ML20126C126
| ML20126C126 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/09/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126C113 | List: |
| References | |
| NUDOCS 9212220380 | |
| Download: ML20126C126 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C. 20555 t,
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR kECL'LATION RELATED TO AMENDMENT NO.103 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 97 TO FACII ITY OPERATING LICENSE NPF-52 QQK.E POWER COMPANY. ET AL.
CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated February 7, 1990, as supplemented May 7, 1990, June 8 and October 8, 1992, the 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 rc4uirements of 10 CFR 20.103, 40 CFR Part 190, 10 CFR 50.36a, and Append'c I te 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 Lic mee Commitment (SLC) Hanual." With these chanys, the specifications related to RETS reporting requirements were sitplified.
Finally, changes to the definition of the Offsite Dose Calculation Manut.1 (ODCM) was proposed consistent with these changes. Guidance on these proposed changes was provided to all power reactor licensees and applicants by Generic Letter (GL) 89-01 dated January 31, 1989.
The definition of the Process Control Program (PCP) war, already consistent with this guidance. The letters of June 8 and octobe 8,1992, provided clarifying information and corrections which were not outside the scope of the original Federal Reaister notice and did not change the initial proposed no significant hazards cons'? J'on determination.
2.0 EVALVATIOjl The licensee's proposed changes to the TSs are in accordance with the guidance provided in GL 89-01 with the exception of relocating-the RETS to the SLC Manual instead of to the ODCM.
Changes to the SLC Manual, as part of the FSAR, are made subject to um requirements of 10 CFR 50.59.
In addition, the licensee has also proposed to relocate the TS for the chemical treatment pond to the FSAR. While suva a TS was net enumerated as being within the guidance of GL 89-01, the NRC staff has reviewed this proposal and finds that it is consistent with the guidance of the GL and is acceptable.
The GL proposes, for inclusion in the TSs, a description of a Radioactive Effluent Controls Program and a description of a Radiological Environmental Monitoring Program to be contained in the ODCM. The GL also proposes that 9212220380 931209 PDR ADOCK 06000413 p
, record retention requirements and controls governing changes to the ODCM and to the PCP be added to the TSs.
With the licensee's proposal for placing these programs in the FSAR Chapter 16 SLC Manual, instead of in the ODCM, the licensee has also proposed that the GL's record retention and change control requirements be made applicable to the Catawba FSAR Chapter 16 SLC Manual.
Therefore, since the program descriptions and the associated record retention and change control requirements described by the GL have been coupled in the Catawba TSs, this alternative to the GL is acceptable.
The specific changes are addressed below.
Changes to TS page numbers and format have also been made to accommodate the changes discussed below.
(1)
The licensee has proposed to incorporate programmatic controls for radioactive effluents and radiological environmental monitoHng in Specification 6.8.4, " Procedures and Programs" of the TSs as noted in the guidance provided in GL 89-01.
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 30 days from the issuance of these amendments.
Sf1ClFICATION TITLE 3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONI[0 RING INSTRUMENTATION 3/4.3.3.11 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 3/4.11.1.1 RADI0 ACTIVE EFFLUENTS: LIQUID EFFLUENTS CONCENTRATION 3/4.11.1.2 RADI0 ACTIVE EFFLUENTS: LIQUID EFFLUENTS DOSE 3/4.11.1.3 RADI0 ACTIVE EFFLUENTS: LIQUID RADWASTE TREATMENT SYSTEM 3/4.ll.l.E RADI0 ACTIVE EFFLUENTS: CHEMICAL TREATMENT PONDS 3/4.11.2.1 RADI0 ACTIVE EFFLUENTS: GASEOUS EFFLUENTS DOSE RATE 3/4.11.2.2 RADI0 ACTIVE EFFLUENTS: DOSE - N0BLE GASES 3/4.11.2.3 RADI0 ACTIVE EFFLUENTS: DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM 3/4.11.2.4 RADI0 ACTIVE EFFLUENTS: GASEOUS RADWASTE TREATMENT SYSTEM
[.
5 3/4.11.3 RADI0 ACTIVE EFFLUENTS: SOLID RADIDACTIVE WASTES 3/4.11.4 RADI0 ACTIVE EFFLUENTS: TOTAL DOSE 3/4.12.1 RADIOLOGICAL ENVIRONMENTAL MONITORING: MONITORING PROGRAM 3/4.12.2 RADIOLOGICAL ENVIRONMENTAL MONITORING: LAND USE CENSUS 3/4.12.3 RADIOLOGICAL ENVIRONMENTAL MONITORING: INTERLABORATORY COMPARIS0N PROGRAM 6.9.1.6 ANNUAL RADIOL 0GICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT These procedural details that have been removed from the TSs are not required by the Commission's regulations to be included in the TSs. They_have been prepared for incorporation in the SLC manual within 30 days from the issuance of these license amendments and may be subsequently changed by the licensee without prior NRC approval.
Changes to the FSAR Chapter 16 SLC Panual are documented and will be retained for the duration of the operating license in accordance with Specification 6.10.2n.
(3) The licensee has proposed replacing the existing specifications in the Administrative Controls section of the TSs for the Arinual Radiological L
Environmental Operating Report, Specification 6.9.1.6, for the Semiannual l
Radioactive Effluent Release Report, and Specification 6.9.1.7, with the l
updated specifications that were provided in GL 89-01. Given the licensee's alternative to relocate the procedural details into tha SLC, TS 6.13 for the PCP, and TS O 14 for the ODCM, do not require any-revision.
L The following specifications that are included under the heading of Radioactive Effluents have bran retained in the TSs. This is in accordance with the guidance of GL 89-01, i
SPECIFICATION TITLE 3/4.3.3.10 JPL0SIVE G4 S MONITORING INSTRUMENTATION (Retained existing requirements of this specific:
s) 3/4.11.1.1 LIQUID HOLDUP TANKS 3/4.11.2.1 EXPLOSIVE GAS MIXTURE 3/4.11.2.2 GAS STORAGE TANKS u
. 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 Appendix 1 to 10 CFR Part 50, the NRC staff concludes that this change is administrative in nature and there is no impact on plant safety as_a consequence. Accordingly, the staff finds the proposed changes acceptable.
3.0 STATE CONSULTATION
in accordance with the Ctmmission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 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 changes surveillance requirements.
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 (55 FR 32325 dated August 8, 1990). Accordingly, the amendments meet the 4
eligibility criteria for categorical exclusion set Tnrth 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 the amendments.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
R. E. Martin, POII-3 S. P. Klementowicz, PRPB Datei December 9,1992 l
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