ML20198E822

From kanterella
Jump to navigation Jump to search
Forwards Outstanding Operating Reactors Events Assigned to Equipment Qualification & Mechanical Engineering Branches. Scheduled Inputs Requested by 850930
ML20198E822
Person / Time
Issue date: 05/08/1986
From: Bosnak B
NRC
To:
NRC
Shared Package
ML20151L176 List:
References
FOIA-86-266 NUDOCS 8605280285
Download: ML20198E822 (19)
v • d • e


Text

{{#Wiki_filter:.. 0 UNITED STATES j NUCLEAR REGULATORY COMMISSION 5 e ,[ WASHINGTON. D.C. 20555 NOTE TO: E0B i

SUBJECT:

OR EVENTS ASSIGNED TO CSE Please see attached on outstanding OR events.

  • 1 85/14 Assigned to EQB

._ /2 Assigned to MEB / / V .O'.-y -eS72* 45 Both have,/j y '3 scheduled inputs or closure by 9/30/85. Please advise me of your plans for action. Bob Bosnak Enci-v As stated hg52pg586050s h 's, MURPHYBo-266 PDR s (4..S s i' /7

p. #

/ p6 s s \\,<..,()? $ j0jb'd s ,3 A,b h/8)' ' ' C- '[

f.,

j), 9 0 "*) ' f, . a.. : t e q im v N,l %. ~ l. p ; t bL(('{jj.hy.'ul. L. /.. ' l b' \\ A , / -L,/ - ,,/,,f,0.y/i- '( s'7e'J NO ~,.. i,.. &:., c,.t ys. V%f< -7 F., /N' i.by f~1[f'J a .. { ~- ./ 1 ~ M. '+~.! ', T. /Uf :- A/9- /

f$$NW:WN#v5$kR&%22LdCth ML+%*t%V2414. rcrre ~Ls;~.:: n sw, i ~ - fpn-f e / j Hugh L. Thompson, Jr. W \\ U ) t_ / - -cc: H. Denton. E. Rossi, IE %e j

t. #

R. Bernero R. Hernan F. Schroeder / g A, J. Knight / / v T. Speis G. Knighton (M , L. C e C. Heltemes D. Silver p,i f, T. Novak J. Lyons p 34 C k W. Russell D. Brinkman J. Taylor E. Weiss L~ # b) M'M E. Jordan R. Baet L F. Rowsome J. Stolz the W. Minners E. Butcher 7 L. Shao R. Bosnak -eq T. Ippolito R. Gilbert

  1. y 1
  2. ym g

S. Varga M. Thadani J. Zelinski D. Vassallo E. Sullivan T. Alexion D. Beckham B. J. Youngblood L G. Edison K. Jabbour K. Seyfrit E. G. Adensam T. Murley, R-I D. Sells J. Nelson Grace, R-II J. Giitter ~ R. Clark J. Keppler, R-III R. D. Martin, R-IV C. Stahl J. B. Martin, R-V T. Colburn R. Starostecki, R-I R. Walker, R-II, C. Norelius, R-III N R. Denise, R-IV D. Kirsch, R-V G. Lainas P. Baranowski I l t l

