ML022550559
| ML022550559 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Grand Gulf, Pilgrim, Arkansas Nuclear, River Bend, Vermont Yankee, Waterford, FitzPatrick  |
| Issue date: | 09/12/2002 |
| From: | Alexion T NRC/NRR/DLPM/LPD4 |
| To: | Kansler M Entergy Nuclear Operations |
| Alexion T W,NRR/DLPM,415-1326 | |
| References | |
| TAC MB3439, TAC MB3440, TAC MB3456, TAC MB3457, TAC MB3476, TAC MB3477, TAC MB3479, TAC MB3486, TAC MB3488, TAC MB3489, TAC MB5847, FOIA/PA-2011-0242, FOIA/PA-2011-0246, FOIA/PA-2011-0263 | |
| Download: ML022550559 (23) | |
Text
Mr. Michael R. Kansler September 12, 2002 Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue P.O. Box 5029 White Plains, NY 10601-5029
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2; GRAND GULF NUCLEAR STATION; INDIAN POINT NUCLEAR STATION, UNITS 1, 2 AND 3; JAMES A.
FITZPATRICK NUCLEAR POWER PLANT; PILGRIM NUCLEAR POWER STATION; RIVER BEND STATION; VERMONT YANKEE NUCLEAR POWER PLANT; AND WATERFORD STEAM ELECTRIC STATION, UNIT 3 -
EXEMPTION FROM THE REQUIREMENTS OF 10 CFR PART 20, SECTION 20.1003 DEFINITION OF TOTAL EFFECTIVE DOSE EQUIVALENT (TAC NOS. MB3456, MB3457, MB3488, MB3439, MB3440, MB3479, MB3489, MB3476, MB3477, MB5847, MB3486)
Dear Mr. Kansler:
The Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 20.1003, for the subject units.
This action is in response to your application dated July 20, 2001, as supplemented by letter dated June 13, 2002. By letter dated November 19, 2001, you adopted the application for Indian Point Nuclear Station, Units 1 and 2; and by letter dated August 7, 2002, you adopted the application for Vermont Yankee Nuclear Power Plant.
Your application requested an exemption from the 10 CFR 20.1003 definition of total effective dose equivalent (TEDE), which is the sum of the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). The exemption changes the definition of TEDE to mean the sum of the effective dose equivalent or the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-313, 368, 416, 003, 247, 286, 333, 293, 458, 271, and 382
Enclosure:
Exemption cc w/enclosure: See next page A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-313, 368, 416, 003, 247, 286, 333, 293, 458, 271, and 382
Enclosure:
Exemption cc w/enclosure: See next page DISTRIBUTION:
PUBLIC RidsNrrPMPMilano PDIV-1 r/f RidsNrrPMGVissing RidsOgcRp RidsNrrPMTTate RidsAcrsAcnwMailCenter RidsNrrPMMWebb RidsNrrDlpmLpdi (SRichards)
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RidsNrrLATClark RidsNrrDlpmLpdi2 (JClifford)
RidsNrrLADJohnson RidsOgcRp RidsRgn4MailCenter (K. Brockman)
RidsAcrsAcnwMailCenter RPedersen GHill (22)
LBerry TBergman, EDO RI SMorris, EDO RIV RidsNrrPMTAlexion RidsNrrPMWReckley RidsNrrPMDJaffe Ri dsNrrPMBVaidya RidsNrrPMJMinns Accession No.: ML022550559
- parallel concurrence, **see previous concurrence OFFICE PDIV-1/PM PDIV-1/LA IEHB/SC PDIV-1/SC OGC IEHB/BC DIPM/D NAME TAlexion:
DJohnson KGibson*
RGramm CBray**
TQuay BBoger DATE 09/06/02 9/6/02 08/15/02 9/6/02 08/27/02 9/11/02 9/12/02 OFFICIAL RECORD COPY
7590-01-P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ENTERGY OPERATIONS, INC.
