RBG-26202, Application for Amend to License NPF-47,changing Leak Detection Setpoints for RWCU & Rcic/Rhr Sys.Fee Paid

Application for Amend to License NPF-47,changing Leak Detection Setpoints for RWCU & Rcic/Rhr Sys.Fee Paid

ML20215L325
Person / Time
Site:	River Bend
Issue date:	06/18/1987
From:	Deddens J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20215L327	List: ML20215L345 RBG-26202, Application for Amend to License NPF-47,changing Leak Detection Setpoints for RWCU & Rcic/Rhr Sys.Fee Paid
References
RBG-26202, NUDOCS 8706260013
Download: ML20215L325 (7)

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' N.23r Benditoxion - Unit 1 ,' F -

L Docket No.-50-45i0 t,a Y , /' ~i f -

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- Gulf fStates Ve?lities (]G5U) here:by files ~an amendment to the River l Bad +. l '

Statics Un1 F 11 Tcch'n fal'. Specifications, . Appendix 'A to- .Facilfty d

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0perating.*1dcenses NPFJ

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'i i filed'to; change ^the.iled;47,pursuantto-10CFR50.90. detection setpoints~-for the Reactor: This application Wa t e r'4s.

Cleanur (RWCU), . Attdch'. ppt [] O 'and the Reactior # Core Isolation

- Coolin;;/Residigl Heat" Pemovs1 GCIC/RHR) -System,' Attachment 2. The attachtsnts j fnclude : 'the psip6sedl revisions and justifications to the. 1 River;Berid 1%chnical Specifications.e /  !

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Pursuantt to 10Ci/F176.12, CSU has' enclosed a check in the amount..of '

Lone-hundred andddifcy' dollars ($150,00) for- the license amendment application? fee. 'Your prompt'. attention to thisI application is i

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. C, Peddens

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1. River Bend Nuclear Group JCD/ / B /je ,

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" bb: 'Mr. Robert D. Martin, Regional Administrator

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U.S. Nuclear Regalatory Commission Region IV- l 611 Ryan Plaza Drive, Suite 1000 ,

Arlington, TX 76011

.iRC Senior Resident Inspector.

P.O. Box 1051 i St. Francisville, LA 70775 j

>Mr. William H. Spell, Administrator l Nuclear Energy Division

,, ' Louisiana Department of Environmental Quality

, F.0. Box 14690 9I. , ,/9 ton Rouge, LA 70898 i

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INE'ND SUdES T MERICA f

, NUC[ EAR 1EGULA20RY 03MISSIGi l SDdE & IOUISIANA *'  !

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. In the Matter of

• Docket Nos. 50-458 GUIF SUGES ITfILITIES C34PANY

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Unit 1) I AFFIDAVrf J. C. Deddens, being duly sworn, states that he is a Senior Vice i President of Gulf States Utilities C mpany; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Cemnission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and I belief.

/ Anhbwf J. CX Deddens ]

l Subscribed and sworn to before ne, a Notary Public in and for the State and and Parish above named, this day of /7 6 , 19 Mt- 4 / W

/Joan

• j W. Middlebrooks Notary Public in and for West Feliciana Parish, Icuisiana My Comission is for Life. j i

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i ATTACHMENT 1 GULF STATES UTILITIES COMPANY RIVER BEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 REACTOR WATER CLEANUP AREA TEMPERATURE LICENSING DOCUMENT INVOLVED: TECHNICAL SPECIFICATIONS ITEMS: Table.3.3.2-2 PAGE: 3/4 3-20 3/4 3-21 REASON FOR REQUEST .

A proposed change is being requested in accordance with 10CFR50.90 to revise the leak detection trip setpoints and allowable values for the Reactor Water Cleanup (RWCU) system heat exchanger room ambient and differential temperatures setpoints and allowable values. The RWCU heat exchanger room equigment area temgerature-high trip setpoint is being changed from ( 98.5 F to < 104.5 F and the allowable value from

( 101.5 F to ~ < 107.5 F. TIIe RWCU heat exchanger room equipment area differential temperature-high trip setpoint is being changed from ( 33 F to < 39 F and the allowable value from < 36.5 F to ( 42.5 F.-This '

proposed Technical Specification revision is required to avoid unecessary engineered safety feature (ESF) isolation signals due to ,

restricting RWCU heat exchanger room ambient and differential setpoint temperatures. GSU requests to amend the subject Technical Specifications contained in Appendix A to the River Bend Station (RBS)

Operating License, as discussed below.

