ML18051A995
| ML18051A995 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 12/14/1981 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18051A993 | List: |
| References | |
| T-147, NUDOCS 8407110377 | |
| Download: ML18051A995 (12) | |
Text
'. '
J ATTACHMENT I PALISADES NUCLEAR PLANT PROC NO T-1!17 PAGE 1
OF 6
SPECIAL TEST PROCEDURE c1:msum:::rs Power REVISIOtl b
DATE TIT LE i WATER HAHHER TEST TECHNICAL REVIEW PRIOR TO USE:
APPROVED BY PI.:~\\T GENERAL MANAGER Ref.:
Engineering Ma"1U2..l EM-14 REVIEWED BY PRC/QC DATE 11 /l? 8J I
DATE
- a~r1v&-1.v~... *~
I NOV 1 3 19.31 n;::-:::
- 1. 0 PURPOSE To ascertain whether or not a main feedwater line or auxiliary*feedwater line water hammer will result from the covering of the feed*""ater spargers follo"i~;
their uncover and drainage at various pressures and auxiliary feedwater flm*
rates.
Due to the symmetry of the feedwater lines and the nearness of the containment access to the B steam generator, the feedvater piping connected to the B steam generator will be tested for a ~ater hammer.
Test will be conduct£ at 200 psi and 900 psi on secondary side.
2.0 REFERENCES
2.1 Combustion Engineering letter to Consumers dated De*cember 7, 1979 entitled Guideline for Palisades Water Hammer 7es~.
2.2 NUREG 0291 -
An Evalu.:i.tion of PWR Steam Generatdr Water Hammer.
2.3 NSC Report entitles Evaluation of Auxiliarv_ Fee~uater_ Hammer at Palis~~e Plant 7/9/79.
2.4 NSC Report entitles Potential for Auxiliary FeeC-,.rater and Main FeedK2te:-
Paf°isades_ Plantz/24/77.
2.5 Test and test data from the Feedwater Line \\-.Tater Hammer Test conducted at Palisades after Core 4 reload.
2.6 Operating Procedure GOP 2.
2.7 Standard Operation Procedure SOP 12 Feedwater System 3.0 PREREQUISITES
/1 3.2 All personnel clca c<l from cont.:i.inmcnt.
Shift Supervisor' ~~,~-:~~~..,....---~--~
.-'f 1:.-, ~::~~-,l~L-( (:.. ~.' -
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PALISADES NUCLEAR PLANT SPECIAL T~ST PROCEDURE PROC NO T-1!+ 7 PAGE 2
OF 6
Consumers -l>O\\'ter TITLE; WATER HAMNER TEST REVISION o DATE 3.3 3.4 Communication has been North cable penetrat" Test Engineer:
Test Engineer:
between perso:mel in Control Roor:i.'.lnc the instrlll::e~~ation is located.
/.2 -1'/-tJ /
/.2. /it:' - 8 )
bubble formed in pressurizer and T hot ds to 200 psi in stc'1:1 generator).
3.5 Verification o'f reasonably lowest achievable concen'tration of non-
- Ji?O d
- .-condensible gases in secondary system ("f'eedwc::e:- line, S. G.) shal::..
be made by Test Engineer through consultation lo."'ith the Chemistry Department *v~ ~IN{.. p-o~'
~........_
'/~ '
/-' - ti' &J - e /
Verified:
-~
-Date: /.z.-/e' - 81
~tJ' 11~r_....q.,~-+-~--=-------------- Date: /.).. - /l(-J J 3.7 Notify QC prior t~~.t of t 1
~.ty /Jlz- _,
QC Inspector: <j$P:LG11-wfi, 1[
4.0 PRECAUTIONS AND LIMITATIONS
/ z_ - /.) -- tf'/
Date:
1tJ1~/B'""'"{ __ _
4.1 When adding feedwater during a test, PCS tempera:ture and pressure will drop which will result in a shrinkage of PCS.
4.2 If during a test indications of a water hammer arc present, remainder of test shall be aborted unless evaluation of test data proves other~ise.
4.3 If during a test indications of a water hammer are present, consideration shall be given to EOP 6 main steam line break/m~in fee<lwatcr line br~a~
inside containment.
4.4 At the discretion of the Test Engineer, steps cnn be terminated early and reinitialized.
4.5 Chart strip recordings must be labeled for ench test in matrix with dat~,
time, pressure in S.G. an<l refill rntc.
