ML20217D272
| ML20217D272 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/12/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217D270 | List: |
| References | |
| NUDOCS 9910150098 | |
| Download: ML20217D272 (4) | |
Text
n gA Ef C
[e li UNITED STATES j
j NUCLEAR REGULATORY COMMISSION
'C WASHINGTON, D.C. 20555 4 001
/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 239 TO FACILITY OPERATING LICENSE NO. DPR-79 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT. UNITS 1 AND 2 POCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
By application dated March 2,1999, the Tennessee Valley Authority (TVA, the licensee) proposed an amendment to the Operating Licenses for Sequoyah Nuclear Plant (SON) Units 1 i
and 2. The requested changes would eliminate the Independent Safety Engineering Group (ISEG) from the License Condition section (2.C) of each license. This action would be consistent with the action taken on August 26,1999, also originally requested by the TVA letter dated March 2,1999, to eliminate the requirement for independent technical reviews and ISEG from the TVA Nuclear Quality Assurance Plan.
2.0 EVALUATION The ISEG concept was developed as part of the U.S. Nuclear Regulatory Commission (NRC)
Action Plan (NUREG-0660) to implement the various recommendations of official studies and investigations of the 1979 accident at Three Mile Island Unit 2. The ISEG was created to improve site organizations by providing on-site technical support and continuous evaluation and feedback of lessons learned from operating experience. The ISEG requirements established by NUREG-0737, item 1.B.1.2, apply to all operating licenses granted after June 26,1980. SON Unit 1 was granted an operating license on September 17,1980. SON Unit 2 was granted an operating license on September 15,1981. The ISEG functions, established by NUREG-0737, are to:
Examine plant operating characteristics, NRC issuances, Licensing Information Service advisories, and other appropriate sources of plant design and operating experience for areas for improving p! ant safety.
Maintain surveillance of plant operations and maintenance activihs to provide independent verificat.bn that these activities are performed correctly and that human errors are reduced as far as practicable.
I Perform independent reviews and audits of plant activities including maintenance, modifications, operational problems, and operational analysis, and aid in the establishment of programmatic requirements for plant activities.
9910150098 991012 PDR ADOCK 05000327 p
PDR L
7-
-0 2-The ISEG function is one of oversight only. The proposed amendment does not directly make changes to any system, structure or component (SSC). The change would not negatively impact the ability of an SSC to perform its safety function or negatively impact the ability of licensee personnel to ensure the SSC is capable of performing its intended safety function. The function that ISEG was intended to provide is now an everyday aspect of WA's operations. A number of improvements in TVA's operating environment, industry initiatives, and some rulemaking since 1979 have superseded the ISEG functions. Collectively, they provide TVA's rationale as to why it is appropriate to eliminate ISEG as a specific SON License Condition.
These operating improvements include the following:
The Design Engineering organization has been relocated to the SON site. This organization provides technicalleadership for TVA plants. Site Design Engineering functions include the development and maintenance of the plant design bases, implementation and maintenance of configuration management programs, and development of technically-correct, innovative, and cost-effective solutions to plant problems.
Site System Engineering is now available for everyday consultation and is an integral e
part of the plant team. They readily monitor performance and resolve performance problems. They provide technicalleadership through optimization of system performance and reliability, quality management for assigned engineering programs, and proactive identification and resolution of plant issues. Additionally, they provide technical assistance to the plant Operations and Maintenance organizations, TVA's Design Bases Reconciliation Programs have positioned TVA ahead of recent e
industry probicms associated with conflicting and inadequate design bases at some facilities. WA has kept pace with the latest developments in the industry and NRC regarding design bases and configuration management programs.
{
System Status Reports provide a summary analysis of system performance that focuses e
management attention on systems not meeting goals cy indicating adverse trends and problem areas. TVA's program for monitoring maintenance complies with Title 10, Code j
of Federal Reaulations (10 CFR), Section 50.65 and employs Nuclear Management and Resource Council (NUMARC) 93-01, " Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."
TVA's Operating Experience Review Program has matured into a strong programmatic element under the Institute of Nuclear Power Operations guidance.