f 4 Page No. 2 08/29/C5 OPERATING REACTORe* EVENTS HEETING FCLLDWP ITEH8 AS OF MEETIPM 85-14 ON AUGUST 26, 1985 m (IN ASCENDING 81EETING DATE, NSSS VENDOH, FACILITV ORDER) SCHEDULE (10848 CATE CONr1ENTB NEETING FACILITY RESPONSIBLE TASK DESCRIPTION ao COMPLET. DV 00CUMENT, Nur1BER/ NSSS VENDOR / DIVISION / DATE18) NEETING, ETC. a NEETING EVENT DESCRIP. INDIVIDUAL DATE 85-11 RANCHO SECO 1 DL / MINER, S. SCHEDULE CONFERENCE CALL WITN 09/30/85 OPEN / / EVALUAfl0N IN e Rl010N AND LICEN8EE PRIOR TO 08/15/05 PROGRESS i 07/01/85 BW / STARTUP / RESTART TO DETERMINC PLAHf 07/12/95 PROBLENS-JUNE e READINCSS FOR OPERATIONS. 1985 i CONSIDER ISSUANCE OF IE NOTICE. 08/3C/05 CLOSED 08/30/05 i e 85-11 LASALLE 2 IE /BAER, R. / / IE NOTICE 85-75 07/01/05 GE / EQ / / / NODIFICATION / PROBLENS AND m LOSS OF ALL ECCS JUNE 5-10, 1985 l 05-1i OYSTER CREEK 1 DHFS/B006ER, H. DETLftNIhC EFFICACY OF EPG/ 09/15/95 OPEN / / t g OPER4 TOR ACTION AND EXCESSIVE 08/30/85 07/01/85 GE / / / / RESPONSE IINF., UNCONTROLLED e LEAKAGE OF REACTOR COOLANT l i OUTSIDE l g CONTAINNENT l' 6/12/05 l ANALYlE SAFETY INPLICATIONS OF 09/30/63 OPEN / / 85-12 SEABROOK DSI /NAREN 07/23/85 W / CROSBY NAIN / VALVE FLOW DEFICIENCV / / / / STEAN SAFETY VALVE FLOW DEFICIENCY 12/84 DE / CHERNEY INVESTIGATE ADEDUACY OF TESTING 09/30/95 OPEN / / 05-12 SEABROOK f AND VALIDITY OF EXTMAPOL ATING / / ,07/23/85 W / CROSBY HAIN / DATA FRON Gr%LL TO LARGE VALVES / / 7 STEArt SAFETY VALVE FLOW e DEFICIENCY 12/84 } l 85-13 CALVERT CLIFFS AEOD/LANNING, W DETEftflNE IF RECENT DE /.K-2-25 09/13/05 OPEN / / i i TRIP BAEAKER PROBLEN3 REPORTED / / ,08/13/85 CE / REACTOR / / / ' VIA NPRDS TRIP BREAKER = PROBLEN

  • 85-13 FOREIGN IE /ROSSR, E.

CONSIDER ISSUANCE OF IE 09/13/85 OPEN / / 09/03/85 INFORMATION NOTICE. 08/13/05 NA / NULTIPLE / / / I FEEDWATER FAILURES i 85-13 FOINT BEACN IE /LONG, S. DRAFT INFORMATION HOTICE ON PT. 09/13/85 OPEN / / / / 08/13/85 W / SAFETY ORAB/ CARUS 0, M. BEACH EVENT. CONSIDER TEMP. INSTRUCTION FOR RES. INSFECTOR / / l INJECTION REGARDING CONFt.l ANCE WITH APP. MINI-FLOW RECIRC g g DESIGN l DEFICIENCY I 1 1 1

\\ Pe:e No. 3 08/29/85 CPERATING REACTORa* EVENT 3 MEETING FOLLOWUP ITENS AS OF HEETING C5-14 ON AUGUST 26, 1985 I (IN ASCENDING HEETING DA1E, Nr.63 VENDOR, FACILITY ORDER) HEETING FACILITV RESPONSIBLE TASK DkSCRIPTION SCHEDUL.E CLOGEO DATE ComENTS WMBER/ NSSS VENDOR / DIVISION / COMPLET. BY DOCtMENT, NEETING EVENT DESCRIP. INDIVIDUAL DATE(8) NEETING, ETC. DATE 6 e 05-13 TURKEY POINT 3 DL / MCDONALD, D. HAVE LICENSEE INCORPORATE USE 10/13/85 OPEN / / 08/83/85 W / POST-1 RIP / OF N0 TOR DRIVEN AFW PUMPS IN / / LOSS OF AFW ON EMERGENCY PROCEDURES / / 7/21/85 I 85-13 TURKEY POINT 3 DSI /PARR, O. REVIEW ADEQUACY OF GOVERNOR 10/13/05 OPEN / / I ~ 08/13/05 W / POST-TRIP / DESIGN ON TURSINE DRIVEN AFW / / LOSS OF AFW PUMPS / / / 85-14 CALLAWAY t DL /0CONNOR CHECK WOLF CREEK FOR SIMILIAR 08/30/85 CLOSED 08/29/85 WOLF CREEK USING 08/26/05 W / ELECTRICAL / PROBLEM / / / NTG WITH PN IDENTICAL I POWER TRANSIENT / / COMPONENTS-CONDUCTING WEEKLY j SURV. UNTIL l RESULTS OF GE ANAL. ARE KNOWN l 85-14 CATAWBA 1 DSI /9ERNERO R REVIEW SEPARATION OF LNIT 1 AND 09/30/85 OPEN / / I 08/26/05 W / BLACKOUT / UNIT 2 AND NEET WITH DtEE PRIOR / / l SIGNAL AND TO LICENSING OF UNIT 2 / / i INTERACTION l BETWEEN UNITS 1 l AND 2 85/I4 SEQUOYAH DE /BOSNAK R IMPLICATIONS OF EQ INADEQUACIES 12/30/85 OPEN / / 08/26/95 W / UNITS 1 AND / AND STATUS OF EQ REVIEW 09/30/85 / / J 2 VOLUNTARY 3 SWTDOWN BY TVA BECAUSE OF EQUIPMENT GUALIFICATION (EOl f INADEQUACIES' [ 85-14 SEQUDYAH DL / STAR. C IMITIATENTAFFREVIEWOFTVA 12/30/85 OPEN / / 08/24/85 W / UNITS 1 AND / "SWOMATTALS '09730/85 2 VOLUNTARY / / j SHUTDOWN SY TVA 1 DECAUSE OF I EQUIPMENT 3 OUALIFICATION (EQ) INADEQUACIES 4 W 4 l, e u

