ML19209A257

Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Pumps Utilizing Deep Draft Design Are Planned for Use.Contracts Not Yet Awarded

ML19209A257
Person / Time
Site:	Yellow Creek
Issue date:	09/10/1979
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7910030238
Download: ML19209A257 (7)

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TENNESSEE VALLEY AUTHORITY Pe1 CHATTANOOGA TENNESSEE 374o1 @

• 400 Chestnut Street Tower II -

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,~: e" September 10, 1979 .7 Cd CO Mr. James P. O'Reilly, Director -

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Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

OFFICE OF INSPECTION AND ENFORCDtENT BULLETIN 79 RII:JP0 50-254, 50-260, 50-296, 50-327, 50-328, 50-390, 50-391, 50-438, 50-439, 50-518, 50-519, 50-520, 50-521, 50-553, 50-554, 50-566, 50-567 - BROWNS FERRY, SEQUOYAH, WATTS LAR, BELLEFONTE, HARTSVILLE, PHIPPS BEND, AND YELLOW CREEK NUCLEAR PLANTS In response to your July 11, 1979, letter which transmitted OIE Bulletin 79-15, we are enclosing the results of our investigations for Brovns Ferry, Cequoyah, Watts Bar, Bellefonte, Hartsville, Phipps Bend, and Yellow Creek Nuclear Plants.

If you have any questions regarding this matter, please call Tish Jenkins at FTS 854-2014.

Very truly yours, TENNESSEE VALLEY AUTHORITY N. h L. M. Mills, Manag r Nuclear Regulation and Safety Enclosure cc (Enclosure):

Mr. Victor Stello, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 1087 166 Director of the Division of Operating Reactors ['

Office of Nuclear Reactor Regulation -

U.S. Nuclear Regulatory Commission Washington, DC 20555 23[

291ooso a 79o3 u An Equal Optortunity Employer y-0FElcig COPY

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ENCLOSURE RESPONSE TO NRC-0IE BULLETIN 79-15 DEEP DRAFT PUMP DEFICIENCIES BROWNS FERRY NUCLEAR PLANT (50-259, 50-260, 50-296)

Item 1. Browns Ferry Nuclear Plant has 12 deep draft pumps similar to those shown in figure 1 of the subject IE bulletin in safety-related systems.

Item 2. These pumps are manufactured by Byron Jackson, size 20 KXH, 4500 gpm at 275 total developed head, and are used for RHR service water and EECW.

Item 3. The pumps are approxiuately 46 feet lont from suction to discharge and 22 inches in diameter.

, Item 4. Browns Ferry Nuclear Plant began making power in June 1974 with unit 1. The startup tests for the RHR and EECW pumps were per-formed in June 1973 and December 1974. The startup tests were completed several months before each unit's fueling. Each pump was tested for capacity, rated pressure, automatic start and stop, and legic. Once each month, a pump operability test is performed on each pump and the data from these tests are compared to the pump design performance curve.

Item 5. Operational problems are minimal, and there has been only one major repair. The pump leaks water from the stuffing box and requires continuous checking and adjustin; of the packing. This is normal for this type of service. The only major repair was performed in August 1978. The pump failed to pump water. Upon disassembly of the pump, it was found to have a broken shaft and the bearings had excessive clearances. The pump was completely rebuilt. One other pump showed signs of a decrease in performance diring testing. The pump was removed from service and inspection revealed impeller wear which reduced the pump's capacity.

Item 6. Upon reviewing the in-servi e records of the purps from 1974 until the present, we fino th:t there have been one major pump failure and one routine pump rebuild. The two pump problems were on pumps that are in operation 50 percent of the time. This is indicative of an excellent pump record. The longest interval that each pump has been available for operation, without corrective maintenance, would be from 1974 until the present, with the exception of the two pump repairs described in item 5. Three of the RHRSW pumps (one per unit) were not added until the summer of 1976.

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Some of these pumps are automatic start and an accumulated run time, cycles of operation, and duration of each cycle cannot be obtaine< in exact detail.

The design specifications are being met; therefore, no additional maintenance activities or tests are planned. TVA has the applicable information, identified on page 3 of 3 of Bulletin 79-15, available at the site for inspection by NRC personnel.

SEQUOYAH NUCLEAR PLANT (50-327, 50-328)

Item 1. Sequoyah has '6 deep draft pumps similar to those shown in figures 1 and i of the subject OIE bulletin in use in safety-related systems.

Item 2. Refer to Attachment A for the listing of manufacturer, model, capacity, and plant application.

Item 3. Refer to Attachment A for the overal] dimensions at each type pump.

Item 4. TVA has not completed the investigation for these items. We

5. anticipate transmitting the results of our investigation for

6. Sequoyah on or before September 21, 1979.

WATTS BAR NUCLEAR PLANT (50-390, 50-391)

Item 1. Watts Bar has 16 deep draft pumps similar to those shown on figures 1 and 2 of the subject OIE bulletin in use in safety-related systems.

Item 2. Refer to Attachment A for the listing of manufacturer, model, capacity, and plant application.

Item 3. Refer to Attachment A for the overall dimensions of each pump.

NOTE: The pumps identified in items 1, 2, and 3 have not been transferred from CONSTh to P PROD. These pumps are in the initial stages of being put in:o service. Therefore, there has been no appreciable accumulation of operational and maintenance history. However, all available infcrmar. ion is given in items 4, 5, and 6.

Item 4. A summary of startup, testing, and routine maintenance history is given below for each type pump:

a. Screen wash pumps - These pumps have been operated 15 minutes per day for 15 days.

b. Essential raw cooling water (ERCW) pumps - These puc7s have been used to flush the system with a maximum duty o,f 4 days at rated flow. Since August 2,1979, D, G, and H pumps have intermittently been used to supply cooling water at approxi-mately rated flow.

