ML20010E084

Board Notification 81-22 Forwarding Rh Vollmer 810327 Memo Re Failure of Power Operated Relief & Block Valves to Operate During EPRI PWR & BWR Valve Qualification Program Testing.Safety Significance Being Evaluated

ML20010E084
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/26/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
TASK-AS, TASK-BN-81-22 BN--81-22, NUDOCS 8109030052
Download: ML20010E084 (1)

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Docket Files LB #4 r/f RBirkel RHartfield, MPA DEisenhut/RPurple MDuncan OELD NRC PDR MJollensten, OELD OIE (3)

EAdensam RVollmer TERA /NSIC/ TIC ASchwencer TMurley ACRS (16)

JYoungblood Dross HDenton/EGCase FMiraglia SHanauer PPAS(H. Thompson)

MEMORANDUf1 FOR:

The Atomic Safety and Licensing Appeal Panel EHughes for McGuire Nuclear Station, Units 1 & 2 bcc: WDircks FROM:

Robert L. Tedesco, Assistant Director VStello for Licensing Division of I.icensing, NRR

SUBJECT:

BOARD NOTIFICATION - SAFETY RELIEF AND BLOCK VALVE TEST RESULTS (BN 81-22)

The Division of Engineering, with support from the Office of Research is monitoring the EPRI PWR and BWR valve qualification programs. During testing some power operated relief valves and block valves have failed to operate satisfactorily. The enclosed memorandum from R. H. Vollmer to D. Eisenhut discusses these failures.

The specific safety significance of these test results are being evaluated.

We will continue to keep you infomed on this matter.

Original Signed by Robert L Tedesco Robert L. Tedesco, Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation

Enclosure:

Memorandum, R. H. Vollmer to D. Eisenhut, dtd 3/27/81

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MAR 2 71581 MEMORANDUM FOR: Darrell Eisenhut, Director Division of Licensing, NRR FROM:

Ricnard H. Voilmer, Director Divi > ion of Engineering, NRR

SUBJECT:

BOARD NOTIFICATION - SAFETY RELIEF AND BLOCK VALVE TEST RESULTS The Division of Engineering, NRR with support f rc.m the Office of Research and its contractor are monitoring the progress of i.he Electric Power Re-search Institute (EPHI) PWR valve qualification program and the BWR owners group program conducted by General Electric. The monitoring system established by the staff, with NRR maintaining overall cognizance of the program from a licensing perspective and supported with detailed technical monitoring by RES, is adequate to determine whether test results rcreesent relevant and material new information which should te provided to appropriate Boards. All available test data has been and will continue to be evaluated on a case by case basis in accordance with NRR Office letter No. 19.

The test data in cur possession is enclosed for your information as follows: - EPRI PWR Safety and Relief Valve Test Program Status Report, March 1981. - EPRI PWR Safety and Relief Valve Test Program NRC Meeting viewgraphs, March 20, 1981. - Summary of Westinghouse testing activities related to valve closing problems.

As you know, the issue of Board notification of the PORV block valve failures resulting from EPRI testing has been raised by the UCS.

It is my view that the test of relevancy and materiality is not passed unless such valves are in service or are to be put into service at a facility based on the fact that valves of specific design and material construction failed, rather than a class of valves, and that the test conditions were not necessarily representative of conditions under which the PORV block valve would be required to close. Therefore, it is my conclusion that the staff acted properly in not suggesting Board notification and my recommendation that' Board notification is not needed in this case. However, I recognize that a case can be made for the notification as discussed in the proposed response to the Pollard letter, and that it is DOL's responsibility to make the find-If DOL finds the Board notification is appropriate, I will fully ing.

support it, hJA M.

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t D. Eisenhut Please note that the current version of out' response to the, Pollard letter states that the Boaras will be notified.

A Richard H. Vollmer, Director Division of Engineering cc:

H. Denton E. Case L. Shao, RES T. Novak R. Tedesco J. Knight V. Noonan D, Muller R. Bosnak F. Cherny M, Stolzenberg, RES

ENCLOSURt.i EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM STATUS REPORT PARCH, 1981 JOHN CAREY l

l JJC/AD 3/19/81

EPRI PWR SAFETY AND RELIEr !ALVE ;iS:

. wei STATUS.

MARCH. 1981

{E" ACTIVITIES MARSHALL:

e ALL TESTS COMPLETE AS OF JANUARY 29, 1981 10 POWER OPERATED RELIEF VALVES 7 BLOCK VA'.VES e

PORV RESULTS GENERALLY FAVORABLE EXCEPT:

COPES VULCAN (OLD TRIM)

FISHER CONTROLS e

BLOCK VALVE TEST RESULTS GENERALLY FAVORABLE.

MODIFICATION TO OPERATORS REQUIRED IN SOME CASES FOR CLOSURE AGAINST FULL STEAM FLOW (ANCHOR / DARLING, WESTINGHOUSE MODELS 3GM88 AND 3GM99) e TEST REPORT IN PREPARATION; FIRST DRAFT DUE MAY, 1981 WYLE:

e RELIEF VALVE TEST FACILITY CONSTRUCTION (PHASE 1) COMPLETED DECEMBER 1980.

(CAPABILITY FOR SUBC00 LED LIQUID DISCHARGE TESTS) e STEAM AND SUBC00 LED WATER TESTS ON DRESSER AND CROSBY PORVs (PHASE 2) COMPLETED JANUARY 1981 e

FACILITY MODIFICATIONS FOR PHASE 3 IN PROGRESS.

TESTING ANTICIPATED TO RESUME ON APRIL 1sT.

ALL REQUIRED RELIEF VALVE TESTS WILL BE PERFORMED AT WYLE e

PHASE 1, PHASE 2 REPORT IN PREPARATION

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'WR SAFELY AND.iELIEF VALVE TEST PROGRAM pTATUS:

MARCH, 1981 (CONT'D.)

