ML19210A661

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Agrees to Monthly Insps & Tests of Decay Heat Pumps Per 770907 Meeting.Forwards 770908 Calibr Data Sheets for Decay Heat Pump Shafts,Personnel Certification & 750801 Frequency Spectrum Analysis
ML19210A661
Person / Time
Site: Crane, Crystal River  Constellation icon.png
Issue date: 09/08/1977
From: Herbein J
METROPOLITAN EDISON CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
GQL-1234, NUDOCS 7910300691
Download: ML19210A661 (19)
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Text

DISTRI3CTION AFTER ISSUAN_CE OF OPERATI'iG LICENSE v.s. NUCLEAR REGULATCRY

'SSIC N OCCXET NUM BE R iRC scau 195

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n-ses NRC D STRIBUTION PCR PART 50 DCCKET MATERIAL l

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R W Reid Metropolitan Edison Company I

9-8 U Reading, Pa J G Herbein cATE REcEwEo l

9-14-i7 EE ER C NCTO RIZE D PRCP INPUT FORM NUM8ER CP CCPtES RECEIVE 3 l

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NPIGIN AL 2t.INCLAS3t PI E D 2 Cerv i S f 6 A.) E D j

sscRIPT:CN ENcLCsuRE Advisitg that they agree to Sep tember 3 & 4 Testing results.......

accomplish following items related to heat decay pump shafts..........

1 Vibration testing

'2 ltrasonic Inspection s

& transmitting the following:

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?LANT NAME:

Threa Mile Island #1

.,9-14-77 ehf SAFETY FOR ACTION /INFORMATION i BRXTCH CHIEF

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/ METROPOLITAN EDISON COMPANY scermun er cruew avauc cnu,r:c;en-j POST OFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 September 3, 1977 GQL 123h N

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/ /A Director of Nuclear Reactor Regulation J

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R. W. Reid, Chief Operating Reactors Branch N. k Q

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Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (T'C-1)

Docket No. 50-289 Operating License No. DPR-50 Decay Heat Pump Shafts As a result of cur reeting with you on September 7, 1977, Met-Ed agrees to acecmplish the following items which are related to the D:I-1 Deca-y Heat Pumps.

1.

Monthly inspections and tests vill be performed on each Decay Heat Pump.

These vill include both U'.srasonic and Vibration testing. Liquid Penetrant pump shaft inspections vill be deferred, but may be conducted in the event the specific acceptance criteria of the UT and/or Vibration tests are not met.

A.

Vibration Testine Vibration testing shall be performed monthly at a flow rate of cCO GPM.

Two sets of vibration data shall be t den for each monthly test.

"he first set of data shall be taken prior to de-coupling the shaft, and the second set of data shall be taken after the shaft has been re-coupled.

The second set of data shall be the baseline data for the next mcnthly test.

If the vibration level at any of the normally measured frequencies (900, 1800, 3600, and 13,000 RFM) increases by more than 1493 129 c 2 s c' 0 7c7

R. '4. Eeid, Chief September 8, 1977 GQL 123h 50% above that month's baseline, or if any new frequency peaks are detected, such changes shall be evaluated.

This evaluation will be based on the following criteria:

(1) If vibration peaks exceed Eydraulic Institute limits for 1800 RPM (3 5 mils peak to peak) or the corresponding IRD Chart limits for other frequencies then pu=p coupling realignment, adjustment of operating conditions, and any other possible contributing factors will be investigated and evaluated with appropriate corrective actions takan.

If these corrective actions do not reduce the vibrati-below the specified limits within 2h hours, then the pump will be disassembled and the punp shaft shall be removed for liquid penetrant and radial ultrasonic inspection.

(2) If vibration levels increase by 50%, but are still less than the specified Hydraulic Institute limits, then the vibration levels will be analyzed to determine if they indicate an existing problem. This analysis will consider amplitude changes at all other frequencies, and whether re-coupling of the shaft or changes of system conditions caused the vibration changes. If this analysis results in a determination that a problem exists, then the pump will be disassembled and the pu=p shaft shall be removed for liquid penetrant and radial ultrasonic inspection.

The analysis of the 50% increase data shall be provided to the NRC together with the detailed test data.

(3) If one pump shaft is inspected as a result of vibration tests, and it is confirmed to be defective, then the shaft shall ce replaced with a new shaft, and the second pump shall be d3 = assembled and inspected as soon as the first pump is returned to service.

(h) Technical Specification limits en pump operability shall be observed.