k

  • .w e t Nyf=N 7 N M %t!4 N.%""4Ef fas:'y?f Wif W.ecew4vxc%Ar.

ff4V ~ i / n -l -2 / Hugh L. Thompson, Jr. W v .As_ s c fr cc: H. Denton E. Rossi, IE R. Bernero R. Hernan ,A, F. Schroeder / g J. Knight / / p T. Speis G. Knighton Ca " ,Lci-C. Heltemes D. Silver y ' y, 1 T. Novak J. Lyons p 3d~ G, i-j W. Russell D. Brinkman J. Taylor E.. Weiss L~ # I E. Jordan R. Baer 6 L'M i /#' /bL-F. Rowsome J. Stolz W. Minners E. Butcher L. Shao R. Bosnak 7.#g ,7 T. Ippolito R. Gilbert -<3 1

  1. y" m S. Varga M. Thadani J. Zwolinski D. Vassallo E. Sullivan T. Alexion D. Beckham B. J. Youngblood Z-G. Edison K. Jabbour K. Seyfrit E. G. Adensam T. Murley, R-I D. Sells J. Nelson Grace, R-II J. Giitter J. Keppler, R-III R. Clark R. D. Martin, R-IV C. Stahl J. B. Martin, R-V T. Colburn 1

R. Starostecki, R-I R. Walker, R-II. ~ C. Norelius, R-III R. Denise, R-IV I D. Kirsch, R-V G. Lainas P. Baranowski l ?

en. m. 3 l 08/29/05 OPERATING REACTORa* EVENT 3 MEETING FOLLOWUP ITEMS l AS CF NEETING 85-84 DN AUC'.33T 26, 1985 IIN ASCENDING HEETING DATE, NESS VENDOR, FACILITY ORDERI MEETING FACILITY RESPONSIBLE TASK OkSCRIPTION SCHEDLLE CLOSED DATE COMMENTS DAJMisER/ NSSS VENDOR / DIVISION / CDPFLET. DV DOCLMENT, MEETING EVENT DESCRIP. INDIVIDUAL DATE(S) MEETI,NG, ETC. DATE 05-83 TURKEY PolNT 3 DL / MCDONALD, D. HAVE LICENSEE INCORPORATE USE 10/13/95 OPEN / / 08/13/85 W / POST-TRIP / OF MOTOR DRIVEN AFW PUMPS IN / / LOSS OF AFW ON EMERGENCY PROCEDLJRES / / 7/21/95 1 85-13 TURKEY POINT 3 DSI /PARR, O. REVIEW ADEQUACY OF GOVERNOR 10/13/85 OPEN / / 08/13/05 W / POST-TRIP / DESION ON TURBINE DRIVEN AFW / / I LOSS OF AFW PUMPS / / / 05-14 CALLAWAY t DL /OCONNOR DECK WOLF CREEK FOR SIMILIAR 09/30/95 CLOSED 06/29/85 WOLF CREE 3C USING 08/26/05 W / ELECTRICAL / PROBLEM / / MID WITH PM IDENTICAL POWER TRANSIENT