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CE:

e TEST FACILITY CONSTRllCTinN APPR0XIMATELY

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I 3 WEEKS 3FHIND SCHEDVIF e

TAta HYM0 COMPLElCD.v1U8!

e ANTICIPATE SfAR1 0F SHAKEDOWN IESTS EARI.Y APRIL., 1981 o

UTILITY REVIEW MFElING SCHE 0ilLED FOR APRIL 15, 1981 FRENCH IN-PLANI Test e

TO BE PERFORMED AT CHIN 0N B1 IN SEPTEMBER 1981 e TEST PREPARATION ON SCHEDULE e

eof HAS REQUIRED PRELIMINARY PIPING TESTS AT INDIRA SAFETY / RELIEF VALVE TEST FACILITY t

i JJC/Ao 3/19/81 L

e q' EPRI PWR SAFETY Af1D RELIEF VALVE TEST PROGRA?'

ANALYSIS ACTIVITIES CONTIllGENCY ANALYSIS:

e NSSS VENDOR ANALYSES 70 BE COMPLETED BY APRIL, 1981, PRIOR TO CE SAFETY VALVE TESTS PIPING ANALYSIS:

o CONTINUED CODE EVALUATION LIMITED TO RELAP 5-MOD 1 AND SOLA-NET IECHNICAL SUPPO?,T ACTIVITIES VAi3E SELEC110N/

JUSilFICATION e

TEST VALVES SELECTED; 10 POWER OPERATED RELIEF VALVES; 9 SAFITY VALVES e

FIRST DRAFT OF VALVE SELECTION /

JUSTIFICATION CORRELATION REPORT EXPECTED MAY, 1981 l

l JJC/AD 3/19/81

.e UTILITY APPLICATIONS?

PROGRAM OUTPOT DEFINED; UTILITY REQUIREl'ENTS TO SATISFY NUREG 0737, ITEM II.D 1 IDENTIFIED AND REVIEWED WITH TECHNICAL ADVISORY. GROUP.

FOUR PRINCIPAL PROGRAM OUTPUTS:

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TEST REFORTS FROM THE MARSHALL, WYI.5, AtlD CE VA!.VE TEST PR0rRAllR.

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A RF_PUdi 00LUMENiliiG file :iElfC!10n 0F fHl REllEF AND SAFETY VALVES 10 BE TESTED AND JUSTIFYINC THE AFPLICABILITY OF THE TEST RESULTS TO VALVES UTILIZED IN OPERATING PLANTS AND PLANTS UNDER CONSTRUCTION f

A RIPLF.i P30VIDING JUSTIFICAT(0h 0F fHE SET OF GENERICALLY LIMITING FLUID CrGITIONS UTil(7F.0 TO ESTASI.lSH THE VALVE TERT C0.01710'5

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A RcPORf ve'.uMENI1:1G A CODi t 0R COMUTING HYOROUYNAf'ilC LOADS FOR RELIEF AND SAFETY VALVE DISCHARGE PIPING UNDER STEAM AND WATERFLOW CONDITIONS.

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SIGNIFICANT ITEMS 1.

ADDITIONAL ltELIEF AND SAFETY VALVES TO BE TESTED ~

ORIGINALLY (7/1/80) 4 SAFETY VALVES 6 PORVs NOW 9 SAFETY VALVES 10 POPVs.~

a C0Sf AND SCHEDULE IMPACT e

FAllLifY UTILIZAfl0N WYLE:

PORVs (ALL REQUIRED fESTS)

CE:

SVs BLOCK VALVE IESf PROGRAM I

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PWR UflLITIES ',di.L COMPll in ihRM i 8 Lark t.,y.!.vF TESI PROGRAM PLAN BY JULY 1, 1981 e

EPRI TO DEVELOP BLOCK VALVE TEST PROGRAM PLAN AND SUBMIT TO UTILITY ADVISORY GROUPS BY JUNE 1, 1981 i,

SCHEDULE e

COMPLETION OF ALL TESfS BY JULY 1,1981 DEPENDENT ON SUCCESSFUL PERFORMANCE OF CE TEST FACILITY e

DATES FOR PLANT SPECIFIC REPORfS ARE UNREALISTIC: NO NRC RESPONSE TO YOUNGDAHL'S LETTER OF 12/15/80, 3

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JJC/AD 3/19/81

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EPRI PWR SAFETY AND RELIEF VALVE TEST - u o.

1 RELIEF AND SAFETY VALVE TEST SCHEDL cf CONTRACTOR DUKE POWER - MARSHALL STEAM STATION

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MILESTONE EVENTS COMPLETED

!i PHASE I TEST SYSTEM FABRICATION AND CHECK 0UT 8/80 PHASE Il PERFORMANCE TESTING PORV

- CONTROL COPPONENTS 8/13/80

- COPES-VULCAN l' 9/10/80 3

- COPES-VULCAN 2*

9/11/80

- FISHER C0!!TROLS 9/24/80

- MASONEILAN 10/20/80

- TARGET ROCK 12/3/80

- CROSBY 12/12/80

- DRESSER 12/17/30

- MUESCO CONTROLS 1/20/80

- AIRESEARCH (GARRETT) 1/23/80 COPES-VULCAN 1 17-4PH PLUG COPES-VULCAN 2 316SST/ STELLITE PLUG b

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i MILESTONE;IVENTS COMPLETED PHASE II-PERFORMANCE TESTING (contrNUED) 1 BLOCK VALVES WESTitlGH0VSE (3GM88) 8/13/80 ANCHOR DARLING 9/25/80 ROCKWELL 10/27/80 BORG WARNER 11/4/80 VELAN l' 1/13/81 VELAN 2*

1/14/81 WESTINGHOUSE 1/28/81

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PHASE II REPORTING i

QUICK LOOK DATA SUEMITTAL 7/1/81 FINAL TEST REPORT 10/1/81 VELAN 1 MODEL C2345 VELAN 2 MODEL B10-3054B013M (MO)

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COUTRACTOR WYLE LABS - NE'CO, CA MILEST0f!E EVEUTS C0l'.PLETED PHASE I TEST SY3 TEM CCUSTRUCTION 1/16/81 AND CHECK 0UT PHASE 11 PERFORMANCE 1ESTl;;G

- CROSEY FORV 1/16/81

-- DRESSER PORV 1/29/81 SCHEDULED FHASE'll INTERIM REPORT 5/1/81 e

j PHASE III TEST SYSTEM MODIFICATI0f; 4/6/81 Ai10 CHECK 0UT l

JC/JT 3/16/31 a

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• i PHASE 111 i

PERFORMANCE TESTING SCHEDULE WEEK OF PORV

- TARGET ROCK 4/6/81

- DRESSER

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4/13/81

- CROSBY 4/20/81

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- C0ilTROL COMP 0 net!TS 5/4/81 1

- MASONEILAN 5/11/81 i

- COPES VULCAN l' 5/18/81~

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- COPES VULCAN 2*

5/25/81 j

- MUESCO CONTROLS 6/1/81 i

- FISHER CONTROLS 6/8/81

- AIRESEARCH (GARRETT) 6/22/81 PHASE II/Ill REPORTING l

t id;

- QUICK LOOK DA L SUBMITTAL 7/1/81 i

- FINAL TEST REPORT 10/1/81 i

COPES VULCAN 1 17-3 PH PLUG lt COPES VULCAN 2 316SST/ STELLITE PLUG p

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EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM.

