ML16138A715
| ML16138A715 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/22/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A716 | List: |
| References | |
| NUDOCS 9101280089 | |
| Download: ML16138A715 (4) | |
Text
REGUW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 187TO FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 187TO FACILITY OPERATING LICENSE DPR-47 AMENDMENT NO. 184TO FACILITY OPERATING LICENSE DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287
1.0 INTRODUCTION
By letter dated February 7, 1990, as supplemented May 7, 1990, Duke Power Company (the licensee) proposed to incorporate programmatic controls for radiological effluents and radiological environmental monitoring in the Administrative Controls section of the Technical Specifications (TSs) consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. At the same time, the licensee proposed to transfer the procedural details of the Radiological Effluent Technical Specifications (RETS) from the TSs to Chapter 16 of the Final Safety Analysis Report (FSAR), "Selected Licensee Commitment (SLC) Manual." With these changes, the specifications related to RETS reporting requirements were simplified. Finally, changes to the definitions of the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) were proposed consistent with these changes. Guidance on these proposed changes was provided to all power reactor licensees and applicants by Generic Letter 89-01 dated January 31, 1989.
2.0 EVALUATION The licensee's proposed changes to the TSs are in accordance with the guidance provided in Generic Letter 89-01 with the exception of relocating the RETS to the SLC Manual instead of the ODCM and PCP. Changes to the SLC Manual, as part of the FSAR, are made in accordance with the requirements of 10 CFR 50.59. As such, this document is more restrictive than the ODCM and PCP and is, therefore, an acceptable alternative. The remaining changes are addressed below.
(1) The licensee has proposed to incorporate programmatic controls for radioactive effluents and radiological environmental monitoring in Specifications 6.4.6 and 6.4.7 of "Station Operating Procedures" of the TSs as noted in the guidance provided in Generic Letter 89-01.
9101280089 910122 PDR ADOCK 050C0o269 P
-2 The programmatic controls ensure that programs are established, implemented, and maintained to ensure that operating procedures are provided to control radioactive effluents consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50.
(2) The licensee has confirmed that the detailed procedural requirements addressing Limiting Conditions for Operation, their applicability, remedial actions, associated surveillance requirements, or reporting requirements for the following specifications have been prepared to implement the relocation of these procedural details to the SLC Manual.
These changes to the SLC Manual have been prepared so that they will be implemented within 30 days of issuance of these amendments.
SPECIFICATION TITLE 3.5.5 RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION 3.9.1 RADIOACTIVE LIQUID EFFLUENTS: CONCENTRATION 3.9.2 RADIOACTIVE LIQUID EFFLUENTS:
DOSE 3.9.3 RADIOACTIVE LIQUID EFFLUENTS:
LIQUID WASTE TREATMENT 3.9.4 RADIOACTIVE LIQUID EFFLUENTS:
CHEMICAL TREATMENT PONDS (CTP 1 and 2) 3.10.1 RADIOACTIVE GASEOUS EFFLUENTS:
DOSE RATE 3.10.2 RADIOACTIVE GASEOUS EFFLUENTS:
DOSE 3.10.3 RADIOACTIVE GASEOUS EFFLUENTS:
GASEOUS RADWASTE TREATMENT 3.10.5 RADIOACTIVE GASEOUS EFFLUENTS:
USED OIL INCINERATION 3.11 SOLID RADIOACTIVE WASTES 4.11 RADIOLOGICAL ENVIRONMENTAL MONITORING 4.21 DOSE CALCULATIONS 6.6.1.5 ROUTINE REPORTS: RADIOLOGICAL ENVIRONMENTAL MONITORING 6.6.1.4 ROUTINE REPORTS: RADIOACTIVE EFFLUENT RELEASE REPORT 6.6.2.2 NON-ROUTINE REPORTS:
ENVIRONMENTAL MONITORING These procedural details that have been removed from the TSs are not required by the Commission's regulations to be included in TSs. They have been prepared for incorporation in the SLC Manual upon issuance of these license amendments and may be subsequently changed by the licensee without prior NRC approval.
Changes to the SLC Manual are documented and will be retained in accordance with 10 CFR 50.59.
-3 (3) The licensee has proposed replacing the existing specifications in the Administrative Controls section of the TSs for the Annual Radiological Environmental Monitoring Report, Specification 6.6.1.5; Semiannual Radioactive Effluent Release Report, Specification 6.6.1.4; and Offsite Dose Calculation Manual, Specification 6.1.2.1, with the updated specifications that were provided in Generic Letter 89-01.
A new specification 6.1.2.m for the Process Control Program has been added in accordance with the guidance of Generic Letter 89-01.
The following specifications that are included under the heading of Radioactive Effluents have been retained in the TSs. This is in accordance with the guidance of Generic Letter 89-01.
SPECIFICATION TITLE 4.1.3 TABLE 4.1.3., MINIMUM SAMPLING FREQUENCY AND ANALYSIS PROGRAM, ITEMS 1 THROUGH 6 AND 13 3.9.5 LIQUID HOLDUP TANKS 3.10.6 EXPLOSIVE GAS MIXTURE 3.10.4 WASTE GAS HOLDUP TANKS The following specifications were not specifically addressed in Generic Letter 89-01 due to the unique nature of the Oconee TSs. The proposed changes to these specifications are administrative in nature and either are necessary to be consistent with changes in other specifications resulting from the guidance in Generic Letter 89-01 or the change is consistent with the intent of the generic letter.
SPECIFICATION TITLE 4.1.4 OPERATIONAL SAFETY REVIEW (Table 4.1-4) 4.15.1 IODINE RADIATION MONITORING FILTERS 6.6.3 SPECIAL REPORTS:
- b. Radioactive Liquid Effluents
- c. Radioactive Gaseous Effluents
- h. Radiological Environmental Monitorin
- i.
Dose Calculations 6.8 OFFSITE DOSE CALCULATION MANUAL (ODCM)
On the basis of the above, the staff finds that the changes included in the proposed TS amendment request are consistent with the guidance provided in Generic Letter 89-01. Because the control of radioactive effluents continues to be limited in accordance with operating procedures that must satisfy the regulatory requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and
- i.
f
- 4 Appendix I to 10 CFR Part 50, the NRC staff concludes that the changes are administrative in nature and there is no impact on plant safety as a consequence. Accordingly, the.staff finds the proposed changes acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in requirements with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements.
These amendments also involve changes in recordkeeping, reporting, or administrative procedures and program requirements. The 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 these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
4.0 CONCLUSION
The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (55 FR 30294) on July 25, 1990. The Commission consulted with the State of South Carolina. No public comments were received, and the State of South Carolina did not have any comments.
On the basis of the considerations discussed above, the Commission's staff concludes that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
W. Wayne Meinke, PRPB/DREP Thomas G. Dunning, OTSB/DOEA Leonard Wiens, PDII-3/DPR I/II Dated:
January 22, 1991