ML17291B227

From kanterella
Jump to navigation Jump to search

Forwards RAI Re 951026 Request for Amend to WNP-2 TS to Support Planned Reactor Recirculation Sys Adjustable Speed Drive Upgrade.Requests Response in Writing No Later than 30 Days
ML17291B227
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 02/13/1996
From: Clifford J
NRC (Affiliation Not Assigned)
To: Parrish J
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
TAC-M93949, NUDOCS 9602150318
Download: ML17291B227 (14)


Text

4 February 13, i996 Mr. J.

V. Parrish (Mail Drop 1023)

Vice President Nuclear Operations 3000 George Washington Way Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968

SUBJECT:

RE(UEST FOR ADDITIONAL INFORMATION FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)

NUCLEAR PROJECT NO.

2 (WNP-2)

(TAC NO. M93949)

Dear Mr. Parrish:

The NRC staff has reviewed your October 26, 1995 request for amendment to the WNP-2 Technical Specifications to support the planned reactor recirculation system adjustable speed drive upgrade.

As a result of the review, the staff has determined that additional information is needed to complete the review.

The information needed is detailed in the enclosure.

Since NRC approval of the request is needed to support your April 1996 refueling outage, we request that you respond in writing to this request for additional information as soon as possible but no later than 30 days from receipt of this letter.

The requirements affect nine or fewer respondents and, therefore, are not subject to the Office of Management and Budget review under P.L.96-511.

If you have any questions, please contact me at (301) 415-1362.

Sincerely, Original signed by K. Thomas for:

James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

Request for Additional Information cc,w/encl:

See next page DISTRIBUTION'Docket File PUBLIC JRoe EAdensam WBateman JClifford EPeyton

JStewart, HICB JWermi'el, HICB
ACRS, TWFN PDIV-2 Reading
OGC, 015B18
KPerkins, WCFO Djg

~ ~L II

HWong, t4(,ri)

KThomas

OChopra, EELB
JCalvo, EELB DOCUMENT NAME: WNP93949.RAI OFC NAME DATE PDIV-2 e

n 2 19 96 PDIV-2 KTho as:

k 2(

96 PDIV-2n JCli for 2

/96 Fol OFFICIAL RECORD COPY 9602i50318 9602i3 PDR ADQCK 05000397 P

PDR

Jl

) 'L>

i II mA'l

'/

p l

I' t

I l)

I

(

l I'\\

f L

/r I

I

,t/'y

'I 4

I L

I C

February 13, 1996 Mr. J.

V. Parrish (Nihil Drop 1023)

Vice President Nuclear Operations 3000 George Washington Way Washington Public Pmer Supply System P.O.

Box 968

Richland, Washingtora

'99352-0968

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)

NUCLEAR PROJECT NO.

2 (WNP-2)

(TAC NO. M93949)

Dear Mr. Parrish:

The NRC staff has reviewed your October 26, 1995 request for amendment to the WNP-2 Technical SpecMications to support the planned reactor recirculation system adjustable speed drive upgrade.

As a result of the review, the staff has determined that additional information is needed to complete the review.

The information needed is detailed in the enclosure.

Since NRC approval of the request is needed to support your April 1996 refueling outage, we request that you respond in writing to this request for additional information as soon as possible but no later than 30 days from receipt of this letter.

The requirements affect nine or fewer respondents and, therefore, are not subject to the Office of Management and Budget review under P.L.96-511.

If you have any questioes, please contact me at (301) 415-1362.

Sincerely, Original signed by K. Thomas for:

James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

Request fer Additional In format i on cc w/encl:

See next page D~IET IDDTIDII:

Docket File PUBLIC JRoe EAdensam WBateman JClifford EPeyton

JStewart, HICB
JWermiel, HICB
ACRS, TWFN PDIV-2 Reading
OGC, 015B18
KPerkins, WCFO
JDyer, RIV
HWong, WCFO KThomas
OChopra, EELB
JCalvo, EELB DOCUMENT NAME: WNP93949.RAI OFC PDIV-2 83IV-2 PDIV-2 NAME Eke %n s)

KTho as:

k

'cV JCli for DATE 2 19 96 2

I 96 2

/96 OFFICIAL RECORD COPY

Mr. J.

V. Parrish cc w/encl:

Mr. G. 0. Smith WNP-2 Plant General Hanager Washington Public Power Supply System P. 0.

Box 968

Richland, Mashington 99352-0968 Chief Counsel (Hail Drop 396)

Washington Public Power Supply System P.O.

Box 968 Richland, Mashington 99352-0968 Mr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P. 0.

