ML19323A075

Water Hammer Test on Addition of Auxiliary Feedwater to Steam Generator.

ML19323A075
Person / Time
Site:	Sequoyah
Issue date:	04/15/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323A073	List: ML19323A072 ML19323A075
References
PROC-800415, NUDOCS 8004170140
Download: ML19323A075 (14)

Text

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- . . . 't I . . WATER HAMMER TEST ON ADDITION OF AUXILIARY FEEDk'ATER  !

TO UNIT 1 STEAM GENERATOR {

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, e WATER HAMMER TEST ON ADDITION OF AUXILIARY FEEDWATER TO UNIT 1 STEAM GENEI'.ATOR TEST DESCRIPTION

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This test verified the configuration of the Steam Generator Feedwater Ring

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add associated Feeduater piping design to eliminate the potential for a Water Ha=cer caused by slugging in the feedline at the Steam-Water interface.

s. ~0 The J-Tube modification has been incorporated in the feedwater rings at the '"

Sequoyah Nuclear Plant and the feedwater line to each Stean Generator has

.. .. an extremely short horizonal run from the Steam Generators before turning

. down. Both of these design features should minimize or eliminate this water hac=er phenomenom. The water hancer han.been known to occur at other plants of similar design, but without .the J-Tube codification, on recovery of the Sten: Generator water level which was below the feedwater ring using the Auxiliary Feedwater System for makeup.

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This test will consist of lowering the level of the water in Steam Generator No. 2 to belev the fecdvater ring while the unit is at hot standby conditions.

The level will be maintained here without any water addition for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to allow time for the feedwater ring to drain. Thercocouples .will be placed near the inlet no:=le on the feeducter line to detect draining of the feedwater ring. Observers will be positioned to detect any water haccer as the Auxiliary Feedwater is initiated. It sould be noted that the Hot Functicnal Testing has been completed en Unit 1 and this Test is to be perforced af ter fuel loading in Hot standby conditions using putp heat to maintain RCS '. '

temperature near 5470F.

P This procedure will be maintained in the permanent plant historical file.

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. SPECIAL TEST Page 1 3/24/80

- 1.0 OB.hECTIVES 1.1 Verify that excessive transient vibrations or any evidence of water hat =er do not occur along the main feedwater and Auxiliary feedwater line associated with Ste== Generator #3, during the injection of Auxiliary feedwater while the Steam Generator wate.r-

. level is below the feedvater ring.

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SPECIAL TEST '.

• Page 2 3/24/80 2.0 PREREQUISITES 2.1 The main feedvater and Auxiliary feedwater piping, hangers,scismic supports (snubbers), and pipe . rupture restraints . associated with Steam Cencrator #3 have'been inspected between.the Steam Cencra-tor and the last check valve. to verify that no previous damage

. or abnor alities exist.

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2.2 Verify the construction' prerequisites for.TVA-25B, Thermal Ex- ,

pansion of Au::iliary piping Systems are' complete and any exceptions would not preclude conduct of this tesf. '

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2.3 Verify the thercocouples are in position and properly attached to the Main Feedwatcr line to indicate draining of the feedwater .

ring of Steam Generator #2.

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2.4 Verify the Unit is in Hot Standby condition with makeup.to Steam .

Generators being supplied from the cotor driven Auxiliary Fcedwater pucps per SOI 3.2.

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2.5 Notify representatives of the NRC, at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in advance, that the test will begin.

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• • - . SPECIAL TEST Page 3 3/24/80 3.0 PRIdAUTIONS 3.1 During the injection of Auxiliary Feedwater do not allow the Reactor Coolant System to be cooled at a rate approaching 1000/Hr.

3.2 During the actual water hatner test, the obser'ers cust be aware

," that piping movecent may occur and that if a rupture of the pipe j results, the leaking water will shortly be followed by live. steam.

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- Every effort must be made to position the observers in a protected

-but easily escapable area. These observers should also be avdre

. . of Ilot piping and supports in their area of observation.

3.3 If water ha==cr does occur, terminate Auxiliary Feedwater i==ediately to this Steam Generator to prevent dacage to piping and equip =ent.

(The Auxiliary Feedwater may be reinitiated at a much slower rate to maintain the water level.) .:

3.4 While maintaining the water level below the feedwater ring, do not allow any unter to enter the feedwater ring for the Steam Generator in test prior to the purposeful initiation of Auxiliary Feedwater or the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> wait may have to be repeated.

1 3.5 Be' aware that the isolation valves from the Auxiliary Feedwater .

• pumps to Steam Generator #2, which are norcally locked open will be closed during the draining of the feedwater ring to ensure no makeup at this time. -

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4.0 SPECIdL TEST EOUIPME!;T Identification Calibration i

Instru=ent- Specification Nu=ber Verification

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~. 8~Thereocouples Type T , .

