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Provides 18 Months of Addl Data for All Six Switches within Scope of Bulletin 86-002, Static O-Ring Differential Pressure Switches. Evaluation of Six Switches within Long Term Corrective Action Program Requested
	ML19325D295
Person / Time
Site:	Oyster Creek
Issue date:	10/13/1989
From:	Fitzpatrick E; GENERAL PUBLIC UTILITIES CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	IEB-86-002, IEB-86-2, NUDOCS 8910230048
	Download: ML19325D295 (26)
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OPU 06uoleer Corporet6en Ng f

Post Office Box 388 Route 9 South l

Forked River.New Jersey 087310388 i

609 971-4000 Writer's Direct DialNumber:

October 13, 1989 l

l U.S. Nucioar Regulatory Comeission i

Document Control Desk Nashington, DC 20555

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Dear Sir:

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I subject:

oyster Creek Nuolear Generating station

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Docket No. 50-219 IRB Bulletin 86-02; Static-0-Ring Differential

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Pressure switches t

l References (1) Letter; Donohew to Fiedler, dated December 15, 1986 f

I This letter is being written in response to a request for information from the r

U.S. Nuclear Regulatory Commission documented in reference 1.

l In response to IE sulletin 86-02, " Static o-Ring Differential Pressure

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switches *, GPU Nuclear had requested the removal of two static-O-Rings switches I

from the scope of the bulletin and provided six smooths of surveillance data.

The U.S. NRC deferred the request for removal of the switches from the scope of

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the bulletin until GPU Nuclear could submit an additional six amonths of data.

, to this letter provides 18 months of additional data for all six i

switches within the scope of IEB86-02, and an engineering evaluation of that data.

I To assist in the closure of this bulletin, CPU Nuclear, by this letter, i

withdraws the previous request to remove the two specified switches from the scope of IEB 86-02, and requests the USNRC to evaluate ali six switches within l

the long term corrective action program required'by IRB 86-02.

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i 8910230048 891013

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FDR ADOCK OS000219 MI o

FDC fjpl GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation l'

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U.S. Nuclear Regulatory Commission j

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t If you should nood any further assistance, plasse contact Mr. John Rogers at (609) 971-4093.

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I very truly yours, l

Jf B.E. Fitspatrick z

Vice President & Director i

oyster Creek EEF/JR/jc l

(5-6) cc: Mr. William T. Russell, Administrator i

Region !

U.S. Nuclear Regulatory Commission I

475 Allendale Road King of Prussia, PA 19406 i

Mr. Alexander W. Dromerick U.s. Nuclear Regulatory Commission i

d Washington, DC 20555 NRC Resident Inspector oyster Creek Nuclear Generating Station i

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EMCL0$URE 1 I

Attachments A-F to this enclosure provide copies of the actual material history cards on file at the Oyster Creek Nuc) ear Generating station for the j

SOR differential pressure switches.

i Based on the attached data, covering the test results through July 1988, OPU Nuclear has performed a statistical analysis of switch performance and f

receptability. The analysis assesses the setpoint data obtained from t

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surveillance tests of the core spray Pump failure differential switches

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(RV-40A, B, C, and D) and the Reactor Building / Torus Vacuum Breaker switches f

(DPS-66 A and B).

The intent of the analysis was to provide statistical l

information on the switches setpoint drift so that a judgement could be made about their ability to function reliably. Analysis for switches RV-40, A, B, C, D is based on the time period from February 1985 through July 1988, Analysis for switch DPs-66A is based on the time period from September 1985 i

i through June 1988. Analysis of DPS-66B is based upon OLD switch data from

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September 1985 thrcugh November 1987, and NEW switch data from November 1987 through June 1988. With the sxception of DPS-668, calculations were based on I

the assumption that the underlying distribution of the data populations were approximately " normal" in shape.

For DPS-668 (OLD) and DPS-668 (NEW), a t-statistic analysis was used because of the small sample sises.

A summary of the calculated results is shown in attached Table 1.

As is seen in the attached copies of the instrument history cards, the six month readings (February 1988 through July 1988) reflected minimal drift in the settings for RV-40 A, B, C, D, with values being well within the "as found" surveillance limit of 45-50 paid for the trip settings; and well within the "as found" surveillance limit of 37-47 paid for the reset setpoints.

With respect to DPS-66A, the Technical Specification limit of 13.84 *H O 2

was not exceeded in 26 readings, whereas for DPS-668 (OLD and NEW), the Technical Specification limit of 13.84* H O was not exceeded in a total of 2

23 readings.

An analysis of the reset setpoint readings was not considered l

based on the fact that no equipment actuation is effected by the reset setpoint.

l The statistical analysis of setpoint readings for differential switches I

RV-40 A, B, C, D and DPS-66 A, B indicated that these switches can be expected to perform their function reliably and that simultaneous drift of switch setpoints equal to the maximum drift a}1 owed is unlikely. As shown in Table i

1, the greatest likelihood of exceeding a prescribed tolerance limit is 5.16%.

This is the probability of exceeding the RV-408 reset setpoint lower tolerance.

The greatest maximum observed shift in setpoint readings was

-3.2 paid for both RV-40B and RV-40C.

Tolerances for the RV-40 switches were assumed to be the "as-left" limits of 46-49 paid for the trip settings, and 41-45 psid for the reset setpoints.

Trip point upper tolerance for the DPS-66 switches was assigned the technical specification limit of 13.84" H 0.

2 The results on drift have been satisfactory based on the increased number of surveillance samples now available.

In addition, the statistical analysis of r

setpoint readings for differential switches RV-40A, B, C, D and DPS-66A and B indicated that these switches can be expected to perform their function reliably and that simultaneous drift of switch setpoints equal to the maximum drift allowed is highly unlikely. Documentation to support Table 1 and this evaluation are available at GPUN for NRC review, if required.

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Table 1 Swmary of Statistical Analysis l

for Switches RV-40A.B.C.D. and DPS-66A.B j

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SWITCH RV-40A RV-40B RV-40C RV-40D pPS-66A DPS-66B f

PROBABILITY OF 3.92%

0.10%

0.45%

1.66%

0.34%

<0.30%(OLD) l EXCEEDING TRIP POINT

<0.05%(NEW)

UPPER TOLERANCE t

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PROBABILITY OF 1.07%

0.06%

0.01%

2.62%

N/A N/A

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EXCEEDING TRIP POINT LOWER TOLERANCE PROBABILITY OF 0.43%

0.11%

0.02%

2.22%

N/A N/A i

EXCEEDING RESET POINT UPPER TOLERANCF PROBABILITY OF EXCEEDING RESET POINT LOWER TOLERANCE 3.22%

5.16%

3.51%

1.32%

N/A N/A e

1 MAXIMUM OBSERVED SET 2.1 1.5 1.3 1.6 2.13 2.23(OLD) j POINT SHIFT FROM 0.93(NEW)

I NOMINAL TRIP POINT

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l MAXIMUM OBSERVED SET 2.2

-3.2

-3.2 2.0 N/A N/A POINT SHIFT FROM NOMINAL RESET POINT I

0T10 results for DPS-66B(OLD) are for the "SOR" switch used prior to November, 1987.

(0235A\\JR)

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