ML20206T923

Responds to IE Bulletin 86-002 Re Static O-Ring (Sor) Switches.Sor Series 103 Differential Pressure Switches Installed in Oct 1985 as Part of Environ Qualification Mod

ML20206T923
Person / Time
Site:	Oyster Creek
Issue date:	09/23/1986
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-86-002, IEB-86-2, NUDOCS 8610070231
Download: ML20206T923 (27)

Text

.

GPU Nuclear Corporation NggIgf Post Office Box 388 Route 9 South Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

September 23, 1986 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

iubject: Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 86-02, Static 0 Ring Switches IE Bulletin 86-02, Static 0 Ring Differential Pressure switches, on page 8 required GPUN to submit two written reports within 60 days of the receipt of the Bulletin. This submittal meets those requirements.

Action Item No. 5 required submittal of a written report describing GPUN's interim performance monitoring program for the identified switches.

Attachment I answers this requirement.

Action Item No. 6 required submittal of a written report describing:

1) the margin and basis for switch actuation; 2) long term corrective actions to be taken and an implementation schedule; 3) the impacts of potential common mode failures; and 4) an analysis to demonstrate that requisite systems will meet regulatory requirements and function reliably. Attachment II answers, these requirements.

8610070231 860923 PDR ADOCK 05000219 G

PDR

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GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

. If any further information is required, please contact Mr. John Rogers of my staff at (609)971-4893.

Very truly yours, Vice President and Director Oyster Creek SworntoandSubscribedbeforemethisdd$ayo so,1986.

Aa d. M&

A Notary Public of NJ paf, ggp PBF/JJR/ dam (0235A)

Attachments cc:

Document Control Desk (original)

U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Jack N. Donohew, Jr.

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 Mail Stop No. 314 NRC Resident Inspectors Oyster Creek Nuclear Generating Station l

Forked River, NJ 08731 l

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ATTACHMENT I IE Bulletin 86-02 Action Item No. 5 Within 60 days, develop, implement and submit a written report describing your interim perfomance monitoring program to provide continuing assurance that the performance of the switches and plant systems remains acceptably reliable until long term corrective actions are fully implemented.

Response

The following SOR series 103 differential pressure switches were installed in Nuclear Safety Related/Important To Safety systems at the Oyster Creek Nuclear Generating Station (0CNGS) in October 1985 as part of environmental qualification modification. The RV40's were installed in February '85.

Table 1-1 Device Function Tag No.

Action Tech. Spec.

Inst. Setpoint

1. Low Reactor RE05Al, RE05/19Al Scram hl37" TAF 138.9" TAF Water Level RE05B1, RE05/1981 (4-60.22" H 0)

(58.9+0.3" H O) 2 2

2. Low Low Reactor RE02A, B, C & D

-Core Spray 86" above TAF 90" TAF Water Level

-Cont. Spray (696.3" H 0)

(93.5+1.0" H O)

-SGTS 2

2

-Reactor Iso

-cont. isol

-Recir. Pump Trip

-Iso cond.

init

-RBCCW/Drywell Isol

-Stby Diesels

3. Reactor Bldg./ DPS-66A & B

-0 pens vacuum *0.5 psid 11.07"+1.38" H O Torus Vacuum breakers (13.86" H 0)

~~

2 2

Switch (Butterfly Valves)

4. Core Spray RV40 A, B, C & D

-Starts back-Integral part of 47.5+1.5 psid Booster Pump up booster & core spray and Failure trips ADS Logic Pressure Switch priority booster pump

Both the RE05's and RE02's SOR series 103 differential pressure switches are being replaced by analog trip system (Foxboro Spec 200 System) during

'the 11R refueling outage now under way at OCNGS. The analog trip system shall be operational prior to the re-start of the plant.

This report therefore will not include data on RE05's, RE05/19's and RE02's but will concentrate in providing information only on DPS 66's and RV40's delineated in the IE Bulletin 86-02 (item #6).

Based on surveillance data and special test data acquired to date, the DPS-66's will be surveilled monthly, vice quarterly as required by the Technical Specifications.

