ML17310B207
| ML17310B207 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/06/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17310B208 | List: |
| References | |
| NUDOCS 9404180057 | |
| Download: ML17310B207 (10) | |
Text
7590-01 UNITED STATES NUC EAR R GULATORY COMMISS ON ARIZONA PUBLIC SERV CE COMPANY ET L.
DOCKET NOS.
STN 50-528 STN 50-529 AND STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNITS I AND 3 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment
.to Facility Operating License No. NPF-41, NPF-51, and NPF-74 issued to Arizona Public Service
- Company, (the licensee),
for operation of Palo Verde Nuclear Generating Station Units 1, 2,
and 3
located in Wintersburg, Arizona.
ENVIRONMENTAL ASSESSMENT Identification of Pro osed Action:
The proposed action would revise the provisions in the Technical Specifications (TS) related to increasing the pressurizer safety valve (PSV) setpoint tolerance from +/-1 percent to +3 percent and -1 percent, increasing the main steam safety valve (HSSV) setpoint tolerance from
+/-1 percent to +/-3 percent, reducing the high pressurizer pressure trip setpoint (HPPT) response time from 1. 15 seconds to 0.5 second, and reducing the Technical. Specifications minimum auxiliary feedwater (AFW) pump flow requirement from 750 gallons per minute (GPH) to 650 GPH.
The proposed action is in accordance with the licensee's application for amendment dated November 13,
- 1990, as supplemented by letters of additional information dated Hay 27,
- 1992, Hay 13,
- 1993, and November 12, 1993.
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The Need for the Pro osed Action:
The proposed changes
.to the TS are required in order to provide the licensee with operational flexibility in meeting surveillance requirements for auxiliary feedwater (AFW) flow, and pressurizer safety valve (PSV) and main steam safety valve (NSSV), li,ft setpoint tolerances.
The proposed change to the TS al,so involves a reduction of the high pressurizer pressure trip (HPPT). response time.
This reduction is necessary to ensure that the peak pressures during postulated accident scenarios for the other changes (AWF,
- PSV, and HSSV) do not violate safety limits.
Environmental Im act of the Pro osed Action:
The Commission has completed its evaluation of the proposed revision to the TS and the licensee's assessment of increased radiological release as a result of the safety valve setpoint tolerance change and the proposed reduction in auxiliary feedwater flow.
For the most limiting SGTR
- scenario, this results in an,increase in the 2-hour thyroid dose from. 200 rem to less than 248 rem.
Adding the increased dose due to the expanded PSV and HSSV setpoint tolerances (which the licensee calculated as a
5-percent dose increase),
results in a 2-hour dose of 260 rem.
This. value provides adequate margin to the 10 CFR Part 100 guideline of 300 rem.
The licensee also evaluated radiological release for the reactor coolant pump (RCP) shaft seizure
- event, and determined that the calculated 0.5 rem increase was insignificant compared to the 246 rem dose reported in Supplement 2 to the staff's Safety Evaluation Report rel'ated to the Combustion Engineering Standard Safety Analyses Report (CESSAR) for System 80, and the 300 rem SRP acceptance criteria.
The staff finds the analysis results, uti.lizing proper conservatisms, to be within 10 CFR guidelines.
0 Therefore, the proposed changes do not significantly increase the probability or consequences of accidents, no changes are being made in -the types of any effluents that may be released offsite, and there is no significant increase in the allowable individual or cumulative occupational radiation exposure.
Accordingly, the Commission concludes that this proposed action would result in no significant radiological environmental impact.
With regard to potential nonradiological
- impacts, the proposed changes do not affect nonradiological plant effluents and have no other environmental impact.
Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed amendment.
The Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the Federal
~Re ister on December 27, 1990 (55 FR 53220).
Two petitions for leave to intervene and request for hearing were filed following this Notice.
One request was denied and the other granted.
- However, the party that was granted the hearing later voluntarily withdrew their contention.
Alternative to the Pro osed Action:
Since the Commission concluded that there are no significant environmental effects that would result from the proposed
- action, any, alternatives with equal or greater environmental impacts need. not be evaluated.
The principal alternative 'would be to deny the requested amendment.
This would not reduce environmental impacts of plant operation and would result in reduced operational flexibility.
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Alternative Use of Resources:
This action does not involve the use of resources not previously considered in the Final Environmental Statement related to.operation of the Palo Verde Nuclear. Generating Station Units 1, 2,
and 3, dated February 1982'NUREG 0841).
A encies and Persons Consulted:
The staff consulted the State of Arizona official regarding environmental impact of the proposed action.
The State official had no comments.
FINOING OF NO SIGNIFICANT IMPACT Based upon the foregoing environmental assessment, the Commission concludes that the proposed action will not have a significant effect on the quality of the human environment.
Accordingly, the Commission has determined not to prepare an environmental impact statement for the proposed license amendment.
For further details with respect to this action, see the licensee's application for amendment dated November 13,
- 1990, and supplemented by letters of additional information dated May 27,
- 1992, May 13,
- 1993, and November 12,
- 1993, which are available for public inspection at the
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Commission's Public Document
- Room, Gelman Building, 2120 L Street, N.W.,
Washington, D.C.
20555 and at the local public document room at the Phoenix Public, Library, 12 East McDowell Road,
- Phoenix, Arizona 85004.
Dated at RockvW'3e, Maryland, this 6th day of April 1994.
FOR THE NUCLEAR REGULATORY COMMISSION Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Project III/IV Office of Nuclear Reactor Regulation
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