RELIEF AND SAFETY VALVE TEST SCHEDULE CONTRACTOR COMBUSTION ENGINEERING - WINDSOR, CT.

MILESTONE EVENTS SCHEDULE i

ll PHASE I TEST FACILITY C0flSTRUCTI0tl AND 1

CHECK 0UT 4/15/81 PHASE II PERFORMANCE TESTING WEEK OF k

SAFETY VALVES i

TARGET ROCK 4/17/81 j

DRESSER 31739A 4/28/81 CROSBY 3K6 LS*

5/7/81

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DRESSER 31709NA 5/18/81 CROSBY 6N8 LS*

5/27/81 CROSBY 6M6 LS*

6/6/81 CRCSBY 3K6 6/17/81 CROSBY 6M6 6/22/81 CROSBY 6N8 6/26/81 PHASE 11 REPORTING QUICK LOOK DATA SUBMITTAL 7/1/81 FINAL DATA REPORT

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AND RELIEF VALVE TEST PROGRAM i

NUREG 0737, II.D.1 PERFORMANCE TESTING 0F BWR AND PWR REL AND SAFETY VALVE (NUREG 0578, SECTION 2.1.2)

I l3 REQUIREf1ENTS:

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A.

PERFORIMNCE TESTING OF RELIEF AND SAFETY VALVES g

B.

QUALIFICATION OF PWR BLOCK VALVES

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C.

ATWS TESTING

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1 i

NUREG 0737 REQUIREMENTS:

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PERFORMANCE TESTING OF RELIEF AND SAFETY VALVES 4 -

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EVIDENCE SUPPORTED BY TEST OF SAFETY AND RELIEF VAL e

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FUNCTIONABILITY F0P. EXPECTED OPERATIt!G AND ACCIDENT f

CONDITIONS, TESTS TO BE COMPLFTF BY JULY 1, 1981, IESIING SHOULD DEMONSTRATE FHA) THE VALVES WILL O e

AND RECLOSE UNDER THE EXPECTFD FLOW CONDITION.C e

EACH LICENSEE f1051 SUBMIT A CORRELATION OR OTHE e

THAT THE VALVES TESTED IN TliE EPRI PROGRAM DEMON THE FUNCTIONABILITY OF AS-INSTALLED PRIMARY RELIEF SAFETY VALVES CORRELATION SHOULD ALSO SHOW THAT fliE TEST CONDIfl e

USED Ill EPRI PROGRAM ARE EQUIVALENT TO EXPECTED O TING AND ACCIDENT CONDITIONS AS PRESCRIBED IN FINAL SAFETY ANALYSIS REPORT (FSAR)

EFFECTS OF DISCHARGE PIPING ON val.VE OPERABILITY MU e

ALSO BE ACCOUNTED FOR JJC/AD 3/19/81

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QUALIFICATION OF PWR BLOCK VALVES l

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a PROVIDE EVIDENCE SUPPORTED BY TEST THAT BLOCK CAN BE OPERATED, CLOSED, AND OPENED FOR ALL FLUID i

CONDITIONS EXPECTED UNDER OPERATIf1G AND ACCIDE y

b, CONDITIONS i

l BLOCK VALVE TEST PROGRAM PLAN TO BE SUBMITTED B e

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JANUARY 1, 1981 BLOCK VALVE TESTS TO BE COMPLETED BY JULY 1 IE2 e

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C.

ATWS TESTING VALVE TEST FACILITY SHOULD BE DESIGNED TO ACCOM e

ATWS CONDITIONS OF APPR0XIMATELY 3200 TO 3500 PSI 700 F TESTING NEED NOT BE COMPLETED BY JULY 1, 1981 l

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EPRI PWR SAFETY AND RELIEF VALVE TEST PR I

{t, A.

FERFORMANCE TESTING OF RELIEF AND SAFETY j

TEN (10) POWER OPERATED RELIEF VALVES A e

j SAFETY VALVES SELECTED FOR TEST

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EPRI WILL DEVELOP JUSTIFICATION THAT THES e

ARE FULLY REPRESENTATIVE OF RELIEF AND f

I IN OPERATING PLANTS AND PLANTS UNDER CO (FOR PARTICIPATING PWR UTILITIES ONLY)

TEST CONDITIONS BASED ON e

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FSAR TRANSIENTS COLD OVERPRESSURIZATION TRANSIENTS HIGH PRESSURE INJECTION EFFECTS OF DISCHARGE PIPING ON VALVE OPER 3

ACCOUNTED FOR DISCHARGE PIPING LOAD DATA WILL BE OBTAIN e

CE FACILITY.

A CODE FO.R PREDICTING DISCHARGE PIPIN HYDRAULIC LOADS WILL BE DEVELOPED

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EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM B.

QUALIFICATION OF PWR BLOCK VALVES o

EPRI DEVELOPED PRELIMINARY BLOCK VALVE TEST PLAN IN e

DECEMBER, 1979 (SUBCOMMITTEE DECIDED NOT TO SUBMIT TO NRC, PENDING RESULTS OF RELIEF VALVE TESTS)

PWR UTILITIES NOW WILL COMMIT TO SUBMIT A BLOCK VALVE e

TEST PROGRAM PLAN BY JULY 1, 1981 EPRI WILL DEVELOP A BLOCK VALVE TEST PLAN BY JUNE 1, e

1981 ADDITIONAL FUNDS REQUIRED:

APPR0XIMATELY $4,000,000, i

TEST PRCGRAM DURATION, 5 - 6 MONTHS

'i BLOCK VALVE TEST PROGRAM COUI.D BE INITIATED IN CE TEST e

FACILITY BY SEPTEMBER 1, 1981 i

JJC/AD 3/19/81

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EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM C.