Based on surveillance data and special test data acquired to date, the RV-40's will continue to be surveilled monthly.

Specifics of the surveillance and special test data are included in Attachment II to this report.

If any subsequent special test provides data which indicates an unacceptable shift, then requisite interim corrective actions will be initiated, and a supplemental response to this report will be submitted to the USNRC. -

I l

i

f ATTACHMENT II IE Bulletin 86-02 Action Item No. 6 Within 60 days, submit a written report which describes the margin and basis for switch actuation. The report should also describe the long term corrective actions to be taken, including the implementation schedule, the impacts of potential common mode failures, and an analysis to demonstrate that the system involved will meet regulatory requirements and function reliably. The report should include specific information on the installed SOR switches:

the manufacturer's specified range for the switch, the nominal and allowable values for the calibration setpoint in the Technical Specifications in the same tems as the manufacturer's specified range for the switch, the relative locations of the instrument taps for water level monitoring applications, sources of systematic errors such as the differences in elevations of the installation of condensing pots, and "as found" and any subsequent test data for any switch that does not conform to the Technical Specifications or is otherwise unacceptable.

Response

Margin and Basis For Switch Actuations A.

DPS 66's - Reactor Bldg. To Torus Vacuum Switch 1.

Technical Specification section 3.5.A.4.a specifies the limit for the Reactor Building to Suppression Chamber (Torus) differential pressure switch setpoint at:

"not to exceed 0.5 psid" 2.

The switch actuation setpoint is selected at approx 80% of 0.5 psid, allowing a 20% margin for instrument drift, repeatability and other instrument errors. Tolerance for the setpoint is set at 10% of the tech. spec, limit. Thus:

0.5 psid = 13.84" H 0 2

l 80% of 13.84 = 11.07" l

Tolerence + 1.38" (10% of 13.84)

Instrument Setpoint: 11.07" f.1.38" H O 2

B.

RV40's - Core Spray Booster Pump Failure Pressure Switch l

OCNGS Technical Specifications do not address the basis of the RV 40 setpoints.

l Booster pump operability is directly monitored by the ability l

of the pump to develop a minimum differential pressure of 50 psid within 5 seconds and maintain a differential pressure l

above the 40 psid reset value throughout the system flow range.

The setpoint verification calculation for the RV40's is documented under GPUN calculation #Cl302-212-5360-19. The following setpoints have been detennined to be adequate for system operability:

For RV 40-A thru D Setpoint (trip): 47.5 + 2.5 psid i

43.016psid Reset To allow for a margin of safety, the instrument setpoints are set as follows:

For RV 40 A thru D Setpoint (trip): 47.5 + 1.5 psid Reset

43.012.0psid Long Term Corrective Actions A.

DPS-66's The old Barton switches were replaced with SOR series 103 switches in October '85 (10M outage). Only one (1) calibration could be done between restart from 10M and refueling outage llR, which began i

in April '86.

This calibration data is attached as exhibits A & B for DPS 66A & B switches.

Additional calibration data were obtained on a daily basis beginning September 2,1986.

It can be seen from the calibration sheet that in a period of 5 months:

DPS 66-A drifted from 11.0" to 12.9" DPS 66-B drifted from 11.0" to 12.2" t

This period consisted of 2 months of non-operating and 3 months of operating cycle 10. The 'as found' value at the end of this period is well below the tech. spec. limit of 13.86" H 0.

2 SOR series 103 differential pressure switches, in this application, are not subjected to any static pressure. The process fluid is air. Therefore, the potential for deformation of the "0" Ring and subsequent binding on the cross shaft does not exist.

It is anticipated that any drif t during the surveillance period will be within the specified limits.

No replacement or long tenn corrective actions for these switches l

are required.

B.

RV40's l

The old Mercoid switches were replaced by SOR series 103 differential pressure switches in February '85.

The calibration data for the four (4) switches are attached as exhibits C, D, E,

& F.

I l

1

The switch setpoint is adjusted to 47.5 + 1.5 psid.

