B12644, Forwards Responses to Questions A5 & M7 & Revised Responses to Questions M6 & T1 Re 860625 Rev 1 to Inservice Testing Program for Pumps & Valves,Per 870602,03 & 0724 Meetings & 870819 Telcon

Forwards Responses to Questions A5 & M7 & Revised Responses to Questions M6 & T1 Re 860625 Rev 1 to Inservice Testing Program for Pumps & Valves,Per 870602,03 & 0724 Meetings & 870819 Telcon

ML20238C263
Person / Time
Site:	Millstone
Issue date:	09/02/1987
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
B12644, NUDOCS 8709100006
Download: ML20238C263 (23)

Text

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f f 9, NORTHEAST tlTILITIES ceneral Offices

• Selden Street, Berlin. Connecticut

d l I. sin vN$N 2cUa P.O. BOX 270 e .<me wea .<w c """ H ARTFORD, CONNECTICUT 06141-0270 L L j [ [ , [ , Z ;'$ 7, (203) 665-5000 L )'

/ i lh September 2,1987 3

Docket No. 50-423 S B12644 Re: 10CFR50.55a(g)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 4

References:

(1) 3. F. Opeka letter to V. S. Noonan, inservice Testing (IST)

Program for Pumps and Valves, dated June 25,1986.

(2) E. L. Doolittle letter to E. 3. Mroczka, Pumps and Valves Inservice Testing Program, dated March 9,1987.

(3) E. 3. Mroczka letter to U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Responses to the Staff's Questions an Pumps and Valves Inservice Testing (IST) Program, dated July 10,1987.

(4) Summary Meeting: Inservice Testing Program for Pumps and Valves, dated July 24,1987.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 3 Responses to the Staff's Questions on the Pumps and Valves Inservice Testing (IST) Program in Reference (1), Northeast Nuclear Energy Company (NNECO) transmitted Revision 1 of the Millstone Unit No. 3 program for Inservice Testing of pumps and valves. In Reference (2), the Staff provided their questions and comments on the IST program for pumps and valves. A meeting was held between the Staff, their Contractor EG&G, and NNECO representatives at the Millstone Site on June 2 and 3,1987 to discuss our responses to their questions (Reference 2).

In Reference (3), NNECO transmitted responses to all questions except Questions A5 and M7 and stated that responses to Questions A5 and M7 would be submitted by September 2,1987. Accordingly, the responses to questions A5 and M7 are provided herewith. In addition, revised responses to Questions M6 and T1 are also provided to resolve Staff's concerns identified in Reference (t;) and during a conference call held August 19, 1987. A copy of the responses has been forwarded to the NRC's contractor, Mr. Ransom, EG&G, Idaho.

8709100006 070902 '

PDR ADOCK 05000423 *

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<O U.S. Nuclear Regulatory Commission B12644/Page 2 September 2,1987 If there are any questions regarding this submittal, please contact our licensing representative directly.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

- J E. 3. MrpfzkaSeniort Wce Preside (n/

cc: W. T. Russell, Region I Administrator R. L. Ferguson, NRC Project Manager, Millstone Unit No. 3 W. 3. Raymond, Resident inspector, Millstone Unit No. 3 l

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Docket No. 50-423 l B12644 l

l' Millstone Unit No. 3 Responses to Questions A5, M6, M7, and Tl related to the IST Program for Pumps and Valves J

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September 1987 I

l

_.___.-_._____________________._____D

i Millstone 3 Intervice Testing Program General Questions and Comments A3. What are the bases used to assign the limiting values of full-stroke time for the power-operated valves in the Millstone Unit No. 3 IST program?

Provide the limiting values of full-stroke time for those valves that have NSR(1)in the maximum stroke time column of Table 5.4.

Respont*

The Active Valve Response Times Document (NM-027-ALL) provides the criteria for selection of power-operated active valves and maximum allowable full-stroke times for those active valves.

For all no-stroke time required (NSR) designated valves the baseline valve operating time value data is doubled to provide a maximum limiting stroke time.

Upon exceeding this value the corrective action will be taken in accordance 'with  !

IWV 3417B. )

Relief Request 27 has been resised to establish adequate testing.of the power operated valves. Also, Relief Request 27 justifies the non-NSR stroke times (O&M6, Draf t 11).

l AS-1

Relief Request: R-27 All power operated valves listed in the valve lists.

l Component Identification: ASME Code Class: 1,2,3 IWV 2200 Valve Category: A, B Valve Function: As identified in valves lists.

