ML17310A518

Application for Amends to Licenses NPF-41,NPF-51 & NPF-65, Requesting Change to Word Pressurizer to RCS for Item 4 in Tables 3.3-10 & 4.3-7

ML17310A518
Person / Time
Site:	Palo Verde
Issue date:	08/05/1993
From:	CONWAY W F ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17310A520	List: ML17310A518 ML17310A521
References
102-02604-WFC-T, 102-2604-WFC-T, NUDOCS 9308130151
Download: ML17310A518 (15)

Text

ACCELERATED D STBZBUTION DEMONS RATION SYSTEM V t V REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9308130151 DOC.DATE: 93/08/05 NOTARIZED:

YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-.50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION CONWAY,W.F.

Arizona Public Service Co.(formerly Arizona Nuclear Power g RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)I

SUBJECT:

Application for amends to Licenses NPF-41,NPF-51 requesting change to word pressurizer to RCS for tables 3.3-10 6 4.3-7.DISTRIBUTION CODE: ADO ID COPIES RECEIVED: LTR I ENCL L TITLE: OR Submittal:

General Distribution NOTES:STANDARDIZED PLANT Standardized plant.Standardized plant.NPF-65, item 4 in SIZE: D 05000528 A 05000529 05000530 D D RECIPIENT ID CODE/NAME PDV LA TRAMMELL, C INTERNAL: ACRS NRR/DRCH/HI CB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PDV PD TRAN,L NRR/DE/EELB NRR/DRPW/OTS B NRR/DSSA/SRXB OC EG FILE 01 NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 0 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:

D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 21 t T~~

~'.'v WILLIAM F.CONWAY EXECUTIVE VICE PRES I 0ENT NUCLEAR Arizona Public Service Company P.O.BOX 53999~PHOENIX.ARIZONA 85072<999 102-02604-WFC/TRB/JNI August 5, 1993 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos.STN 50-528/529/530 Proposed Amendment to Technical Specification Section 3/4.3.3.6 File: 93-005-41 9.05 In accordance with 10 CFR 50.90, Arizona Public Service Company (APS)is requesting an amendment to Technical Specification 3/4.3.3.6"Post-Accident Monitoring Instrumentation," Table 3.3-1 0 and Table 4.3-7.This amendment is requested to change the word"Pressurizer" to"Reactor Coolant System" for item P4 in both Tables 3.3-1 0 and 4.3-7.This change is administrative in nature in that it only corrects the nomenclature of the instrumentation.

Provided in the enclosure.to this letter are the following:

A.Description of the Proposed Amendment Request B.Purpose of the Technical Specification C.Need for the Technical Specification Amendment D.Safety Analysis of the Proposed Technical Specification Amendment E.No SigniTicant Hazards Consideration Determination F.Environmental Impact Consideration Determination G.'arked-up Technical Specification Pages Pursuant to 10 CFR 50.91 (b)(1), a copy of this request has been forwarded to the Arizona Radiation Regulatory Agency.y3Q023 9308130151 930805'DR ADOCK 05000528')P PDR U.S.Nuclear Regulatory Commission ANN: Document Control Desk Proposed Amendment to Technical Specification Page 2 If you have any questions, please contact Thomas R.Bradish at (602)393-5421.Sincerely, WFC/TRB/JNI/rv Enclosure cc: B.H.Faulkenberry J.A.Sloan A.V.Godwin

STATE OF ARIZONA))ss.COUNTY OF MARICOPA)I, W.F.Conway, represent that I am Executive Vice President-Nuclear, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true and correct.W.F.Conway Sworn To Before Me This D Day Of , 1993.Notary Public My Commission Expires I)v

ENCLOSURE PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION 3/4.3.3.6

A.DESCRIPTION OF THE PROPOSED AMENDMENT REQUEST The proposed Technical Specification amendment changes Table 3.3-1 0, item 4, and Table 4.3-7, item 4, from"Pressurizer Pressure-Wide Range" to"Reactor Coolant System Pressure-Wide Range." The new wording agrees with the as-built configuration and the field equipment identification.

This is an administrative change and does not change equipment, configuration, or operation.

B.PURPOSE OF THE TECHNICAL SPECIFICATION Section 3/4.3.3.6, POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation (Table 3.3-10)ensures that sufficient information is available on selected plant parameters following an accident.This capability is consistent with the recommendations of Regulatory Guide (RG)1.97,"Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG 0578,"TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." C.NEED FOR THE TECHNICAL SPECIFICATION AMENDMENT This Technical Specification amendment will clarify the intended instrumentation required and eliminate potential confusion between the reactor coolant system pressure instruments and the pressurizer pressure instruments.

D.SAFETY ANALYSIS OF THE PROPOSED TECHNICAL SPECIFICATION AMENDMENT The Post-Accident Monitoring Instrumentation Tables in the Technical Specification use the wording"Pressurizer Pressure," instead of"Reactor Coolant System Pressure," to describe the wide range pressure instrumentation required for Post-Accident Monitoring.

RG 1.97, Revision 2, December 1980, refers to Reactor Coolant System Pressure with a range of 0 to 4000 psig.The PVNGS UFSAR, Table 1.8-1, refers to Reactor Coolant System Pressure with a range of 0 to 4000 psig.PVNGS equipment descriptions list both instruments, Reactor Coolant System Pressure 0-4000 psig and Pressurizer Pressure 0-3000 psig.This amendment will clarify the intended instrumentation required and eliminate potential confusion between the reactor coolant system pressure instruments and the pressurizer pressure instruments.

E.NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92.A proposed amendment to an operating license for a facility involves a no significant hazards consideration if operation of the facility, in accordance with a proposed amendment, would not: (1)Involve a significant increase in the probability or consequences of an accident previously evaluated or;(2)Create the possibility of a new or different kind of accident from any accident previously evaluated or;(3)Involve a significant reduction in a margin of safety.A discussion of these standards as they relate to this amendment request follows: Standard 1-Involve a significant increase in the probability or consequences of an accident previously evaluated.

This amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated since the change clarifies the equipment description of Technical Specification Table 3.3-1 0, item 4, and Table 4.3-7, item 4, by changing the wording from"Pressurizer Pressure" to"Reactor Coolant System Pressure."

\I Standard 2-Create the possibility of a new or different kind of accident from any accident previously analyzed.This amendment request does not create the possibility of a new or different kind of accident from any accident previously analyzed since the change does not modify, add or remove equipment.

The change clarifies the equipment description of Technical Specification Table 3.3-10, item 4, and Table 4.3-7, item 4, by changing the wording from"Pressurizer Pressure" to"Reactor Coolant System Pressure." Standard 3-Involve a significant reduction in a margin of safety.The margin of safety presently provided is not affected by the change.The change does not affect any process parameters or system setpoints.

The change clarifies the equipment description of Technical Specification Table 3.3-1 0, item 4, and Table 4.3-7, item 4, by changing the wording from"Pressurizer Pressure" to"Reactor Coolant System Pressure." F.ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION APS has determined that the proposed amendment involves no change in the amount or type of effluent that may be released offsite, and that there is no increase in individual or cumulative occupational radiation exposure;As, such, operation of PVNGS Units 1, 2, and 3, in accordance with the proposed amendments, does not involve an environmental impact.G.MARKED-UP TECHNICAL SPECIFICATION PAGES Units 1, 2, and 3: page 3/4 3-58 (Table 3.3-10)page 3/4 3-60 (Table 4.3-7)

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