The observed drift has been within the specification values over a period of 16 months.

These switches are not subjected to the reactor operating pressures under operating conditions. Therefore, the potential for defomation of the 'O' ring in SOR switches is minimal and subsequent binding on the cross shaft does not exist.

No replacement or any long term corrective actions for these switches are required.

Implementation Schedule Existing DPS 66's and RV 40's differential pressure switches will be maintained and are not planned to be replaced. Scheduling is not applicable.

Impact of Common Mode Failures A.

Reactor Building / Torus Vacuum Switches (DPS-66A, B)

The function of these switches is to detect if the pressure in the torus is 0.5 PSI (13.84" H 0) less than the reactor building 2

pressure, and to deenergize a solenoid valve to open the vacuum breaker butterfly valves (V-26-16 and V-26-18) which isolate the RB/ torus vacuum breaker check valves (V-26-15 and V-26-17) if this condition exists. The switch actuation setpoint is selected at 80%

of 0.5 PSID (11.07" H 0) allowing a 2.77" H O (13.84-11.07) 2 2

margin to ensure that the valves open at a differential pressure not greater than 0.5 PSID.

The probability of the setpoint drifting beyond the Technical Specification limit has been calculated based on the data obtained from the limited number of surveillance tests performed on these switches.

The Technical Specification limit has not been exceeded in the six surveillance test readings performed since September 1985. The maximum observed shift from the desired setpoint for either switch has been +1.9" H 0.

This reading (12.9" H O) is below the 2

2 Technical Specification limit (13.84" H 0).

2 A statistical analysis performed for the setpoint data using small sample techniques indicated that the probability that the Technical Specification limit for DPS-66A may be exceeded is approximately 4.5% and significantly less than 0.5% for DPS-668.

Due to the relative stability (i.e. small shifts) of the setpoints for both switches observed during the recent daily readings and the long time (5 months) between readings where the larger shift (1.9" H 0) took place, shifts of the magnitude that would compromise 2the safety function of the switches (2.77" H 0) are highly 2

i improbable.

i The simultaneous setpoint drift of the DPS-66 switches equal to the

~

maximum drift experienced would not compromise the safety function of the system as the setpoint would still be below that which is required for system operability.

Additionally, the RB/ torus vacuum breakers are not required to function for any LOCA or Main Steam Line Break postulated within

)

the design basis of the plant.

B.

Core Spray Booster Pump Failure Detection Differential Pressure 3

Switches LRV-40A, B, C, & D)

The function of the RV-40 switch across each core spray booster pump is to determine if the preferred core spray booster pump is operating. The pump develops a minimum differential pressure of 50 psid within 5 seconds after the pump start.

If after the pressure t

exceeds the trip point (47.5 psid), the differential pressure across the preferred pump drops below the 43 psid reset point, as detected by the differential pressure switch (DPS), the operating preferred pump is tripped and the standby core spray booster pump is started by the actuation of the differential pressure switch.

i From the statistical analysis of the setpoint data obtained from surveillance tests, the greatest probability that the upper or lower tolerance of the trip setpoint of any switch will be exceeded is 2.4%.

For the reset setpoint, this probability is 3.5%.

r The maximum observed shift from the desired trip setpoint for any of the switches is + 1.5 psid.

The maximum observed shift from the desired reset point for any of the switches is - 1.8 psid.

i The upper and lower surveillance limits for the RV-40 switch i

setpoints have not been exceeded in the 16 times that they have been surveilled.

l The maximum drift experienced by the RV-40 switches from February l

1985 through May 1985 has been within the upper and lower setpoint i

limits and the statistical analysis indicates that there is a low i

arobability of exceeding these limits. Additionally these limits lave been set to allow a margin of safety of at least + 1 psid l

greater than the limits used for surveillance purposes!