The Training Rule was issued as 10 CFR 50.120, " Training and Qualification of Nuclear e
Power Plant Personnel," after ISEG requirements were first created. It requires licensees to establish, implement, and maintain a training program derived from a systematic approach, TVA has established a probabilistic safety analysis for each cperating unit, incorporated o
risk assessments into work activities, and has obtained computer-based software tools
l i
F that enhance risk oversight. Risk assessments are performed for shutdown, outage, and online work activities.
Self assessments are conducted by line organizations as a tool to monitor and improve overall performance. These assessments are self-critical evaluations of specific programs or processes, both technical and administrative, and typically result in the identification of findings or areas for improvement.
Quarterly site trend reports are published with input from Problem Evaluation Reports, Self Assessment Reports, Nuclear Assurance (NA) Audit Reports and assessment l
results, and external assessment results. These reports are consolidated into a single
" Level i Trend Report."
NA functional area audits focus on selected systems, functions or components and do a more thorough job of assessing program performance. Typical functional area audits review prior line self assessments, NA oversight, industry trends, corrective actions, institute of Nuclear Power Operations performance criteria, NRC inspection modules, lessons learned from previous audits and assessments, and documentation requirements.
TVA's senior management meets annually to set strategic business performance goals.
e Performance indicators are readily available to management and employees through periodic trending reports posted on the TVA Network, Newsletters, and bulletin board postings.
TVA has developed, and is in the process of implementing, the Excellence in e
Performance Program. This program reduces human performance errors through routine employee self evaluations, supervisor observation and coaching, and process improvements.
i The NA Evaluations and Analysis Group adds senior-assessment leadership and e
technical expertise to the Quality Assessment Program. This corporate-based group manages the programs associated with assessing Operations, Engineering / Technical Support, Modifications, Maintenance, Security, Chemistry, Emergency Preparedness, and Radiological Control Programs Met of the review functions performed by this group are identical to the review functions out!ined for the ISEG.
TVA has established a work environment where, (1) people identify problems, (2) the entire team focuses on solutions, and (3) TVA is increasingly self-critical with high expectations for performance. These developments are integral to a strong management culture that emphasizes system performance, the right people, program goals, assessment of performance aqains+ goals, and actions to correct deviations. These developments collectively assist TVA operating plants in resolving day-to-day operational problems and improve overall quality and safety. Therefore, the NRC staff agrees that ISEG's composition has become burdensome and redundant, and that it is appropriate to eliminate the ISEG and refocus these resources on more beneficial activities. The staff, therefore, agrees with TVA's proposed deletion of the Operating License Conditions that require maintenance of an ISEG.
I L
p 1
4
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.
l
4.0 ENVIRONMENTAL CONSIDERATION
l The amendments change recordkeeping, reporting, or administrative procedures or i requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion
. set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
l
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.
I Principal Contributor: Ronald W. Hernan, NRR 1
Date: October 12, 1999 I
I I
I j
i l.
i.
r p * *%
t t
f n
UNITED STATES NUCLEAR REGULATORY COMMISSION of WASHINGTON, D.C. 20555 4 m
,,.... 4 l
August 26,1999
)
Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
SAFETY EVALUATION OF ELIMINATION OF INDEPENDENT SAFETY ENGINEERING GROUP - BROWNS FERRY, WATTS BAR AND SEQUOYAH NUCLEAR PLANTS (TAC NOS. MA5105, MA5106, MA5107, MA5054, MA5055, MA5056)
Dear Mr. Scalice:
By letter dated March 2,1999, supplemented by letters dated June 29 and August 25,1999, the Tennessee Valley Authonty (TVA or licensee) submitted a request to eliminate the requirement for independent technical reviews from the Nuclear Quality Assurance (NOA) Plan (TVA-NQA-PLN89A). This function implements the guidance of NUREG-0737 for establishment of an independent safety engineering group (ISEG) at nuclear sites.
