ML18127B102

03/02/1977 Letter Enclosure of Completed Pre-Operational Test Procedure 0700080B, Revision 2

ML18127B102
Person / Time
Site:	Saint Lucie
Issue date:	03/02/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Ziemann D Office of Nuclear Reactor Regulation
References
L-77-70
Download: ML18127B102 (61)

Text

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DOCVET NUMUEfl 50 S85 335 FILE NVMOE Il NRC DISTR)OUT!ON FoB )TAT 50 DOCKET MATCRIAL FROM: FPL DATE Ol DOCUMENT TO: Mir. Ziemann Miami, Fl 33101 03-02-77, Robert E. Vhrig DATE BLCEIVED 03-21-77 QNOTOBIZED PBOP INPUT FOAM NVMGEB OF COPIES BQCEIVED gLCTTI'- B

6) OfllGINAL Bf UN C LASS IF I E D QcopY ~ 1 signed DESCBIPTION ENCLOSU BE Xitr Ref their 02-25-77 ltr...Trans Consists of Pre-operational test .

The Ii'ollowing: procedure 0700080B, Revision 2. Also, chart recordings from the loose parts monitoring system, .the special press'ure transducer, and

( 1 pag ) the test parameter monitors....

( 30 pages ) .

(41 encl rec;d )

PLANT NAME: ST LVCXZ VNZT ]$ 1 ~CKNO~@DGLD lcm NOT ><MOVa NOTE: recordings are being returned to AppU.ca SAI'ETY FOR ACTION/INFORMATION,T.r ASSXGNED AD:

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PRO I'.c'r I '."i:vv~E ~ PROJECT I IANAGER

'LXC ASST LICs ASST NTERNAI 0 IST R I I)UTION hRC PD FXLE SYSTEllS SAFETY HEXING'EHAN PLANT SYSTEilS TEDESCO STSTE MRS~~

Ei~ZBLYELi T&E SCHRO)'DER ~1,"N~ A OSLO GOSSXCK 4 STAFF ENGINEERING XPPOLITO ENLQPO~Q HXPC HACARRY KX EKE ERNST CASE I)OS)I.'EK BAI,LARD I)ANAUER SIIII)E>,f OPERATING REACTORS YOUNG)3I COD 1!ARLESS STv.'LLO PANIC K SITE Ti;CH PROJECT HANAGEHENT RlOiCTOR SAFE'EL OPEPdiTING TECII ~ GAiiMILL BOYD ROSS EISE'.iHUT STEPP PE COLLXNS QLI/~0 I!ULNAN NOVAI'OSZTOCZY HOUSTON HAK PETERSON Cl)EC)" I3IJ)'l.l'.. SITE ANALYSIS HEI.TZ QIQl IES VOIrI ) IER HELTEHES AT&I )3UNCH SKOV)!OLT SAIrT/ZAN J. COLLINS Rl)T)31'.l<G KRE( ER EX I'EI)NAL DISTR IOUTION CONTROL NUMI3F Il NAT ~ID) )3!NO!xIV<VJ~N LIAT. LtLII UI~R)'SO~NORNI,)

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r FLORIDA POWER 8 LIGHT COMPANY March 2, 1977 9A L-77-70

<Vl tff Office of Nuclear Reactor Regulation Attn: Dennis L. Ziemann, Chief Operating Reactors Branch 42 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Ziemann:

Re: St. Lucie Unit No. 1 Docket No. 50-335 License Condition C Enclosed is a copy of the completed Pre-operational Test Procedure 0700080B, Revision 2. This document is pro-vided in accordance with the commitment made in our letter of February 25, 1977 (L-77-59). Also enclosed are copies of the chart recordings from the. loose parts monitoring system, the special pressure transducer, and the test parameter monitors.

Very truly yours, Robert E. Uhrig Vice President, REU/NLR/hlc Attachments cc: Norman C. Moseley, Region lX Robert Lowenstein, Esq.'