Box 43172 Olympia, Mashington 98504-3172 Mr. D. A. Swank (Hail Drop PE20)

WNP-2 Licensing Hanager Mashington Public Power Supply System P.O.

Box 968

Richland, Mashington 99352-0968 Mr. Paul R. Bemis (Mail Drop PE20)

Director, Regulatory and Industry Affairs Mashington Public Power Supply System P.O.

Box 968

Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 5 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O.

Box 69

Prosser, Mashington 99350-0190 Mr. R. C. Barr, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 69

Richland, Washington 99352-0968 M. H. Philips, Jr.,

Esq.

Winston

& Strawn 1400 L Street, N.M.

Washington, DC 20005-3502

Enclosure WASHINGTON PUBLIC POWER SUPPLY SYST NUCLEAR PROJECT NO.

2 WNP-OC 5 -3 U

S F

D ONAL N ORHAT ON REGARDING OCTOBER 6

1995 SUBMI In order to complete the review of Washington Public Power Supply System's proposal for using an adjustable speed drive (ASD) for control of reactor recirculation pumps at WNP-2, the following additional information is required.

On page 5, Appendix A, it is stated that to increase system reliability, the GE-FANUC control system uses redundant power supplies and the ASD control system uses a separate uninterruptible power supply.

Provide the sources of power for these devices.

2.

3.

4.

6.

7.

On page I, Appendix 8, it is stated that filter capacitors are applied across the ASD output to filter the harmonics.

Since these filters are in parallel with the motor inductance, it could create an inductance-capacitance circuit with a resonance frequency that can be excited by the ASD harmonics.

If this frequency is present, harmonics currents can be amplified.

To eliminate this concern the inverter uses GTO SCRs to switch currents on or off at. appropriate times during a cycle.

Please explain how these SCRs work and what are the consequences if they fail.

Is the GTO SCR failure indicated in the control room?

Describe surveillance/periodic testing to be performed which will assure that harmonic current from the adjustable speed drive will be maintained within established limits at safety as well as non-safety buses.

Given that the harmonic currents generated are kept within a 5 percent limit by harmonic filters, will there be any resonant conditions generated which could produce currents greater than what the electrical equipment is designed to?

At WNP-2, have electrical, instrumentation, and control system equipment been designed to operate satisfactorily with a harmonic voltage of 5 percent superimposed on the input. voltage by operation of the proposed adjustable speed drive?

Have the harmonic filters been designed and sized for the harmonic current generated from the adjustable speed drive as well as the harmonic current from the power supply system for all modes of plant operation?

With the harmonic filters inoperable and the adjustable drive speed at 100 percent, what is the harmonic distortion contribution from the variable speed drive?

It is stated in Appendix B, page 22, that the onsite operational testing of the ASDs was performed in June 1995 (during a plant outage).

During the testing, the highest voltage total harmonic distortion was 5.2 percent as measured at bus SN-6.

This value exceeds the 5 percent value established in IEEE-519.

What effects does this have on the remaining loads on bus SM-6?

Are there any other tests done on the ASDs since then?

If so, please provide the test results.

If not, how many tests are planned in the near future?

Appendix B, page 4, provides the results of an analysis in percentage of total harmonic distortion in startup as well as in generation mode.

Please explain the last three columns of tables on this page.

It is stated in Appendix B, page 2, that the adjustable speed operation affects RPT breaker performance.

Since the ASDs vary the frequency of the power supplied to the motor, the opening time of the breaker will vary inversely with the supplied voltage, i.e., if the system is operating at 15 HZ the opening time of the RPT breakers increases to 20 cycles (assuming normal opening time of the breaker to be 5 cycles).

With this delay in opening time, are these breakers still properly coordinated with the containment electrical penetration conductors for all possible short circuit conditions, including the maximum available fault current?

Your response should also include the coordinated fault-current-versus-time curves for these penetrations.

Provide a schematic diagram that shows all the protective devices used for the ASD system.

The change from 18 month to 24 month surveillance and some of the accident analysis sections refer to the high reliability of the FANUC and HEM units.

The numbers are given as "per demand."

a.

Provide a description of this term as it relates to the startup and normal oper ation of the ASOs.

b.

Provide the information which forms the basis for those reliability numbers.

Are all of the alarms listed in Table 2 of Appendix B annunciated in the control room?

Does the logic provide for continued acceleration if there is a failure of one of the ASD channels between 2 and 15HZ?

Describe the loss of one ASD in more detail.

Is the change of the remaining ASD to 52 HZ instantaneous (as fast as the sense and command can perform it) or is it ramped at the pump coast down rate?