The submittals document the evolution of the licensee's site processes and organizations since i
creation of the ISEG organizations in the early 1980s. Since that time, the licensee's operating expenence program and corrective action programs have matured, design organizations have been relocated to each of the licensee's nuclear sites, and site system engineering organizations have been established. These processes and organizations, supplemented by other processes described in the submittals, effectively duplicate the independent technical review function.
The licensee proposes to transfer the responsibility for independent technical review to the site engineering organizations. The licensee has committed to incorporate changes reflecting this transfer of responsibility into the next updates to its NQA Plan and into its organizational topical (WA-NPODP9), which is incorporated by reference into its quality assurance program plan.
ENCLOSURE 4 Y O&)j h O f' f
i
r l
J. A. Scalice 2-Because the ISEG functions have become redundant, in that they are accomplished by alternate means, its resources can be redirected toward more beneficial activities without reducing the ability of the licensed facilities to operate in a safe mar ner. The proposed tr&nsfer of responsibility for independent technical reviews to the engineering organizations is acceptable.
Sincerely, l
0 erbert N. Berkow,' Director Project Directorate il Division of Licensing Project Management Office of Nuclear Ree.or Regulation Docket Nos. 50 390 50-259 50-260 50-296 50-327 50-328 Enclosure. Safety Evaluation cc w/ encl: See next page i
f e nc 8t UNITED STATES y*
g, NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D.C. 20555 0001
.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION NUCLEAR QUALITY ASSURANCE PLAN (TVA-NOA-PLN89-A)
ELIMINATION OF THE INDEPENDENT SAFETY ENGINEERING GROUPS TENNESSEE VALLEY AUTHORITY BROWNS FERRY. SEQUOYAH. AND WATTS BAR NUCLEAR PLANTS DOCKET NOS. 50-259. 50-260. 50-296. 50-327. 50-328. 50-390
1.0 INTRODUCTION
By letter dated March 2,1999 (Ref.1), as supplemented by letters dated June 29 and August 25,1999, the Tennessee Valley Authority (TVA, the licensee) submitted a request proposing to eliminate the independent technical review function, which is currently the responsibility of Nuclear Licensing. The term " independent technical review," as used by the licensee, is synonymous with the term " independent safety engineering" (ISE) as described by NUREG-0737, item 1.B.1.2.
The submittal documents the evolution of the licensee's site processes and organizations since creation of the ISE Group (ISEG) organizations in the early 1980s. Since that time, the licensee's operating experience program and corrective action programs have matured, design organizations have been relocated to each site, and system engineering organizations have been established. These engineering organizations are responsible for review of all changes affecting the design basis, monitoring the performance of plant equipment, evaluating plant events such as reactor trips, plant transients and adverse equipment trends, and providing technical assistance to the operations and maintenance staffs.
Coupled with other established site processes described in the submittal, the licensee concludes that the ISEG organizations are redundant and should be redirected toward more beneficial activities.
This safety evaluation addresses the acceptability of the licensee's attemate means of satisfying the NUREG-0737 ISEG guidance.
- 2. BACKGROUND 2.1 Independent Safety Enaineerina Group The ISEG concept was developed as part of the U.S. Nuclear Regulatory Commis::en (NRC)
Action Plan (NUREG-0660) to implement the various recommendations of official studies and investigations of the 1979 accident at Three Mile Island (TMI) Unit 2. The ISEG was created to
% O h i l D.3 I k/?[
l l
l l
improve site organizations by providing on-site technical support and continuous evaluation and feedback of lessons learned from operating experience. The ISEG requirements established by NUREG-0737, item 1.B.1.2, apply to all operating licenses granted after June 26,1980.
The ISEG functions, established by NUREG-0737, are to:
- 1. Examine plant operating characteristics, NRC issuances, Licensing information Service advisories, and other appropriate sources of plant design and operating experience for areas for improving plant safety.
- 2. Maintain surveillance of plant operations and maintenance activities to provide independent verification that these activities are performed correctly and that human errors are reduced as far as practicable.
Perform independent reviews and audits of plant activities including maintenance, e
modifications, operational problems, and operational analysis, and aid in the establishment of programmatic requirements for plant activities.