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FLORIDA POh'1'.)k & LXGJIT COR~PAaaY ST. L)JCXJ? PLANT UNIT (/1 PREOPE)U!!TIOJRAL TEST PROCEDURE NO. 0700080B REVISIOiN 2

1. TXTLE: STEAfl GENERATOR FEEDHATER HA'L&KR TEST

2. PREPARED BY:

6'i' f.~ 6-f-~ . 19 76 r

S. REVIEllED BY: l v'J)4' 'l~;~'W~f FOR C+ fU~ ~ 197~

J 4 SUPRCO)'JAJXTTEE REVXE'H BY.:

5. REVIEJJED BY FRG OiN: -,. i~r7 Zw.~ ~

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G. APPROVED BY:. I2 iwtN R Ir, JDrlA> /C~gr 19~r,'ce.fr~

7. REVISION REVIEIIED BYfPRG ON:~le l 1971

8. APPROVED )3Y: PLANT MANAGVR~r>~I. )~<a jj73!3 l'l

(~ TEST CONDUCTED BY:

re

10. RESDLTS RBVIEHED BY: C FOYP Z

11. TEST RESULTS REVXE!CED BY: 19 2:2

12. TEST RESULTS REVXEMED BY FPG, DEFXCI,NCXES CORRECTED, AND ACCEPTANCE RECOK%.'NDED Q,4 t'i . 19~7 13, RESULTS ACCEPTED ANIYD APPROVED BY: Plant Hanagm 77 j

14. REVXSION 2 REVXF D BY FRG: 19 15 'PPROVED BY PLANT MANAGER fLL) )g '719~

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s s Page 1 of ll FLORIDA POIKR & LIGHT CONP PREOPERRT10NAL TEST PR CL'DERE IioaI QIi00)IE I ) () )J REVXSIO IRIS DOCUMENT IS HOT COIITROLLED. GEFORE USE, VERIFY (HFORMATIOHWITH A COHTRDI.LED DOCUMEHT FLORIOA POY(ER AND L1GHT GO.

1.0 Ticla

POI'lER RESOURCES STEAM GENERATOR FEEDkvATER 1' DATE V'ERIFIED ST. LUCIE PIAHT IIIITIAL IRI'IIR.

2.0 ~Puz osal DATE VERH'IED QAIE VERIFIFD IHIIIA Due to the modification to th fe'edna'Leb~srgars, cb ssproce ura will be performed to verify t eIrsbs'en'cog damaging sfeam,.gener-ator feedwater hammer during j eI7e 1 r'e'c'o% eEESf RerCJDie-"Rsvel is below the feedwater sparger. S/G'B will be u sed. for the tes t since it has a longer run of feedwater piping.

3.0

References:

3.1 Ebasco Flow Diagram 8770-G-080; Feedwater, Condensate 6 Air Evacuation Systems.

3.2 CE Technical Instruction 1'manual - Steam Generator 3.3. Operating Procedure OP 0700022, Auxiliary Feedwater Normal Operation.

3.4 Emergency Procedure EP 0700040, Loss of Feedvater or Steam Generator Level.

r 4.1 Except for the level of S/G 1B, the plant "hould be at normal operating hot standby conditions with 4 RCP's running.

S/G 1B level should be restored to " 40%. Use Aux. PW pumps to maintain S/G levels.

Verified by D.ate 9 4.2 The decay heat input Lo the pr"'mary system at the beginning of the test shall be equal to or greater than the decay heat rate

. generated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after a shutdown from a minimum of 30% power /R2 following a minimum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of operatiAln.

1)

--'~s &'te Using ANS-5 calculate the decay heat rate using the above Vexified by Reactor EngineerSng Using ANS-S and actual plant power hisILory preceeding the

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2) test, calculate actual decay heat rate at the beginning of NN T>rf Verified by R Dace R sc  ? 7 R ctor En ineernng

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Page 2 of ll PREOPERATIONAL TEST PROCEDURE NO. 0700080B, Rev. 2 STEAM GENERATOR PEEDNATER HAIR TEST 4.0 Prerequisites (Cont.)

4. g'Cont. )

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Item 2 shall be equal to or greater than Item 1.

Vezif iud by (2 . Date 3. + 7 J IR2 4e3 Test Personnel have been briefed.