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Data Logger -Fluke Model 22403 - . . - . - .

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If test instru=ents are changed during this test, the instrucent-inforestion must be recorded here and an entry cade in the. chronological log explaining this change.

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• 3/24/80 5.0 TEST INSTRUCTION 5.1 Verify the water icvel in Steam Generators #1, 3, and 4 is above the "LO" Icvel (25% of the narrow range level indicators) .

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• NOTE: ' An effort must be made to naintain the levels of Steam

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Generators #1, 3,.and 4'.above the "LO-LO" level (21% of

-narrow rcnge indicators) during the testing.and avoid any sudden. slugging of ATW into the-Steam Generators which

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may drop the RCS temperature an unexpected amount.

NOTE: Attempt to maintain RCS Te=perature between,5400 and 5470F and Steam Generator pressure between 950 and 1005 psig especially just prior to water hac=er test.

5.2 Begin lowering the water level in Steas Generator #2 by placing 1-HS-3-156A and 1-HS-3-173A in " MANUAL" and ratp closed 1-LCV-3-156 and 1-LCV-3-173 to prevent Auxiliary Feedwater frem being added to Steam Generator #2 on a "LGW-LOW" Steam Generator signal. When the LO-Lo Steam Generator accident signal is brought in, move the handsuitches to Acc. reset and ensure valves are rarped closed again.

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NOTE: Maintain low steam off rate in Stean Generators to keep witer level in Steam Generator #2.between the tube bundle and the~

feedwater ring. This may be done by lowering the RCS tecpera-ture sece what just prior to the test and allowing the RCS temperature to siculy rise to 5470 to keep the stencing rate down. Also, one or core of the Reactor Coolant Pu=ps could be tripped off to rdnimize the heat input.

5.3 Lower the water icvel of Steam Generator f2 using Steam Generator Bicudcun (or any other means) to between 0" and 9% of the narrow range indicctor (1-LI-3-51, 52, or 55 on panel 1-M-4) and hold at 1 css than 9% level for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.without makeup.'

(Refer to isolation of Main Feeduater and Auxiliary Feedwater in next few steps). This should ensure drainage of the feedwater ring.

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NOTE: Do not add water to Steam Generator #2 unless the level falls near the icvel of the tube bundle (71% of the wide range indicator, 1-LR-3-43P2 on Panel.1-M-4) at which time the test -

should either commence or the atte=pted draining of the fecdwater ring should be repeated.

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SPECIAL TEST .

• Page 6 3/24/80 5.4 Provide double isolation in the Auxiliary Feedwater System,151n Feeduster System and the Steam Generator System by closing rr verifying the following valves are closed.

1-LCV-3-156 'AFW Level Control VLV from MF AWP 1A-A to SG!2 1-LCV-3-156A AW Bypass VLV From MD AWP 1A-A to SG#2 1-LCV-3-173 - Am Level Control VLV from TD A WP 1A-5 to SG#2 1-3-884 - AFU Iso.lation VLV Bypass 3-876 -

.051 Isolation-VLV to SGP2 -'

3-835 ABv Isolation VLV to SGC2

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1-~3-84 4 AFW Isolation VLV Bypass

_ 1-FCV-1-182 Steam Generator #2 Blowdoun Isolation Valve 1-FCV-1-14 ' Stcan Generator #2 Blowdown Control Valve 1-FCV-3-47 SG < .' Feedwater Isolation Valve 1-FCV-3-48 SG #2 Feedwater Control Valve i-FCV-3-48A SG #2 Yeedwater Bypass Valve

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5.5. Hold these conditiens for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until the thermocouples on the Feedwater piping indicate the Feeduater ring is drained of water by a sudden increase in temperature which indicates stes= is circulating within the Feedwater pipe. Record temperature at T/C at 10 minute intervals on Data Sheet.5.5.

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5.6 Ensure the level of Steam Generator #1 is close to normal and plac'c 1-HS-3-164A in "RGUAL" to ensure flow from AW Pump 1A-A vill be available and consistent to. Steam Generator #2.

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5.7 Position observers in the Main Steam Valve Room, near the AFR I valves and around the Stcam Generator #2.

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5.8 Record data as necessary on Data Sheet 5.8.

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5.9 ' Open Auniliary Feedwater manual isolation valve 1-3-835.

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CAUTION: During the following steps do not allow the Reactor l Coolant System to be cooled at aLrate approaching 1000/hr.

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.This has been interpreted by EN DES.during Hot Functional-to be no nore than 50_ degrees.in any half. hour.

