ML20077F006
| ML20077F006 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/22/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077E996 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9106110341 | |
| Download: ML20077F006 (3) | |
Text
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION Mh4
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.119 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO 101 TO FAClllTY OPERATING LICENSE NPF-17 DUKEPOWERCOMPAg DOCKET NOS. 50-369 AND 50-370 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2
1.0 INTRODUCTION
By letter dated February 7,1990, as supplemented May 7,1990, Duke Power Company (the licensee) submitted a request for chan Units 1 and 2 Technical Specifications (TS)ges to the McGuire Nuclear Station, The requested changes would 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 Pert 190,10 CFR 50.36a, and Appendix ! 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 RETS reporting requirement specifications were simplified.
In addition, changes were proposed to the definitions of Offsite Dose Calculation Manual (0DCM) and Process Control Program (PCP).
Guidance regarding the removal of RETS from the TSs was provided by Generic letter (GL) 89-01, dated January 31, 1989, The May 7, 1990 'etter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 EVALUATION The licensee's proposed ch6nges to the TSs are in accordance with the guidance provided in GL 89-01 and are addressed below.
(1) The licensee has proposed to incorporate progra"1matic controls for radioactive effluents and radiological environmental monitoring in Specification 6.8, " 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 ! to 10 CFR Part 50.
(2) The licensee is relocating the detailed procedural requirements associated with Limiting Conditions for Operation, their applicability, remedial actions, surveillance requirements, or reporting requirements for the specifications identifieo below to the FSAR Chapter 16 SLC Manual.
This is a deviation from the GL 89-01 guidance. This 01061lo u2 9 3,7;.,
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l 2-i deviation is acceptable since the controls placed Jn the relocated RETS (to the SLC) provide an equivalent level of administrative control as those placed on the 00CM and PCP.
Additionally, since the SLC Manual is part of the McGuire FSAR, l
changes to the SLC Manual, and consequently the relocated REN,
will require a 10 CFR 50.59 evaluation. The licensee is pre)ared to implement the RETS as relocated in the ELC Manual wit 11n 30 days of issuance of these amendments.
SPECIFICATION TITLE 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3/4.11.1.1 RADI0 ACTIVE EFFLUENTS: LIQUID EFFLUENTS CONCENTRATION 3/4.11.1.2 RADI0 ACTIVE EFFLUE!vTS: LIQUID EFFLUENTS DOSE 3/4.11.1.3 RADI0 ACTIVE EFFLUEiTS: LIQUID RADWASTE TREAIMENT SYSTEM 3/4.11.1.5 RADI0 ACTIVE EFFLUEl'TS: CHEMICAL TREATMEliT PONDS 3/4.11.2.1 RADI0 ACTIVE EFFLUENTS: GASEOUS EFFLUENTS DOSE RATE 3/4.11.2.2 RADI0 ACTIVE EFFLUENTS: DOSE - NOBLE GASES 3/4.11.2.3 RADI0 ACTIVE EFFLUENTS: DOSE - 10 DINE-131 AND 10 DINE-133. TRITIUM AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM 3/4.11.2.4 RADI0 ACTIVE EFFLUENTS: GASEOUS RADWASTE TREATMENT SYSTEM 3/4.11.3 RADICACTIVE EFFLUENTS: SOLID RADI0 ACTIVE WASTE 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 COMPARISON PROGRAM 6.9.1.6 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT t
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The procedural details that have been reriovcd from the TSs are not rec;uired by the conmission's regulations to be included in the TSs.
The RETS, as relocated in the SLC l'anual, can be subsequently changcd by th< licensee (per 10 CPR 50.E9) without prior 11PC approval.
Changes 'o the CCCM and PCP are docun'ented and will be retained for the c'uration of the l'cCuire operating licenses in accordance with TS 6.10.2.n.
(3) The licensee has proposed teplacing the existing slecificatioris in the Adninistrative Controls section of the TSs f or the Annual Padiological Envirottental Operating Percrt, Specification 6.9.1.6 for the SemiannualRadioactiveEffluentPeleaseReport, Specification 6.9.1.7, for the Process Control Program, Specification 6.13, and for the Offsite Dose Calculation Manual, Specification 6.14, with the upda'ed specifications that were provided in GL 89-01.
The following specifications that are included under the heading of Radioactive Effluents have becn retaired in the TSs. This is in accordance with the guidance of GL 09-01.
SPEClflCAT10N TITLE 3/4.3.3.9 EXP'.051VE GAS M0filTOR1tiG If4STRUMEt4 TAT 10tl (R9tained existing requirements of this specification) 3/4.11.1.4 L10UID HOLOUP TAtlKS 3/4.11.F.5 EXPLOS!VE GAS MIXTURE 3/4.11.2.6 GAS STORAGE tat!KS On the basis of the above, the Corrnission's staff finds that the changes included in the proposed TS an.endrient request are consistent with the guidance provided in GL 89-01.
Because the control of radioactive effluents continues to be limited in accordance with operating procedures that rnust satisfy the regulatory requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.30a, and Appendix 1 to 10 CFR Part 50, the 'JC stoff concludes that this change is administrative in nature and consequently has no in' pact on plant safety.
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Accordingly, the staff finds the proposed changes acceptable.
3.0 STATE CONSULTATION
l In accordance with the Conrnission's regulations, the florth Carolina State
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official was notified of the proposed issuance of the amendments. The State of ficial had no corrnents.
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- w. 4,0 ENVIRONMENTAL CONSIDERATION The amendments change requirerrents 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.
The amendments also involve changes in recordkeeping, reporting, or administrative procedures and program 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 these amendments involve no significant hazards consideration, and there has been no public comment on such finding (55 FR 34367 on August 2?, 1990).
Accordingly, the amendrents meet the eligibility criteria for categorical exclusion set forth in 10 CFR SI.22(c)(9) and (10),
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be preparLJ in connection with the issuance of these amendments.
5.0 CONCLUSION
The Conmission 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, and (2) such activities will be conducted in compliance with the Corrnission's regulations, and (3) the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributors:
W. Wayne t1einte, PRPB/DREP Thomas G. Dunning, OTSB/DOEA Timothy A. Reed, PDil-3/DRP-!/Il Date: May 22, 1991
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