ML20151A996

Safety Evaluation Supporting Amend 60 to License DPR-34

ML20151A996
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/20/1988
From:	Office of Nuclear Reactor Regulation
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ML20151A991	List: ML20151A988 ML20151A992 ML20151A996 ML20151B003
References
NUDOCS 8807200193
Download: ML20151A996 (3)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

\...../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.6n TO FACILITY OPERATING LICENSE N0. OPR-34 PbBLI: SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267

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1.0 INTRODUCTION

This Safety Evaluation is in response to a series of proposals by the licensee to revise the Fort St. Vrain (FSV) Technical Specifications (TS) concerning the setpoints for the Plant Protective System (PPS). The PPS setpoints were originally determined withcut allowance for the errors l caused by changes and inaccuracies in the instrumentation setpoints.  ;

This was not an imediate safety concern because of the wide safety l margins in the FSV accider.t analyses. However, the staff and the i licensee have worked for several years to correct this problem.

l By submittals dated June 21, 1985, May 15, 1986, August 28, 1987 and February 8, 1988, the licensee proposed a series of changes to the TSs to l address this problem. The specific changes proposed allowed for l instrunent errors in accordance with Instrument Society of America (ISA)

Standard S67.04-1982. This standard is entitled Setpoints For Nuclear Safety-Related Instrumentation Used In Nuclear Power Plants". A key part of the staff's review was an evaluation of the licensee's proposals l against this standard. l The process of reviewing the licensee's proposals involved several steps. .

First, in some cases, there was not sufficient margin between the old I accident analysis value of the trip parameters and the current setpoints to fully accomodate the instrument errors. In these cases, the licensee has submitted a revised accident analysis or a sumary thereof. These were reviewed by the staff and approved in a safety evaluation dated January 24, 1986. With certain exceptions that are noted herein, the staff accepted the licensee's revised safety analyses. Those findings are incorporated by reference in this evaluaiion.

The staff requested assistance in this review from its contractor, Idaho National Engineering Laboratory (INEL). In order to complete this review, INEL generated a Technical Evaluation Report (TER) which is Enclosure 3.

The INEL TER provides both the basis for this Safety Evaluation and recomendations for future actions to be performed by the licensee.

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2.0 EVALUATION In this proposed change, the licensee has reanalyzed the setroints for eight trip functions of the PPS. These are:

- Primary Coolant Pressure - High & Low, Superheat Header Temperature - Low,

- Circulator Speed - High & Low.

- Fixed Feedwater Flow - Low,

- Loss of Circulator Bearing Water, and

- Neutron Flux - High.

All of these revised setpoints were reevaluated in the staff's January 24, 1986 Safety Evaluation. They arc. also discussed in detail in the enclosed TER for completeness. In view of these previous detailed evaluations, the staff concludes that the revised evaluations of the trips setpoints listed above are acceptable.

The licensee's propcsed changes to the TSs reflect the revised safety evaluations above and new setpoints determined by the ISA standards as recomended above. The specific changes are incorporated in Sections 2.3 and 4.4 of the FSV TSs. Other improvements to the TSs include clarification of the bypass and disablement conditions for the PPS moisture monitors and an improved description of the undervoltage systen. Since the setpoints have now been correctly determined to allow for instrumentation errors with an approved methodology, the staff finds they are acceptable.

3.0 FUTURE ACTIONS i l

The review performed by INEL was also directed to the ouestion of other tasks that the licensee needed to perfonn. These future tasks involved follow-up activities to this TS change. Other tasks involved changes to the FSAR to make it note consistent with the results of the current activity and its findings. Specific future changes idertified by the staff included:

- Reantlysis of the programed and fix feedwater flow-low trip and their associated bypass conditions, Justification of the PPS bypass conditions for the startup and low power modes,

- Upgrade of certain other PPS setpoint functions to STS standards, with upgraded surveillance and calibration requirements, and  ;

Provide appropriate setpoints for the automatic engineered safeguards in the plant's electrical system.

The licensee should provide the staff with a specific schedule for accomplishing these tasks in a timely manner.

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4.0 ENVIRONMENTAL CONSIDERATION

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The NRC staff has considered the environmental impact of the proposed l changes to the TS. An "Environmental Assessment and Finding of No M (53 N 2039

5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, andsuch (2) public activities will be conducted in compliance with the Comission's regulations, and the issuance of the amendment will not be inimical to the con 7ron defense and security or to the health and safety of the public.

Date: June 20,1988 Principal Contributors: J. Mauck, SICB K. Heitner, PD-IV a

7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.60 to Facility Operating License No. DPR-34, to Public Service Company of Colorado, which revised 'the Technical Specifications for operatior.

of the Fort St. Vrain Nuclear Generating Station, located in Platteville, Colorado. The amendment will be effective 90 days after its date of issuance.

The amendment revised certain setpoints for the Plant Protective System to allow for instrumentation errors.

The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.

Notice of Consideration of Issuance of Amendment and Opportunity for Prior Hearing in connection with this action was published in the FEDERAL REGISTER on May 9, 1988 (53 FR 16481). No request for a hearing or petition for leave to intervene was filed following this notice.

The Commission has prepared an Environmental Assessment and Finding of No Significant Impact related to the action and has concluded that an environmental impact statement is not warranted because there will be no p3co# Mf

environmental impact attributed to the action beyond that which has been predicted and described in the Comission's Final Environmental Statement for the facility dated August 1972.

For further details with respect to this action, see (1) the application for amendment dated February 8,1988,(2) Amendment No. 60 to Facility Operating License No. DPR-34, and (3) the Environmental Assessment and Finding of No Significant Impact (53 FR 22239). All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W. , Washington, D.C. , and at the Greeley Public Library, City Complex Building, Greeley, Colorado. A copy of items (2) and (3) may be obtained upun request addressed to the U.S. Nuclear Regulatory Comission, Washington, D.C.

20555, Attention: Director, Division of Reactor Projects - III, IV, Y and Special Projects.

Dated at Rockville, Maryland, this 20th day of June,1988.

FOR THE NUCLEAR REGULATORY COWISSION l

00Y" Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

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