse General Counsel Chattanooga, TN 37402 i
Tennessee Valley Authority ET 11H 400 West Summit Hill Drive i
Knoxville, TN 37902 Mr. P. P. Carier, Manager Corporate Licensing Tennessee Valley Authority 4G Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ralph H. Shell Site Licensing Manager Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37379 9
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