ML14191A438
| ML14191A438 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/22/1990 |
| From: | Lo R Office of Nuclear Reactor Regulation |
| To: | Eury L Carolina Power & Light Co |
| References | |
| TAC-66079 NUDOCS 9003290068 | |
| Download: ML14191A438 (5) | |
Text
March 22, 1990 0
Docket No. 50-261 Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 27602
Dear Mr. Eury:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATING TO PROPOSED OPERATING LICENSE EXTENSION - H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. 66079)
By letter dated August 17, 1987, you submitted a request to change the expiration date of your operating license for the Robinson Steam Electric Plant, Unit No. 2 (HBR-2).
As noted in the enclosure, we have identified additional information needed to complete our review.
To finalize our review, you are requested to provide the requested additional information within 90 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, 0MB clearance is not required under P. L.96-511.
Sincerely, Brenda Mozafari/for Ronnie H. Lo, Senior Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/encl:
See next page DISTRIBUTION See attached page OFC
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_Document Name:
LTREURY 2/20
- 90032906 ocs =oo:22 FR ADO.C 05000261 1
Mr. L. W. Eury H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr.
R. E. Jones, General Counsel Mr.
Dayne H. Brown, Director Carolina Power & Light Company Department of Environmental, P. 0. Box 1551 Health and Natural Resources Raleigh, North Carolina 27602 Division of Radiation Protection P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Mr. H. A. Cole Special Deputy Attorney General Mr.
Robert P. Gruber State of North Carolina Executive Director P. 0. Box 629 Public Staff - NCUC Raleigh, North Carolina 27602 P. 0. Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Mr. C. R. Dietz Resident Inspector's Office Manager, Robinson Nuclear Project H. B. Robinson Steam Electric Plant Department Route 5, Box 413 H. B. Robinson Steam Electric Plant Hartsville, South Carolina 29550 P. 0. Box 790 Hartsville, South Carolina 29550 Regional Acministrator, Region II U.S. Nuclear Regulatory Commission Mr.
Heyward G. Shealy, Chief 101 Marietta Street Bureau of Radiological Health Suite 2900 South Carolina Department of Health Atlanta, Georgia 30323 and Environmental Control 2600 Bull Street Mr. R. Morgan
- Columbia, South Carolina 29201 General Manager H. B. Robinson Steam Electric Plant P. 0. Box 790.
Hartsville, South Carolina 29550
DISTRIBUTION Docket File NRC PDR Local PDR S. Varga 14-E-4 G. Lainas 14-H-3 E. Adensam 14-B-20 P. Anderson 14-B-20 R. Lo 14-B-20 OGC (For inform. Only) 15-B-18 E. Jordan MNBB-3302 L. Cunningham ACRS (10)
P-315 ROBINSON FILE
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR EXTENSION OF OPERATING LICENSE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (HBR-2)
DOCKET NO. 50-261
- 1. Provide an assessment of the impact (10 CFR Part 100) on the Exclusion Area Boundary, Low Population Zone and the nearest population centers based on population projections through the requested extension periods.
- 2. Provide a discussion of population distribution trends within 50 miles of the plant based on 1970 and 1980 census data. Include projections through the period of the proposed extensions.
- 3. Provide a quantification of the radiological impacts upon the general population based on calculated off-site doses.
Include a discussion on the impact of the estimated dose commitments for 40 years of operation.
How do offsite dose calculations for actual effluent releases compare with 10 CFR Part 50, Appendix I, objectives?
- 4. For the uranium fuel cycle, provide a statement regarding the environmental impact of the longer production run for the fuel cycle and any net annual effects per Table S-3 in 10 CFR 51.51. Also state any impacts of the 18 month fuel cycles versus the 12 month cycles used for the FES and FSAR.
- 5. Provide a discussion on how HBR-2 intends to meet the requirements of 10 CFR 51.52, paragraph (a) or (b), and Table S-4.
- 6. Describe any dose goals you may have for HBR-2 annual doses through the requested extension period, the bases for these dose goals (e.g., input from each plant department, historical doses), and CP&L's time frame for meeting these goals. Provide dose goals for both outage and non-outage years. Describe the HBR-2 "track record" for meeting dose goals in the past, the accuracy of these past dose goals, and how HBR intends to establish and enforce realistic dose goals in the future.
- 7. a. Although Robinson's annual collective dose of 209 R/yr in 1989 was below the PWR industry average, Robinson's annual collective exposures for most of the plant life have been well above the industry average for PWRs.
Describe how CP&L plans to maintain the 1989 level of success and reduce the HBR-2 annual collective dose over the next few years to levels which will be more comparable to the industry average during the period of extension. Describe any changes/improvements that may have already been made to reduce the annual doses at HBR-2 and their effectiveness in reducing annual doses.
- b. Describe Robinson's radioactive "source term" relative to other plants of the same vintage. What plans (short-range and long-range) does CP&L have to reduce this source term (e.g. system chemical decon, cobalt material replacement during the time of the extension).
-2
- 8. Detailed and accurate ALARA job preplanning plays an important role in minimizing job time and the resultant occupational doses. Describe how ALARA job preplanning, along with coordination and cooperation among plant management, ensures that pertinent jobs receive adequate ALARA reviews well in advance of the actual outage. Describe how these ALARA reviews, coupled with accurate man-hour job estimates, can contribute to lowering annual doses during the period of the extension.
- 9. Provide a comparison between actual radwaste shipments in recent years and the information provided in FES section 11.1.7., and estimate the impact for the extension periods.
- 10.
Provide the current National Pollutant Discharge Elimination System (NPDES) permit number and dates of issuance and expiration.
- 11.
Identify any potential impact that prolonged plant operation may have on properties with historical, architectural, or archeological significance.
- 12.
Assess the impact of the proposed extension on the reactor vessel mechanical equipment, electrical equipment, and plant structures.
- 13.
Provide a listing of all FES or FSAR sections in which less than 40 years of operation was assumed; provide an assessment of the impact of the extensions on conclusions found in the sections identified. For example, 30 years was used as the expected plant life in section 5.1.1 of the FES.