Given that a single ASD has torque capability of 52 HZ, are there any effects on the system as a result of motoring at 60 HZ down to 52 HZ?

Is the ASD maximum frequency limiter changed at the same time?

16.

Provide the FANUC and HEH operation, maintenance and installation manuals or the following excerpts.

Particular items of interest include the self diagnostics (what parameters are monitored), the manufacturers claimed environmental parameters (temperature, humidity, etc.),

automatic actions taken upon a diagnostic result.

17.

Are there any alarms or indications in the control room of problems with the FANUC and HEH other than microprocessor interrupt?

18.

Describe the quality controls of the manufacturing process.

Were the devices under a gA program including software gA, VSV, and configuration management?

Is an error and change reporting mechanism in place to assure that MNP-2 is informed of changes/errors in the products?

Has WNP-2 or an industry group performed any gA audits of the vendors?

19.

Provide the company names and factory locations of the designers and manufacturers of the FANUC and HEH.

20.

Is there any indication to the operator when the limiting functions in the FANUC or HEH override the operators demand?

21.

Are the ASD overfrequency relays separate electromechanical/solid state relays or is this function implemented in the software of the HEH?

22.

Verify that there are no changes to the safety-related RTP.

February 13, 1996 Hr. J.

V. Parrish (Hail Drop 1023)

Vice President Nuclear Operations 3000 George Washington Way Mashington Public Power Supply System P.O.

Box 968

Richland, Mashington 99352-0968

SUBJECT:

REQUEST FOR ADDITIONAL INFORHATION FOR THE MASHINGTON PUBLIC POWER SUPPLY SYSTEH (MPPSS)

NUCLEAR PROJECT NO.

2 (MNP-2)

(TAC NO. H93949)

Dear Hr. Parrish:

The NRC staff has reviewed your October 26, 1995 request for amendment to the MNP-2 Technical Specifications to support the planned reactor recirculation system adjustable speed drive upgrade.

As a result of the review, the staff has determined that additional information is needed to complete the review.

The information needed is detailed in the enclosure.

Since NRC approval of the request is needed to support your April 1996 refueling outage, we request that you respond in writing to this request for additional information as soon as possible but no later than 30 days from receipt of this letter.

The requirements affect nine or fewer respondents and, therefore, are not subject to the Office of Hanagement and Budget review under P.L.96-511.

If you have any questions, please contact me at (301) 415-1362.

Sincerely, Original signed by K. Thomas for:

James M. Clifford, Senior Project Hanager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

Request for Additional Informat ion cc w/encl:

See next page

~OI T IBOTIO Docket File PUBLIC JRoe EAdensam WBateman JClifford EPeyton

JStewart, HICB
JWermiel, HICB
ACRS, TWFN PDIV-2 Reading
OGC, 015818
KPerkins, WCFO
JDyer, RIV
HWong, WCFO KThomas
OChopra, EELB
JCalvo, EELB DOCUMENT NAHE: WNP93949.RAI OFC PDIV-2 NAME ke%n DATE 2 18 96 PDIV-2 s)

KTho as:

k 2(

96 PDIV-2

'rY JCli for 2

/96 OFFICIAL RECORD COPY

Hr. J.

V. Parrish cc w/encl:

Hr. G. 0. Smith MNP-2 Plant General Hanager Mashington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 Chief Counsel (Hail Drop 396)

Mashington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968 Hr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P. 0.

Box 43172 Olympia, Mashington 98504-3172 Hr. D. A. Swank (Hail Drop PE20)

MNP-2 Licensing Hanager Washington Public Power Supply System P.O.

Box 968

Richland, Mashington 99352-0968 Hr. Paul R. Bemis (Hail Drop PE20)

Director, Regulatory and Industry Affairs Washington Public Power Supply System P.O.

Box 968

Richland, Mashington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 5 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O.

Box 69

Prosser, Washington 99350-0190 Hr. R. C. Barr, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 69

Richland, Mashington 99352-0968 H. H. Philips, Jr.,

Esq.

Minston 5 Strawn 1400 L Street, N.M.

Mashington, DC 20005-3502

Enclosure M SH NG ON PUBLIC POWER SUPP Y S ST UCLEAR OBJECT NO.

2 WNP-2 OC E

N 50-3 E

U 0

D ONA OR T 0 EG DI G

C OBER 26 1995 SUBN TTAL In order to complete the review of Mashington Public Power Supply System's proposal for using an adjustable speed drive (ASD) for control of reactor recirculation pumps at MNP-2, the following additional information is required.

On page 5, Appendix A, it is stated that to increase system reliability, the GE-FANUC control system uses redundant power supplies and the ASD control system uses a separate uninterruptible power supply.