ENTERGY NUCLEAR OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2; GRAND GULF NUCLEAR STATION; INDIAN POINT NUCLEAR STATION, UNITS 1, 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; PILGRIM NUCLEAR POWER STATION; RIVER BEND STATION; VERMONT YANKEE NUCLEAR POWER PLANT; AND WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NOS. 50-313, 368, 416, 003, 247, 286, 333, 293, 458, 271, and 382 EXEMPTION
1.0 BACKGROUND
Entergy Operations, Inc. and Entergy Nuclear Operations, Inc. (the licensees) are the holders of Renewed Facility Operating License No. DPR-51; Facility Operating License Nos. NPF-6 and NPF-29; Provisional Operating License No. DPR-5; and Facility Operating License Nos. DPR-26, DPR-64, DPR-59, DPR-35, NPF-47, DPR-28, and NPF-38, which authorize operation of Arkansas Nuclear One, Units 1 and 2; Grand Gulf Nuclear Station; Indian Point Nuclear Station, Units 1, 2 and 3; James A. Fitzpatrick Nuclear Power Plant; Pilgrim Nuclear Power Station; River Bend Station; Vermont Yankee Nuclear Power Plant; and Waterford Steam Electric Station, Unit 3. The licenses provide, among other things, that the facilities are subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect.
The facilities consist of pressurized and boiling water reactors located in Pope County, Arkansas; Claiborne County, Mississippi; Westchester County, New York; Oswego County, New York; Plymouth County, Massachusetts; West Felciana Parish, Louisiana; Windham County, Vermont; and Saint Charles Parish, Louisiana. (The operating authority of Provisional Operating License No. DPR-5 for Indian Point Nuclear Station, Unit 1, was revoked by Commission Order dated June 19, 1980).
2.0 REQUEST/ACTION Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 20.1003 states that the definition of total effective dose equivalent (TEDE) is the sum of the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). The proposed exemption would change the definition of TEDE to mean the sum of the effective dose equivalent or the deep-dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). The licensee requests the exemption because the current method of calculating TEDE, under certain conditions, can significantly overestimate the dose received.
In summary, the licensees application dated July 20, 2001, as supplemented by letter dated June 13, 2002, requests an exemption from the 10 CFR 20.1003 definition of TEDE.
3.0 DISCUSSION Pursuant to 10 CFR 20.2301, the Commission may, upon application by a licensee or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 20 if it determines the exemptions are authorized by law and would not result in undue hazard to life or property.
The staff examined the licensees rationale to support the exemption request and concluded that the new method for calculating TEDE, under certain conditions, is a more accurate means of estimating worker radiation exposure and therefore would not result in undue hazard to the workers. The basis for this is as follows.
4.0 REGULATORY EVALUATION
By letter dated July 20, 2001, as supplemented by letter dated June 13, 2002, the licensee requested an exemption from the current definition, and the approval to use an alternate definition, of TEDE in 10 CFR 20.1003. The licensee requested that the definition of TEDE, as used in 10 CFR 20.1003 (i.e., for the purpose of complying with the dose recording requirements, dose reporting requirements, or the dose limits), be changed to mean the sum of the effective dose equivalent or the deep dose equivalent (for external exposures), and the committed effective dose equivalent (for internal exposures). The licensee also requested approval to use a method for estimating the effective dose equivalent for external exposures (EDEex) published by the Electric Power Research Institute (EPRI) in Technical Report TR-101909, Volumes 1 and 2, and the Implementation Guide TR-109446. (These EPRI documents were provided on the docket as enclosures to a previous May 1, 2001, application from the licensee, which was superseded by the July 20, 2001, application). The effect of granting this request would be to allow the licensee the option to control TEDE using EDEex in those cases where it is a more accurate predictor of the risk from occupational radiation exposure.