Based on the foregoing information, it is concluded that simultaneous drift of the RV-40 switch setpoints equal to the i

maximum drift experienced is unlikely and that if it did occur it would not compromise the function of system, because the setpoint would still be within the acceptable range for system operability.

l

. _. _ _ _..,.,. _ _ _,,,, _... _... ~ _ _ _,,, _ _ _ _ _ _, _ _.. _,

_ _ _. =

~ - _ _ _ -

i Analysis to Demonstrate that Systems Involved Meet Regulatory Requirements and Function Reliably i

The intent of this analysis is to provide statistical information about A.

the setpoint drift for the subject switches, from which a judgement can be made about their reliability.

}

For DPS 66-A & B - Trip point : 11.07 + 1.38" H O 2

Reset point : 7.0711.5" H 0 t

2

't i

Using a small sample statistical technique (t-statistic) the estimated

• probability of exceeding the tech. spec. limit of 13.84" H O is:

2 DPS66-A 4.5%

DPS66-B 0.5%

The maximum observed setpoint shift from the desired setpoint is DPS66-A

+1.83" H O 2

DPS66-B

+1.13" H O 2

i l

From the statistical analysis of l) the limited data; 2) the magnitude of the maximum observed setpoint shift; 3) and the stability of the setpoint i

readings exhibited during the recent daily surveillance tests, it is projected that these switches will function reliably.

B.

From the calculations following is obtained:

4 l

RV-40-A, B, C, D RV-40A RV-40B RV-40C RV-40D Probability of exceeding 1.3%

1.8%

0.4%

0.5%

j trip point upper tolerance l

Probability of exceeding 2.4%

1.8%

0.3%

1.2%

l trip point lower tolerance Probability of exceeding 0.5%

0.5%

0.5%

0.3%

j reset point upper tolerance Probability of exceeding 1.4%

3.5%

2.2%

0.9%

reset point lower tolerance Maximum observed set point

-1.3psid

+1. 5psid

+1.0psid

-1.0psid l

shift from desired trip setpoint i

Maximum observed set point

-1.6psid

-1.5psid

-1.8psid

-1.6psid shift from desired reset point From the above results and the fact that the setpoint tolerances for any switch has not been exceeded in the 16 times that they have been checked l

during surveillance (attachments C thru F) it can be concluded that it is j

highly improbable that the setpoint tolerances will be exceeded.

I

• Due to the limited data with which to perform a statistical analysis, the l

estimate of the probability of exceeding tech. spec. limit is considered j

preliminary until more data for a longer period of time is available, i

i 1

1

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Specific Information on Installed SOR Switches 1.

Manufacturer's Specification for the Switch A.

DPS-66 A & B Model - 103 AS-B202-NX-JJTTX6 Range 35" WC Max. " Static" operating pressure: 1500 psig Repeatability

+ 1% Full scale Reset - Fixed Dwg. #8305-126 (see exhibit 'H')

Test Data - see exhibit 'G' B.

RY-40 A thru D Model - 103AS-B905-NX-JJTTX6 Range 90 psi Max. " Static" operating pressure: 1500 psig Repeatabili ty: + 1% full scale Reset: Fixed Dwg. #8305-241 (see exhibit 'I')

Test Data - RV40's were exhaustively tested by GPUN SU&T department at 0.C.

Results are filed separately.

2.

Nominal and Allowable Values for the Calibration Setpoint In the Technical Specification A.

DPS-66 A & B Instrument Setpoint 11.07" j; 1.38" H O 2

Reset 7.07" f;1.5" H O 2

B.

RV-40 A thru D Instrument Setpoint 47.5 + 1.5 psid Reset 43.012.0psid 3.

Relative Locations of the Instrument Taps For Water Level Monitoring Applications A.

DPS-66 A & B Not Applicable.

B.

RV-40 A thru D i

Not Applicable.

4.

Source of Systematic Errors

(

I A.

DPS-66 A & B Condensing pots are not applicable. No other sources of systematic errors have been identified.

B.

RV-40 A thru D.

Condensing pots are not applicable. No other sources of systematic errors have been identified, t

5.

'As Found' Or Any Subsequent Test Data for Any Switch That Does Not Conform to the Technical Specification or is Otherwise Unacceptable A.

DPS-66 A & B None B.

RV-40 A thru D None f

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