ML19241B043
| ML19241B043 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19241B039 | List: |
| References | |
| NUDOCS 7907110592 | |
| Download: ML19241B043 (4) | |
Text
UNITED STATES
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 26 TO FACILITY OPERATING LICENSE NO. DPR-64 POWER EUTHORITY OF THE STATE OF NEW YORK INDI AN POINT NtJCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 Introduction By letter dated April 26, 1979, Power Authority of the State of New York (the licensee) requested an amendment to Facility Operating License No.
DPR-64 for the Indian Point Nuclear Generating Unit No. 3.
The proposed amendment would change the Technical Specifications to require actuation of safety injection based on 2 out of 3 channels of low pressurizer pressure.
Until this change has been accomplished, it is understood that the low pressurizer level trips in the existing safety injection logic would remain tripped as piovided for in IE Bulletin 79-06A (Item 3) and 79-06A, Revisiori 1.
As discussed with you, it is further understood and acceptable for the pressurizer level bistables to be returned to their normal position
'vhile this modification is underway.
Further, it is understood that the changes will be made one train at a time, with each train tested before being placed into service.
Discussien As a result of our ongoing review of the events associated with the March 28 accident at Three Mile Island Unit 2, the NPC Office of Inspection and Enforcement issued a number of IE Bulletins describing actions to be taken by licensees.
IE Bulletin 79-06 (April 11, 1979) called for licensees with Westinghouse PWR's to instruct operators to manually inir.iate safety injection when the pressure indication reaches the actuation setpoint whether or not the level indication has drooped to the actuation setpoint.
IE Bulletin 79-06A ( April la,1979) further called for these licensees to trip the low pressurizer level bistable.1 such that, when the arrssurizer pressure reaches the low setpoint safety injec.icn woul' be initiated regardless of the pressurizer level This action was comc1 ced on April 14, 1979.
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IE Bulletin 79-06A, Revision 1 (April 18, 1979) modified the action called for in 79-06A by allowing pressurizer level bistables to be returned to their normal (untripped) operating cositions during the pressurizer pressure channel functional surveillance tests.
The effect of tripping the cressurizer low level bistables which are normally coincident with the cressiirizer low pressure bistables, has the effect of reducing this safety injection actuation icgic to a 1 out o# 3 logic.
A single instrument failure of 1 of the 3 low pressure bistable channels could therefore result in an unwanted safety irjection.
To prevent. this, the licensee nroposed in an April 26, '979 letter, a design mod 1 #ication which would align the 2 out of 3 logic existing pr essurizer los pressure bist. ables in.
Evaluation The proposed modification to the safety injection actuation systen entails remcving the cressurizer level signal from each of the pressurizer level /
?ressure channel trip and converting the system to a two-out-of-three pres-The instrumentation logic takes pressurizer surizer low pressure trip.
pressure signals from three cressure tran<mitters and initiates a safety injection actuation whenever two of the three signals reach the low pressure These modifications will satisfy the requirements setpoint of l'00 psig.and other 3:andards of installation required during the of IEEE 279-1971, ae find these modifications acceptable.
olant construction stage.
We have reviewed the instrumentation and controls "nect of the proposed change in accordance with 1EEE-279 and other app'.
e standards and Reg. Guides.
The trocification eliminates pressur level as a required initiating signal to actuate ECCS.
The licensee proposes to use a 2-out-of-3 logic on low pressurizer pressure alone.
Sepatation of trains will be maintained, testability will be maintained, and verification of proper actuation of the first train can be cerformed prior to modification of the second train, p2 286
. We have reviewed the instrumentation power sources and determined there are four 120V instrument buses. Three of the buses (31, 32 and 33) are supplied from inverters which in turn are energized from three independent battery banks for the plant.
The faarth bus (34) is supplied by a constant voltage transformer connected to 480 volt (emergency power) motor control center 368.
Alternate power to the four buses can be supplied from the lighting switchgear.
The three pressurizer pressure transmitters channels are energized fra buses 31, 32 and 34; consequently, a single failure will fail anir cne instrument channel.
The licensee has committeed to install a fourth battery and inver+.er as an additional source of instrument power during the.iext refueling outage (fall 1979), pending the receipt en site of the necessary materials, but to be installed not later thin l'81 refueling outage.
The proposed Technical Specifications change Section 3.5 to specify automatic safety injection actuation on a two-out-of-three pressurizer low pressure of 1700 psig. We find the changes to the Technical Specifications to be acceptable.
Based on our review of the licensee's submittal, we conclude that the modifications to the safety inje. tion actuation system logic satisfy the requirements of IEEE 279-1971 and that the associated Technical Specificaions are correct; and therefore, are acceptaole.
We also conclude that tne proposed change will be in accordance with the above standards and guides, and that none of the transient and accident analyses are adversely affected by the change.
The only effect may be a sooner SI actuation.
Therefore, we find the procosed change to be acceptable.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or totai amounts nor an increase in power level and will not result in any significant env'ronmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR @51.3(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be crepered in connection with the issuance of these amendments.
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. Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a sigrificant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hczards consideration, (2) there is reasonable assurance that the health and safety of the public uil1 not bc cndangered by operation in the proposed manner, and (3) such activities will be conducted in coc.pliance with the Cer, mission's regulations and the issuance of this ancodt.ent will not be inimical to the comr.on defense and security or to the health and safety of the public.
Date: May 31,19,;
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7590-01 UNITED STATES NUCLEfR REGULATORY COMMISSION DOCKET NO. 50-286 POWER AUTHORITY OF THE STATE OF NEW YORK NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.26 to Facility Operating License No. DPR-64 issued to the Power Authority of the State of New York (the licensee), which revised Technical Specifications for operation of the Ir :hn Point Nuclear Generating Unit No. 3 (the facility) located in Buchanan, l'istchester County, New York. The amendment is effective as of the date of issuance.
The amendment revises the Technical Specifications to require actuation of safety injection based on 2 out of 3 channels of low press-urizer pressure.
The application for 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 amendments.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
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7590-01 The Commission has determined that the issuance of this amendment will not restit in any significant environmental im,)act and that pursuant to 10 CFR 551.5(d)(4), an environmental impact statement or negative declaration end environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application 'or amendment dated April 26,1979,(2) Amendment No. 26 to License No. DPR-64, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, NW, Washington, D. C. and at the White Plains Public Library,100 nartine Avenue, White Plains, New York.
A single copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attention:
Director, Division of Operating Reactors.
Dat 2d at Bethesda, Maryland, this 31st day of Pay,1979.
FOR THE NUCLEAR REGULATORY COMMISSION ht.BMW q
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors r.
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