  1. /

COMPONENTS-CONDUCTING WEEKLY SURV. UNTIL RESULTS OF GE ANAL. ARE KNOWN i 85-14 CATAWBA 1, dst /BERNERO R REVIEW SEPARATION OF LNIT t AND 09/30/85 GPEN / / i 08/26/85 W / BLACKOUT / UNIT 2 AND MEET WITH DUKE PRIOR / / SIGNAL AND TO LICENSING OF UNIT 2 / / INTERACTION DETWEEN UNITS 1 f N4D 2 1 05/14 SEQUOYAH DE /BOSNAK R IMPLICATIONS OF EQ INADEQUACIES 12/30/95 OPEN / / 09/26/85 W / UNITS 1 AND / AND STATUS OF EQ REVIEW 09/30/85 2 VOLUNTARY / / SHUTDOWN SY TVA BECAUSE OF EQUIPMENT GUALIFICATION (E01 l INADEQUACIES ~ B5-14 SEQUOYAH DL /STAM C IMITIATE TAFF REVIEW OF TVA 12/30/85 OPEN / / t 2 VOLtJNTARY "S$9M6TTALA

  • 09730/85 08/26/05 W / UNITS 1 AND

/ / / SNUTDOWN SY TVA i DECAUSE OF EQUIPMENT QUALIFICATION (EQB e INADEQUACIES i l

s% - ek. %. 2 OPERATING REACTORS

  • EVENTS MEETING FOLLOWUP ITEMS 08/29/05 AS OF MEETING 95-14 ON AUGUST 26, 1995 A

IIN ASCENDIN3 MEETING DATE, NSS8 VENDOR. FACILITY ORDERI 3 SCHEDLA.E CLOSED DATE COMMENTS e NEETitW3 FACILITY RESPONSIBLE TASK DCSCRIPTION COMPLET. BY DOCUMENT, NUMBER / NSSS VENDOR / DIVISION / DATEtBD NEETING, ETC. anNEETING EVENT DESCRIP. INDIVIDUAL DATE 85-11 RANCHO SECO I DL / MINER S. SCHEDULE CONFERENCE CALL WITH 09/30/85 OPEN / / EVALUATION IN 1 e REGION AND LICENSEE PRION TO 08/15/R5 PROGRESS 07/05/85 BW # GTARTUP / RESTAR1 (D IETERNINE PLANT 07/12/95 PROBLEMS-JUNE en READINESS FOR OPERAftDNS. 1985 e 95-11 LASALLE 2 IE /BAER, R. CONSIDER ISSUANCE OF IE NOTICE. 09/30/95 CLOSED 08/30/05 / / IE NOTICE 85-75 07/01/85 OE / EQ / / / MODIFICATION / PROBLEMS AND e, LOSS OF ALL ECCS JUNE 5-10, 1995 05-18 OYSTER CREEK 1 DHFS/B00HER, H. DETERMINE EFFICACY OF EPG/ 09/15/95 OPEN / / me OPERATOR ACTION AND EXCESSIVE 08/30/85 07/01/95 GE / / RESPONSE TINE. / / tJNCONTROLLED m e LEAKAGE OF REACTOR COOLANT OUTSIDE j g CONTAINMENT 1 6/12/05 ANALYZE SAFETY IMPLICAT10NS OF 09/30/85 OPEN / /' i 85-12 SEABROOA DSI / MARSH 07/23/95 W / CROSBY MAIN / VALVE FLOW DEFICIENCY / / / / STEAM SAFETY g VALVE FLOW DEFICIENCY 12/84 I g 85-I2 SEASROOK f DE / CHERNEY INVESTIGATE ADEQUACY OF TESTING 09/30/95 OPEN / / ,07/23/85 W / CROS8Y MAIN / AND VALIDITY OF EXTRAPOLATING / / DATA FROM SMALL TO LARGE VALVE 8 / / STEAM SAFETY VALVE FLOW e DEFICIENCY 82/94 } g B5-13 CALVERT CLIFFS AEOD/LANNING, W DETERtfINE !F RECENT DE AK-2-25 09/13/Es3 OPEN / / TRIP BREAKER PRO 9LEMS REPORTED / / ,08/13/85 CE / REACTOR / / / VIA PF1tDS TRIP DREAKER. PROBLEM

  • 05-13 FORE 10N IE /ROSSI, E.

