ML17083A341

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Requests Performance of Tests to Obtain Specific Baseline Hydraulic Data W/Core Installed at Unit 1.Data Could Be Used for Comparison in Case of Future Accident.Data May Be Obtained from Tests at Similar Plants as Alternative
ML17083A341
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/02/1980
From: Tedesco R
Office of Nuclear Reactor Regulation
To: Furbish M
PACIFIC GAS & ELECTRIC CO.
References
NUDOCS 8005160260
Download: ML17083A341 (16)


Text

NAY 2 1980 Docket Nos.:

60-27 60 2

Hr. Malcolm O', Furbush Vfce President and General Counsel Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 DISTRIBUTION:

Docket File NRC PDR Local PDR LB g3 DEisenhut RPurple RTedesco BBuckley JLee DRoss SHanauer JKnight

, VHoore HKreger HErnst RDenise.

ELD IE (3)

JTourtellotte NI8008180 aC'6 bcc:

NSIC TIC ACRS (16)

Dear fear. Furbush:

SUBJECT:

BASELINE HYDRAULIC DATA - DIABLO CANYON, UNIT 1 The staff believes that ft would be very desirable to obtain the specific baseline hydraulic data described below with the core installed in the Diablo Canyon, Unit 1 plant. If there is an accfdent involving core damage at some future time, similar data could be obtained and compared to the baselfne data to infer the extent of'ore damage.

Alternatively, instead of conducting the tests described below you may wish to obtain the results of tests that will be performed at other similar plants.

such as the Salem Nuclear Generating Station, Unit 2, and determine their applicability to Diablo Canyon, Units 1 and 2.

Should you elect to take this alternate

approach, we require that your operating personnel and other appropriate technical staff be thoroughly familiar with the test data and that this data be available fn the on-site technical support center at all times for immediate use.

The tests that we require to be performed are relatively simple.

They involve experfmntally determining the differential pressure across the elbow pressure taps in each reactor coo'lant loop for various pump combinations.

These tests should be conducted with the core installed, b0t all control rod assemblies inserted.

The reactor coolant system should be at about normal operating temperature and pressure.

The tests should be performIed >>ith one pump, bm pumps, and three pumps operating.

The differential pressure data should be obtained in all four loops; that fs. the loops with flow in the normal direction and the loops having flow fn the reverse direction.

Pump

data, sbch as motor current and revolutions per minute (ff possible to obtain), should also be recorded.

OFFICE SURNAME DATEP NRC FORM 318 {9-76) NRCM 0240 i a OU.S. GOVERNMENT PRINTING OFFICE( 1979 289 369

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Hr. fhlcolm H. Furbish gK; 4 i88u The tests may be performed either as a portion of the proposed low power test program, or, as an extension of the pump trip tests performed as a part of your commitment to Regulatory Guide 1.68. If the tests are performed in con)unction arith the pump trip tests, the data requested above should be taken ofter the tripped pump has completely stopped.

Please provide your commitment to perform the tests required or your commitment to obtain the applicable. test data by Hay 5, 1980.

Sincerely,

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cc:

See next page Robert L. Tedesco Assistant Director for Licensing Division of Licensing OFFICE SURNAME I9ATE)

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NAY 2 t980 Docket Nos. j 50-275 50-323 Mr. Malcolm H. Furbush Vfce President and General Counsel Pacfffc Gas and Electric Company 77 Beale Street San Franc1 sco.

Cal 1 fornfa 94106 DISTRIBUTION:

Docket File NRC PDR Local PDR LB ¹3 DEisenhut RPurple RTedesco BBuckley JLee DRoss SHanauer JKni ght VMoore WKreger MErnst RDenise ELD IE (3)

JTourtellotte bcc:

NSIC TIC ACRS (16)

Dear Mr. Furbush:

SUMECT:

BASELINE HYDRAULIC DATA - DIABLO CANYON, UNIT 1 The staff believes that ft would be very desfrable to obtain the specific baselfne hydraulfc data described below with the core fnstalled 1n the Diablo Canyon, Unit 1 plant. If there fs an accident involving core damage at some future time, sfmflar data could be obtained and compared to the baseline data to 1nfer the extent of core damage.