Verified by Date 2- a - )~

4.4 Verify kiFW isolation valve I-MV-09-8 closed and lA and 1B main feedwater pumps secured.

Veri.fied by Date -W-'7~

4.5 Ba k-up RR i ld be in t Mode w leve oint at 45 er para ete shoul arne as th crating Veri. Dat 4e6 Obtain CST temperature and record.

CSV. i.ueeuaututu 70 ea Vucij.ied 'uy Vv'Jld te 4.7 Ensure the atmospheric dumps HCV-08-2A and HCV-08-2B, are controlling S/G pressure and RCS temperature.

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Page '3 of 11 PREOPERATIONAL TEST PROCEDURE No. 0700080B, (ev 2 STEAN GENERATOR FEEDMATER HA&fER TEST

5.0 Instrumentation

The following parameters shall be monitored and/or recorded during the test. (S/G 1B level'nd Aux H4P flow to S/G lB shall be con-tinuously recorded during steps 12.2 thru 12.3.

NOTE: Aux FHP flow will probably be pegged high at 300 gpm.

Aux FtB'A & lB Amperage (Record while feeding up)

Pzr Pressure S/G lA & 1B Level Pzr Level S/G lA & 1B Pressure Loop 1A & lB Hot Leg Temp. Aux FHP Flow to S/G 1B Loop lA & 1B Cold Leg Temp. Aux H6'ressure Loose Parts Honitor (if in service)

Pressure transducer and high speed recor8ei (0-5000 psi

> 10000 hertz.) /R2 6.0 Related S stem Status:

6.1 Atmospheric steam dumps are operational. /R2 Verified by Date 7.0 S ecial Materials or E ui ment:

7.1 Temporary recorders (as necessary) 8.0 Tem orar Connections:

8.1 Temporary recorders may be connected to parameters given in.

Section 5.0 in addition to installed recorders/indicators.

8.2 Install the pressure transducer and recorder (from 5.0) on V-9283 (1B feed header drain just outside containment). Open V-9282 and V-9283.

Verified by Date 9.0 Precautions & Limits:

9.1 The test shall be aborted if S/G level is off scale. Recovery shall be made in accordance with EP 0700040, Loss of Feedwater or Steam Generator Level.

9.2 The test shall be aborted if RCS cooldown is excessive. Cool-down shall not exceed 75F/hr. The test shall be aborted of Pzr level reaches 27%.

9.3 The fourth RCP shall be secured below 510F (Tcold).

9e4 The preferred mode of adding feedwater during the feedup test is via motor driven Aux HK to minimize heat removal from the RCS.

Page 4 of PREOPERATIONAL TEST PROCEDURE No. 07000808, Rev 2 STEAM GENERATOR FEEDHATER HAtQKR TEST

9. 0 (cont) 9.g Only persons authorized by the Test Director and/or Nuclear Plant Supervisor are allowed in containment.

10.0 Acce tance Criteria:

10.1 The test is complete upon successful completion of steps 12,2, 12.3 and 12.~i with no audible or visual indications of damaging /R2 Feedwater hammer.

11.0 Records Re uired:

11.1 The completed copy of this procedure with applicable recorder traces shall be filed in accordance with gX 17-PR/PSL-1.

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I PREOPERATIO TEST PROCEDURE NO. 0700080B, . 2 STEQf GENERATOR I'EEDWATER 1M'AMER TEST 12.0 Detailed Instructions:

NOTE:This test is performed twice..First test is at 600gpm,second at 300 gpm.

12.1 Initial Setup & Steamdown 12.1.1 Commence raising Pressurizer level to at least 45%.

Charging pump high level override bypass may be used to allow running 2 charging pumps if desired. When level is at 45%, switch to Backup RRS. This step shall be completed by 12.3.4. Proceed with 12.1.2-12.3.3 concurrently.

Verified by I D.t. =a -77 12,1. 2 Record the time of trip and pre-trip power level;.

Verify I-HCV-08-1B is closed.

/R2 Time of trip 0 ~> ~ Pre-trip Power level V + ~5 by Date 'erified

12. 1. 3 Raise the pressure setpoint for I-11CV-08-2A to 920 /R2 psig. Ha'!.ntain water level in S/G lA using 1A Aux. FW pump. Ensure 1A and 1B main feedwater. pumps are off.Secure lB Aux EfP and close HV-09-10. Verify 1C Aux.FWP is secured.