It is noted that NUREG-0737 states clearly that the term " audits" is not to be interpreted in the formal sense of the audit program described by Section 4.5 of American National Standards Institute (ANSI) N18.7-1976 (Ref. 2). Further clarification is provided by the improved Standard Technical Specifications (Ref. 3,4) which drop the term " audit" from the scope of technical review responsibilities.
2.2 Imorovements in On-Site Technical Support Since TMI The licensee's submittal provides background information on improvements in providing on-site technical support since the creation of the ISEG organizations.
In accordance with the guidance of NUREG-0737, Item I.C.5, the licensee established an operating experience program at about the same time that the ISEG organizations were created.
The operating experience program evaluates and distributes in-house and industry information to appropriate corporate and site personnel for review. Recommendations resulting from these reviews are implemented to improve safety and reliability, in the 1980s, design engineering organizations were relocated to each of the sites. During this period, design basis issues were resolved through design basis reconstitution programs completed prior to restart of the Sequoyah units in 1988 and Browns Ferry Units 2 and 3 in the following decade. A similar design verification effort was completed for Watts Bar Unit 1 prior to i
obtaining a full-power operating license in 1996.
Also during the 1980s, system engineering orlani7atione were.4tetlished at each site with the responsibility to optimize system performance and reliability and to prc, le technical assistance to the operations and maintenance organizations.
The licensee's corrective action program contains the essential process elements of problem reporting, root-cause analysis, and corrective action. Oversight committees, comprised of site managers at least as senior as members of the Plant Operations Review Committee, are
y
.a established at each site. The submittal states that these committees have been effective in maintaining the quality, integrity, and visibility of the site corrective action programs.
The submittal concludes that the above elements: (1) a mature operating experience program, (2) an effective corrective action program, and (3) site design and systems engineering organizations, supplemented by other processes and programs described in the submittal, satisfy the intent and guidance of NUREG-0737, item 1.B.1.2.
- 13. EVALUATION This evaluation is performed in accordance with the guidance of NUREG-0737, the Improved Standard Technical Specifications, and the applicable acceptance criteria of NUREG-0800 (Ref.
5), Chapter 13.4, " Operational Review."
3.1 - Functions / Responsibilities
~The staff position with regard to tSEG responsibilities is provided in the improved Standard Technical Specifications as encompassing:
Plant operating characteristics, NRC issuances, industry advisories, Licensee Event o
Reports, and other sources which may indicate areas for improving plant safety, e Plant operations' modifications, maintenance, and surveillance to independently verify that tnese activities are performed safely and correctly and that human errors are reduced as much as possible, Internal and external operational experience information that may indicate areas for e
improving plant safety.
Evaluation: The proposed ISEG alternative encompasses these responsibilities within the general responsibilities of the site engineering crganizations. ' These responsibilities include system performance monitoring, review of operating experience information, operability
' evaluations, and review'of changes to the technical specifications and the Final Safety Analysis Report that affect the design bases.
Design engineering organizations are responsible for maintaining the design bases and design configuration for each plant. Design bases reconstitution and verification programs have been implemented for each site. Engineering activities include support for operations, maintenance and outage activities and support for outage planning and execution.
System engineering organizations provide technical assistance to the plant maintenance and
. operations staffsc Through implementation of the Maintenance Rule, system engineers
. continuously collect equipment performance data and assess the data against performance goals. The licensee's corrective action program requires structured investigations and root
. cause analyses of adverse operational characteristics such as reactor trips, significant events, and negative trends.
The responsibilities of the site engineering organizations, as described in the submittal, meet the functional guidelines of NUREG-0737, item 1.B.1.2.
7 4
3.2 Independence NUREG-0737 states that ISEG must be independent of the operating organization. The ISEG organization should report offsite to a corporate official who holds a high-level, technically-oriented position that is not in the management chain for power production.
Evaluation. The proposed ISEG alternative provides technical expertise by on-sne engineering staffs. These engineering staffs report offsite to the Chief Engineer, a high-level corporate position that is not in the management chain for power production. The proposed alternative satisfies the NUREG 0737 guidance concerning organizationalindependence.