The URC shall t=nediately be notified if any vibration testing condition requiring the above evaluations is observed. The results of these evaluations and the detailed test data shall be forvarded to the NRC as part of a complete report.

B.

Ultrasonic Instecticn Ultrasonic Inspections shall be performed monthly. If the presence of any new ultrasonic reflector is detected in one of the pump shafts, the following acticns shall be taken:

(1) The pump shall be disassembled within 2h hours, and the pump shaft removed for further inspecticns to deter =ine the cause of the reflector.

These inspections shall include liquid penetrant and radial ultrasonic inspecticns.

1493 130

R. W. Reid September 8, 1977 GQL 123h (2) If a defect condition is determined to be present, the shaft shall be replaced with a new shaft, and the second pump vill be disassembled and inspected as soon as the first pu=p is returned to service.

(3) Technical Specification limits en pump operability shall be observed.

The NRC shall i=cediately be notified if any ultrasonic inspection condition rr. quiring the abcVe actions, is observed. The inspection data and test cesults shall be forwarded to the NRC with a detailed report.

C.

Sectember 3 & h Test Results Attached hereto are the results of the vibrational testing and UT inspections performed on the shafts of decay heat pump 1A and 13 en September 3 and 4, respectively.

The seccnd set of vibration data establishes the baseline for the next monthly test, and the UT inspection data establishes the baseline for all subsequent UT inspecticns.

Menthly inspections shall follow the September 3 and 4 inspection dates 25% of the inspection interval per TMI-1 Technical Specification Section h.

2.

A metallurgical and Fracture analysis of the Crystal River Unit #3 failed shaft is being performed by Babcock and Wilecx. The preliminary report shall be submitted to the NRC by September lh, and the final report by September 28, 1977.

3 Met-Ed and B L W are investigating and reviewing the metallurgical the 1A and 1B decay heat pump shafts based on the QC records and material certi-fications.

A preliminary report shall be submitted to the NRC by September 21, and the final report by October 5, 1977 h.

A review of the decay heat punp design and its operation in the 80 GFM recirculation mede is being performed by Met-Ed and 3 & W.

The results of this review shall be submitted to the NRC by October 5,1977.

5 The pump =anufacturer has established that the decay heat pumps vill provide continuous operaticn in the 80 gpm recirculation mode for two (2) hours while maintaining their capability to respond to full flow demand.

Our NSSS vendor has reviewed this capability and ccmpared it to his analysis of the capability required to respond to the loss of coolant accidents as analyzed in the TMI Unf : I FSAR and has concluded that the decay heat pumps are adequate for tt.s application.

In addition, our 1493 131

R. W. Reid, Chief h-September 8, 1977 GG,L 123h Met-Ed Generation E.ngineering Department has reviewed the results of both of these foregoing reviews and has concluded that the decay heat pumps do indeed provide assurance that 31I Unit 1 meets the requirements of the

, Final Safety Analysis Repcrt, thus assuring the health and safety of the public.

Sincerely,

/. G. Herbein J

,! Vice President

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JGH:WEP:ies Attachments 3 1493 132

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nJ t 1.S_6_7_H.90c.d.l,inso ecto ~rlSta ff Sof 1- ~ s t . a . ~. Esp.ec. ioit. lLS J.. ^ N .y,' '. in, n n g nn riici8'1Mi c Pe'r't" .'- 7. 825 7W I^'- Tr.d; i 9 2C'o 6 0' Cpna m Inscecti_on ? Cols_,__OH ~ '-t 4-5-72 to 2-20-73 II RT;MT;PT;UT -f Conam Insoectich. R'ahway NJ ' -p t y6-74 ' II RT;MT;PT;UT - A e-rspace Ma.t.edals - CalLOH~ ' 6 -7 4_t_o 8-75' 'III' (QC Mei. also')- Con = Inspection. Col.a.RH 10-7-76 to pr esent Il RT:MT;PT:UT - l \\ 'Ce rt i f i e d To SNT-TC-1 A, Ty.pe_. . D a t e. '..s...L e..v e l.' ".:y _s -- - :: . =.- n w-('onam Inspection,In c._P T, M T, _ 5-11-7 2 II - donam Inspection, Iric. UT, RT, 5-4-72 II .-J Conam Inspection i R a h wa y NJ_.D_iv. RT;MT;PT;UT 2-73_ ,-l__. 2 - II A erosnac_e_.LLa_teridls. Cols. OH. MT:PT_f_UT 6-74 , III - '~ "6 e s Con n m.In.s oection Cols. OJi RT;M.T_,;.PT_;UT 10-7-76 II - 3 Conam Insoection .C ol.s. OH. _ R.T., M...T P..T.. > UT 2-77 II 9 9 - C N T__ - 0 01_ P J - ~~ ~ ' 6]G 0 dhk U GITu MI'uTC 5 a Sipn e-d by Dale T. kiste[I eM '55N'T[-TC-35 ' % y,[ [ y,yZh; eseom-149p1ym

