ML20086A435
| ML20086A435 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/29/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086A428 | List: |
| References | |
| NUDOCS 9111190123 | |
| Download: ML20086A435 (4) | |
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5AFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.104 TO FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395
1.0 INTRODUCTION
By letter dated June 3,1991, South Carolina Electric & Gas Company proposed to incorporate programatic controls for radiological effluents and radiological environmental monitoring in the Administrative Controls section of the Technical Specifications (TS) consistent with the requirements of 10 CFR 20.106, 40 CFR Part 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 TS to the Offsite Dose Calculation Manual (ODCM) or to the Process Control Program (PCP) for solid radioactive wastes, as appropriate. With these changes, the specifications related to RETS reporting requirements were simplified.
Finally, changes to the definitions of the ODCM and 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 TS are in accordance with the guidance provided in Generic Letter 89-01 and are addressed below.
(1) The licensee has proposed to incorporate programatic controls for radioactive effluents and radiological environmental monitoring in TS 6.8.4, Procedures and Programs, as noted in the guidance provided in Generic Letter 89-01. The programmatic controls ensure that programs are established, implemented, and maintained to ensure that operating procedures are proviced 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 TS have been prepared to implement the relocation of these procedural details to the ODCM or PCP. These 9111190123 9110*29 l
DR ADOCK 0500 5
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l changes to the ODCM and PCP have been prepared in accordance with the new Administrative Controls in the TS on changes to the ODCM and PCP so that they will be incorporated into the ODCM or PCP when this amendment is issued.
SPECIFICATION TITLE 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4.3.3.9 LIQUID EFFLUENTS: CONCENTRATION 3/4.11.1.1 LIQUID EFFLUENTS: DOSE 3/4.11.1.3 LIQUID EFFLUENTS: LIQUID WASTE TREATMENT 3/4.11.2.1 GASEOUS EFFLUENTS: DOSE RATE 3/4.11.2.2 RADIOACTIVE EFFLUENTS: DOSE - N0BLE GASES f
3/4.11.2.3 RADI0 ACTIVE EFFLUENTS:
DOSE - RADIOI0 DINES, s.
RADI0 ACTIVE MATERIAL AND TRITIUM 3/4.11.2.4 RADI0 ACTIVE EFFLUENTS: GASEOUS RADWASTE TREATMENT 3/4.11.3 RADIOACTIVE EFFLUENTS: SOLID RADI0 ACTIVE 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 COMPARISON PROGRAM 6.9.1.6 REPORTING REQUIREMENTS: ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.8 REPORTING REQUIREMENTS:
SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.10.2 RECORD RETENTION 6.13 PROCESS CONTROL PROGRAM 6.14 0FFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS In addition, the bases associated with the above listed TS will be deleted.
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The procedural details that have been removed from the TS are not required by the Commission's regulations to be included in the TS. They have been prepared for incorporation in the ODCM or PCP upon issuance of this license amendment and may be subsequently changed by the licensee without prior NRC approval. Changes to the ODCM and PCP are documented and will be retained for the duration of the operating license in accordance with TS 6.10.3 o.
(3) The licensee has proposed replacing the following TS in :he administrative controls section of the TS with the updated TS provided by GL-89-01:
SPECIFICATION TITLE 6.9.1.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.4 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.13 PROCESS CONTROL PROGRAM 6.14 0FFSITE DOSE CALCULATION MANUAL In accordance with the quidance of Generic Letter 89-01 the following sections, which are included under the heading of Radioactive Effluents, have been retained in the TS.
SPECIFICATION TITLE 3/4.3.3.9 WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION (Retained existing requirements of this specification) 3.11.1.4 LIQUID HOLOUP TANKS 3.11.2.5 EXPLOSIVE GAS MIXTURE 3.11.2.6 GAS STORAGE TANKS 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 I 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.
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ccordance with the Comission's regulations, the South Carolina j
ar. ate official was notif' 1 of the proposed issuance of the amendment.
The State official had no coments.
y
,, p V.'tObMENTAL CONSIDERATION ac amere eri e s a requirement with respect to installation or use y.<
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'P af a facility, o c.ent located within the restricted area as cefined in
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10 CFO Part 20.
Lne NRC staff has determined that the anendment involves if A no sigtiificant increase in the amounts, and no significant change in the typs, cf any eftluents that may be released offsite, and that there is no P
wignifi' ant increase in individual or cumulative occupational radiation exposure. The Cochiss';an has previously issued a proposed finding that the amendment involves.no significant hazards censideration, and there has f
beten no public coment on such finding on June 26, 1991 (56 FR 29200).
Accordingly, the amendment meets the eligibility criteria for categorical
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exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 C0ht!.t!S10N The Commission has ';oncluded, 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 Comission's regulations, and (3) the issuance of the ammiment will not be inimical to the common defense and sectirity or to the health e.d safety of the public.
1 Principal Contributors:
W. Wayne Meinke Thomas Dunning G. Wunder e
Date:
October 29, 1991
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