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SPECIAL TEST Paga 7 3/24/80 5.10 Using 1-ES-3-156A, canually racp open 1-LCV-3-156 and using Auxiliar/ Feedwater Pc=p 1A-A, increase flow to Steam Generator

1. 2 to greater than 220 spo as quickly as possible. Maintain the flow until the Feeduster ring is covered cnd above the "Lo-L,o" level of 21% and then decrease to a much lower flow rate to raise the level to above the "LO" level. Terninate flow in=ediately

. if water hac=cr is observed or if an excessive cooldown rate is

. _ . _ approached. Record data as required on Data Sheet 5.10.

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5.11 Verify'that there was no excessive vibration 'or any evidence of

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. water ha==cr during or af t.cr the trancient.

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5.12 Return ATW isolation valves 1-3-876 and 1-3-835 to their " Locked Open" position.

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5.13 When the corresponding Stean Generator levels are near nor=al, place 1-ES-3-156A, 1-ES-3-172A and 1-ES-3-164A in the "AUT0"

.. or as necessary for nor=al plant operation.

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4 5.14 Return the Main Feedwater Systen and Steam Generator Blowdown Systcc Valve aligncent to Steau Generator #2 as required for norr2.1 plant operation.

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SPECIAL TEST Data Sheet 5.8 .

• Page 1 of I WATER I!AM:ER TEST 3/24/80 Data Shoct 5.5 Just P'rior to Au::111ary Feedwater Injection Temperature of Thereoccuples near Steam Generator #2 Feedwater no::le Temperature of T/C No:

• (10 nin. Interval) h (Last entry just prior to injection) 1 Data Recorded by /

T/C Position

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SPECIAL TEST Data She t 5.8 WATER HA122R TEST Page 1 of I Data Sheet 5.8 3/24/80 Just Prior to Au::iliary Feedvater Injection DESCRIPTION ACC DATA IMST. LOCATION DATA CRIT ACCEPTAI Steam Generator #2 Level 1-11-3-51 1-M-4 49% t Log LO422

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Steam Cencrator f2 Level .

1-LI-3-52 1-M-4 49% <

.a. Log LC421 .

Steam Cencrator #2 Level 2-LI-3-55 1-M-4 (9% /

. Log LO420 -

'. Steam Generator #2 Level LR-3-43P2 1-M-4 > 71% j 4- -

Log LO423A Steam Generator f2 Steam Press.ure 1-PI-1-9B 1-M-4 Log PO421 Steam Generator 62 Steam Pressure 1-PI-1-9A 1-M-4 Log P0420 Steam Generator #2 Steam Pressure 1-PI-1-12 1-M-4 Log P0422 Steam Cencrator f2 Feedwater Prescure 1-PI-3-50 1-M-3 Log PO423A RCS Ter:perature Temperature of W Log T2426 Data Recorded by /

COM:IENTS:

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. SPECIAL TEST

' Data Sheet 5.10 , . .  ;

Page 1 of 1 WATEPg HMS'ER TEST 3/24/80 i Data Sheet 5.10  ;

During initiction of Au: ciliary Feeduater ,

Steam Cer.crator f2 Bi Level Stcan Pres ; AMi Flow AMI Temp Mi Temp RCS Teep l Time 1-LI .h 1-PI 1-FI Log T2426 TC#

Log Log Log Log 430 sec . -

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3 min.

4 min.

5 min. >

6 nin.

7 min.

8 min.

9, min. -

10 min.

Data Recorded by /

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. SPECIAL TEST Appendix A Page 1 of.1 3/24/80 APPENDIX A 1.0 TVA Drawings 1.1 Flow Diagram , .

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47W801-1~ R15 .

-47W801-2 .R11 _ , , , ~_.._._ .

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47WS03-1 R11 _

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- 47W803-2 .R16 -

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'1.2 Centrol Diagram

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47W610-3-1 R10-47W610-3-2 R12 47W610-3-3 R8 c

1.3 Instrunent Tabs q 47B601-3 Series ,Lu ev ku a u 1.4 Mcchanical Piping Diagrans 47W401-1 R16 47W401-4 R9

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1.5 Isonetric Drawings 47U335-2 2.0 Manuals '

TVA Contract (D 123 2.7.2 Gen-2, Installation of J-Tube 68C60-91934 Series 51 Steam Generators U2M-2-4

() Instructions.forVerticalSteamCencrators 68C60-91934 for Tennessee Valley Authority N2M-2-4 Sequoyah Unit No. 1 4

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APPETDIX B  !

Deficiencies and Exceptions i i- .

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" r.ber  ::=ber  !!=ber Description of Deficiency Dispositio'n of Deficiency m

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