Test Requirements: Paragraph IWV-3417 "(a) If, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 seconds or 50% or more for valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased..to.once.each month until' corrective action is taken, at which time the original test frequency shall be resumed. In any case, any abnormality or erratic action shall be reported.

Code Relief: Relief is requested from comparing present stroke times to stroke times from the previous test.

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Basis for Relief: Use of the " previous test" stroke time does not adequately identify slow degradation of valve performance. For example, repeated ]

increases in stroke time of 15 to 24 percent would not require that the valve be considered in " Alert", with attendant additional investigation and testing. The proposed alternative acceptance criteria would identify such valves and require that they be formally evaluated for acceptability or declared inoperable. In instances where the evaluation does not result in a determination of inoperability additional or increased frequency testin8 may be specified to aid in evaluating valve pe rfo rmance. This criteria provides increased assurance that degrading valves are promptly identified and that such degradation is promptly evaluated for its impact on valve operability.

Proposed Alternative: Test results shall be compared to the reference values of stroke time for each valve.

a. Valves with reference stroke times greater than 10 seconds shall exhibit no more than a 25% change in stroke time when compared to the reference value.

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b. Valves with reference : J less than 10 seconds si more than a 50% or 1 se ever is greater) change when compared to the re 1

c. Valves with reference stroke times of '

less than 2 seconds shall not exhibit a stroke time in excess of 2 seconds.

Valves with measured stroke times which do not meet the above acceptance criteria shall be immediately retested (or declared inoperable).

{ If retested and the second set of data also i

i does not meet the acceptance criteria either the data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable valve operation, or the valve shall be de lared inoperable. If the analysis indicates the deviation is acceptable, operation of the valve shall be tested monthly until it is repaired or declared inoperable, or until a new reference value is established. If trended test results indicate the valve will exceed the limiting value of stroke time prior to the next test or that valve operation is unreliable the valve shall be declared inoperable. The evaluation shall be documented in the record of the tests.

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If the second set of data meets the acceptance criteria, the cause of the initial deviation shall be analyzed and the results documented in the record of tests.

Valves for which measured stroke times exceed limiting values for stroke times shall be immediately declared inoperable.

Valves which are declared inoperable shall be readjusted, repaired, or replaced prior

f. to returning the valve to service. A test s

4 e demonstrating satisfactory valve performance shall be performed prior to returning the valve to service.

i r

4 Feedwater System 1

M6'- Which auxiliary feedwater check valves present diversion of flow through an idle auxiliary feedwater pump when another pump is operating? How are these individually verified to close?

Response

Valves 3FWA-V35,39, 43,47,12,7,21,26,3,17, and 31 are not active valves in the open-to-closed position as defined in .1WV-2100. The above valves are category "C" valves as defined in IWV-2000 and need not be tested in accordance with IWV-3420. Therefore, these valves are not required to be and are not in the in-service test program in the closed position.

Outside of the program these valves are verified shut during operation rounds.

Each shift the temperature of the auxiliary feed pumps are felt to enstre that there is no backflow through the pump. This does not verify that each valve in service is closed but only one valve is required to be fully closed to prevent backflow. It should also be noted that 3FWA-V13, 48, 8, 44, 22, 40, 27, 36, 34, 38,42, and 46 have been added to the program. If af ter the initial response to an accident the check valves do not fully shut when the associated pump is secured, then the isolation valves can be shut to secure backflow.

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\. i Relief Request: CSR-21 Valves: 3FWA*V3, V7, V12, V17, V21 V26, V31, V35, V39, V43' V47 i

Category: C Code Class: 2 Function: Pass required auxiliary feedwater flow to the steam generator.

Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Operating the auxiliary feedwater system at power is undesirable at the required flows to fully open these check valves. This places an undesirable thermal transient on the feedwater piping.

Alternate Testing: These valves will be full stroke tested open during cold shutdowns.

s

1 Feedwater System <-

}

h M7. Review the safety function of the following valves (located in  !

P&lD 25212-26930 Sh. 2) to determine if they should be included in the IST program and tested to the code requirements.