The radiation protection approach and dose limits contained in 10 CFR Part 20 are based on the recommendations of the International Commission on Radiation Protection (ICRP) in their 1977 publication No. 26 (ICRP 26). For stochastic effects, the ICRP-recommended dose limitation is based on the principle that the risk should be equal, whether the whole body is irradiated uniformly or whether there is non-uniform irradiation (such as when radioactive materials are taken into the body and, depending on their physical and chemical properties, concentrate in certain tissues and organs). This condition will be met if TTT < wb,L where T is a weighting factor representing the proportions of the stochastic risk resulting from tissue (T) to the total risk, when the whole body is irradiated uniformly; T is the annual dose equivalent in tissue (T); and wb,L is the recommended annual dose-equivalent limit for uniform irradiation of the whole body, namely 5 rem (50 mSv). The sum TTT is called effective dose equivalent (EDE). The values for T are given in ICRP 26, for the various tissues (T), and are codified in 10 CFR Part 20.
For the purposes of implementing workplace controls, and due to the difference in dosimetry, 10 CFR Part 20 breaks this total EDE, or TEDE, into two components: 1) dose resulting from radioactive sources internal to the body, and 2) dose resulting from sources external to the body. For radioactive material taken into the body, the occupational dose limit is based on the resulting dose equivalent integrated over 50 years (50) of exposure such that TT50,T < wb,L This quantity TT50,T is called the Committed Effective Dose Equivalent (CEDE) in 10 CFR Part 20.
Demonstrating compliance with the dose limits from internal exposures is accomplished using direct measurements of concentrations of radioactivity in the air in the work areas, or quantities of radionuclides in the body, or quantities of radionuclides excreted from the body, or a combination of these. Having determined the quantities of radionuclides present or taken into the body, these can be compared to secondary or tertiary limits (e.g., Annual Limits on Intake or Derived Air Concentrations) listed in Appendix B to 10 CFR Part 20. These secondary and tertiary limits have been calculated using standard assumptions of the physical and chemical forms of the radionuclides, the standard physiological parameters from the Reference Man, and the bio-kinetic models adopted in ICRP 26. Alternatively, the regulations allow the licensee to adjust certain of these standard assumptions and calculate CEDE directly, using appropriate models.
The common practice for determining radiation dose from external sources is to measure the radiation intensity at the surface of the body with a monitoring device (dosimeter) calibrated to read in terms of a tissue dose equivalent at a specified tissue depth. In 1991, when 10 CFR Part 20 was revised to adopt the ICRP 26 recommendations on limits and controls, there was little guidance on how to determine the dose to the several tissues necessary to calculate EDEex. It is impractical to separately monitor (or measure) the dose received by the various organs and tissues that contribute to TEDE. As a practical, conservative simplification, 10 CFR Part 20 limits the dose from external sources in terms of Deep Dose Equivalent (DDE). The DDE is the dose equivalent at a tissue depth of one centimeter, and is required (by 10 CFR Part 20.1201(c)) to be determined for the part of the body receiving the highest exposure. The TEDE annual limit is met if DDE + TT50,T < 5 rem (50 mSv).
In addition to the annual limit on TEDE, 10 CFR Part 20 provides a non-stochastic annual limit of 50 rem (0.5 Sv) for each individual tissue such that DDE + 50,T < 50 rem (0.50 Sv) for all tissues except the skin and lens of the eye.
Using the highest DDE, to bound the individual tissue doses from radioactive sources outside the body, generally results in a slightly conservative estimate of EDEex from uniform exposures; however, it can be overly conservative for non-uniform exposure situations. Since many high-dose jobs at nuclear power plants are performed under non-uniform exposure conditions, this can lead to a significant overestimation of the actual TEDE dose, and the risk, to the workers. To address this issue, the licensee has requested approval to provide a more accurate dose assessment by replacing DDE with EDEex when calculating TEDE from non-uniform exposures, where the EDEex is determined with a method developed by the EPRI.
In developing this method, the EPRI investigators used mathematical equations developed by Cristy and Eckerman to model standard, adult human male and female subjects (phantoms). The Monte Carlo radiation transport computer code MCNP was used to calculate the dose to individual tissues modeled in the phantoms, and simulated dosimeter readings, for a range of different exposure geometries. Dosimeters with an isotropic response were modeled at several locations on the surface of the phantoms. Both broad beam and point radiation sources (with selected photon energies) were considered. Indicated doses (e.g., simulated dosimeter readings) and the actual EDEex (e.g., the sum of the products of the calculated phantom tissue doses and their respective ICRP 26 weighting factors) were calculated for photons incident on the phantoms from various locations. Empirical algorithms were developed to relate the EDEex resulting from the full range of exposure situations to the indicated doses that could be measured at the surface of the body. Two algorithms were developed to estimate EDEex from just two dosimeters worn on the trunk of the whole body (front and back, respectively). The first algorithm is a simple, non-weighted averaging of the front and back dosimeter readings. The second algorithm weights the higher of the two dosimeter readings.