. 3.3 Composition NUREG-0737 describes the ISEG organization as comprised of a minimum of five dedicated, full-time engineers.
. Evaluation: 'The staff position regarding the composition of the ISEG organization has evolved, such that the staff has allowed and encouraged the integration of the ISEG function into a cohesive program that provides senior level management with an assessment of facility operation and recommendations to improve nuclear safety and plant reliability. A precedent for deletion of the composition requirement was established for Seabrook (Ref. 6), by an amendment issued on February 14,1995. Deletion of the specific composition requirement in the proposed ISEG alternative is consistent with the current staff position and is acceptable.
3.4 Personnel Qualifications The licentee follows the guidance of Regulatory Guide 1.8, Revision 2, " Qualification and Training of Personnel for Nuclear Power Plants," for engineering support personnel. The licensee's policy, implemented through position descriptions, is to staff the site engineering organizations with experienced engineers having, as a minimum, bachelor's degrees in eng.neering.
The licensee is a member of the National Academy for Nuclear Training, which assists members in developing, implementing and maintaining performance-based training programs and evaluates the quality and effectiveness of these programs. The lic':nns's implementation of the accredited Engineering Support Personnel training program is in compliance with 10 CFR 50.120, " Training Rule."
Evaluation: Qualification requirements for personnel performing the independent technical review function satisfy the guidance of NUREG-0737, Item l.B.1.2.
3.5 Reoortt Quarterly trend reports, which identify plant reliability issues and provide a summary of plant 4
performance, are submitted to the Executive Vice President and Chef Nuclear Officer. Input for i
these reports is prepared by system engineers, who collect equipment performance data and examine the data against established performance goals, in accordance with the Maintenance Rule (10 CFR 50.65).
l I
I L
5-Evaluation: NUREG-0737 guidance states that detailed recommendations should be provided to corporate management for such things as procedures, equipment modifications or other means ofimproving nuclear safety and reliability. These reports, coupled with a strong corrective action program, provide an acceptable method of implementing the NUREG-0737 guidance.
3.6 Licensee Commitments The licensee has committed, in its letters of June 29 and August 25,1999, to include in the next updates of its quality assurance plan (TVA-NOA-PLN89-A) and organization description (TVA-NPOD89) the information provided in support of the proposed alternate means of satisfying the NUREG-0737 ISEG guidelines.
The licensee's quality assurance plan incorporates, by reference, the TVA Nuclear Organization Desenption, TVA-NPOD89, which describes responsibilities for management, technical support, i
and operating organizations that meet the " content" guidance of Regu!atory Guide 1.70.
Revision 3.
The next update of TVA-NPOD89 willinclude the responsibilities of the site engineering organizations, which satisfy the ISEG functions of NUREG-0737, item I.B.1.2. These responsibilities include (1) system health monitoring, (2) implementation of the Maintenance Rule, and (3) evaluation of industry operating experience. TVA-NPOD89 will also contain the explicit requirement to submit quarterly Level i Trend Reports, which provide system performance and status, to the Executive Vice President and Chief Nuclear Officer.
The next update of TVA-NOA-PLN89-A will transfer the responsibility for independent technical reviews from the Nuclear Licensing Manager (Section 4.1.4.D) to the Vice President, Engineering and Technical Services.
4.0 CONCLUSION
S NUREG-0737, Item 1.B.1.2, provides guidance for establishment of an independent safety engineering function to provide increased on-site technical support and evaluation and feedback of lessons learned from operating experience. Since creation of ISEG organizations in the early 1980s, other site organizations and processes have matured such that they essentially implement the ISEG functions. These processes include a mature operating experience program and an effective corrective action program. Site engineering comprised of design engineering and system engineering, effectively incorporate and, thus, duplicate the ISEG functions of NUREG-0737, item I.B.1.2.
Because the ISEG functions have become redundant in that they are accomplished by alternate means, these resources can be redirected toward more beneficial activities without reducing the ability of the facilities to operate in a safe manner. The proposed transfer of responsibility for independent technical review from Nuclear Licensing to Engineering and elimination of the formallSEG organization are acceptable.'