Alternatively, instead of conducting the tests described below you may wfsh to obtain the results of tests that will be performed at other sfmflar plants, such as the Salem Nuclear Generating Statfon, Unit Z. and determfne thefr applfcab11fty to Diablo Canyon, Units 1 and Z.

Should you elect to take this alternate

approach, we requfre that your operating personnel and other appropriate technical staff be thoroughly famflfar with the test data and that thfs data be available fn the on-site technical support center at all times for fmedfate use.

The tests that we require to be performed are relatfvely simple.

They fnvolve experimentally determfnfng the differential pressure across the elbow pressure taps fn each reactor coolant loop for various pump combfnatfons.

These tests should be conducted with the core installed, but all control rod assemb'cafes inserted.

The reactor coolant system should be it about normal operating temperature and pressure.

The tests should be performed w1th one

pump, two pumps, and three pumps operating.

The differential pressure data should be obtained in all four loops; that fs, the loops with floe fn the normal direction and the loops having flow fn the reverse direction.

Pump

data, such as motor current and revolutions per minute (ff possible to obtafn), should also be recorded, OFFICE SURNAME

,OATEN..

NRC FORM 318 (9 76) NRCM 0240

'0 U.S. GOVERNMENT PRINTING OFFICE: 1979 289 369

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Mr. Malcolm H. Furbish.

The tests may be performed either as a portion. of the proposed low power test program, or as an extension of the pump trip tests performed as a part of your comitment to Regulatory Guide 1.68. If the tests are perforated in coQunction with the pump trip tests.

the data requested above should be taken after the tripped pump has completely stopped.

Please provide your coamitment to perform the tests required or your comitment to obtain the applicable test data by Hay 6, 1980..

Sincerely.

gt/fly Signed cc:

See next page Robert L. Tedesco Assfstant Director for Licensing Division of Licensing

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DATEP NRC FORM.318 {9.76) NRCM 0240

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.0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 vavts ts80 Docket Nos.:

50-275 50-323 Hr. IIalcolm H. Furbush Vice President and General Counsel Pacific Gas and'Electric Company 77 Beale Street San.Francisco, California 94106

Dear Hr. Furbush:

SUBJECT:

BASELINE HYDRAULIC DATA - DIABLO CANYON, UNIT 1

The staff believes that it would be very desirable to obtain the specific baseline hydraulic data described below with the core'nstalled in the Diablo Canyon, Unit 1 plant.

If there is an accident involving core'damage at some future time, similar data could be obtained and compared to the baseline data to infer the extent of coI'e damage.

Alternatively, instead of conducting the tests described below you may wish to obtain the results of tests that will be performed at other similar plants, such as the Salem Nuclear Generating Station, Unit 2, and determine their applicability to Diablo Canyon, Units 1

and 2.

Should you elect to take this alternate

approach, we require that your operating personnel and other appropriate technical staff be thoroughly familiar with the test data and that this data'e available in the on-site technical support center at all times for immediate,use.

The tests that we require to be performed are relatively simple.

They involve, experimentally determining the differential pressure across the elbow pressure taps in each reactor coolant loop for various pump combinations.

These tests should be conducted with the core installed, but all control rod assemblies inserted.

The reactor coolant system should be at about normal operating "temperature and pressure.

The tests should be performed with one

pump, two pumps, and three pumps operating.

The differential pressure data should be obtained in all four loops; that is,.the loops with flow in the normal direction and the loops having flow in the reverse direction.

