ML041700089
| ML041700089 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/21/2004 |
| From: | Sean Peters NRC/NRR/DLPM/LPD2 |
| To: | Jamil D Duke Energy Corp |
| Peters S, NRR/DLPM, 415-1842 | |
| Shared Package | |
| ML041750108 | List: |
| References | |
| TAC MC1166, TAC MC1167 | |
| Download: ML041700089 (15) | |
Text
June 21, 2004 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MC1166 AND MC1167)
Dear Mr. Jamil:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 215 to Renewed Facility Operating License NPF-35 and Amendment No. 209 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 15, 2003.
The amendments revise TS 3.9.2, Nuclear Instrumentation, to delete the requirement for the Boron Dilution Mitigation System automatic valve actuations and makeup water pump trip during Mode 6. Additionally, the amendments add a new TS 3.97, Unborated Water Source Isolation Valves, to preclude a boron dilution event during Mode 6. Combined, these changes would facilitate preventive and corrective maintenance on the volume control tank valves, refueling water storage tank valves, and their respective power supplies.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 215 to NPF-35
- 2. Amendment No. 209 to NPF-52
- 3. Safety Evaluation cc w/encls: See next page
June 21, 2004 Mr. D. M. Jamil Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MC1166 AND MC1667)
Dear Mr. Jamil:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 215 to Renewed Facility Operating License NPF-35 and Amendment No. 209 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October0.
15, 2003.
The amendments revise TS 3.9.2, Nuclear Instrumentation, to delete the requirement for the Boron Dilution Mitigation System automatic valve actuations and makeup water pump trip during Mode 6. Additionally, the amendments add a new TS 3.97, Unborated Water Source Isolation Valves, to preclude a boron dilution event during Mode 6. Combined, these changes would facilitate preventive and corrective maintenance on the volume control tank valves, refueling water storage tank valves, and their respective power supplies.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 DISTRIBUTION:
PUBLIC TBoyce
Enclosures:
PDII-1 R/F DLPMDPR
- 1. Amendment No. 215 to NPF-35 RidsRgn2MailCenter (RHaag) KDesai
- 2. Amendment No. 209 to NPF-52 RidsNrrDlpmLpdii (EHackett)
- 3. Safety Evaluation RidsNrrDlpmLpdii1 (SCoffin/JNakoski)
DClarke/CHawes cc w/encls: See next page RidsOgcRp RidsAcrsAcnwMailCenter Package No.: ML041750108 TS: ML041750292 Adams Accession No.: ML041700089 NRR-058 OFFICE PDII-1/PM PDII-1/LA (A) SRXB/SC IROB/SC OGC PDII-1/SC (A)
NAME SPeters DClarke JUhle TBoyce GLongo CGratton for SCoffin DATE 6/2/04 6/2/04 6/2/04 6/7/04 6/16/04 6/17/04 OFFICIAL RECORD COPY
DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 215 Renewed License No. NPF-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility)
Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated October 15, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA Chis Gratton for/
Stephanie M. Coffin, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: June 21, 2004
DUKE ENERGY CORPORATION NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 209 Renewed License No. NPF-52
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility)
Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Corporation, acting for itself, North Carolina Municipal Power Agency No. 1 and Piedmont Municipal Power Agency (licensees), dated October 15, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 209, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA Chis Gratton for/
Stephanie M. Coffin, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: June 21, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 215 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 209 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert iii iii 3.9.2-1 3.9.2-1 3.9.2-2 3.9.2-2 3.9.2-3 ---------
3.9.7.1 B iii B iii B 3.9.2-1 B 3.9.2-1 B 3.9.2-2 B 3.9.2-2 B 3.9.2-3 B 3.9-2-3 B 3.9.2-4 ---------
B 3.9.2-5 ---------
B. 3.9.7.1
B. 3.9.7.2
B. 3.9.7.3
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 215 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 209 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CORPORATION, ET AL.
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated October 15, 2003, Duke Energy Corporation (Duke the licensee), submitted a request for changes to the Catawba Nuclear Station, Units 1 and 2 (Catawba) Technical Specifications (TSs). The requested changes would revise TS 3.9.2, Nuclear Instrumentation, to delete the requirement for the Boron Dilution Mitigation System (BDMS) automatic valve actuations and makeup water pump trip during Mode 6. Additionally, the proposed changes would add a new TS 3.9.7, Unborated Water Source Isolation Valves, to preclude a boron dilution event during Mode 6. Combined, these changes would facilitate preventative and corrective maintenance on the volume control tank (VCT) valves, refueling water storage tanks (RWST) valves, and their respective power supplies.