Principal Contributor: K. Heck, NRR Date: August 26,1999
p
,s
- 6-I 5.0' REFERENCES TVA Lett' r to N'RC, " Elimination of Independent Safety Engineering Group - Nuclear 1.
e
)
Quality Assurance Plan (TVA NOA-PLN89-A)," March 2,1999.
2.'
ANSI N18.7/ANS-3.2, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants," February 19,1976.
. 3.
NUREG-1431, " Standard Technical Specifications, Westinghouse Plants," Vol.1,
. Section 5.5.2, " Review and Audit," January 1991.
- 4. ~
NUREG-1433, " Standard Technical Specifications, General Electric Plants, BWR/4,"
l Vol.1, Section 5.5.2, " Review and Audit," January 1991.
5.
NUREG 0800, " Standard Review Plan for the Review of Safety Analysis Reports for i
Nuclear Power Plants," Chapter 13.4, " Operational Rev4w " June 1987.
6.
Amendment No. 35 to Facility Operating License NPF-86, Seabrook Station, Unit No.1, j
February 14,1995.
1 1
i 4
i 4'
3 Mr. J. A. Scalice Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT cc:
Mr. Karl W. Singer, Senior Vice President Mr. Pedro Salas, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Sequoyah Nuclear Plant GA Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37379 Mr. Jack A. Bailey Mr. D. L. Koehl, Plant Manager Vice President Sequoyah Nuclear Plant Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Soddy Daisy, TN 37379 1101 Market Street Chattanooga, TN 37402-2801 Mr. Melvin C. Shannon j
Senior Resident inspector j
Mr. Masoud Bajestani Sequoyah Nuclear Plant j
Site Vice President U.S. Nuclear Regulatory Commission i
Sequoyah Nuclear Plant 2600 Igou Ferry Road Tennessee Valley Authority Soddy Daisy, TN 37379 P.O. Box 2000 Soddy Daisy, TN 37379 Mr. Michael H. Mobley, Director TN Dept. of Environment & Conservation Division of Radiological Health i
General Counsel 3rd Floor, L and C Annex Tennessee Valley Authority 401 Church Street ET 10H Nashville, TN 37243-1532 400 West Sumrnit Hill Drive Knoxville, TN 37902 County Executive Hamilton County Courthouse Mr. N. C. Kazanas, General Manager Chattanooga, TN 37402-2801 Nuclear Assurance Tennessee Valley Authority SM Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
m o
M Mr. J. A. Scalice Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT cc:
Mr. Karl W. Singer, Senic,r Vice President Mr. Pedro Salas, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37379
. Mr. Jack A. Bailey Mr. D. L. Koehl, Plant Manager Vice President.
Sequoyah Nuclear Plant Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority.
P.O. Box 2000 6A Lookout Place Soddy Daisy, TN 37379
' 1101 Market Street Chattanooga, TN-37402-2801 Mr. Melvin C75hannon Senior Resident inspector Mr. Masoud Bajestani Sequoyah Nuclear Plant Site Vice President U.S. Nuclear Regulatory Commission
. Sequoyah Nuclear Plant 2600 Igou Ferry Road Tennessee Valley Authority Soddy Daisy, TN 37379 P.O. Box 2000 Soddy Daisy, TN 37379 Mr. Michael H. Mobley, Director TN Dept. of Environment & Conservation Division of Radiological Health General Counse1 3rd Floor, L and C Annex
-Tennessee Valley Authority 401 Church Street
. ET 10H Nashville, TN 37243-1532 i
400 West Summit Hill Drive Knoxville, TN 37902 County Executive Hamilton County Courthouse
! Mr. N. C. Kazanas, General Manager Chattanooga, TN 37402-2801 Nuclear Assurance Tennessee Valley Authority SM Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Mark J. Burzynski, Manager i
Nuclear Licensing
. Tennessee Valley Authority l; j 4X Blue Ridge 1101 Market Street
- Chattanooga, TN 37402-2801 b