~ g \\ a g g) ~ s CONAM INSPECTION, Cols.OII Div." I und: 5-3-76 ITlSONNEL CERTIFICATION NAF.E Clyde Wm. Thompson ALL llISTORICAL INFORMATION SUPPLIED BY ME TO COMPILE Ti!IS CERTIFICATION IS TRUE AlfD CORRECT TO THE BEST OF MY KNOWLEDGE. SIGNEDCb([$ Mm, pTE2-77 O. ff / ~ Q CETITIFIQfTInNS EXAM SCORES TNG RECEllTIFICATIONS h O JlN!OD LEV ET, DATE ' EXAMINER CEN SPEC PRAC COMP HRS DATE/ EXAMINER DATE/ EXAMINER DATE/EXAMINEN llT II 1-77 A././T LD,. 12 n qn 45 90 240 2-77 47A' MT Tr 1-77 4 42 72E-. 77 R2. 5 100 88 80 2-77 /W ~ PT n 1-77 A-6 7 %W.--r-46.6 72 95 86 80 2-77 azf n7 IT 1-77 /or /-Z L E -- on 79 9 inn no 190 2-7744 i I 1 I EXPERIENCE FROM TO (M0/YR) COMPANY NIYP METH01'S & HICHEST LEVEL ATTAINED 1967 10-71 USAF NDT - Inspector (Staff Sgt. ) 1977 73 Conam Insoectior Cols.OII RT:MT:PT:UT - Level II 73 64 Conam Inspectinr Rahway NJ -RT. MT PT:UT - Level II 7A 75 A ornqm en Mat t 'niq OTI - Or Mar. RT.M PT. HT -Level HI _.36,,,,,, nennnnt rnnn rn ingnectinn 'rn19. OH -HT _. lViT. PT. UT '-Level H ~~j ) LTE EXAMIN/.TIONS , EDUCATION AND TRAINING (IIICIIEST PUDLIC, ADVANCED AlfD NDT ) DATE EXAMINED BY SCHOOL LOCATION DATE LENGTH SUDJECT 1-12-7 7 F. Ma rschC D see attached Worthington Ohio 6-56 3 yrs General H illia rd, Ohio 6-60 4 yrs Industrial Arts m -Si Chanute AFT TL 7-70 3 mos. NDT 'O, Air Univ.Extention Course 7-71 6 mos. NDT O: CD J ,O, i t

Q. NUCLEAR ENERG. SERVICES, INC. ,.' ] CONAM INSPECTION DIVISION .{ 138S WITHER $PCCN ST./ BOX 189 .J 3-RAMWAY. PiEW JEASEY 47C65 U.S A. l1 (231) 341.CC50 FREQUENCY SPECTRUM ANALYS I S M'ANUFACTURER: Autorration Industries S/N 26496 MARKED FREQUENCY: 5.0 MHz biZE: .25" Panarr.etrics DATA SUPPLIED BY: c =,=l - ~r g I + i 7 + l I l.3! l I. l !Il-dld.d.I.!.J j, . fl l i - l l l i t i .) l +.i. i i 1 .I ~_ i l..,1, I ~ i i x i l c 3 i l L .-.:..a._ .as. .p. ..,,.I.. ._[.____ (. e / )7 i y y.r.--c am v -- Wir -w_..

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llf A RESULTS .( a o ooJ m Central Scale Frequency 5.0 MHz (1.0 MHz/ Division) Transducer-Centra l Frequency 5.0 MHz 1493 139 ~ [g] AcceptabIe [ ] Unacceptable I nterp reta t i on By C+ F.T. CAPR 8/1/75 o...:..:s