Pump

data, such as motor current and revolutions per minute.(if possible to obtain), should also be recorded.'

e Mr. malcolm H. Furbish gAY 2 1980 The tests may be performed either as.a portion of the proposed low power test program, or as an extension of the pump trip tests performed as a part of your commitment to Regulatory Guide 1.68.

If the tests are performed in conjunction with the pump trip tests, the data requested'above should be taken after the tripped pump has completely stopped.

Please provide your commitment to perform the tests required or your commitment to obtain the applicable test data by May 5, 1980.

Sincerely, cc:

See next page

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Robert L. Tedesco Assistant Director for Licensing Division of Licensing

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Mr. Malcolm H. Furbush cc:

Philip A. Crane, Jr.,

Esq.

Pacific Gas 5 Electric Company 77 Beale Street San Francisco, California 94106 Janice E. Kerr, Esq.

California Public Utilities Commission 350 McAllister Street San Francisco, California 94102 Mr. Frederick Eissler, President Scenic Shoreline Preservation Conference, Inc.

4623 More Mesa Drive Santa Barbara, California 93105 Ms. Elizabeth E. Apfelberg c/o Nancy Culver 192 Luneta San Luis Obispo, California 93401 Ms. Sandra A. Silver

'1760 Alisal Street San Luis Obispo, California 93401 Mr. Gordon A. Silver 1760 Alisal Street San Luis Obispo, California 93401 Paul C. Valentine, Esq.

321 Lytton Avenue Palo Alto, California 94302 Yale I. Jones, Esq.

19th Floor

'00 Van Ness Avenue San Francisco, California 94102 Mr. Richard Hubbard MHB Technical Associates Suite K

1723 Hamilton Avenue San Jose, California 95125 Mr. John Marrs Managing, Editor San Luis Obispo County Telegram - Tribune 1321 Johnson Avenue P.

0.

Box 112 San Luis Obispo, California 93406 Elizabeth S.

Bowers, Esq.,

Chairman Atomic.Safety E Licensing Board U.

S. Nuclear Regulatory Commission Washington, D.

C; 20555 Mr. Glenn 0. Bright Atomic Safety

& Licensing Board U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555 Tolbert Young P. 0.

Box 219 Avila Beach, California 93424 Richard S.

Salzman, Esq.,

Chairman Atomic Safety 8 Licensing Appeal Board U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Dr.

W.

Reed Johnson Atomic Safety 8 Licensing Appeal Board U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Alan S.

Rosenthal, Esq.

Atomic Safety 5 Licensing Appeal Borad U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555 Ms.

Raye Fleming 1920 Mattie Road Shell Beach, California 93440 Brent Rushforth, Esq.

Center for Law in the Public Interest 10203 Santa Monica Boulevard Los Angeles, California 90067 Arthur B. Gehr, Esq.

Snell 5 Wilmer 3100 Valley Center

Phoenix, Arizona 85073 Mr; James
0. Schuyler, Nuclear Projects Engineer Pacific Gas 5 Electric Company 77 Beale Street San Francisco, California 94106

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A "l

t

Hr. Halcolm H. Furbush cc:

Bruce Norton, Esq.

3216 North 3rd Street Suite 202 Phoenix, Arizona 85012 Hr.

W.

C. Gangloff Westinghouse Electric Corporation P.

0.

Box 355 Pittsburgh, Pennsylvania 15230 Hichael R. Klein, Esq.

Wilmer, Cutler 5 Pickering 1666 K Street, N.

W.

Washington, D.

C.

20006 David F. Fleischaker, Esq.

Suite 709 1735 Eye Street, N.

W.

Washington, D.

C.

20006 Dr. William E. Hartin Senior Ecologist Battelle Hemorial Institute

Columbus, Ohio 43201 W. Andrew Baldwin, Esq.

124 Spear Street San Francisco, California 94105 Resident Inspector/Diablo Canyon NPS c/o U, S.

NRC P. 0.

Box 219 Avila Beach, Californi'a 93424

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