ML20214U038

Forwards Table Listing Valves Meeting Revised Definition of Pressure Isolation Valve,Per Generic Ltr 87-06 Request.Table Includes Periodic Leakage,Operational Tests & Frequency of Testing

ML20214U038
Person / Time
Site:	Kewaunee
Issue date:	06/05/1987
From:	Hintz D WISCONSIN PUBLIC SERVICE CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-87-84 GL-87-06, GL-87-6, NUDOCS 8706110023
Download: ML20214U038 (5)

Text

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NRC-87-84

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• Green Bay, WI 54307-9002 June 5, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Response to Generic Letter 87-06

References:

1) Letter from D. G. Eisenhut (NRC) to All LWR Licensees dated February 23, 1980

2) Letter from E. R. Mathews (WPSC) to D. G. Eisenhut (NRC) dated March 18, 1980

3) Letter from S. A. Varga (NRC) to E. R. Mathews (WPSC) dated April 20, 1981

4) Letter from H. R. Denton (NRC) to All Holders of Operating Licenses dated March 13, 1987 (Generic Letter 87-06)

Your letter of February 23, 1980 (reference 1), identified a potential problem with system designs which utilize two check valves in series or two check valves in series with a motor operated valve which isolate the high pressure reactor coolant system from the low pressure injection system. The failure of these check valves is a significant contributor to risk from core melt accidents (Event V). You requested that we indicate if either of these valve con-figurations exist at the Kewaunee Nuclear Power Plant (KNPP).

We responded in our letter of March 18, 1980 (reference 2), that one system (RHR/ low pressure safety injection) utilizes the Event V design. You issued an Order for Modification of License (reference 3) which revised our Technical Specifications to include the primary coolant pressure isolation valves and the associated leakage testing requirements.

000 8706110023 870605 ,l PDR ADOCK 05000305 p PDR I

Document Control Desk

. June 5, 1987 Page 2 In Generic Letter 87-06 (reference 4) you defined pressure isolation valves as any two normally closed valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system from an attached low pressure system. This definition expands the scope of the leakage program to include all pressure isolation valves regardless of the type or size.

This letter provides our response to the NRC request put forth in Generic Letter 87-06. The attached table lists all the valves which meet the revised defini-tion of pressure isolation valve. The table includes the periodic leakage and operational tests along with the frequency of testing.

Sin erely, i D. C. Hintz Vice President - Nuclear Power 1 PMF/jms Attach.

cc - Mr. Robert Nelson, US NRC US NRC, Region III i

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Document Control Desk N224,2A June 5, 1987 Attachment Page 1 Leakage Operational Test Freq.

Test Allowable Test Leakage-Volva (Partner) Drawing Description Procedure Leakage Procedure Operation Notes SI-304A (303A) X-K100-28 6", check, HPSI and LPSI to Rx. Vessel SP34-203 15 GPM SP55-167-9 CSD-REF 1,2,3,4 SI-3048 (3038) X-K100-28 6" check, HPSI and LPSI to Rx. vessel SP34-203 15 GPM SP55-167-9 CSD-REF 1,2,3,4 SI-303A (304A) X-K100-28 6" check, LPSI to Rx. vessel SP34-203 15 GPM SP55-167-9 CSD-REF 1,2,3,4 l SI-3038 (3048) X-K100-28 6" check, LPSI to Rx. vessel SP34-203 15 GPM SP55-167-9 CSD-kEF 1,2,3,4 S1-228 (+) X-K100-28 12" check, Accum. disch. to cold leg SP33-204 15 GPM SP33-144 CSD-CSD 1,2,3,4 RHR-11 (SI-228) X-K100-28 10" M0V, RHR to loop B cold leg None N/A SP55-167-6 N/A-CSD 3,5 SI-218,(SI-228) X-K100-28 12" checi, Accum. disch. stop valve None N/A SP33-144 N/A-CSD 3 SI-22A (SI-21A) X-K100-28 12" check, Accum disch. to cold leg None N/A SP33-144 N/A-CSD 3 SI-21A (SI-22A) X-K100-28 12" check, Accum. disch. stop valve None N/A SP33-144 N/A-CSD 3 RHR-1A (2A) X-K100-18 8" MOV, RHR take-off from hot legs None N/A SP55-167-6 N/A-CSD 3,5 RHR-1B (28) X-K100-18 8" M0V, RHR take-off from hot legs None N/A SP55-167-6 N/A-CSD 3,5 RHR-2A (IA) X-K100-18 8" MOV, RHR take-off from hot legs None N/A SP55-167-6 N/A-CSD 3,5 RHR-28 (IB) X-K100-18 8" MOV, RHR take-off from hot legs None N/A SP55-167-6 N/A-CSD 3,5 RC-200A (201A) X-K100-10 2" manual, RCS to RCDT None N/A None N/A RC-2008 (201B) X-K100-10 2" manual, RCS to RCDT None N/A None N/A l

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Document Contral Desk N224,28 June 5, 1987

, Attachment Page 2 .

1 Leakage Operational Test Freq.

, Test Allowable Test Leakage-Volva (Partner) Drawing Description Procedure Leakage Procedure Operation Notes RC-201A (200A) X-K100-10 2" manual, RCS to RCDT None N/A None N/A RC-2018 (2008) X-K100-10 2" manual, RCS to RCDT None N/A None N/A PR-1A (2A) X-K100-10 3" MOV, Prz. relief block valve None N/A SP55-167-5 N/A-3 mos. 3,5 PR-1B (28) X-K100-10 3" M0V, Prz. relief block valve None N/A SP55-167-5 N/A-3 mos. 3,5 l

PR-2A (IA) X-K100-10 3" A0V, Prz. relief valve None N/A SP55-167-9 N/A-REF 3 l

PR-28 (18) X-K100-10 3" A0V .Prz. relief valve None N/A SP55-167-9 N/A-REF 3 LD-300 (301) X-K100-35 1" A0V,, Excess letdown hx inlet None N/A None . N/A LD-301 (300) X-K100-35 1" control. Excess letdown hx outlet None N/A None N/A Abt:reviations: CSD - Cold Shutdown REF - Refueling MOV - Motor Operated Valve A0V - Air Operated Valve

+ - Valve has more than one partner

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l\ Document Control 0;sk June 5, 1987 N224.3 Attachment Page 3 Notes: 1. From Table Tech Spec 3.1-2:

a. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

b. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the l maximum permissible rate of 5.0 gpm by 50% or greater.

c. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

I d. Leakage rates greater than 5.0 gpm are considered unacceptable, i

l 2. From Table Tech Spec 3.1-2:

Minimum test differential pressure shall not be less than 150 psid.

3. All valves are stroke tested with the stopwatch starting on actuation and stopping upon control panel indicator illumination.

4. Surveillance testing of pressure isolation valves (From Tech Spec 4.2.3):

a. Periodic leakage testing on each valve shall be accomplished prior to entering the operating mode after every time the plant is placed in the cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repair, or replacement work is performed.

b. Whenever integrity of a pressure isolation valve cannot be demon-strated, the integrity of the remaining pressure isolation valve in each high pressure line having a leakage valve shall be deter-mined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.

l S. Valves RHR-1A(B), RHR-2A(B) and RHR-11 are included in preventive l maintenance procedure 34-4. Valves PR-1A and PR-18 are included in preventive maintenance procedure 36-3. Both these procedures con-sist of circuit breaker maintenance, an insulation resistance test, I

valve operator maintenance, and an amperage and timing check.

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