ATWS TESTING d

SOME COMPONENTS OF CE FACILITY DESIGNED FOR ATWS e

VALVE TEST CONDITIONS:

FOUNDATION, TWO HIGl!

PRESSl1RE TANKS MODlHCATION OF CE FACILt fY WOULD BE REQUIRED FOR e

ATWS TESTS-P!PiNti AND SUPPORTS CONTROL VALVES N2 OVERPRESSURE SYSTEM (DRIVER)

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O EPRI PWR SAFETY AND RE:..'.: VALVF TFST LROGRAF DATES FOR PLANT SNC'F K StiBMITTALS ITEM NUREG 0737 UTILITY POSITION' 1.

FINAL PWR (EPRI) SAFETY AND RELIEF VALVE TEST PROGRAM PLAN JULY 1, 1981 JULY 1, 1981 2.

BLOCK VALVE TEST PROGRAM PLAN JANUARY 1, 1981 JULY 1, 1981 3,

PWR (EPRI) GENERIC S/RV TEST PROGRAM RESULTS JULY 1, 1981 OCTOBER 1, 1981 4

PLANT SPECIFIC SUBMITTALS CONFIRMING ADEQUACY OF SAFETY AND RELIEF VALVES BASED ON LICENSEE / APPLICANT PRELIMINARY REVIEW OF GENERIC TEST PROGRAM RESULTS JULY 1, 1981 JANUARY 1, 1982 5.

oLANT SPECIFIC REPORTS FOR SAFETY AND RELIEF VALVE QUALIFICATION OCTOBER 1, 1981 APRIL 1, 1982 6.

PLANT SPECIFIC SUBMITTALS FOR PIPING AND SUPPORT EVALUATIONS JANUARY 1, 1982 JULY 1, 1982 7.

Pl. ANT SPECIFIC SUBMITTALS FOR BLOCK VALVE QUALIFICATION JULY 1, 1982 JULY 1, 1982

, R. YOUNGDAllL 10 D. G.

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_ Anchor / Darling The Anchor / Darling block valve was tested per the EPRI procedures September 25, 1980 in line with the Fisher Controls PORY.

times against full flow (194,468 It was cycled 21 and seat leakage ranged from.019 to.066 gpm.lbm/hr) with no significant ano noted; a-The valve had a Rotork 16 flax 1 operator set at 5 (175 ft lbs) for the test.

from its original "as received" design when preliminary teeThis valve had been m inability to close completely against full flow and produce

'ng showed an j

wear patterns at the disc / seat interface.

ore significant J

leakage to zero, Anchor / Darling is pursuing additional.In an attemp+

e uce the seat to retest sometime in mid-May.

This particular valv

. *a ions and hope I

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Company for field testing and evaluation.

s loan d to Duke Power Anchor / Darling block valve, it is air operated aAlthoug. 4 ofre I has an u

the performance data acquired at Marshall for th h

e.

e, unlikely that v%v is representative of any operating nuclear unit.

Barc-Warner h

The Borg Warner (tiVD) block valve wa w t. '

line with the Masoneilan PORV 'Jovember 4, 1980.

It was cycle ate against a full flow of 209,307 with no anomalies noted.

The val. a a 16f1AX1 set at 5 to open and

• 5 ated with a Rotork operator Model A-o 1 There was no seat leakage during the entire test sequence.

IV. u e

valve had been modified b, oted, however, that the Borg Warner

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earlier testing (prior to

.urer and Duke Power as a result of i.3 valve type is believec t ting their program at Marshall).

This Duke Power Cocoany p

Guire and the valve remains the property of L

Rockwell The Rockwell iav i

~ ~ (li...ited by the 2" Rockwell valve).as tested in line with the full flow o. '.

zation of the 'o::

Initial pressuri-design was modi uncovered a body to bonnet seal problem.

The four bolt o a six bolt design and testing per the EPRI procedure

.c was conducted Octae r 27, 1980.

21 cycles and seat leakage was 0.0 gpm each of the five times meas valve was actuated by a Limitorque operator Model SMB-00-10 set at

. The 1.8 (95 ft lbs).

for field testing and evaluation.The valve was loaned to Duke Power Company by the Velan, Model C2345 S/!4-243402 currently in operating 'J plants.This Velan valve is believed to be represent It was equipped with a Limitorque SMB-00-15 operator set at 1.7 (153 ft lbs) and tested against a full flow of lbm/hr January 13, 1951.

246,441 The valve opened / closed 21 times and had a zero gpm seat leakage throughout.

Af ter completion of the test the valve wcs cycled

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EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM 1

I l C h

thre ? -ore t i a

Wal se 2ingd.t. sa tis "."drj)g)t d G cue ir f fu

' low I r.<

cycin s-i.g for each

~M ly ;yci d *

[

l.0 (82 ft lbs).

when the valve was disassembled and inspected.There were galling i va o 2s i

Velan, Model 810-30548013M (MO) j, arm as the main feature difference.This version of the Velan valve SMS-00-10 set at 1.5 (110 ft lbs) operator and cycled agairIt was equi orque i', '

244,790 lbm/hr on January 14, 1981.

a flow of

)

grn seat leakage throughout the test sequence.It too cycled 21 times a d had a zero performed and the torque setting lowered to 1.0 (82 f' Again a 1 cycles were

't

i. 1 s,.

Westincheuse Model 3GMS8 f

This valve was placed in the test loop the end times over the next month and a half.

t u nd was cycled several Init' against full ficw with a Rotork operatKs

.alve did not close t

'n ft-lb. A series of measurements showed that approximatelyV' valve against a full flow of 232,243 lbm, r.

we e required to close the s i out August 13, 1980 with a Lin.itorcu test sequence was carried i

The valve cycled 21 times and had a operator actuating the valve.

a s e

Oc eat leck rate throughout.

Westinchouse Model 3GM99 h

This valve was sized simila

• o *n receipt of this valve at

• Model 3GM88, and data gathered before Ajrs 'Oouse had made a change in the valve yok close against full flow.

assembly and operator M'c i nte this condition.

information, the val' To ebtain some baseline v ed twice on January 12, 1981.