CONSIDER ISSUANCE OF IE 09/13/85 OPFN / / INFORMATION NOTICE. 09/03/85 08/13/85 NA / NULTIPLE / / / FEECWATER FAILtJRES 95-13 FOINT BEACN IE /Lf1NG, S. DRAFT INFORMATION NOTICE ON PT. 09/13/95 OPEN / /

  • 08/13/95 W / SAFETY ORA 9/CARUSO, M.

DEACH EVENT. CONSIDER TEMP. / / INSTRUCTION FOR RES. INSPECTOR / / INJECTION HINI-FLOW RECIRC REGARDING CDPFL{ANCE WITH APP. g DESIGN DEFICIENCY

W W ^ 9 I* 3 a ,/ x as / N 7 \\ j} ,Y 6 yyjdd/- W g ( x.. y / 3 -~ ,L.,i, / L,', .z ,,. !,,l T WV j - (/ "4 x \\ 'N \\ f,, s a I

Page )io.

  • 2

.01/01/80, OPERATIN6 REACTCRs' EVENTS EETINS FOLLOG ITEMS AS OF MEETING E5-16 DN SEPTER!ER 14,1995 (IN ASODDING HEETINS DATE, NS$$ VENDOR, FACILITY ORtER) MEETINS FACILITY RESPC.vS!$:.! TASK N SCRIPTICN SCHEDULE CLOSED DATE COMMENTS NUMBER / MS$$VEEOR/ DIVI!!ON/ COMPLET. BY DOCUMENTr MEETINS EVENT H SCRIP. ICIVIDUAL DATE(S) MEETING,ETC. DATE 85-11 07/01/85 ~ RANCHO SECO 1 DL /MIER, S. SCEDULE CONFERENCE CALL MITH 09/30/85 OPEN // EVALUAT!DNIN BW / STARTUP / RE6!DN AC LICENSEE PRIOR TO 08/15/85 PROGRESS PR08tD S-JUNE RESTART TO DETERMIT PLANT 07/12/85 1985 READIESS FOR OPDATIONS. 85-11 DYSTD CREEK 1 DNFS/CLAYTOR 8. MTERMINE ETFICACY.0F !?S/ 10/30/85 OPS // 67/01/95 8E / / OPERATOR ACTION A C EICES!!VE M/15/85 UN:0NTROLLD RESPONSE TI E. 08/30/85 LEAKAGE OF EA TOR CCOLANT ~ DUTSIM CONTAINMENT 6/12/85 f 85-12 SDjRua $$1 / MARSH ANALYIESAFETYIMPL!tATIONSOF M/30/85 OPS / / 87/23135 N / D 0!8Y MAIN / VALVE FLON MFICI DCY // f g ' Cg STEAMSAFETY // f [g vntvE nCv DE*!CIENC1 / LA 12154 b e/ b f -l 85-12 SEABROOK M /CEREY INVEST!EATE AM OUACY OF TESTING09/30/85 OPEW / / 07723/83 N / CRUD f AAIN / ANDV4LIDITY,0FEITRAPOLATIN6 // STDMSAFETY DATA FROM SMALL TO LARSE VALVES // / VALVE RON ( AEF1CID Y 12/84 fp; $5-13 CALVERTCLIFFS AE03/LANNINS,M DETERMINE IF RECEXT BE AK-2-25 09/30/85 DPD /. / 08/13185 CE / EACTOR / TRIP 3REAKER PROBLDS REPORTD 09/13/85 TRIP 3REAKD VIA NPRDS // PROBLEM 85-13 FORE 18N !! /ROSS!, E. CCNSIER !$5UANCE OF IE 09/30/85 OPEN // 1ENOTICEtu l C/13/25 NA / MULTIPLE / INFORMATIONNOTICE. 09/13/85 CONCURRENCE FEONATER 09/03/85 FAILURES 85-13 POINT MACM IE /LONS, S. MAM INFORMAfl0K W I!CE DN FT. 09/30/85 OPEN // DRAFT IE NOTICE IN ' C/13/85 N / SAFETT ORAL /CARUSD,M. MACH EVENT. CONSIDER TDP. 09/13/85 NRR CCN URRENCE INJEIT10li INSTRUCT!DN FOR RES. INSPETOF. // RINI-FLONRECIRC RESAu!Ns COMPLIANCE NITH APP. MSISN K EFICID:Y , 85-23 TljRKEY POINT 3 DL /MC:GNALD, D. HAVE LICENSEE IN CRPCRATEUSE 10/13/85 DPEN // 0B!13185 N / POST-TRIP / OFMOTOR3RIVENAFMPDMPSIN // LOSS OF AFV ON DERSEN ? PROCEDURES // 7/21185 e