600 gpm Test Verified by Date + X 7 300 gpm Test Date 12.1.4 Reduce the leve in S/G 1B by discontinuing feed to that generator and by maintaining its pressure at /R2 900 psia. Close Aux FW cross-connect'alves hiV-09-13 and HV-09-14.

6QQ gpm Test Verified by 8 '

Data N Q 11 300 gpm Test Verified by N'. Date 12.1.5 Note the time t'.hat S/G lB level drops below 34.2%.

(Bottom of Feedwater Thermal Sleeve).

600 gpm Time Q 5 D 8 300 gpm Time R2 600 gpm Test Verified by Date 7 300 gpm Test Verified by Date I- -1e 12,1.6 Note the time that S/G 1B level reaches 29%. Rl 600 gpm Time R/I obl7 300 pm Time 0 t a. 3 600 gpm Test Verified by //- 7 7 R2 300 gPm Test Verified by Date  % E " '? 7 12.1.7 Verify Blowdown is s cpred from S/G 1B.

600 gpm Test Verified by Date 300 gPm Test Verified by Date ~ % <<7'7 12.2 Hold Period (2 hrs. or 5% Level) 12.2.1 When S/G 1B level has dropped to between 27% a 29%, Rl Decrease the setpoint on I-HCU-08-2A to 900 psia and increase

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Page 6 of ll PREOPERATIONAL TEST PROCEDURE NO. 0700080B, Rev. 2 STEAM GENERATOR FEEDWATER 1UQMER TEST 12.0 (cont) 12.2 (cont) 12.2.1 (cont) the setpoint for I-HCV-08-2B to 925 psig. Verify that steam flow from S/G 1B atmospheric dump has 600 gpm Tost 300 gpm Test 12.2.2 decreased, Verified Veri -'ed 65% to trolled 70%.

by by Feed S/G lA as by S/G Verify the ecessary RCS

'~7 Date to maintain 9-temperature a level of is con-600 gpm Test by 1A.~'erified 0< Date ' 2 +->7 300 gpm Test: Verified by R2 12.2.3 Near the end of the hold period, verify an observer is stationed in the area of the Aux HB'nd that communications re established with the control room.

600 gpm Test Verified by /)

300 gpm Test Verified by Date g-- 2 -7 12.2,~i Near th~ end of t'e hold period. Perform the fnllowiug:

All Pzr backup hers ON Pl & P2 Pzr heaters ON Verify Pzr pressure controlling via Pzr spray. Pzr pressure setpoint may have to be adjusted to maintain 2250 psia.

600 gpm Test Verified by 4 /4 Date 6 W- 7 7 300 gpm Test Verified by Date R2 NOTE: If S/G 1B level approaches 5%, imnediately abort the test.

12.3 Feedup Test:

12.3.1 Verify that 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> have passed since the time re ded in step 12.1. 5 . Record the time > ~ > I . . /jlO Rl 2 ~- 7 '7 R2 600 gpm Test Verified by Date

.300 gpm TestVerified by Date >- L.-7 12.3.2 Verify there has been no feedwater addition to S/G 1B during the above time interval.

600 gpm Test Verified by Date W- ~ 7~

300 gpm Test Verified by 12.3.3, Secure Blowdown from S/G 1A.

6QQ gpm Test Verified by 300 gpm Test Verified by

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Page 7 of ll PREOPERATIONAL TEST PROCEDURE NO. 07000808, Rev. 2 STEAM GENERATOR FEEDMATER HAKiER TEST

12. 0 (Cont. )

12. 3 (Cont. )

12.3.4 Station an observer inside the personnel airlock with the inner door open a few inches to listen for PH hammer. Stop feeding lA S/G, st:art 1B Aux. Feed-water pump and open Aux. Hf cross-connect valves MV-09-13 and hiV-09-14. Using the two motor driven Aux HB"s, initiate feedwater flow to S/G 1B by open-ing MV-09-10 fully. Maintain as close to maximum flow (all valves in Aux. PW flowpath to S/G 1B open) as cool-down rates allow. If cooldown rates appear'excessive, make small reductions in Aux. HG'low. H NOTE: Init:iate feedwat:er flow slowly to avoid thermal shock to the S/G.