__:.~.*'
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- I PALISADES NUCLEAR PLANT PROC NO T-147 SPECIAL TEST PROCEDt;RE PAGE 3
OF 6 ccnsumers Power R E.V 1.S I 011 0
DATE Tl TLE; WATER 1!Af!}1ER TEST
- ~--
5.0 4.6 4.7 4.8 Consideration sl1all be given to actual vs. ind!c~ted steam generator level.
Steam Generator level referenced in this procedure shall be from the narrow range indicators.
)
Presstirizer heaters shall be kept. on.
Pressure :lili.11 be controlled throug_h cycling of -~-pray valves.
4*. 9 Pressurizer level control may have to be put in manual at large au:dli.ar feedwater flow rates.
4.10 Operable charging pumps will be put in auto.
4.11 Boron concentration shall be at cold shutdown concentration or greater.
PROCEDURE 5.1 5.2 Isolate A steam generator by closing M0-0501 and CV-0737A.
Stabilize PCS at 3820 F. or 532° F. (+/- 50 F.) depending on whether stea~
generator 200 psi or 900 psi test is being done through adjustment of M0-0510 and CV-0736A.
- 5. 3 Close CV-0736A and.,adjust H0-0510 to drop stea!il generator B le\\rel *co s-;;
while maintaining primary system temperature at value of Step 5.2.
NOTE:
Blowdown can be used in addition to the above to drop level.
5.4 When level reaches 5% in steam generator B, adjust. CV-0736A and H0-0510 to "rna"intain 'this level while k'eeping prima*ry sys~cm temperature-- s-tabTe.
NOTE:
Isolate blowdown if blowdown used in Step 5.3.
5.5 Hold level at 5% in B steam generator for greate~ than 5 minutes.
5.6
.. Clos~_ 'M0-0510 and establish desired.. flow rat.e.through_.adjustment of
- tv-0736A and ~SC of FI-0736.
NOTE: *.. For *test runs *with low flow rates, M0-0510 will have to be ope::-:.cd sli~1tly to maintain desired PCS temperature.
For test runs with hir,h flow rates, PCS temperature may drop.
CAUTION:
Water hammer event should be anticipated <luring refill process.
I
i*.
I PALISADES NUCLEAR PLANT SPECIAL TEST PROCEJ)U;u; TITLE; WATER HAMNER TEST PROC HO T-14 7 PAGE 4
QF 6 REVISION o
DATE
- 5. 7 When level reaches 72% in steam generator B, a.!just *cv-0736A and ~!0-0.51' to maint.:iin level at 72% o.nd to stabilize PCS ~e..-::perature.
5.8 Repeat Steps 5.2 through 5.7 for new matrix val'.l-es upon consent of Test Engineer and Shift Surervisor.
NOTE:
Prior to consent, Test Engineer will eYaluate data from previous test and compare with acceptance criteria:
5.9 Return to service
- 1.
Adjust steam generator level in both stea~ generator A and steam generator B to Shift Supervisor's advised level.
- 2.
Disposition charging pumps per Shift Supen>isor's advice.
- 3.
Restore blowdown per Shift Supervisor's advice.
6.0 ACCEPTANCE CRITERIA 6.1 200 psi test
- 1.
Pressure from test pressure sensors within+/- 100 psi of 200 psi.
- 2.
565 microst:i;ain (uin/in).
6.2 900 psi test
- 1.
Pressure from test pressure sensors within +/- 100 psi of 900 psi.
- 2.
455 microstrain (uin/in).
7.0 RECORDS AND ATTACHHF.NTS 7.1 Attachment - Test Matrix 7.2 Records
- 1.
Chart Strlp Recordings
- 2.
Calibration information on equipment
I
- Consumers Pn'.Yer 8.0 REVIEW 8.1 8.2 8.3 PALISADES NUCLEAR PLANT SPECIAL Tf,ST PROCEDUi;.E Tl TLE; WATER HAf1MER TEST PROC NO T-147 PAGE s
'O"F 6
REVISIDH D
'DATE Test Data Evaluation performed
_....f.:::~;L::~2::::::'.::!:~- Date : /.2 - / '/-8 /
/ - /.:;,--J='.J..
Technical Review performed by: --.l~c...!:....:=::::z:.:;~;.;i_:.-- Date : p- /'f? -8 I Administrative Review performed 1/1~
- I 0
I I:.
Ccn:;u1.1:?rs Po:'lcr TEST NO.