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c. High-pressure fire pumps (HPFP) - These pumps have not been operated. They are currently undergoing final checks before initial operation.

Item 5. Operational problems and major repair efforts, as applicable, are described below:

a. Screen wash pumps - Only one pump packing has been replaced; no other maintenance has been required.

b. ERCW pumps - No maintenance has been required other than adjust-ment of packing.

c. HPFP - No problems or repair efforts.

Item 6. Operational intervals are given below:

a. Screen wash pumps - These pumps have been svailable for 15 days.

They are operated for 15 minutes per day at approximately rated flow. One of the original packings was replaced during initial operation. Pum,s have performed satisfactorily to date.

b. ERCW pumps - While supplying cooling water at approximately rated flow, three of the ERCW pumps received the following duty:

G 48 hours H 24 hours G 8 hours H 11.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> G 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> H 16 hours D 72 hours H 72 hours D 144 hours H 144 hours In addition to these hours, all ERCW pumps (A through H) were operated intermittently for system flush. The average time for continuous operation was approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

The lor.;est continuous run has been at approximately rated flow for 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br />. At the end of each service run, all pumps have been operable.

There have been no maintenance problems to date.

c. HPFP - This item is not applicable since these pumps are not operational.

BELLEFONTE NUCLEAR PLANT (50-438, 50-439)

Item 1. Bellefonte has 8 deep draft pumps similcr *> f> c identified in figures 1 and 2 of the subject OIE bulle '- in ye in safety-related systems. .

Item 2. Refer to Attachment A for the manufacturer, model, capacity, and plant application.

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• Item 3. Refer to Attachnent A for the overall dimension of the pumps.

Item 4. These pumps hr.o not undergone testing yet. Only receipt

5. inspection ane periodic preventive maintenance checks have

6. been made. No deficiencies have been found to date.

HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS (50-518, 50-519, 50-520, 50-521, 50-553, 50-554)

Items 1, 2, 3, 4, 5, and 6 Hartsville and Phipps Bend have 9 deep draft pumps similar to those id-ntified in figures 1 and 2 of the subject DIE bulletin planned fcr use in safety-related systems (Hartsville, 6; Phipps Ber.d 3) . These pumps have not undergone testing yet.

Only receipt inspection and periodic preventive maintenance checks have been made. No deficiencies have been found to date.

Hartsville and Phipps Bend have additional deep draft pumps within the Reactor Island design (STRIDE). GE has informed TVA that GE plans to respond generically on NSSS and STRIDE pumps on a schedule that will not permit the information to be included in this report. TVA will provide information, as applicable, for the Hartsville and Phipps Bend Nuclear Plants on or before October 26, 1979.

Refer to Attachment A for a description of these pumps.

YELLOW CREEK NUCLEAR PLANT (50-566, 50-567)

TVA plans to have 4 CIM pumps and 4 screen wash pumps which utilize the deep draft design. However, the contracts on these pumps have not been awarded yet.

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ATTACm!ENT A TVA SAFETY-RELATED, DEEP DRAFT, TURBINE-TYPE PUMPS (RESPONSE TO IEB 79-15)

Flow (gpm)/ Head (f t) Dimension **

TVA Plant Pump ID No.* Manufacturer Model No. Capacity Plant Application Length /Dia.

Sequoyah ERCW 8 Johnson Pump Company 21 QMC 9000/180 Essential Raw 58'-3"/

(2 units) (orig) Cooling Water 2'-4-1/2" (ERCU)

ERCW 8 Johnson Pump Company 30 CC 11000/200 "

95'-7"/

(new) 3'-0" Aux. 2 Johnson Pump Company 27 DC/ 12600/155 "

14'-9"/

ERCW 24 QMC 2'-4-1/2" ERCW 4 8 CC 270/350 ERCW Screen Wash 90'-2"/

Screen Wash in Intake 8-1/2" Wash Pumping Station HPFP 4 "

14 CC 1500/400 High Pressure Fire 57'-8"/

Protection and 13-1/2" Flood' Supply _to Aux. Feedwater Watts Bar ERCW 8 Byron Jackson 32" RXL 12000/200 Essential Raw 90'-0"/

(2 units) VCT Cooling Water 2'-0" ERCW 4 Johnson Pump Company 8 CC 270/350 ERCW Screen Wash 87'-10"/

Screen in Intake Pumping 8-1/2" Wash Station HPFP 4 Goulds Pumps, Inc. VIT-12X16 1590/330 High Pressure Fire 84'-8"/

BLC-3-Stg. Protection and 16-3/4" Flood Supply to Aux. Feedwater _

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ATTACHMENT A '

TVA SAFETY-RELATED, DEEP DRAFT, IURBINE-TYPE PUMPS (RESPONSE TO IEB 79-15) Page 2 Flow (gpm)/ Head (f t) Dimension **

TVA Plant Pump ID No.* Manufacturer Model No. Capacity Plant Application Length /Dia.

Bellefonte ERCW 8 Weir Pumps CW2N54- 13,300/200 Essential Raw 70'-3"/

(2 units) 60A Coolin3 Water 2'-0" _

Hartsville Cm 9 Hitachi American SP-CV 28,800/133 Cooling Tower 47'-4"/

and Makeup Pumps Used 4'-8" Phipps Bend for Essential (6 units) Service Water (ESW) Tornado Backup Mode NSSS and STRIDE Pumps Yellow Creek CTM 4 Contracts on these pumps not 21,400/310 Cooling Tower Not Known (2 units) awarded yet. Makeup Pumps Used for ERCW Backup Water Source Screen 4 210/250 Screen Wash Pumps Not Known Wash in Intake Pumping Station Support the CM Pumps for ERCW Backup.

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