5.0 TECHNICAL EVALUATION
The staff reviewed the technical descriptions of the EPRI method for estimating EDEex; the resulting data and conclusions contained in Technical Report TR-101909, Volumes 1 and 2; the Implementation Guide TR-109446; and supporting technical papers published by the principal EPRI investigators. The staff also performed independent calculations to verify a sampling of the results tabulated in these documents.
Table 8 in TR-101909, Volume 2, provides a summary of the EDEex and dosimeter (front and back) readings calculated for parallel beams and point sources used to develop the EPRI algorithms. The staff noted that the magnitude of the units for the parallel beam dose factors listed in Table 8 are low by five orders of magnitude (e.g., E-15 rad-cm squared per photon instead of the correct E-10 rad-cm squared per photon). The licensee verified, in its June 13, 2002, supplemental letter, that this is a typographical error in the EPRI document. However, this error does not affect the conclusions drawn from the data. The licensee has stated that they will not use the specific dose factors listed in Table 8 to calculate EDEex.
The EPRI work indicates that a single dosimeter (calibrated to read DDE) worn on the chest provides a reasonably accurate estimate of EDEex when the individual is exposed to a number of randomly distributed radiation sources during the monitoring period. This is consistent with current allowable dosimetry practices and requires no special approval. The alternate definition of TEDE requested would allow the licensee the option to monitor worker dose with a single DDE measurement, as currently required, or to control TEDE using EDEex (as determined by the EPRI two-badge method). This would benefit the licensee in situations where monitoring the highest DDE would require moving or supplementing the single badge.
The data presented in the EPRI reports indicate that the weighted, two-dosimeter algorithm provides a reasonably conservative estimate of EDEex. However, the non-weighted algorithm does not always give a conservative result. The licensee has stated that it will only use the weighted, two-dosimeter algorithm such that EDEex = 1/2 (MAX + 1/2 (Rfront + Rback))
where Rfront is the reading of the dosimeter on the front of the body, Rback is the reading of the dosimeter on the back of the body, and MAX is the higher of the front or back dosimeter readings.
Additional issues and limitations noted in the staffs review are included in the following paragraphs.
Partial-body irradiations that preferentially shield the dosimeter could bias the EPRI method results in the non-conservative direction. The licensee has stated that they will ensure that the dosimeters are worn so that at least one of the two badges sees the source(s) of radiation. In other words, the radiological work will be conducted and the dosimeters worn in such a way, so that no shielding material is present between the radioactive source(s) and the whole body, that would cast a shadow on the dosimeter(s) and not over other portions of the whole body.
Isotropic dosimeters (e.g., dosimeters that respond independently of the angle of the incident radiation) are impractical and not widely available commercially. Therefore, the licensee must implement the EPRI method using dosimeters that will have an angular-dependent response. If the dosimeter reading decreases more rapidly than EDEex, with increasing exposure angle, the resulting EDEex estimate will be biased in the non-conservative direction. The EPRI principle investigators have addressed this issue of angular dependance in their published technical paper entitled, A Study of the Angular Dependence Problem In Effective Dose Equivalent Assessment (Health Physics Volume 68. No. 2, February 1995, pp. 214-224). The licensee has stated that the dosimeters used to estimate EDEex will have demonstrated angular response characteristics at least as good as that specified in this technical paper. In addition, the dosimeters will be calibrated to indicate DDE at the monitored location, to ensure their readings reflect electronic equilibrium conditions.