1 2
3 4
. 5
(
PALISADES NUCLEAR PLANT SPECIAL TEST PROCEDURE TITLE; WATER HAHHER TEST TEST MATRIX SHIFT SUPERVISOR CONSENT & DATE 1-:1.-/D -s I 1?-1t: -e, PROC NO T-147 PAGE 6 OF 6 R£VISIOll o DATE G?:1 S/G PSIA F\\.J FLO~*;
200 150 200 300 900 200
,..... /,/.
r.!-~o 900 300 P-1r-s -~~-C.L~£,
~*,;J-,..j-=-n 900 400 I(
---~-
... ~
ATTACHMENT II Steam Generator Refill Rates Using Auxiliary Feedwater Flow Steam *Generator r.efill rat.e sha14. _ l:>e ; ____ ::_.
- ,,;,... I* 1L... o o I..,., ~
7"..,.,,
- Two operable Steam Generators 150 gpm for Steam Generator level ~ 15%
100 gpm (or less) for Steam Generator level.::::>15% and ~ 25%
unrestricted for Steam Generator leve1:::...25%
One operable Steam Generator 300 gpm for Steam Generator level c15%
100 gpm (or.less) for Steam Generator Level::::.15% and ~25%
unrestricted for Steam Generator level ->25%
PR821020a OCT 2 :. 1922 7'..:..'J :t*.:e::.:;:VELT F\\O~D.
"3L.::i*J i:LL';'i*J, :LLi;JCJS.;otJ7
- ." '!""! r:;.. n 1 rr::"'~ii\\'r.".
Docket No. 50-255 Consumers Power Company ATTN:
Mr. B. D. Johnson Staff Licensing Engineer 212 West Michigan Avenue Jackson, Michigan 49201 Gentlemen:
October 20, 1982 This is in response to your letter of August 17, 1982, requesting removal of the administrative limit on auxiliary feedwater flow rate to a single steam generator which was a subject of our letter of October 1, 1980.
We have reviewed the modifications to the auxiliary feedwater system, witnessed the water hammer testing on the modified system and reviewed the test results.
We agree that the administrative limits discussed in our October 1, 1980 letter are no longer appropriate and that new maximum flow rates should be established and administratively con-trolled based on those flow rates attained during the performance of the water hammer tests.
Accordingly, the conditions of our October 1, 1980, Immediate Action Letter are considered satisfied.
Should you have any further questions concerning this matter, please contact this office.
cc:
D. J. Vande Walle, Nuclear Licensing Administrator R. W. Montross, General Manager DMB/Document Control Desk (RIDS)
Resident Inspector, RIII Ronald Callen, Michigan Public Service Commission
~~~r Regional Administrator DOCUMENT CONTROL CENTER PAUSAD~S c\\ z_ :?" 2 c / 133 7 c L/2-x c6x 16.. -- _.
GARB Rev~J:'~~~*'
consumers
'~
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Power after evaluaiiop ;..1,
-r Company ni;:J,11-G)A*JR/RErtc iii SA£.U:i RELAHD y.__l\\.._X_
No __
IDENTIFICATION AND DES P.!PT N PART 1 TITLL -~S~t~e~am==-~G~e~n~e~r~a~t~o~r~-E~--5..__.,_0~A~A~ux~~j~l_i~*a~r~y~F~e_e,__,_.d~wua~t~.e....._._r~N~a_......z~z~l-,e~~C~r~a~c-"-k~i~ff~g,,__, _________ ~---
PLANT SYSTEM (UF I)
EQUIPMENT -
CLASS(UFI)
EQUIPMENT NUMBER DESCRIPTION OF OCCURRENCE OR CONDITION. Tear-like cracking located on the aiixi liary feedwater nozz,J e radius.
Multiple cracking exists in two locations on the nozzle radius.
Facing the nozzle, the areas are from the lJ o 1cJock to the J o'clock position and from the 5 o'clock to the 7 o'clock IJOsition.
All cracking starts at the end of the nozzle bore__and extends axj alJy ont over the rading.
Maxim11m 1 ength of any single crack is 2"; width of cracks are an average of 1/1 11 ; depth is *estimated to be
.O maximum.
D 111MED1ATE AmoN: Combustion Engineering field engineers contacted Combustion Engineering design engineers to prepare a recommendation for corrective action.
REFERENCES:
D-PAL-84-123.