~ca arries ....,,,o. ..T }. tilts ~: Sal 10SimU LahDralDUET - T 832 " me-Ave-m wzncore p. o. sox is n 'i.nt. cic=. - omi n, ci.cusix avrwr. w e - o,a........ n ~ ii.1-i.r:) 1! *. and Onld:nh [nginsan (2158 C34 5433 Walghers[i-iniilers and Assaycra ~helARKET STREET 578." NEWARK. N. J., o7tos puong (201) 539-4772-3-4 TELcX 133387 I RR.PGRT GT ASSAY r NOo 416945 August 12, 1976 DATE Cur essay of the :cmple of Ultragel II Ultrasonic Couplant Frern Echo Laboratories -?.= Merked: .. Bat;h f8276 Spec. ASTM-0-129 and D-808 Purchase Order No. 1452 '"d submitted'to 5' Sh # Halogens-------------------7.5 ppa Sulphur--------------------4.1 ppa To Echo Laboratories ~ Titusville, Penna. INTERNATIONA!. TESTING LABORATORIES, INC. The D2hiity of the faterna:Icnal Testics Labor cories. Inc. wia respect to de jf f services charged for her.n sha!! la no event exceed the sciount of the invoice. / pe Our reporu pertain to ths sample tested only. Inferreatios contained hereim // ~

  1. 'sTL n as arv. aow e-?s is not to be reproduced, except with our pc.rrnheion.

.,q.- .... 7-7 Ia -,e-. O I l . =* [ 0.2 e. 1493 140

~ ~ ~ N LE/1 E N ER&Y "ycs C 14 km i N SfECTloM i AIC. -. - - -.. ((.~T k.Eil_E_CTO_5_CDEC '*]ld$f"N$*-llf;( L s p t n s.s 8 - s 0- IM5ZAllAERT CALL 6L8 Tied DATE__2Lo_aLR I97_7 LMSTRum.E;ST Libl.E&&lTY t/ E K i Fi C A z zos ! DATE Lkbl61tST_lBT7 D.t[E N&XT &UE NDRM6ER_ L9.77 e6e 2/ Rd6H571977 / ) d GyW Co

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m ao m emom m M .o 1493 141 -ew-6e -e.d eee.e -me em m e, m*e=-e e-ow ee ww h

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NUCLEAR ENE / SERVICES, INC. ( CONAM INSPECTION DIVISION IMS WITHER 5PCCN ST./SQX 134 a /g, RAMwAY. ht# JER$f447:45 U.SA La w mn us.ma FREQUENCY SPECTRUM ANALYSIS gANUFACTURER: Automation Industries S/N 46111 MARKED FREQUENCY: 2.25 'MHz SIZE: .5" diameter DATA SUPPLIED BY: Automation Industries .r s' ~ ~' 4 - 1 .r Z $$ a s. d4 N t g..;Mr ~ .4 r -8 .kJ L Fg ~- =2 55

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s. i t / i s,. i. 1 l l 371 6 ..cs; 4 g,,, s ki I f ,L wemmcc'MWwomg+ffs % _,; n D

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  • ID ~TY a

b. @o e RESULTS Central Scale Frequency 2.5 MHz (g.s MHz/ Division) Transducer Central Frequency 2.25 MHz [XX} Acceptab I e 1493 142 [_] Unacceptable Interpretation By ,k/ 8/26/77 A % A ** * *) S

  • s * *, * *- ".~"

F. T. Carr

DATA TAKEN: ___2/5 /77 TAKEN SY:' _W. M.SMT7 INST. MODEL : 330 CAL.DUE DATD 3-/4-76 EL OW. ). -~ 6 7.5 G r u EV p AV MOTOR EH AH v l CPM 900 1800 3600 18,000 A\\/ $ .OS 0Y .06 02 WFi BV G .04 .of 05 .ol w2 O AH < .o5 05 .a .o1e BH 08 .o? ./ , 0.2 )_ CPM 900 I800 3600 IB,000 AV ./5 ./3 06 03 i BV f 09 17 .o7 03 w 3 AH a 6 52 .c9 06 d se BH ./ ,? ,03 .ol 1493 143

Attachc.ent #2 Met-Ed GQL 123h 9/8/77 Babcock & Wilcox ro.- c.,-.m.,c., P.O. Box 1260. t ynchrg. va. 24505 TeW: (804) 354 5111 September 8, 1977 i Mr. R. M. Klingaman D* 'D 9 4T3 4

    • J

]"'g u Manager, Ceneration Engineering Metropolitan Edison Company P.O. Box 542 Reading, Pennsylvania 19603

Dear Hr. Klingersn:

Per Met Ed requert, va are responding to the NRC question raised yesterday, Se pterrbe r 7, 19 7 ), in an NRC/Het Ed meeting in which B&W participated. This ques tion concerned limits on extended operation of the Het Ed, THI-l Decay Beat pumps in the 80 gpm recirculation mode and the impact of those limits on requirements of the TMI-1 ECCS analysis. B&W requested that Worthington, the Decay Heat pump vendor, state in writing the 1 mits th at apply to those pumps during the 80 gpm recirculation mode chich would avoid pump degradation. B&W has received a worthington IvX on september 8,1977, copy attached, that supports 30 minute runs, four times per year or a two-hour run at one time. The upper limit in this mode is a total of 80 hours for the life of the pump. Worthington has verbally stated that, with further investigation, these limits may be further relaxed without pump degradation. B&W has investigated this situation relative to the two-hour Decay Heat pump limit and the TML-1 ECCS analysis and recor=>end a procedure change to align the ECCS systems for piggyback operation (DH pump discharge align to MU pucp suction) at one hour following the small LOCA if the Decay tient pump flow rate is less than $50 gpm (including 80 gpm recirculation flow rate). If only one nakeup pump is operating, the decay heat pump associated with the makeup pump which is not operating should be shut down. This 'recornendation is based upon the following: During a small break LOCA two depressurization phenonema occur independent of break size or orientation. The system immediately depressurizes (several seconds) to saturated pressure corresponding to the initial hot leg enthalpy. This initiates a reactor trip shutting down the core fission reaction. De-pressuri zation continues vj n heat trans fer through the steam generatorn until such time as the primary system is in approximate equilib rium. The process takes only a few minutes and the resulting pressure corresponds to the setpoint for the secondary system safety valves (1050 psig). Further depressurization vill continue at a rate depending on break size. In the piggyback ECCS lineup, each high pressure pump will flow 475 gpa against a back pressure cf 1050 psig. 1493 144 The Dabco k & WA o. Comer / tst.Wa*wo IB67

Obcoc' &W3Cox A MR. R. M. KLINGAMAN SEPTEMB ER_8,, 19,7 7 This flow, plus the 80 gpu decay heat pump recirculation flow, will assure adequate flow through the decay pumps well before the time limit specified by Worthington. In addition, we believe that the one hour time limit is conservative vi th respect to the NRC allowance of a half an hour for operator action.

Also, placing the plant in the piggyback mode is consistent with operating the plant in a "norml" mode of operation for a small LOCA.

The modified procedure for implementing piggyback operation prescribed above amoures the mitigation of all postulated small break LOCA's within the con-straints specified for operation of the DH pumps in the recirculation code and within the NRC criteria for ECCS performance analysis. The ECCS analyses supporting the operating license award for Three Mile Island Nuclear Station Unit I will be unaf fected by the recommended procedu~re ch ange. Very truly yours, rs D. Phinney, Manager Operating Plant Services JDP/hh D"] ^- h

        • Ch"*"'

o 1 cc: (w/ attachment) GP Hiller JP O'Hanlon JC Herbein LC Rogers JT Janis EL Logan j gg jjc /> I 't J LL Lawyer

Attach =ent #3 ~ ~ - - ~ Otf R // All Met-Ed GQL 123h 9/8/77 11,,..i.?....,,g ~~~ l g kl i.2 : ,s 'e .i1 j . Nf"'Q,.!A \\5. + EAbw!LCcx LUR0 kOh1HGTN HSCN URGEN 1 S EF' T 'd *d A fv h ! S ON NJ 032 to8e A11N DON WOOD / S1 AN FUNKHAUSE.R RE CONVEhS ATI ONS ME7 ED 1MI WE FEEL 1HAl 8 NN -19 4 OrEbA110N Al 30 MINU1E I Nl Ehv ALS 4 LINES PER YEAb OP a HOUFS e-1 QNE llME IS S A113F AC1 CRY. YCU CAN OPERAlE IN IN I S S i lV Al l CW Ur 10 60 HOUNS hdICH IS EWulvALEN1 10 40 Y E F. A LIFE. hk H Av '- t AI) EACELLEN1 OPEb A110N WI1H THIS PbCDUC1 LINE AN D 1NIS I NF L UENC E.i 1HIS DECISION JUHN N BROCE WO A 1 H I N G1 DN PUMP CChP HARRISON NJ T LX 13ts 97 a D mmD o g -Q~ oz CC: J AN DE hS ON _cd o E O M 0hh t S CW BABWI LC OA LUPG W4GoDYMMMG%5MWP:%YE+%.=r+.'~.?'3.=:n +9:= a ~....,, ... ~. e. .~ r . srMS,.m.w^s w - '.<~ M p.k.%R.?.y-7+4Y" :?c&vm.c'~xcy1:'mv*?:%.'M'.**'.r.W

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'~'#* ? 1493 146 L :;i3.;+,: :,...~ r.,..m w~.z. c - ~. ...~ ~.. - ...}}

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