ML20198S328

Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b

ML20198S328
Person / Time
Site:	Hope Creek
Issue date:	01/06/1999
From:	Richard Ennis NRC (Affiliation Not Assigned)
To:	NRC
References
TAC-MA2259, NUDOCS 9901110270
Download: ML20198S328 (4)

Text

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. January 6, 1998

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MEMORANDUM TO: Docket File FROM:

Richard B. Ennis, Project Manager /s/

Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION, DELETION OF AUTOMATIC

! DEPRESSURIZATION SYSTEM (ADS) VALVE STARTUP TESTING (TAC NO. MA2259)

In telephone conversations on December 18, December 22, and December 23,1998, i

Mr. Joseph Ondish and Mr. James Priest of Public Service Electric & Gas Company (PSE&G) discussed the attached information with Mr. Richard Ennis, the NRC Hope Creek Project Mar,ager. This information clarifies PSE&G's license change request number LCR H98-03 dated June 25,1998, which requested (in part) to revise Technical Specification (TS) 4.4.2.1.b a

such that the 18 month channel calibration for the safety relief valve (SRV) acoustic monitors

, will no longer require an exception to the provisions of TS 4.0.4, nor adjustments to full open noise levels.

1 Docket No. 50-354

Attachment:

Hope Creek SRV Acoustic Monitor Information 4

DISTR!BUTION Docket File PUBLIC WDean REnnis SMazumdar Il/

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NAME REnn 9 DATE 1/ 5 /99 OFFICIAL RECORD COPY DOCUMENT NAME: HC2259.MEM

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\ . . . . . ,e January 6, 1998 MEMORANDUM TO: Docket File FROM: Richard B. Ennis, Project Manager Project Directorate 1-2 Division of Reactor Projects -lill Office of Nuclear Reactor Regulation

SUBJECT:

HOPE CREEK GENERATING STATION, DELETION OF AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) VALVE STARTUP TESTING (TAC NO. MA2259) in telephone conversations on December 18, December 22, and December 23,1998, Mr. Joseph Ondish and Mr. James Priest of Public Service Electric & Gas Company (PSE&G) discussed the attached information with Mr. Richard Ennis, the NRC Hope Creek Project Manager. This information clarifies PSE&G's license change request number LCR H98-03

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dated June 25,1998, which requested (in part) to ravise Technical Specification (TS) 4.4.2.1.b such that the 18 month channel calibration for the safety relief valve (SRV) acoustic monitors will no longer require an exception to the provisions of TS 4.0.4, nor adjustments to full oper noise levels.

Docket No. 50-354

Attachment:

Hope Creek SRV Acoustic Monitor information i

L l:

L

HOPE CREEK SRV ACOUSTIC MONITOR INFORMATION 4

Calibration Information The Fluid Flow Detector has 3 outputs:

1) Logic Lights (indicates SRV open or close position)

2) DC analog output (indicates valva position)

3) LED digital display that is switchab!e via an I-C-T switch to display the following:

1 (Input) - selects analog acoustic level input in volts C (Count) - selects accumulated number of valve openings T (Threshold)- selects setpoint The calibration of the Preamplifier end Fluid Flow Detector is peiformed with the I-C-T switch in the "l" position and the display is calibrated over a range of 0.005 to 0.999 volts.

When the calibration of the Preamplifier and Fluid Flow Detector is complete the Acoustic l Monitor Sensor output leads are reconnected to the Preamp. The Integrated System Response

s. Test is then performed.

As required by Technical Specification (TS) 4.4.2.1.b, Hope Creek will continue to ensure that

, acoustic monitor setpoint is less than or equal to 30% of full open noise level. To meet this ,

,  ; requirement Hope Creek will use a spring leaded hammer (designed to impart a 1g force on the pipe) during the Integrated System Response Test and a Fluke meter will display the millivolt

' readings at the Fluki Flow Detector output terminals. To ensure that the millivolt readings ,

obtained during the integrated System Response Test correlate to a channel with a setpoint of

, less than or equal to 30% of full open noise level, Hope Creek will obtain baseline data (rnillivolts output resulting from the 1g hammer impact) at the start of the upcoming refueling outage p' (RFO8). Since the current acoustic monitor channel setpoints were verified during the current cycle's startep, using live steam, and are known tu be less than or equal to 30% w full open noise nevel for its actual installed configuration, the millivolt readings obtained for each channel in its response to this 1g hammer impact wil! u1en be used in oubsequent cycles to ensure that

(. the setting of the system continues to meet or exceed the TS requirements. Thus this Integrated  :

' System RetNnse Test will provide a quantitative means of assessing the channel's response to l a known input, t  ;

• 'O Operator Actions 1 Y!

( The acoustic monitors are installed to provide operator information only (i.e., they do not perform i j j any automatic control function). The instrumentation provides the operator with Open/ Closed 1 e '

SRV position indication and an alarm if the SRV is determined to be open. Each acoustic  ;

monitoring channe! provides input to a common main control room annunciator which actuates if l

j' !one or more SRV's are open.  !

h .. l The acoustic monitor indication and alarms are not the only parameters monitored by plant operators in datermining SRV position. Other parameters monitored to determine SRV position g jnclude SRV tailpipe temperature, suppression pool temperature, suppression pool level, and generator output- '

ATTACHMENT

. l ffl } l

Safety Sionificance The awustic monitors are not safety-related. The capability of the SRV's to perform their intended function is not dependent on the operation of the acoustic monitors. UFSAR Section 15.1.4 provides the accident analyses for an inadvertent opening of an SRV. The operator actions credited for this event are stated in UFSAR Section 15.1.4.2.1.1 as follows: "The plant operator must "reciose" the valve and check that reactor and turbine-generator output return to normal. If the valve cannot be closed, plant shutdown must be initiated." No credit is taken for operability of the acoustic monitors wi+h respect to accident mitigation.

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