2.0 REGULATORY EVALUATION
The BDMS detects and mitigates a boron dilution event during plant operation. It consists of two U-235 fission chambers located at 90 and 270 degrees around the reactor vessel. The chamber output pulses are amplified for control board indication and input to the Shutdown Margin Monitor. The Shutdown Margin Monitor provides a display of the neutron count rate and calculates the high-flux alarm setpoint. When the flux indication reaches the alarm septoint, the values aligning the charging pump suction to the RWST will open, the VCT discharge valves will close, the reactor water makeup pumps will trip, and an alarm will annunciate in the control room. The alarm will alert the control room operator concerning unexpected changes in the core reactivity potentially resulting from a boron dilution event. Appropriate operator action would then follow to mitigate a core reactivity event.
As an alternative, two source range neutron flux monitors, located at 0 and 180 degrees around the reactor vessel, provide input into the Reactor Protection System. The licensee proposes to use the monitors to replace the BDMS function during Mode 6 operation. The BDMS and the source range neutron flux monitors are independent systems used to mitigate boron dilution events during Mode 6.
The Commissions regulatory requirements related to the contents of TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Part 50.36, Technical Specifications.
As stated in 10 CFR 50.36(c)(2)(ii)(C), Criteron 3" states that structures, systems or components that are part of the primary success path and that function to mitigate a design-basis accident or transient must have a TS limiting conditions for operation (LCO). The BDMS functions to mitigate a boron dilution transient, and therefore, it is included in the TS.
To support the proposed amendment, the licensee used the guidance in NUREG-1431, Rev. 2, Standard Technical Specifications Westinghouse Plants, and NUREG-0800, Standard Review Plan, Section 15.4.6, Chemical and Volume Control System Malfunction that Results in a Decrease in Boron Concentration in the Reactor Coolant (PWR). The licensee also complies with the NRC Generic Letter (GL) 85-05, Inadvertent Boron Dilution Events. The NRC staff used the above guidance to evaluate the licensees amendment request.
3.0 TECHNICAL EVALUATION
By letter dated October 15, 2003, Duke proposed to add a new TS 3.9.7 and delete the BDMS automatic actuation requirements during Mode 6. These proposed changes would rely on plant configuration control to preclude inadvertent boron dilution events, in lieu of automatic equipment operation for accident mitigation. These changes would delete the requirement for an audible alarm for source range monitors (SRMs) during Mode 6, as well as revise TS 3.9.2 to be consistent with NUREG-1431, Rev. 2, dated April 2001.
The current TSs 3.5.2, ECCS [Emergency Core Cooling System] - Operating, 3.5.3, ECCS-Shutdown, 3.3.9, Boron Dilution Mitigation System, and 3.9.2, Nuclear Instrumentation, require VCT valves, RWST valves, and their respective power supplies to be operable during various modes of operation. TSs 3.5.2 and 3.5.3 require operability of these valves for ECCS operation during Modes 1, 2, 3 and 4. TS 3.3.9 requires operability of these valves as part of the BDMS during Modes 3, 4 and 5. Furthermore, TS 3.9.2 requires operability of these valves during Mode 6. The overlapping TS requirements for Modes 1 through 6 do not provide an opportunity to remove the valves from service for maintenance activities. This proposal will facilitate outage planning and preventive maintenance activities of the valves during Mode 6.
To facilitate this maintenance, the licensee proposed the following TS changes during Mode 6 operation:
The licensee proposed to add a new TS 3.9.7 to prevent a boron dilution event during Mode 6.
This TS would require Duke to secure in the closed position isolation valves for the reactor makeup water sources containing unborated water that are connected to the reactor coolant system (RCS). One of the following three groups of valves would be required to be secured in a closed position to achieve isolation of unborated water sources.
(1) NV-230, reactor makeup water pump discharge to the chemical volume and control system (2) NV-181A, NV-187, NV-231, and NV-244 (3) NV-175, NV-187, NV-231, and NV-244 These three different groups of valves provide operational flexibility if one or more valves are unavailable for isolation. The first option has an advantage of fewer valves under administrative control and it is easier to implement. The second and third series of valves would isolate the valves downstream of valve NV-230 and would allow operators to provide makeup to the
RWST. The NRC staff finds the isolation of the unborated water sources during Mode 6 would preclude a boron dilution event during Mode 6. Therefore, the changes are acceptable.
