ML17306A804
| ML17306A804 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/18/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17306A805 | List: |
| References | |
| NUDOCS 9206260366 | |
| Download: ML17306A804 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE NO. NPF-41 AMENDMENT NO.
48 TO FACILITY OPERATING LICENSE NO. NPF-51 AND AMENDMENT NO. 34 TO FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY ET AL.
PALO VERDE NUCLEAR GENERATING STATION UNIT NOS.
1 2
AND 3 DOCKET NOS.
STN 50-528 STN 50-529 AND STN 50-530
- 1. 0 INTRODUCTION By letter dated February 14, 1992, the Arizona Public Service Company (APS or the licensee) submitted a request for changes to the Technical Specifications (TS) for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3
(Appendix A to Facility Operating License Nos.
NPF-41, NPF-51, and NPF-74, respectively).
The Arizona Public Service Company submitted this request on behalf of itself, the Salt River Project Agricultural Improvement and Power District, Southern California Edison
- Company, El Paso Electric Company, Public Service Company of New Hexico, Los Angeles Department of Water and
- Power, and Southern California Public Power Authority.
The proposed changes would incorporate programmatic 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 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 TS to the Offsite Dose Calculation Manual (ODCH) or to the Process Control Program 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 ODCH and PCP were proposed consistent with these changes.
Guidance on these proposed changes was provided to all power reactor licenses and applicants by Generic Letter 89-01 dated Janaury 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 programmatic controls for radioactive effluents and radiological environmental monitoring in Specification 6.8.4, "Procedures and Programs," of the TS as noted in 9206260366 920618 PDR ADOCK 05000528 PDR
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 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 requrements, or reporting requirements for the following specifications have been prepared to implement the relocation of these procedural details to the ODCH or PCP.
These changes to the ODCH and PCP have been prepared in accordance with the new Administrative Controls in the TS on changes to the ODCH and PCP so that they will be implemented in the ODCH or PCP when this amendment is issued.
SPEC IF ICATON TITLE 3/4.3.3.8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3/4.11.1.1 RADIOACTIVE EFFLUENTS:
LIQUID EFFLUENTS CONCENTRATION 3/4.11.1.2 RADIOACTIVE EFFLUENTS:
LIQUID EFFLUENTS DOSE 3/4. 11.2. 1 RADIOACTIVE EFFLUENTS:
GASEOUS EFFLUENTS DOSE RATE 3/4. 11.2.2 RADIOACTIVE EFFLUENTS:
DOSE NOBLE GASES 3/4. 11.2. 3 RADIOACTIVE EFFLUENTS:
DOSE IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM 3/4.11.2.4 RADIOACTIVE EFFLUENTS:
GASEOUS RADWASTE TREATMENT SYSTEM 3/4.11.3 RADIOACTIVE EFFLUENTS:
SOLID RADIOACTIVE WASTES 3/4.11.4 RADIOACTIVE 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 ENVIRONHENTAL HONITORING:
INTERLABORATORY COMPARISON PROGRAM 6.9.1.7 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.8 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GL 89-01 also suggested that TS Section 6.15 (Major Changes to Liquid,
- Gaseous, and Solid Radwaste treatment systems) be relocated to the ODCH or PCP as appropriate.
However, Arizona Public Service (APS) has decided to leave Section 6. 15 in the TS as part of the Administrative Controls.
These procedural details that have been removed from the TS are not required by the Commission's regulations to be included in TS.
They have been prepared for incorporation in the ODCH or PCP upon issuance of this license amendment and may be subsequently changed by the licensee without prior NRC approval.
Changes to the ODCH and PCP are documented and will be retained for the duration of the operating license in accordance with Specification 6.10.2.
(3)
The licensee has proposed replacing the existing specifications in the Administrative Controls section of the TS for the Annual Radiological Environmental Operating Report, Specification 6.9. 1.7, for the Semiannual Radioactive Effluent Release Report, Specification 6.9. 1.8, for the Process Control Program, Specification
- 6. 13, and for the Offsite Dose Calculation Manual, Specification 6.14, with the updated specifications that were provided in Generic Letter 89-01.
The following specifications that a} e included under the heading of Radioactive Effluents have been retained in the TS.
This is in accordance with the guidance of Generic Letter 89-01.
SPECIFICATON TITLE 3/4.3.3.8 EXPLOSIVE GAS MONITORING INSTRUMENTATION (Retained existing requirements of this specification) 3/4.11. 1.3 LIQUID HOLDUP TANKS 3/4.11.2.5 EXPLOSIVE GAS MIXTURE 3/4. 11.2.6 GAS STORAGE TANKS 3/4. 11.2.7 HAIN CONDENSER 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.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendment.
The State official had no comments.