0+L,,,, v uss v. res % '[ SSINS No.: 6835 M 'A 9 ", 3 _, m IN 85-XX a W fO / UNITED STATES NUCLEAR REGULATORY COMMISSION .f d 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 J / September, 1985 IE INFORMATION NOTICE NO. 85-XX: MAIN STEAM SAFETY VALVE TEST FAILURES AND RING SETTING ADJUSTMENTS Addressees: ressurizedfater eactor (PWR) nuclear power reactor facilities holding an All operating license (OL) or a construction permit (CP).

Purpose:

This infonnation notice is being provided as a notification of a potentially significant problem pertaining to spring-actuated main steam safety valves (See Figure 1), that may possess less than the full rated flow capacity required for overpressure protection of the secondary cooling system in PWRs. It is expect-ed that recipients will review the information fcf applicability to their facilities and consider actions, if appropriate, to preclude a similar problem-I at their facilities. However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required. Description of Circumstances: p @ ~ f, y, h & 4sta p L > LQ % (anofI99+, n p L.. T J. v i A Public Service of New Hampshire sent the main steam safety valvesfortheirSeabrookplanttoWQeLaboratoriesfortestingtodetermine Pn t" .Tthdr.ringsettings9 Specifically,.the tests were to e.m opp.og...$.... ,, 1 w.Lt y o f J:: sL ms (*ft~S h ask ~t u m f l l '95/

\\ r,. vy.: ...y / (JNITED STATES NUCLEAR REGULATORY COMMISSION l 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C, 20555 SEPTEMBER , 1985 I IE formation Notice No.: 85-xx MAIN STEAM SAFETY VALVE TEST ILURES AND RING SETTING ADJUSTMENTS I Addressees: All PWR nuclear p reactor facilities holdin operating license (OL) or 4 a construction permit

Purpose:

i This Information Notice is bein rov d as a notification of a potentially significant problem pertaini to spring-tuated main steam safety valves i j (See Figure 1), that may sess less thtn full rated flow capacity i i required for overpress protection of the se dary cooling system in PWRs. It is expec hat recipients will review e -infomation for - ) applicability to eir facilities and consider actio if appropriate, to preclude a si ar problem at their facilities. Howeve suggestions contained i his Information Notice do not constitute NRC quirements; therefor, no specific action or written response is required. cription of Circumstances: f 1 Between October 16, 1984, andDecember1,1984,WyleLaboratori$sconducted several full flow steam tests on two separate in steam safety valves (MSSVs) manufactured by Crosby Valve and Gage Company These Crosby 6R10 MSSVs are to. ~ be installed by Public Service of New Hampshir on the Seabrook main steam system. The tests were conducted in order to detemine the adequacy of various MSSV discharge piping arrangements. During the tests the valves were instrumented to measure valve disk lift. The valves were installed on the i test facility with the settings of the valve adjusting rings (see Figure 1) l as received from the valve vendor. With these ring settings the valve achieved about 50% of the full disk lift required to develop full steam flow j capacity within the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code required 3% accumulated overpressure limit. Adequate lift was not achieved for either valve with these factory) adjusted ring settings, i even for the largest diameter (least flow resistance vent pipe tested. The { guide ring of both valves was subsequently adjusted to a lower position by a significant amount (150 notches) during the course of testing and full disk lift was subsequently achieved. t \\ .1 ~ _.,_,.-._....___