NOTE: Aux. H4 header flow indication only goes to 300 gpm. Record (in 12.3.5) 1A and lB Aux.

HG'uction and discharge'pressures. Also record lA and 1B motor amperage. QOI/n /m ~

000 gpm ne" t vo;:f'od I:y (P Date~ 3- - ~)

t-],g age v 300 gpm Test Verified oy Date Q- 2- ,c 12.3.5 Increase level in S/G 1B to greater than 43% while maintaining feedwater flow at the above established rate. Observers shall record t:heir observations on the summary sheet. Record data below. If it is necessary to reduce Aux. FH flow,.ensure data oelow is taken at the reduced flow.

600 gpm Test: 300 gpm Test 1A/1B Suctiou Prassura 1n lloas~~e

/ 7 '+ 1B Suction Plessure~L 9'ig 1A/IB Discharge pressure o lB Discharge Pressure(~90.- >sig Po os a, LIn (n< '1A/1B Calculated Floe 3 f~/ 3 IB Calculated Flos3cn5 amps Cj/m I m;e, PI,m 1A/1B Motor AmPs 'b I /~Y.

V 0' 1B Motor imps Indicated Flow

+ ~) 'I amps'B gpm pnnnnp TO0 (cp(nen ( 35 g~

Verified by Data ~ ID l0 7 Verified by Date-> )7

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Page 8 of PREOPERATXONAL TEST PROCEDURE NO. 0700080B, Rev. 2 STEAM GENERATOR FEEDWATER HA",REER TEST 12.4 Test Run at 300 gpm (nominal) 12.4.1 Reduce Aux Feedwater Plow to 1B S/G to maintain level at 43% or below. Regain RCS temperature to nor'mal hot standby valves. Peed 1A S/G as necessary to maintain 65-70% level.

Verified by Date ~ ~ ~7 12.4.2 Initiate blowdown from S/G 1A and 1B. Pzr backup heaters may be reduced to regain normal control of pzr pressure.

Verified by Date 12.4.3 Repeat steps 12.1.3 thru 12.3.5 except that in step 12.3.4 establish a nominal 300 gpm flow using full flow from 1B Aux pgp with MV-09-13 and MV-09-14 closed.

Verified by Date ~->-~ >

12.,5 The signature below verifies that one or more NRC observers have ""." tncsscd hc per foi.Knee oi ih~s ies i ~

C'RC

....l-g. 77 Observer 12.6 System Restoration

-.12.6. 1 Recommence feeding S/G 'lA as necessary to maintain level. Reduce feedwater flow to S/G 1B- to desired amount to minimize RCS cooldown. When S/G 1B level is above 50%, setpoints for both atmospheric dump con-trollers (I-HCV-08-2A & I-HCV-08-2B) may be reset to normal no-load conditions. I-HCV-08-1B may be opened.

Maintain normal hot shutdo s earn generator levels.

Verified by . ~ Date ~" + "77 zL rm~

Verified by Date 0--> --VV 12.6.3 Initiate Blowdown from S/G lA and S/G 1B.

Verified by Date R2

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PREOPERATXONAL TEST PROCEDURE NO. 07000809, Rev. 2 STEAM GENERATOR PEEDMATER I492iER TEST

12. 0 (Cont. )

12. 6 (Cont. ) v' 12.6e4 Close V-9282 and V-9283 and remove the transducer and

..recorder installed in 8.2.

Uerfffed by 12.6.5 Collect all data, recording charts and document observations of personnel.

'ezfffed by ,.~!~/U~

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Page 10of PREOPERATIONAL TEST PROCEDURE No. 0700080B, Rev STEAM GENERATOR FEEDNATER HAG'KR TEST 13.0 Deviations:

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Page 11 of ll Revision PREOPERATIONAL TEST PROCEDURE NO. 0700080B

.PREOPERATIONAL TEST SIQfARY fl Issue C o S<cf goop~ .

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