The original v

operator was a 56 ti-000-10 and during the two cycles the valve closed to:

(1) 575 e

,v'v 14% AP) res_ c 'v position 22% aP) and (2) 62% closed, valve position c

e valve was then sent to Westinghouse for the i

previously cla, e

..odi fi ca tion.

The valve was modified (yoke and Limitorque SB-00-15 operato turned to the Marshall site and testef on January 28, 1981.

It cycled ag nst a flow of 243,635 21 times and hao seat leakage rates that ranged from 0.0 to 0.06 gpm.

Cimit switch rather than torque switch settings were used in controlling actuations for this series of tests.

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HISTORY OF CLOSING PROBLEM s'

3GM88 FIRST FAILED TO CLOSE UtIDER HIGH-r' RESSURE DIFFERENTIAL STEAM FLOW CONDITIONS DURING AN EPRI TEST 2

PROGRAM AT THE MARSHALL STATION (JULY, 1980).

SEVERAL 3GM88's FAILED TO CLOSE AT TWO PLANT SITES DURING TESTING 0F SAFETY INJECTION SYSTEM AT HIGH-PRESSURE DIFFERENTIALS.

STRAIN GAGE 5 SHOWED CLOSING LOADS TO BE APPR0XIMATELY 13,500 POUNDS.

.E-;

i FULL FLOW TESTS PERF0 PED AT PACIFIC PUMPS HAVE CONFlRFED CLOSING LOAD REQUIREMENT OF t 13,500 POUNDS AT 2700 PSI DIFFERENTIAL.

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l REASON FOR FAILURE T0'CLOSE OPERATOR SIZE BASED ON 9300-P0UtiD CLOSillG LOAD (USED INDUSTRY STANDARD EQUATION)

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OPERATOR SIZE MARGINS MINIMIZED TO REDUCE LOADS AND I

MINIMIZE POSSIBILITY OF VALVE DAFAGE IF AN OPERATOR STALLS OPERATOR SIZING AND TORQUE SWITCH SETTING DID NOT ACKNOWLEDGE CLOSING LOAD AND OPERATOR DYNAMIC CHAPACTERISTICS THIS RESULTED IN OPERATOR BEING Sc7 '2 TO TRIP AT 9300 POUNDS + S?lALL MARGIN AGAINST NO FLOW WHILE THE REQUIRED THRUST LOADS COULD BE AS HIGH AS 13,500 POUNDS i

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VALVE CHARACTERISTICS WITH FLOW l

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a#3 CLOSING LOAD RUNNING LOAD y_

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SimARY OF TESTING ACTIVITIES--VALVE CLOSING PROBLEM t

i ii 1.

Water Flow Testing (at Pacific Pump Coc:p'any) i l1 Condition up to and incl' ding 600 gpm and 2800 psi 4 valves - 3GM88 I. ;

+ field rodifications complete

)

3 valves - 3GM99

?-

3 valves - 4GtSS Field modifications for the 3GM99 and 4GM88 to be tested in early-May.

2..

EPRI Steam Flow Tests (PORY Block, Steam Flow) l valve - 3GMS8 1 valve - 3GM99 complete 3.

Site Testing (Full Flow Water Testing, Safety Injection System)

Almarel: Appmximately 10 valves - 3GM88 CGE:

Approximately 10 valves - 3GM38 compic STP:

3 valves - 3GM88 4.

EdF (Steam and Water Flow Testing) 2 valves - MM99 - in process S.

Mechanical Fixture Testing (At WEMD)

Using hydraulic cylinder to duplicate flow loads so force transfer can be studied 'n depth.

l 1 valve - 3GM88 1 yalye - 3GM99 compiete 1 valve - 4GM88

.r-6.

Seat Friction Factor Tests (At Westinghouse R&D)

To determine stellite on stellite friction facters under water and steam conditions. Test samples are nearing completion at EMD.

O cc:

F. R. Bakos J. A. Drake. Mgr.

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d TESTED 11-18-80 ID SEAL-PRODUCTI0tl DISC 6

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1 l

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?!

SOLUTION TO VALVE CLOSURE PROBLEM

>I:

I i

MODEL 3GM88

}\\ ;

REGEAR VALVES TO HAVE 25,000 POUND STALL CAPABILITY i

USE LIMIT SWITCH RATHER THAN TOROUE SWITCH i

CONTROL e.

3 MODEL 3GM99 AND 4-INCH VeuvES MAY REQUIRE CHANGE 0VT OF OPERATOR i

USE LIMIT SWITCH CONTROL s

j

~

=

FINAL DECISION TO BE FADE IN APRIL

'l

?

l e

5

'E t

52 i

e=

i-Z l[b

.l3

3 55 l^

1 1

BELLEVILLE

)

SPRING S TACK i

I STEM

{

NOPMAL TOROUE I

I SWITCH closing WITH J

l

~

1. 4ING CWPEN5A TOR-A k

I

[

)

k U

Loacs buildup at seat face as motor

]

3

~

11 i

torque increases.

l-1 1 I J u

Belleville spring stack permits tne NUT stem nut to ceflect under stem DEFLECTION loads.

When torque reatnes a preset level VALVE the torque switch trips the motor.

STEM

• Amaining spring stack deflection provides differential enemal expansion protection and absoros motor inertia.

VALVE

/

s DISC l

l N

f VALVE SEAT t

RING f

\\

V

$s i

1 FIGURE 3

\\

1,

.4 l

I BELLEVILLE STACK l

I i

70 ROUE SWITCH CLOSING ASAINST H!GH FLOW CONDI TIONS l

l j

g I

1 a.

6

[f high flow or AP produce nign stem loads, torque switen may trip p

(

J with valve partially open, (lt 3 j

d lj e When AP reduces, believilles will pusn disc toward closed position.

NUT DEFLECTION e

if distance open

'/

nut defection, disc will not reach closed positiJn, i

1 l

li l l

OISTANCE OPEN sW i

i

~

(({dKdG{

I I

t FIGURE 4

i

~

l - l..

)

)

)

f BELLEviLLE STACK s-i i

1 i

r--

1 L

t.lHIT CLOSl% CONTROL i8 I

Edi;6LIsnit6 inE CLOSED t

LIMIT 5 WITCH TRIP POSITIDN g

)

U Operator Hand neel is used deflect

}

the stem out.280*, producing i

II I

11,000 lbs of stem thrust.

l -":

d u

i NUT Closed limit switch is set at enis DE{ECDON e

po int.