The licensee proposed adding Condition A to TS 3.9.7 to require actions when one or more of the isolation valves are not secured in a closed position. If one or more of these valves are not secured, the licensee must immediately suspend core alterations, immediately initiate actions to secure the valve in a closed position, and within four hours verify that the boron concentration of the reactor coolant is within the limits specified within the Core Operating Limits Report (COLR). The licensee also added a note to require boron concentration verification whenever Condition A is entered.
The immediate suspension of the core alterations and the immediate actions to secure the isolation valve in the closed position are conservative actions that help to prevent conditions that would contribute to an inadvertent boron dilution. The verification of boron concentration is necessary because of the potential to have diluted the reactor coolant. A completion time of four hours is sufficient to collect and analyze the boron samples and is a short enough time based upon the importance of meeting boron concentration limits. Furthermore, these actions and completion times are consistent with NUREG-1431, Rev. 2. Therefore, the NRC staff finds them acceptable.
For the new TS 3.9.7, the licensee inserted a note that separate condition entry would be allowed for each unborated water source isolation valve. Based upon the fact that Condition A has the same requirements for one valve as it does for multiple valves, separate entry has no effect on the actions required to be taken. Furthermore, this note is consistent with NUREG-1431, Rev. 2. Therefore, the NRC staff finds the addition of the note acceptable.
The licensee proposed adding Surveillance Requirement (SR) 3.9.7.1, which every 31 days, would require verification that each valve that isolates unborated water sources is secured in the closed position. This surveillance would be demonstrated through system walkdowns and the completion time is reasonable considering that administrative controls will ensure that valve opening is an unlikely possibility. Additionally, this SR and its associated completion time is consistent with NUREG-1431, Rev. 2. Therefore, the NRC staff finds the SR acceptable.
The licensee proposed adding a new requirement for the operability of the source range neutron flux monitors in TS 3.9.2. This new LCO would require that two source range neutron flux monitors be operable during Mode 6 to monitor core reactivity. Located at 0 and 180 degrees around the reactor vessel, these monitors would provide indication to the reactor operators in the event of unexpected changes in core reactivity such as with a boron dilution event. Since these monitors provide a signal to alert the reactor operators in the event of an unplanned boron dilution, this addition meets Criterion 3 of 10 CFR 50.36(c)(2)(ii). Therefore, the NRC staff finds it acceptable.
For Condition A, when one of the neutron flux monitors is inoperable, the proposed TS requires the immediate suspension of core alterations and the immediate suspension of operations that would cause the introduction of coolant into the RCS with a boron concentration less than that required to meet the boron concentration limits. These immediate actions are conservative actions that help to prevent conditions that would contribute to an inadvertent boron dilution.
Furthermore, these actions and completion times are consistent with NUREG-1431, Rev. 2.
Therefore, the NRC staff finds them acceptable.
For Condition B, when both neutron flux monitors are inoperable, the proposed TS requires taking actions immediately to restore one inoperable monitor. It also requires verification that the boron concentration is within the limits of the COLR once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The immediate action is a conservative action to restore indication. Also, the verification of boron concentration is necessary because the loss of indication. A completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient to collect and analyze the boron samples and is sufficient because of the low probability of boron dilution during this time. Furthermore, these actions and completion times are consistent with NUREG-1431, Rev. 2. Therefore, the NRC staff finds them acceptable.
The licensee added an SR to perform a channel check every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on the source range neutron flux monitors. This check is a comparison of the parameter indicated on one channel to a similar parameter on the other channel. The licensee previously performed this check every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in TS 3.9.2 whenever the SRMs were used to provide indication in the event that one or both trains of the BDMS were inoperable. Since the licensee will be using these monitors for indication and since the time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the channel check is consistent with previous requirements, the NRC staff finds this addition acceptable. Additionally, this SR and its completion time is consistent with NUREG-1431, Rev. 2.
In addition, the licensee added an SR to perform a channel calibration every 18-months on the SRMs with a note that the neutron detectors themselves are excluded from the channel calibration requirements. The channel calibration for the Nuclear Instrumentation System SRMs consists of obtaining the detector plateau and pulse height discriminator curves, evaluating those curves, and comparing the curves to the manufacturers data. The channel calibration for the Gamma-Metrics SRMs consists of verifying that the channels respond correctly to test inputs with the necessary range and accuracy. Calibration of the source range channels is important to ensure proper functionality, and the 18-month calibration interval is required because the surveillance must be performed under the conditions that apply during an outage. Additionally, this SR and its completion time is consistent with NUREG-1431, Rev. 2.