DESCRIPTION The RWCU heat exchangers channel high energy fluid and are located I

inside containment. The system takes suction on the recirculation lines inside the drywell with injection back into the feedwater lines.

The RWCU system heat . exchanger room original leak detection original were based on a predicted average temperature equivalent to the l- predicted temperature in the containment area, the type of ventilation supplied to the area, and a steam leakage rate of 25 gpm for one hour.

The leak rate was based on the Nuclear Steam Supply System (NSSS) vendor, General Electric (GE), recommendation that the temperature trip j setpoints be predicted on a normal equipment area temperature rise

! equivalent to a 25 gpm steam leakage rate for system isolation. This

! leak rate is less than the critical crack length for a four inch l diameter pipe such that detection to prior to failure.

The revised setpoints have the same analytical bases as the original setpoints with the exception that the initial temperature is based on actual temperature data. A temperature rise from a 25 gpm leak rate at a higher initial temperature yielded a higher analytical limit and hence trip setpoint. The applied setpoint methodology, utilizing the actual temperature data, accounts for instrument inaccuracies and drift to

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! i ensure the margin of safety in maintained. The analytical value at 25 gpm was calculated to be 113 F for the area temperature-high and 46.5 F for differential temperature-high.

The proposed setpoints are calculated to prevent unnecessary or I inadvertent isolations yet maintain the margin of safety as defined in  !

the Technical Specification bases. During the summer season at normal plant operation, some temperatures are at or exceed the limit and have resulted in unecessary system isolations. The temperature l instrumentation's primary function is to provide indication of a leak )

inside containment. I l

SIGNIFICANT HAZARDS CONSIDERATION i As discussed in 10CFR50.92, the following discussions are provided to i the NRC Staff in support of "no significant hazards considerations". i

1. No significant increase in the probability or the consequences of an i accident previously evaluated results from this change because: )

Actual plant operating temperatures were used as the initial temperature from which the resulting temperature caused by a 25 gpm steam leak after one hour was calculated. The subject building zones have been evaluated for effect of environmental qualification of safety related equipment. The required changes to equipment i qualifications have been determined and documented. The design bases for leak detection have been unchanged. Other leak detection instrumentation available inside containment are: detection of level increases in containuent floor drain cump, equipment drain ,

sump and also monitoring of pump turn on and off times. The containment floor drain sump monitors unidentified leakage and activates an alann when total leakage reaches 5 gpm. The ,

containment equipment drain sump monitors identified leakage and {

also alarms in the main control room. In addition, the containment '

radiation monitors are also available to provide an indication of reactor coolant pressure boundary leakage.  ;

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2) This change would not create the possibility of a new or different  ;

kind of accident from any accident previously evaluated because: J GSU is selecting setpoints which follow the original setpoint bases  !

and prevent unnecessary or inadvertent isolations yet maintains the margin of safety as defined in the Technical Specification. The primary difference between the previous setpoint and the proposed setpoint is that the current setpoint is based on actual data versus predicted data.

Reviews have been performed to ensure that the existing design of equipment and structures can withstand the higher normal operating temperatures and equipment qualification and qualified life of equipment has been revised as necessary. changes made do not add new equipment nor do they affect the function or operations of existing equipment or structures.

3) This change would not involve a significant reduction in the margin  !

of safety because: l l

Calculations have been performed due to higher actual plant d temperatures to ensure that the safety margin is maintained. The I I

applied setpoint methodology, utilizing the actual temperature data, accounts for instrument inaccuraccies and drift. The original design criterion for the ability to isolate prior to a 25 gpm leak has been maintained. Therefore, no significant reduction in the margin of safety is being proposed.

The proposed amendment, as discussed above, has not changed the system design, function and operation contained in the FSAR. Therefore, it will not increase the probability or the consequences of a previously evaluated event and will not create a new or different event. As a result, the ability to perform, as described in the FSAR, is maintained.

Therefore, the proposed changes do not result in a significant reduction in the margin of safety. GSU proposes that no significant hazards are involved.

REVISED TECHNICAL SPECIFICATION As indicated above, River Bend Station is currently in compliance with the applicable Technical Specification. The proposed changes are provided in the Enclosure.

NOTIFICATION OF STATE PERSONNEL A copy of the amendment application and this submittal has been provided to the State of Louisiana, Department of Environmental Quality - Nuclear Energy Division.

ENVIRONMENTAL IMPACT APPRAISAL Revision of this Technical Specification does not result in an environmental impact beyond that previously analyzed. Therefore,'an approval of this amendment does not result in a significant' environmental impact nor does it change any previous environmental impact statcments for River Bend Stati,on.

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1 ENCLOSURE 1

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