~.280 e

On subsequent electrical closings, the limit switch will trip the ector with the 11,000 10.

Preload j

stem tnrust ptesent, s

3 I'l NN

\\

-+-

NM T s

('

I FIGURE 5

l i

)

BELLEVILLE STACK i

LIMIT CONTROL - CLOSING I

AGAINdi FULL FLOW CONDITIONS

{

l I

e If nigh flow or AP conditions product high stem loads, the 6

operator will produce natever loaa g

,i

)

I is required to reacn tne lirait I

(

switch set position.

6_ g ij d

I d e

Distance _ Sternicad - 11,000 it's Open 40.000 lbs/in NUT OEFLECTION Disc closes off the port allowing e

only nor:nal spec leak rates.

I e Since distance open ( the not deflection, the believilles will drive the disc to the seated position if tne AP droos.

/

\\

OlSTANCE OPEN g

}

3 f

M E

n h

I HIGH

}

l j

FLCW '-

l T

~ ~~

m n

(

)

l FIGURE 6

sy..:

t*

ENCLOSURE 2

.<r t

4 j

EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM i

e NRC MEETING MARCH 20, 1981 1

BETHESDA, MARYLAND

t.

, e l'

e

'h e

e JOHN CAREY,.

4 l

I, 4

i i

O 2

1

,.m

..,,,..,,,._,,.,...-......,,.,m_-.

.m.,__,.,

-.,yr.,..

.,.y.y..-wrr-

Lu. J.-

iv i

A EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM PROGRAM OBJECTIVE:

OBTAIN FULL SCALE DATA ON THE OPERATIONAL PERFORMANCE OF FRESSURIZED WATER REACTOR PRIMARY SYSTEM RELIEF AND SAFETY VALVES UNDER EXPECTED'0PERATING CONDITIONS FOR DESIGN-BASIS TRANSIENTS AND ACCIDENTS BY JULY 1, 1981.

I UTILIZATION OF PROGRAF 1 DATA:

LICENSEES AND APPLICANTS WILL UTILIZE DATA TO SUPPCRT PLANT-SPECIFIC SUBillTTALS IN RESPONSE TO SAFETY AND I

RELIEF VALVE TEST REQUIREMENTS IDENT(FIED IN NUREG 0737, ITEM II.D.1

{

I 3

3 i

l

-r.-

r n nien l

Lu ~;,.-

. =.

2-EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM

~

PROGRAM INITIATED IN SEPTEMBER, 1979 BY EPRI NUCLEAR e

POWER DIVISION AT THE REQUEST OF THE TMI AD HOC NUCLFJtR OVERSIGHT COMITTEE PROGRAM PLAN DEVELOPED AND SUBMITTED BY UTILITIES TO e

NRC ON DECEMBER 17, 1979 (REVISION 1 SUBMITTED ON JULY 8, 1980)

SEPARATE PROGRAMilATIC ACTIVITY WITHIN EPRI SAFETY AND e

ANALYSIS DEPARTMENT e

'JTILITY ADVISORY GROUPS:

EPRI-RAC-NSAC SUBCOMITTEE SAFETY AND AllALYSIS DEPARTMENT TASK FORCE I

SAFETY AflD REllEF VALVE SUBCOMITTEE TECHNICAL ADVISORY GROUP l

QUALITY ASSURAtlCE ADVISORY COMMITTEE l

l 3

i JJC/AD 3/19/81

i

)

SAFETY AND RELIEF VALVE SUBCOMMITTEE

~

I i.

DAVID H0FFMAN, CHAIRMAN (CONSUMERS POWER CD.)

i ROGER NEWTON (WISCONSIN ELECTRIC POWER)

JOSEPH TURNAGE (YANKEE ATOMIC)

I JAMES SCOTT (PUBLIC SERVICE ELECTRIC a GAS OF NEW JERSEY)

TECHNICAL ADVISORY GROUP

. I JAMES SCOTT, CHAIRn N (PUBLIC SERVICE ELECTRIC

& GAS OF NEW JERSEY)

KENNETH BERRY (DUKE POWER CO.)

TERRELL CLIFT (TENNESSEE VALLEY AUTHORITY)

I WILLIAM JONES (YANKEE ATOMIC)

I i

I TECHNICAL, LICENSING, AND EXECUTIVE CONTACTS FOR i

i EACH PARTICIPATING PWR UTILITY i

8 II o

I

. l. lf* / u-7." a '9 '

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,. - - - -., = - - - - - -

..?.

I EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM I

I UTILIZES THREE TEST FACILITIES TO COMPLETE ALL REQUIRED TESTS BY PRESCRIBED DATE OF JULY 1, 1981 l

1.

MARSHALL STEAM STATION (DUKE POWER) RELIEF VALVE TEST FACILITY RELIEF VALVE STEAM TESTS f

2.

EPRl/WYLE RELIEF VALVE TEST FACILITY i

RELIEF VALVE SUBC00 LED WATER TESTS I

3.

EPRI/CE SAFETY AND RELIEF VALVE TEST FACILITY i

i e SAFETY VALVE TESTS; STEAM, SUBC00 LED WATER AND STEAM TO WATER TRANSITION l

e SAFETY / RELIEF VALVE DISCHARGE PIPING LOAD DATA

'I i

l

/

e I!

t I

.lJC/AD 3/19/81 u

8 4. ;..;.

~

RELIEF AND SAFETY VALVE TESTS PERFORMANCE SCREENING CRITERIA DE'! ELOPED e

L (NRC NOTIFIED OF CRITERIA FOR RELIEF VALVES)

PROCEDURE ESTABLISHED FOR DISSEMINATING TEST DATA e

(REVIEWED BY NRC)

VALVE MANUFACTURER'S REPRESENTATIVE AT TEST SITE DURING j

e TEST AND SUBSEQUENT DISASSEMBLY OF VALVE 3

QUICK LOOK DATA SHEETS DISTRIBUTED TO AFFECTED UTILITIES, e

i NSSS VENDOR, VALVE MANUFACTURER

{

f f

I e

i 1F /..

7 lin #0*

.....s._

PROGRAM DOCUMENTS 1.