Provide the sources of power for these devices.

2.

3.

4.

7.

On page I, Appendix B, it is stated that filter capacitors are applied across the ASD output to filter the harmonics.

Since these filters are in parallel with the motor inductance, it could create an inductance-capacitance circuit with a resonance frequency that can be excited by the ASD harmonics.

If this frequency is present, harmonics currents can be amplified.

To eliminate this concern the inverter uses GTO SCRs to switch currents on or off at appropriate times during a cycle.

Please explain how these SCRs work and what are the consequences if they fail.

Is the GTO SCR failure indicated in the control room?

Describe surveillance/periodic testing to be performed which will assure that harmonic current from the adjustable speed drive will be maintained within established limits at safety as well as non-safety buses.

Given that the harmonic currents generated are kept within a 5 percent limit by harmonic filters, will there be any resonant conditions generated which could produce currents greater than what the electrical equipment is designed to?

At MNP-2, have electrical, instrumentation, and control system equipment been designed to operate satisfactorily with a harmonic voltage of 5 percent superimposed on the input voltage by operation of the proposed adjustable speed drive?

Have the harmonic filters been designed and sized for the harmonic current generated from the adjustable speed drive as well as the harmonic current from the power supply system for all modes of plant operation?

Mith the harmonic filters inoperable and the adjustable drive speed at 100 percent, what is the harmonic distortion contribution from the variable speed drive?

It is stated in Appendix B, page 22, that the onsite operational testing of the ASDs was performed in June 1995 (during a plant outage).

During the testing, the highest voltage total harmonic distortion was 5.2 percent as measured at bus SN-6.

This value exceeds the 5 percent value established in IEEE-519.

Mhat effects does this have on the remaining loads on bus SH-6?

Are there any other tests done on the ASDs since then? If so, please provide the test results.

If not, how many tests are planned in the near future?

Appendix B, page 4, provides the results of an analysis in percentage of total harmonic distortion in startup as well as in generation mode.

Please explain the last three columns of tables on this page.

It is stated in Appendix B, page 2, that the adjustable speed operation affects RPT breaker performance.

Since the ASDs vary the frequency of the power supplied to the motor, the opening time of the breaker will vary inversely with the supplied voltage, i.e., if the system is operating at 15 HZ the opening time of the RPT breakers increases to 20 cycles (assuming normal opening time of the breaker to be 5 cycles).

Mith this delay in opening time, are these breakers still properly coordinated with the containment electrical penetration conductors for all possible short circuit conditions, including the maximum available fault current?

Your response should also include the coordinated fault-current-versus-time curves for these penetrations.

Provide a schematic diagram that shows all the protective devices used for the ASD system.

The change from 18 month to 24 month surveillance and some of the accident analysis sections refer to the high reliability of the FANUC and HEM units.

The numbers are given as "per demand."

a.

Provide a description of this term as it relates to the startup and normal operation of the ASDs.

b.

Provide the information which forms the basis for those reliability numbers.

Are all of the alarms listed in Table 2 of Appendix B annunciated in the control room?

Does the logic provide for continued acceleration if there is a failure of one of the ASD channels between 2 and 15HZ?

Describe the loss of one ASD in more detail.

Is the change of the remaining ASD to 52 HZ instantaneous (as fast as the sense and command can perform it) or is it ramped at the pump coast down rate?

Given that a single ASD has torque capability of 52 HZ, are there any effects on the system as a result of motoring at 60 HZ down to 52 HZ?

Is the ASD maximum frequency limiter changed at the same time?

16.

Provide the FANUC and HEH operation, maintenance and installation manuals or the following excerpts.

Particular items of interest include the self diagnostics (what parameters are monitored), the manufacturers claimed environmental parameters (temperature, humidity, etc.),

automatic actions taken upon a diagnostic result.

17.

Are there any alarms or indications in the control room of problems with the FANUC and HEH other than microprocessor interrupt?

18.

Describe the quality controls of the manufacturing process.

Mere the devices under a gA program including software gA, V8V, and configuration management?

Is an error and change reporting mechanism in place to assure that WNP-2 is informed of changes/errors in the products?

Has WNP-2 or an industry group performed any gA audits of the vendors?

19.

Provide the company names and factory locations of the designers and manufacturers of the FANUC and HEH.

20.

Is there any indication to the operator when the limiting functions in the FANUC or HEH override the operators demand?

21.

Are the ASD overfrequency relays separate electromechanical/solid state relays or is this function implemented in the software of the HEH?

22.

Verify that there are no changes to the safety-related RTP.

'0 P

l