\\ determine if the "as-shipped" ring settings of the valves would allow the required disc D with minimum tailpipe backpressure and to determine the effects on valve disc travel for a range of backpressures between 180 and 390 psig. The results of the tests indicated that the valves'co"uld not achieve the pid a. ' required disc travel with the factory-set ring setting (+155 notches). The 3 disc travel achieved was 50% of the full lift required to develop full flow steam flow capacity as required by the f.= r Na N dier.icel Engin cra (8.SME) 90!!er ar.d "r::; r: '!::re! Ced: (;cde). Adequate lift was not attain 4J = et4e even with the largest diameter tailpipe. i i During the tests, the upper (guide) ring setting was adjusted from +155 to 0 and to +25 to achieve the Code required disc travel. This is a substantial adjustment. Subsequently, the licensee consulted with the yalve manufacturer and agreed upon ring settings of +25 for the guide ring and -25 (the original setting) for the lower (nozzle) ring. % *hk{-%+ 4 ;4 5 + s n+<9 "ah w, : =: g ?! "'""d W. A s:. t a w ma f u On October 14, 1982, Duke Power Company notified the NRC that they had. deter-St= 8ettbIled mined that pressurizer Code safety valve design flew, based upon known ring' ^ 3m:. t settings, could not be fully : int;ir.;d if called upon. This was detennined from data from the generic relief and safety valve test program recently completed by the Electric Power Research Institute. This problem was limited z.s c.- w '.. Es,' a. to some Dresser valves on Babcock and Wilcox, designed PWRs.% Consultation with c-e licensees, B&W,,and Dresser resulted in resetting of ring settings in a number A of plants. A y j f,% -d CPE

    1. 3' M P*#

- 62% [ 5).+- et

  • I yn s.s. kset3.

weit - YW N## i 9,,,% y

S Full flow, full size test af the sort,describ;d in this notice aro not normally 3 7 performed by either the licensee or valve vendor for 2- ':; r secondary 1-12-J*.* _[ safety valves, nor are they required by the ASME Code, Section III. [The k valvesarecertifiedbyextrgolationsondatafr'omtestsofsmallervalves.] While the Seabrook valves are Crosby 6R10, manufactured by Crosby Valve and ~ Gage Company, similar problems yy exist with any trn, M S S V e v. mv..u a., ig where certification is done by extrepolation. 3 /A, Y /A i ' ~ 4 5. L %g e l D I i \\, ~ \\ s "- ~'

t IN 85-XX ON M September, 1985 / Page of i No specific action or written response is required b] this information notice. .If you have any quest; ions about this matter, please contact the Regional Administrator of the appropriate regional office or this office. Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement ~ Technical

Contact:

Mary Wegner IE F (301)492-4511 1 MD % Fe w*> ~ 1,

Attachment:

List of Recently Issued IE Infonnation Notices ./ ~~ ~~~ DEPER:IE ELJordan 9/ /85 DEPER:IE DEPER:IE DEPER:IE DEPER:IE PSB:IE DEPER:IE DEPER:IE l .a. .--,-,m g --,-,--,---.,.---,,ww ,,,e.e, e., w-, e ---w-ro-~.wo, e, -.-w --,>-+-v==*----e -m-we-e----~^='~v'- ' "' -'

MSWegner DPAllison RLBaer ERossi DGable WFisher SASchwartz 9/ /85 9/ /85 9/ /85 9/ /85 9/ /85 9/ /85 9/ /85 e. a 9 ~ e 4 h I. er

\\ /~ / iAa~y O w,.a 4

  • - a ya

- OL.n n ,na rA a /us d~,. s, .ab~ - s~ sr,p .nh.td M -{dl. ' W WA n // T"'

c-JM ~.---n a.b n p q.LA~y-y p.

y 567 A w w <s 4 m pr 2 a,.... a p i frfe- % Tw x;& Wy. g &- J - d.- ;L & Ak -4 s Q 4A e s 4'.; d 4, % di jd.h a M M +j ~ca y, g+p. _M~&ms %A-m f *