The EPRI method for estimating EDEex from two dosimeter readings is not applicable to exposure situations where the sources of radiation are nearer than 12 inches (30 cm) from the surface of the body. Tables 5 thru 7 in EPRI TR-101909, Volume 2, provide calculated EDEex values resulting from exposure to point sources in contact with the torso of the body. However, the staff review determined that the information provided in these tables does not bound all of the pertinent point source exposure situations. The licensee has stated that the use of EDEex to determine compliance with the TEDE limit, resulting from point sources (i.e., hot particles) on or near the surface of the body, is outside the scope of this request.
The exemption applies only to the TEDE definition and calculations. It does not modify the dose limits for any individual organ or tissue specified in, or method for complying with, 10 CFR Part 20. Also, when DDE is used to calculate TEDE under the revised definition, the requirement that it be for the part of the body receiving the highest exposure in 10 CFR 20.1201(c) is applicable.
6.0 EVALUATION
SUMMARY
The staff concludes that calculating TEDE using this EDEex in place of DDE provides a more accurate estimate of the risk associated with the radiation exposures experienced by radiation workers at a nuclear power plant. Additionally the staff finds that the proposal to limit TEDE such that EDEex + CEDE < 5 rem is consistent with the basis for the limits in 10 CFR Part 20. Therefore, subject to the limitations noted above, defining TEDE to mean the sum of EDEex or DDE (for external exposures) and CEDE (for internal exposures), in lieu of the current 10 CFR 20.1003 definition, is acceptable.
Additionally, the staff concludes that the methods for estimating EDEex described in EPRI Technical Report TR-101909, Volumes 1 and 2, and Implementation Guide TR-109446 are based on sound technical principles. The proposed EPRI weighted, two-dosimeter algorithm provides an acceptably conservative estimate of EDEex with a degree of certainty that is comparable to that inherent in the methods allowed by 10 CFR Part 20 for estimating CEDE.
Therefore, subject to the limitations noted above, using the EPRI weighted, two-dosimeter algorithm so that EDEex = 1/2 (MAX + 1/2 (Rfront + Rback))
for the purposes of demonstrating compliance with 10 CFR 20.1003 is acceptable.
7.0 CONCLUSION
Accordingly, the Commission has determined that, pursuant to 10 CFR 20.2301, the exemption is authorized by law and would not result in undue hazard to life or property.
Therefore, the Commission hereby grants Entergy Operations, Inc. and Entergy Nuclear Operations, Inc. an exemption from the requirements of 10 CFR 20.1003 for Arkansas Nuclear One, Units 1 and 2; Grand Gulf Nuclear Station; Indian Point Nuclear Station, Units 1, 2 and 3; James A. Fitzpatrick Nuclear Power Plant; Pilgrim Nuclear Power Station; River Bend Station; Vermont Yankee Nuclear Power Plant; and Waterford Steam Electric Station, Unit 3. The exemption changes the definition of TEDE to mean the sum of EDEex or DDE (for external exposures) and CEDE (for internal exposures). This Exemption is granted to allow the licensee the option to monitor worker dose using EDEex based on the following conditions:
1.
Only the EPRI weighted, two-dosimeter algorithm will be used such that EDEex = 1/2 (MAX + 1/2 (Rfront + Rback))
where Rfront is the reading of the dosimeter on the front of the body, Rback is the reading of the dosimeter on the back of the body, and MAX is the higher of the front or back dosimeter readings.
2.
The radiological work will be conducted and the dosimeters worn in such a way, so that no shielding material is present between the radioactive source(s) and the whole body, that would cast a shadow on the dosimeter(s) and not over other portions of the whole body.
3.
The dosimeters used to estimate EDEex will have demonstrated angular response characteristics at least as good as that specified in the technical paper entitled, A Study of the Angular Dependence Problem In Effective Dose Equivalent Assessment (Health Physics Volume 68. No. 2, February 1995, pp. 214-224). Also, the dosimeters will be calibrated to indicate DDE at the monitored location, to ensure their readings reflect electronic equilibrium conditions.
4.
The EPRI method for estimating EDEex from two dosimeter readings is not applicable to exposure situations where the sources of radiation are nearer than 12 inches (30 cm) from the surface of the body.
Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment (67 FR 56603, dated September 4, 2002).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 12th day of September 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Bruce A. Boger, Director Division of Inspection Program Management Office of Nuclear Reactor Regulation
Plant Mailing List for Region IV Plants Page 1 Arkansas Nuclear One, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station, Unit 3 cc:
Executive Vice President
& Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Senior Resident Inspector - ANO U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Senior Resident Inspector - GGNS U. S. Nuclear Regulatory Commission P. O. Box 399 Port Gibson, MS 39150 Senior Resident Inspector - RBS U.S. Nuclear Regulatory Commission P. O. Box 1050 London, AR 72847 Resident Inspector/Waterford NPS Post Office Box 822 Killona, LA 70066 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011-8064 Vice President, Operations Support Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205 Director Division of Solid Waste Management Mississippi Department of Natural Resources P. O. Box 10385 Jackson, MS 39209 President Claiborne County Board of Supervisors P. O. Box 339 Port Gibson, MS 39150 General Manager, GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 State Health Officer State Board of Health P. O. Box 1700 Jackson, MS 39205 Office of the Governor State of Mississippi Jackson, MS 39201 Attorney General Asst. Attorney General State of Mississippi P. O. Box 22947 Jackson, MS 39225 Director, Nuclear Safety Assurance - GGNS Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150
Plant Mailing List for Region IV Plants Page 2 Arkansas Nuclear One, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station, Unit 3 cc:
Mr. William A. Eaton Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Manager - Licensing Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775 President of West Feliciana Police Jury P. O. Box 1921 St. Francisville, LA 70775 Ms. H. Anne Plettinger 3456 Villa Rose Drive Baton Rouge, LA 70806 General Manager - Plant Operations Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775 Director - Nuclear Safety - RBS Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775 Attorney General State of Louisiana P. O. Box 94095 Baton Rouge, LA 70804-9095 Attorney General State of Louisiana P. O. Box 94005 Baton Rouge, LA 70804-9005 Mr. Paul D. Hinnenkamp Vice President - Operations Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775 Director Nuclear Safety Assurance - W3 Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 General Manager Plant Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Parish President Council St. Charles Parish P. O. Box 302 Hahnville, LA 70057 Chairman Louisiana Public Service Commission Baton Rouge, LA 70825-1697 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Mr. Craig G. Anderson Vice President Operations, ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
Plant Mailing List for Region IV Plants Page 3 Arkansas Nuclear One, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station, Unit 3 cc:
Mr. Michael E. Henry, Administrator and State Liaison Officer Department of Environmental Quality P. O. Box 82135 Baton Rouge, LA 70884-2135 Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Mr. Mike Schoppman Framatome ANP, Richland, Inc.
Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 County Judge of Pope County Pope County Courthouse Russellville, AR 72801
FitzPatrick Nuclear Power Plant Page 1 and Indian Point Nuclear Generating Unit Nos. 1, 2 and 3 cc:
Mr. Jerry Yelverton Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213 Mr. Theodore H. Sullivan Vice President Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Fred Dacimo Vice President Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Units 1 & 2 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Robert J. Barrett Vice President - Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P.O. Box 308 Buchanan, NY 10511-0308 Mr. Dan Pace Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Knubel Vice President Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Michael J. Colomb General Manager Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Lawrence G. Temple General Manager Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Joseph DeRoy General Manager Operations Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P.O. Box 308 Buchanan, NY 10511-0308 Mr. John Kelly Director of Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene Fiason Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Arthur Zaremba, Licensing Manager Director, Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
FitzPatrick Nuclear Power Plant Page 2 and Indian Point Nuclear Generating Unit Nos. 1, 2 and 3 cc:
Mr. John McCann Manager, Nuclear Safety and Licensing Indian Point Nuclear Generating Unit 2 Entergy Nuclear Operations, Inc.
295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Harry P. Salmon, Jr.
Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. George Tasick Licensing Manager Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. John Donnelly Licensing Manager Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 P.O. Box 308 Buchanan, NY 10511-0308 Mr. Thomas Walsh Secretary - NFSC Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspectors Office U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Senior Resident Inspector, Indian Point 2 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 P.O. Box 38 Buchanan, NY 10511-0038 Resident Inspectors Office, Indian Point 3 U.S. Nuclear Regulatory Commission 295 Broadway, Suite 3 P.O. Box 337 Buchanan, NY 10511-0337 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. J. Spath, Program Director New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399
FitzPatrick Nuclear Power Plant Page 3 and Indian Point Nuclear Generating Unit Nos. 1, 2 and 3 cc:
Mr. Paul Eddy Electric Division New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Ronald Schwartz SRC Consultant 64 Walnut Drive Spring Lake Heights, NJ 07762 Mr. Ronald J. Toole SRC Consultant Toole Insight 605 West Horner Street Ebensburg, PA 15931 Mr. Charles W. Hehl SRC Consultant Charles Hehl, Inc.
1486 Matthew Lane Pottstown, PA 19465 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Karl Copeland Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Tim Judson Organizer Citizens Awareness Network 140 Bassett St.
Syracuse, NY 13210 Deborah Katz Executive Director Citizens Awareness Network P.O. Box 83 Shelburne Falls, MA 01370 Shawn McConnell NYPIRG Project Coordinator 13 Hewitt Union SUNY Oswego Oswego, NY 13126
FitzPatrick Nuclear Power Plant Page 4 and Indian Point Nuclear Generating Unit Nos. 1, 2 and 3 cc:
Tom Dellwo Oswego NYPIRG Environmental Project Leader 13 Hewitt Union SUNY Owego Oswego, NY 13126 Oswego County Administrator Jack Tierney 46 East Bridge Street Oswego, New York 13126
Pilgrim Nuclear Power Station cc:
Resident Inspector U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Post Office Box 867 Plymouth, MA 02360 Chairman, Board of Selectmen 11 Lincoln Street Plymouth, MA 02360 Chairman, Duxbury Board of Selectmen Town Hall 878 Tremont Street Duxbury, MA 02332 Office of the Commissioner Massachusetts Department of Environmental Protection One Winter Street Boston, MA 02108 Office of the Attorney General One Ashburton Place 20th Floor Boston, MA 02108 Dr. Robert M. Hallisey, Director Radiation Control Program Commonwealth of Massachusetts Executive Offices of Health and Human Services 174 Portland Street Boston, MA 02114 John M. Fulton Assistant General Counsel Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Mr. C. Stephen Brennion Licensing Superintendent Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Mr. Jack Alexander Manager, Reg. Relations and Quality Assurance Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Mr. David F. Tarantino Nuclear Information Manager Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Ms. Jane Perlov Secretary of Public Safety Executive Office of Public Safety One Ashburton Place Boston, MA 02108 Mr. Stephen J. McGrail, Director Attn: James Muckerheide Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Chairman Nuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056-0426
Vermont Yankee Nuclear Power Station cc:
Mr. David R. Lewis Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037-1128 Ms. Christine S. Salembier, Commissioner Vermont Department of Public Service 112 State Street Montpelier, VT 05620-2601 Mr. Michael H. Dworkin, Chairman Public Service Board State of Vermont 112 State Street Montpelier, VT 05620-2701 Chairman, Board of Selectmen Town of Vernon P.O. Box 116 Vernon, VT 05354-0116 Mr. Michael Hamer Operating Experience Coordinator Entergy Nuclear Vermont Yankee, LLC P.O. Box 250 Governor Hunt Road Vernon, VT 05354 G. Dana Bisbee, Esq.
Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370 Mr. Raymond N. McCandless Vermont Department of Health Division of Occupational and Radiological Health 108 Cherry Street Burlington, VT 05402 Mr. Gautam Sen Manager, Licensing Entergy Nuclear Vermont Yankee, LLC P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500 Resident Inspector Vermont Yankee Nuclear Power Station U. S. Nuclear Regulatory Commission P.O. Box 176 Vernon, VT 05354 Director, Massachusetts Emergency Management Agency ATTN: James Muckerheide 400 Worcester Rd.
Framingham, MA 01702-5399 Jonathan M. Block, Esq.
Main Street P. O. Box 566 Putney, VT 05346-0566