Valve Valve Valve t ll 3FWA-V6 3F WA-V27 3FWA-46 1-3FWA-V8 3FWA-V34 3FWA-48 3F WA-V11 3FWA-V36 3F WA-60 )

3FWA-V13 3FWA-V38 3FWA-62 3FWA-V20 3FWA-V40 3FWA-854 3FWA-V22 3FWA-V42 3FWA-855 3FWA-V25 3FWA-V44 -

Response

The safety function for Valves 3FWA-V6,3FWA-V11,3FWA-20 and 3FWA-V25 is to fall open and these valves are normally open and, therefore, these are passive .

per ASME IWP2100.

Valves 3FWA-60 and 62 do not have a failure position and, therefore, these are ,

passive per ASMEll IWP2100.

Valves 3FWA-854 and 855 are normally closed and ai-r required to fait close.

Thus, these are passive per ASMEll IWP2100. The remaining valves identified above are included in the IST program. ,

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Emergency Diesel Generator System T1. The NRC Staff position is that the emergency diesel generators perform a safety-related function and that the appropriate valves sn i the emergency diesel air start, cooling water and fuel oil transfer systems should be included in the IST program and be tested in accordance with the code. ,

Review all active valves in these diesel generator subsystems to  !

determine if they should be included in the IST program.

Response

The fuel oil transfer systems valves 3EGF-V1, V3, V7, and V9 will be included in the IST manual and tested quarterly. The attached Relief Request R-25 addresses alternate testing of the emergency generator air start valves. We have reviewed the service water supply system to the emergency diesel generator and determined that there are no additirnal active valves.

In addition to the review of ASME systems supporting the diesel, the diesel skid-

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mounted equipment has also been reviewed to ensure that diesel testing is i capable of identifying component problems. It has been determined that the Technical Specification surveillance testing for the diesel is adequate to demonstrate operability of all the skid-mounted equipment. The attached table describes the performance data monitored on each of the skid's operating pumps.

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Table T1-1 Emergency Diesel Skid Mounted Component Performance Testing Component Performance Data Engine-Driven Intercooler Pump Intercooler temperature to and from the cooler are monitored during operation.

Expected readings are specified.

Engine-Driven Jacket Water Pump Jacket water temperature to and from the engine and pressure at the pump discharge are monitored. Expected readings are specified.

Engine-Driven Lube Oil Pump Lube oil temperature. to and from the engine and header pressure are main-tained. Expected readings are specified. I Rocker Arm Lube Oil Pump The pump filter discharge alarm identi-fies a low-pressure condition. The diesel operating procedure requires investiga-tion and correc+. ion of the low-pressure condition.

Engine-Driven Fuel Oil Pump Fuel oil pressure to the filter and to the engine are monitored. Expected readings are specified.

Motor-Driven Fuel Oil Pump This DC pump only runs during diesel start or in case of a low fuel oil pres-sure. If it does not operate properly the diesel start times may be affected or the diesel may fail to start.

Turbocharger Turbocharger inlet and outlet temper-ature and tube oil level. and flows are monitored. Expected readings are speci-fled for temperature. Oil levels and flows are identified as SAT or UNSAT.

Note: If the operator gets readings outside of the expected range, the operator evaluates the data and initiates appropriate corrective action.

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/ 'Reitef Request: R-25 ,

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) Valves: 3EGF*V25, 26, 51, 52

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-Category: B ,

I Code Class: 3 , p ,,'

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Function: Emergency Diesel Generator Air START Solenoid Valves. ,

Test Requirements: - Full stroke-testing quarterly.

Basis for Relief: It is impractical to measure the limiting value of full-stroke time of these valves. These valves do not have remote position indication. Measuring the ,

stroke time of these valves by observing stem travel would require disassembly of the operator. The

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safety function of these valves is to open to support the start-up of its respective" diesel to provide rated frequency and voltage in less than ten seconds.

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Successful start-up of each emergency diesel generator within the above specified conditions is dependent upon the proper ope' ration and speed of these valves. Measuring start-up time of each

- emergency diesel generator is an indirect method of verifying the degradation of these valves and meets .

the intent of the code. Upon failure of the diesel I- generators to start as required, corrective action shall be taken to assure proper diesel start-up conditions.

L i AlternateTes$ing: These, valves shall be full-stroke tested using the

'- emergency diesel generator start-up times per l '

Surveillance Procedure 3646A.1, 2 as an indirect indication of valve operability. ,

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