F PREPARED BY=
DWRoger s DEPT /PLANT:
PA NONCONFORlllNG ITEM:
YES []I NOD DETERMINED BY:
P-CARB 1 ornrnvOutage act i i tyLJ,,. "'L>Jj DATE: 4-30-84 APPROVED BY: --<-c__-t..Jf'7 c
ER FORWARDED TO:
DEPT /PLANT:
REVIEW AND NOTIFICATION REPORTING REQUIREMENTS:
24-HOUR NOTIFICATION NRC (PERSON CONTACTED) ---,..-----:;----.--+-------
OFFS ITE (PERSO~l CONTACTED)
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SECTION:
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DAT[. ----;{rF!-+,l.Ll~
OATE -'l~H~-
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BY WHOM EVALUATOR:.TATerpst EVALUATION DUE DATE:
5 l0-0)+
EVALUATION AND DISPOSITION YES D NO~
(IF YES, NOTIFY NLA FOR FINAL OETERHINATIONi DETERMINED BY COl'IPLETION APPROVED BY DATE COMPLETI OH REVIEW -
REVIEWED SY -----,=--=~~~.,-,-"""'""'"""'....-:-,;,,----
QUALITY ASSURANCE REPRESENT AT I VE OAlE -----------
(Gold)
COPY 5 -
ro1twARO TO Q.A UPON COMPLETION OF PART 2.
(Pink)
COPY~ -
FORllAAD TO NUCLEAR LICENSING Al>HINISTll.ATOR UPON COMPLETION OF*PART 3.
(C*nuy)-
COPY 3 -
FOltwARO TO Q.A UPON COMPLETION or PART 3.
\\Green! -
COPY 2 -
FOltwARO TO ORIGINATING DEPARTMENT UPON COMPLEJION Ot
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(White) -
COPY I -
FILED IN DOCUllENT CONTROL CENTER UPON COMPLETION OF PART 5.
FORWARD ALL CORRECTIVE ACTION DOCUMENTS THROUGH YOUR CORRECTIVE ACTION COORDINATOR~
FORM 3192 lM 2-83 DATE: SECTION:
TE DATE:
()vi PART 5
FORH QA-16 FORM QA-17 FORH QA-19 REV 4-6/78 CORRECTIVE ACTION SHEET 11 Oate HOUR __
TIME OF OCCURRENCE DETERMlllED BY DATE APPROVED BY (Gold)
COPY 4 -
(FOR ERs) FORWARD TO NUCLEAR LICENSING ADMINISTRATOR UPON COHPLETION (Pink)
COPY 3 -
FORWARD TO QA UPON COMPLETION OF PART 3.
(Canary)-
COPY 2 -
FORWARD :ro ORIGlllATING DEPARTMEtlT UPON COMPLETION OF PART 5.
(White) -
COPY 1 -
FILED IN DOCUHENT CONTROL CENTER UPON COMPLETION OF PART 5.
FORWARD ALL CORRECTIVE ACTION DOCUMENTS THROUGH YOUR CORRECTIVE ACTION COORDINATOR!
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EXAMINER 5"-r~ ~LC.N '£'. w (,_ l. I.. M /!t.tV LEVEL.:IC DATE
~c;-.<-B~ SHEET uS¢ - I CONSUMERS POWER COMPANY EXAMINER Al L.A LEVEL NLA HOT COMPANY. CoNSi.lfftfE~6)Zg~ &.
SYSTEM PROTECTION & LAB SERVICES DEPT PROJECT NO r-J38t.//5 2 2.3D8o REQUESTING DEPT - t._ut_!Al/CA L.
NONDESTRUCTIVE TESTING SERVICES JOB LOCATION ~L1SlllJE-S
- Jf4 LIQUID PENETRANT EXAMINATION REPORT TOTAL HOURS.WORKED~
NOT PROCEDURE NDT-?l*ol REY 2.,
METHOD/TECHNIQUE Co lo/:' (!o;..JT/CAs-r /soLvGVr-?t,,1-1rnl4l?/ ~
CLEANER MANUFACTUR~R A1A61.l.-4~lJ Jt TYPE
-s..t<e -...s BATCH No83Do2.l INTERPRETATION REQUIREMENTS:
PENETRAHT MANUFACTURER J1/l&G.<]A Fl lJ K TYPE sKl - f/f /.s BATCH NO 83:D o3B CODE iJ /A.* YEAR tJ /A SECT! ON. N/J.
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DI RECTIOH OF* FLOW LIGHT I NTEHS I TY
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PAGE _L_ OF I
REVIEWED BY:
REY 2 /B3
.,.