  • d.ro VM -

esa E.m -- up a -9 9 /s + y, s n. /3/#' X 4 A 2L-un,

a isj/ .Y 0 5 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 SEPTEMBER , 1985 IE Information Notice No.: 85-xx MAIN STEAM SAFETY VALVE TEST FAILURES AND RING SETTING ADJUSTMENTS Addressees: All PWR nuclear power reactor facilities holding an operating license (OL) or a construction permit (CP)

Purpose:

This Information Notice is being provided as a notification of a potentially significant problem pertaining to spring-actuated main steam safety valves (See Figure 1), that may possess less than the full rated flow capacity required for overpressure protection of the secondary cooling system ir PWRs. It is expected that recipients will review the information for applicability to their facilities and consider actions, if appropriate, to preclude a similar problem at their facilities. However, suggestions contained in this Information Notice do not constitute NRC requirements; therefore, no specific action or written response is required. Description of Circumstances: g(tsw H} Between October 16, 1984, and December 1, 1984 Wyle Laboratories conducted several full flow steam tests on two separate in steam safety valves (MSSVs) manufactured by Crosby Valve and Gage Company These Crosby 6R10 MSSVs are to be installed by Public Service of New Hampshir on the Seabrook main steam system. The tests were conducted in order to determine the adequacy of various MSSV discharge piping arrangements. During the tests the valves were instrumented to measure valve disk lift. The valves were installed on the test facility with the settings of the valve adjusting rings (see Figure 1) as received from the valve vendor. With these ring settings the valve achieved about 50% of the full disk lift required to develop full steam flow capacity within the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code required 3% accumulated overpressure limit. Adequate lift was not achieved for either valve with these factory) adjusted ring settings, even for the largest diameter (least flow resistance vent pipe tested. The guide ring of both valves was subsequently adjusted to a lower position by a significant amount (15%rnotches) during the course of testing and full disk lift was subsequently achieved. t }. A

4 l,b i'3' Y I f o p t o.,- +o +t.c a 1,. -._ +em

c.. _u J. ' 5 &

S 11 -4 n'ts4, t.sa u <--2 <+<J '3JJi+,'. a ( 4e.s+s 3+ wy t-I L a s. - w. '.., %.t.wa -g.- H5 .s.*.be 41 JJa-7 ra 3- .4 .IJ a g g*yib h.kymsr,.g 's 17o ~ f -d.es s FSM H Based on -the full flow tests ;rfer ;d :t "yi; '.;ber t; & r, "u bli; 0; rvie;- C g.re of L., L..+ hi n (P d 5:1) has concluded thatuthe guide ring setting for the Seabrook MSSVs should be adjusted downward -H0 notches o ensure full flow capacity. The MSSVs will be installed at Seabrook w t the guide ring adjusted downward-tSQ. notches from the as delivered, factory adjusted setting. 13 o G s. + s., 4. w,...,.+ - r . ~. +, ..+a. s > ,...,.+ O e l i I L j

- as. d .i' IN 85-XX September 1985 ";;: ? -ef i %)) These types of full flow tests are not normally performed by either reactor owners or the valve vendor on MSSVs, nor are such tests required for capacity certification according to the ASME Code, Section III. In general, these valves are capacity certified by tests on much smaller size valves, and the capacities then extrapolated to larger size valves. The MSSVs on most Phls, while not necessarily the same model o'r supplied by the same vendor, are oike those at Seabrook in that they are generally at the upper end of the valve This raises the concern that full flow functional demonstration size range. of some valve types' may never have been performed, and that due to incorrect ring settings, the valve may not be capable of providing relief capacity in accordance with facility design requirements. No specific action or written response is required by this Inform Regional Administrator of the appropriate regional office or this office. Notice. I ~ Edward L. Jordan, Director Division of. Emergency Preparedness and Engineering Response Office of Inspection and Enforcement Technical

Contact:

. hommo r. NR - ^ 301-4^2 "951 I' hs 2,7 u> ey. e - (3*t} Fit-fertt t G G f I ~ --}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20198E822&oldid=4100501"