PROGRAM PLAN FOR THE PERFORP.ANCE TESTING OF PWR SAFETY sND RELIEF VALVES, REVISION 1, JULY 1, 1980 2.

PWR SAFETY AND RELIEF VALVE TEST PROGRAM, DESCRIPTION AND STATUS, FEBRUARY 1981 (ISSUED APPR0XIMATELY EVERY SIX WEEKS) i 3.

WEEKLY TEST ACTIVITY REPORTS i

I

/

p 4

JJC/AD 3/19/81

a :. 2..:.

I'. -

t*.-

I EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM -

1I FOUR PP.INCIPAL PROGRAM OUTPUTS:

i 1.

TEST REPORTS FROM THE MARSHALL, WYLE AND CE VALVE TEST PROGRAMS i

2.

A REPORT DOCUMENTING THE SELECTION OF THE RELIEF AND SAFETY VALVES TO BE TESTED AND JUSTIFYING THE APPLICA-I BILITY OF THE TEST RESULTS TO VALVES UTILIZED IN OPERATING PLANTS AND PLANTS UNDER CONSTRUCTION 3.

A REPORT PROVIDiNG JUSTIFICATION OF THE SET OF GENERICAL LIMITING FLUID CONDITIONS UTILIZED TO ESTABLISH THE VALVE TEST CONDITIONS 14. AREPORTDOCUMENTINGACODEFORCOMPUTINGHYDRODY5AMIC LOADS FOR RELIEF AND SAFETY VALVE DISCHARGE PIPING UNDER STEAM AND WATER DISCHARGE CONDITIONS e

s l

j.

.l.lC/An 3/14/R1

n.:.

r.

l.

I l.

EPRI PWR SAFETY AND REllEF VALVE TEST PROGRAM i

I PROGRAM COST:

SEPTEMBER, 1979 T)ECEMBER, 1981

~ APPROXIMATELY $18,000,000.

FROGRAM FUNDING:

e 41 PARTICIPATING PWR UTILITIES

.I e

EPRl/NSAC t

l i

l' t'

i s

l!

l 3

o L;

JJC/AD 3/19/81

s v......

..L...-

v.

PWR BLOCK VALVE TESTS L

BLOCK VALVE TESTS NOT INCLUDED IN NUREG 0578, e

j RECOMMENDATIONS (JULY, 1979)

BLOCK VALVE TEST PROGRAM CURRENTLY NOT A FORMAL PART OF e

EPRI PWR SAFETY AND RELIEF VALVE TEST PROGRAM BLOCK VALVE TEST REQUIREMENTS IDENTIFIED IN NUREG 0660, e

MAY,1980 AND FURTHER CLARIFIED IN NUREG 0737; NOV.,1980:

j.,

e VERIFICATION OF BLOCK VALVE FUNCTIONABILITY I

e TESTS TO BE COMPLETE BY JULY 1, 1982 h!

~

LICENSEE TO PROVIDE EVIDENCE SUPPORTED BY TEST e

THAT BLOCK VALVE CAN BE OPERATED, CLOSED AND OPENED FOR ALL FLUID CONDITIONS EXPECTED UNDER OPERATING AND ACCIDENT CONDITIONS i

i PWR UTILITIES HAVE REQUESTED EPRI TO PREPARE A BLOCK VALVE e

TEST PROGF.'el RESPONSIVE TO THE REQUIREMENTS OF NUREG 0737 r

EPRI IS DEVELOPING A BLOCK VALVE TEST PROGRAM PLAN FOR e

i SUBMITTAL TO PWR UTILITIES BY JUNE 1,1981

}

uI Li s

,wi..

ep.....s

........:..=.....

j-J.

PWR BLOCK VALVE TESTS 4

EPRI BLOCK VALVE TESTS AT MARSHALL STEAM STATION e

MARSHALL STEAM STATION TEST LOOP ORIGINALLY (1978-79)

SET-UP BY DUKE POWER FOR RELIEF VALVE TESTS e

MARSHALL TEST LOOP INCLUDES PROVISION FOR RELIEF AND BLOCK VALVES t

e EPRI CONTRACTED WITH DUKE POWER (EARLY 1980) FOR UTILIZATION OF THE TEST FACILITY TO PERFORM STEAM TESTS ON POWER OPERATED RELIEF VALVES AS PART OF THE EPRI PWR VALVE TEST PROGRAM IN RESPONSE TO NUREG 0578

~

e IN LIGHT OF THE NEW REQUIREMENT FOR BLOCK VALVE TESTS (NUREG 0660), EPRI RECOMMENDED LIMITED BLOCK VALVE TESTS AT MARSHALL WHICH WOULD NOT INTERFERE WITH THE PRIMARY OBJECTIVE OF RELIEF VALVE TESTS AS REQUIRED BY NUREG 0578 e

UTILITY ADVISORY GROUP APPROVED RECOMMENDATION AND NRC l

WAS NOTIFIED OF PLANS TO TEST A LIMITED NUMBER OF BLOCK VALVES.AT MARSHALL i

)

1 ll

• O

,. d.

d o.

l MARSHALL BLOCK VALVE TESTS -

e SEVEN BLOCK VALVES TESTED ANCHOR / DARLING BORG WARNER ROCKWELL VELAN, MODEL C2345 S/N-243402 VEL ^'~

MODEL B10-3054B013M (MO)

WESTINGHOUSE, MODEL 3GM88 i.

WESTINGHOUSE, MODEL 3GM99 VALVE MANUFACTURER TECH 3ICAL REPRESENTATIVE ON SITE e

DURING EPRI BLOCK VALVE TEST (EXCEPT FOR FIRST TEST OF WESTINGHOUSE MODEL 3GM99 ON JANUARY 12, 1981)

CHAIRMAN, SAFETY AND RELIEF VALVE SUBCOMMITTEE NOTIFIED s

0F BLOCK VALVE TEST RESULTS l'

INITIAL TESTS OF THREE BLOCK VALVES INDICATED AN INABILITY l

.e TO FULLY CLOSE AGAINST FULL FLOW (SATURATED STEAM, 42400 PSI)

ANCHOR / DARLING

~

WESTINGHOUSE MODEL 3GM88 WESTINGHOUSE MODEL 3GM99 e

EPRI STAFF NOTIFIED:

i 1

SUBCOMMITTEE CHAIRMAN WESTINGHOUSE r

r i

t f ir / n 7 /10 /Q1

y 4...

ei i MARSHALL BLOCK VALVE TESTS SUBCOMMITTEE CHAIRMAN NOTIFIED NRC e

NRC CONTACTED EPRI STAFF AND WERE PROVIDtiD WITH ADDITIONA e

INFORMATION MARSHALL BLOCK VALVE TEST REPORTS IN PREPARATION; FIRST e

l DRAFT OF EACH BLOCK VALVE TEST REPORT WILL BE SUBMITTED TO ALL PWR UTILITIES AS THEY BECOME AVAILABLE.ALL SEVEN REPORTS WILL BE COMPLETED AND SENT TO UTILITIES ON OR i

BEFORE MAY 1, 1981 i

i

?

