L-81-107, Provides Info Re Results of 800826-30 Test Conducted to Demonstrate Reactor Coolant Pump Seal Design Adequacy During Postulated Station Blackout Conditions.Major Seal Failure Abnormal Leakage Did Not Occur

Provides Info Re Results of 800826-30 Test Conducted to Demonstrate Reactor Coolant Pump Seal Design Adequacy During Postulated Station Blackout Conditions.Major Seal Failure Abnormal Leakage Did Not Occur

ML17209A801
Person / Time
Site:	Saint Lucie
Issue date:	03/10/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-81-107, NUDOCS 8103130429
Download: ML17209A801 (8)

Text

DOCKET 05000389 NOTE'S; REGULA Y INFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESSION NBR 8103130029 DOC ~ DATE' 81/03/10 NOTARIZED NO FACIL:50-389 St. Lucie Plant<

Unit 2< Flor ida Power L Light Co.

AUTH ~ NAME AUTHOR AFFILIATION UHRIGe R ~ E ~

Florida Power.8 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION EISKNHUTgD ~ G.

Division of Licensing

SUBJECT:

Provides info re results of 800826 30 test conducted.to demonstrate reactor coolant pump sea'I desipn adequacy

during, postulated station blackout conditions, Major-seal failure abnormal leakage did not occurs Results will be included-in I

DISTRIBUTION CODE:

B001S COPIES RECEIVED:LTR, +ENCL

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TITLE: PSAR/FSAR AMDTS and Related Correspondence

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INTERNAL: ACCID EVAL BR26 CHEM ENG BR 08 CORK PERF BR 10, EMERG PREP 22'EOSC IENCES 14 HYD/GEO BR 1S IS,K 06 LIC QUAL BR MECH ENG BR 18 NRC PDR 02 OP LIC BR PROC/TST RKV 20.

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FLORIDA POWER & LIGHTCOMPANY March 10, 1981 L-81-107 O

Office of Nuclear Reactor Regulation Attention:

Nr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Nr. Eisenhut:

Re:

St. Lucie Unit 2 Do'cket No. 50-389 Adequacy of Reactor Coolant Pump Seal Design Durin Postulated Station Blackout Conditions This letter is to report the results of Florida Power and Light Company's test of the reactor coolant pump seals used at St. Lucie Unit 2 under simulated conditions to establish their ability to withstand a station blackout event.

The performance of this test has demonstrated that the design of the reactor coolant pump seals is such that no abnormal leakage should be expected to occur from these seals during a postulated loss of all AC power situation when there is no cooling water to the seal coolers.

The test was conducted at the Byron Jackson Pump Division in Los Angeles on August 26-30, 1980, utilizing an actual pump seal cartridge supplied by Florida Power and Light Company from St. Lucie Unit 2.

A test fixture was used which simulated a-reactor coolant pump under hot standby conditions.

All of the seal related parts were of the same material and geometrical configuration as in the actual'pump.

'The seal cartridge

. related portions of this fixture, including the shaft, were made dimensionally the same as that of the reactor coolant pump.'s specified, hot pressurized water was circulated in the fixture duplicating the internal flow system of the pump.

The shaft was sealed at the top of the fixture using the test seal cartridge.

The block-off plate or collection chamber was bolted on top of the seal cartridge in order to direct the seal leakage to a measuring system.

ypo I PEOPLE... SERVING PEOPLE

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Tl I.

Darrell G. Eisenhut, D

- ctor Page Two Temperature detectors were placed in various locations as follows:

(1) in the lower fixture chamber (location of the reactor coolant pump impeller),

(2) in the upper fixture chamber (location of the seal cartridge),

and (3) in the upper seal cavity (between the third and vapor seal locations).

The seal cartridge pressure connections were used to read the pressure in each seal cavity, and the leakage was piped through heat exchangers to cool this flow so that it would remain a liquid to be measured with a beaker and stop watch.

Since this flow exits the pump, from the vapor seal, a pressure and temperature gage was placed in this line to record the vapor seal condition.

The seal cartridge was tested with water at 550oF and 2250 psig to duplicate

.initial conditions expected.in the event of a loss of all AC power.

These test conditions were maintained for more than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.

Significant seal failure did not occur during this test and, with the exception of abnormally high vapor seal temperatures and pressures, the controlled leakage was recorded within normal limits during most of the test, although this leakage was two phase flow as determined from'ithe',ihigh temperature readings of;the

. water in the upper seal cavity.

The maximum seal leakage recorded was 16.1 gph..

The seal cartridge was disassembled and inspected after.the test.

All pressure containing housings and the seal sleeves were still within the drawing tolerances.

Seal damage included a broken vapor seal rotating fact ring, permanent compression of all O-rings, permanent hardening of all U-cups, a slight out-of-round condition in the U-cup followers and the, spring holders, and slight distortion of all lapped surfaces.

In conclusion, this severe test demonstrated the capability of a-reactor coolant pump seal used at St. Lucie Unit 2 to withstand conditions far in excess of the environment encountered in any hypothetical station blackout event.

As requested in Nr. Robert,L..Baer's letter of September..17, 1979, the results of this test will be included.,in.,the Final Safety Analysis, Report for St. Lucie Unit 2.

If there are any questions concerning this test, please contact us.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/TCG/mc cc:

J.

P. O'Reilly, Director, Region II'arold F.;.Reis,'squire

~ ~

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Additional copies to:

Chairman Joseph..M..'endrie U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Commissioner Victor Gilinsky U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Commissioner Peter A. Bradford U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Commissioner, John;.F, Ah'carne U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Secretary U.S.Nuclear Regul ato.ry Commission Washington, D.C.

20555 Attn:

Chief, Docketing and Service Section Michael Glaser, Esq., Administrative

. Judge Alternate Chairman, Atomic Safety 8

Licensing Board 1150 - 17th Street, N.W.

Washington, D.C.

20036 Dr. Marvin M. Mann Technical Advisor Atomic Safety 5 Licensing Board Nuclear Regulatory Commission Washington, D.C.

20555 Dr. David L. Hetrick, Administrative Judge Professor of Nuclar Engineering University of Arizona Tucson, Arizona 85721 Dr. Frank P.

Hooper, Administrative Judge Resource Ecology Program School of, Natural Resources University of Michigan Ann Arbor, Michigan 48104 Martin Harold Hodder, Esq.

1130 N.E. 86th Street Miami, Florida 33138 Dr.

W.

Reed Johnson,, Administrative Judge Atomic Safety 5 Licensing Appeal Board Nuclear Regulatory Commission Washington, D.C.

Richard S.

Salzman, Esq., Administrative Judge

. Chairman, Atomic Safety 8 L'icensing

... Appeal Board Nuclear Regulatory Commission Washington, D.C.

20555 Alan S.. Rosenthal, Esq., Administrative Judge Chairman Atomic Safety 8 Licensing Appeal Panel Nucl.ear Regulatory Commission Washington, D.C.

20555 Edward.,Luton, Esq., Administrative Judge

Chairman, Atomic Safety 5 Licensing Board Nuclear Regulatory Commission Washington, D.C.

20555 Terence-J.

Anderson, Esq.

University of Miami School of Law Coral Gables, Florida 33134 William D. Paton, Esq.

Counsel for NRC Regulatory Staff Nuclear Regulatory Commission Washington, D.C.

20555 William J.

Olmstead, Esq.

Nuclear Regulatory Commission Washington, D.C.

20555 Local Public Document Room Indian River Junior College Library 3209 Virginia Avenue Ft. Pierce, Florida 33450 Norman A. Coll, Esq.

Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131

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