Therefore, the NRC staff finds this addition acceptable.
The addition of new TS 3.9.7 (isolating the possible dilution pathways) and the addition of new requirements for neutron flux monitors (identification of inadvertent dilution) eliminate the need for current TS 3.9.2 requirements for two BDMS trains to be operable in Mode 6. Therefore, the licensee proposed deleting these requirements. As part of this deletion, the licensee proposed removing the LCO that requires two trains of BDMS to be operable, the required actions for BDMS inoperabiltiy, and the SRs associated with the BDMS. These SRs include the requirements to perform a channel operability test on the BDMS (SR 3.9.2.2), the requirements to verify the automatic valve movement and reactor makeup water pumps stopping upon the receipt of an actuation signal (SR 3.9.2.3), and the requirements to verify the reactor makeup water pump flow rates (SR 3.9.2.6). In addition, the licensee proposed removing the requirements to perform a channel check and a channel operability test on the source range neutron flux monitors (SRs 3.9.2.4 and 3.9.2.5). The licensee adequately captured the SRM testing requirements in the proposed TS 3.9.2.
Because the proposed TSs 3.9.2 and 3.9.7 provide adequate protection from a boron dilution event in Mode 6, the NRC staff finds the above changes to the TS 3.9.2 BDMS requirements in Mode 6 to be acceptable. Additionally, these changes are consistent with NUREG-1431, Rev. 2.
The NRC staff has reviewed the proposed TS changes and has found that they will control the plant configuration to preclude inadvert boron dilution events and will provide an opportunity to perform preventive and corrective maintenance of VCT and RWST valves and their respective power supplies during Mode 6 operation. The plant will no longer rely on automatic equipment operation for boron dilution accident mitigation in Mode 6. The NRC staff finds these changes conform to GL 85-05, NUREG-1431, Rev. 2 and NUREG-800, Section 15.4.6 guidelines.
Therefore, the NRC staff concludes that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change SRs.
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 offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 12366). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 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 Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Kulin Desai, NRR Sean Peters, NRR Date: June 21, 2004
Catawba Nuclear Station cc:
Lee Keller, Manager North Carolina Electric Membership Corp.
Regulatory Compliance P. O. Box 27306 Duke Energy Corporation Raleigh, North Carolina 27611 4800 Concord Road York, South Carolina 29745 Senior Resident Inspector U. S. Nuclear Regulatory Commission Ms. Lisa F. Vaughn 4830 Concord Road Duke Energy Corporation York, South Carolina 29745 Mail Code - PB05E 422 South Church Street Henry Porter, Assistant Director P.O. Box 1244 Division of Waste Management Charlotte, North Carolina 28201-1244 Bureau of Land and Waste Management Dept. of Health and Environmental Control Anne Cottingham, Esquire 2600 Bull Street Winston and Strawn Columbia, South Carolina 29201-1708 1400 L Street, NW Washington, DC 20005 Mr. R. L. Gill, Jr., Manager Nuclear Regulatory Issues North Carolina Municipal Power and Industry Affairs Agency Number 1 Duke Energy Corporation 1427 Meadowwood Boulevard 526 South Church Street P. O. Box 29513 Mail Stop EC05P Raleigh, North Carolina 27626 Charlotte, North Carolina 28202 County Manager of York County Saluda River Electric York County Courthouse P. O. Box 929 York, South Carolina 29745 Laurens, South Carolina 29360 Piedmont Municipal Power Agency Mr. Peter R. Harden, IV, Vice President 121 Village Drive Customer Relations and Sales Greer, South Carolina 29651 Westinghouse Electric Company 6000 Fairview Road Ms. Karen E. Long 12th Floor Assistant Attorney General Charlotte, North Carolina 28210 North Carolina Department of Justice P. O. Box 629 Mary Olson Raleigh, North Carolina 27602 Director of the Southeast Office Nuclear Information and Resource Service NCEM REP Program Manager 729 Haywood Road, 1-A 4713 Mail Service Center P. O. Box 7586 Raleigh, North Carolina 27699-4713 Asheville, North Carolina 28802
Catawba Nuclear Station cc:
Mr. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Richard M. Fry, Director Division of Radiation Protection N. C. Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721