~

s o

?

~

,JC/AD 3/N/91

nu F _.,

l '-

. MARSHALL BLOCK VALVE TESTS PRELIMINARY

SUMMARY

OF TEST RESULTS 1.

ANCHOR DARLING

?.

e INITIAL TEST, AUGUST 15, 1980 e

BLOCK VALVE IN-LINE WITH FISHER PORV BLOCK VALVE WOULD NOT FULLY CLOSE AGAINST FULL FLOW e

(70% CLOSED) j DISASSEMBLY INDICATED SOME SIGNIFICANT WEAR PATTERNS.AT e

THE DISC / SEAT INTERFACE

]-

e VALVE RETURNED TO MANUFACTURER FOR MODIFICATIONS VALVE WAS RETURNED TO MARS.tlALL FOR FURTHER TESTS e

e VALVE WAS RETESTED ON SEPTEMBER 25, 1980 IN LINE WITH FISHER PORV, AND UTILIZED A ROTORK 16NAX1 OPERATOR VALVE WAS CYCLED 21 TIMES AGAINST FULL FLOW (SATURATED e

STEAM, ~2400 PSI, ~195,000 LEM/HR) WITH NO SIGWIFICANT ANOMALIES NOTED.

SEAT LEAKAGE AFTER TEST RANGED FROM O.019.T0 0.066 GPM e

ANCHOR DARLING PERSUING ADDITIONAL MODIFICATIONS TO FURTHER REDUCE SEAT LEAKAGE i

I JJC/AD 3/19/81

~

. -.~ -

p-l. :. '

t MARSHALL BLOCK VALVE TESTS PRELIMINARY

SUMMARY

OF TEST RESULTS 2.

BORG WARNER TESTED IN LINE WITH MASONEILAN PORV ON NOVEMBER 4, e

1980.

VALVE ACTUATED WITH A ROTORK OPERATOR s

CYCLED (OPENED / CLOSED) AGAINST FULL FLOW

(*210,000 LBM/HR) WITH NO ANOMALIES NOTED i

1 I

1 i

T JJC/AD 3/19/81

'n n....

I.

i MARSHALL BLOCK VALVE TESTS PRELIMINARY SUMARY OF TEST RESULTS 3.

ROCKWELL INITIAL TEST (PRESSURIZATION OF LOOP) UNCOVERED A e

BODY TO BONNET SEAL PROBLEM; DESIGN WAS MODIFIED l

AND TESTED ON OCTOBEP. 27, 1980 VALVE IN LINE WITH COPES VULCAN PORV AND CYCLED e

(

21 TIMES AGAINST A FULL FLOW 0F 4230,000 LBM/HR.

VALVE WAS ACTUATED WITH A LIMITORQUE OPERATOR M5 DEL SMB-00-10 e

NO ANOMALIES WERE NOTED.

SEAT LEAKAGE WAS 0.0 GPM i

i T

b

y n. :.-

p.

, J MARSHALL BLOCK VALVE TESTS PRELIMINARY

SUMMARY

OF TEST RESULTS 4.

VELAN, MODEL C2345 S/N-24302 e

VALVE WAS EQUIPPED WITH LIMITORQUE ACTUATOR PODEL NO. SMB-00-15 1

VALVE WAS CYCLED 21 TIMES AGAINST A FULL FLOW 0F e

4246,000 LBM/HR ON JANUARY 13, 1981 e

SEAT LEAKAGE WAS 0.0 GPM SOME GALLING INDICATIONS ON ONE OF THE DISC GUIDES e

WAS OBSERVED WHEN THE VALVE WAS DISASSEMBLED AND 3

INSPECTED t

9 t

l l

T I

j..

o v

l l(* /.

7 #1 A #61

p u....-

s..

MARSHALL BLOCK VALVE TESTS

~

~

i-PRELIMINARY

SUMMARY

OF TEST RESULTS I

5.

VELAN, MODEL B10-3054B013M (MO) li e

VALVE WAS EQUIPPED WITH LIMITOROUE OPERATOR MODEL NO. SMB-00-10 e

VALVE WAS CYCLED 21 TIMES AGAINST FULL FLOW g

(4245,000 LBM/HR) ON JANUARY 14, 1981 l,.'

e NO ANOMALIES WERE NOTED; SEAT LEAKAGE WAS 0.0 GPM t

.i

~

T i

e

• • a

?

- ** r fo1

g) 4.

4.'

l..

i t

MARSHALL BLOCK VALVE TESTS i

PRELIMINARY

SUMMARY

OF TEST RESULTS 6.

WESTINGHOUSE MODEL 3GM88 e

INITIAL TESTS PERFORMED IN JULY, 1980 INDICATED THAT THE VALVE WOULD NOT CLOSE AGAINST FULL FLOW i

e VALVE WAS ACTUATED WITH ROTORK OPERATOR SET AT i

110 FT-LB. AND IN-LINE WITH A CONTROL COMPONENTS PORY e

FURTHER TESTS INDICATED THAT APPROXIMATELY 175 FT-LBS.

WERE REQUIRED TO CLOSE THE VALVE AGAINST A FULL FLOW 0F ~232,000 LBM/HR g

e VALVE WAS ACTUATED WITH A LIMITORQUE OFERATOR MODEL NO. SMB-00-15 ON AUGUST 13, 1980 e

VALVE WAS CYCLED 21 TIMES (FULLY OPEN/ FULLY CLOSED).

NO ANOMALIES WERE NOTED.

SEAT LEAKAGE WAS 0.0 GPM 9

e i

iIt'/..

T/10/o1

.