ML17252A719

From kanterella
Jump to navigation Jump to search
Forwards Responses to NUREG-0737 Items,Including RCS Vents, Relief/Safety Value Test Requirements,Auxiliary Feedwater Sys Evaluation/Automatic Initiation & Flow Indication & Dedicated Hydrogen Penetration
ML17252A719
Person / Time
Site: Dresden, Quad Cities, Zion  Constellation icon.png
Issue date: 07/01/1981
From: Delgeorge L
COMMONWEALTH EDISON CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.D.1, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.1, TASK-2.F.2, TASK-2.K.3.01, TASK-2.K.3.02, TASK-2.K.3.05, TASK-2.K.3.13, TASK-2.K.3.14, TASK-2.K.3.15, TASK-2.K.3.25, TASK-2.K.3.27, TASK-TM 2232N, NUDOCS 8107090210
Download: ML17252A719 (37)
v • d • e


Text

{{#Wiki_filter:_; --11----~- . -~~r f

  • . t~

.. & "~ I} Commonwea.Edison One First National Plaza. Chicago, Illinois Address Reply to: Post Office Box 767

  • Chicago, Illinois 60690 Mr. Darrell G. Eisenhut, Director Di~ision of Licensing U.S. Nuclear Regulat-0ry Commission Washington, DC 20555 July 1, 1981

Subject:

.Dresden Station Units l*, 2, and 3 Quad Ctties Station Units l and 2 Z io n S t at i o n U n i t s l a n d 2 Respo~ses to NUREG-0737 Items.

  • Re q u ir i n g July l, l 9 8 l Submittal
  • NRC Docket Nos. 50-10/237/249, 50-2541265-j *and 50*295/304 R~ferences (~):

D~ L. Peoples letter to 0. G. Eisenhut d ate d Dec ember l 4,. l 9 7 9 (b):

  • W. F. Naughton letter to 0. G. Efsenhut dated March 18r 1980 (c):

D. L. Peoples letter to D. G. Eisenhut

  • dated June 12, 1980 (d):

D. G. Eisenhut letter to All Licensees dated October 31, 1980 ( e) : J

  • s. Abel letter to D. G. Eisenhut dated December l 5, 1980

( f ) : J. s. Abel letter to 0. G. Eisenhut dated December 3 l, 1980 (~): J. S. Abel letter to D. G. Eisenhut dated April 1, 1981

Dear Mr. Eisenhut:

In response to the requirement set forth in Reference (d), enclosed are Commonwealth Edison Company's responses to those NUREG-0737 items requiring a July 1, 1981 submittal for Dresden, Quad Cities and Zion Stations. 8101090210 010101 ~OR AOOCK 05000~fi~ fJo'I' .s

  • .I 19,0
    • The enclosure to thts letter includes a response for items th at Reference ( d ) e i the r re q u i re s. a Ju l y l, l 9 8 l " Imp l em en t at i on "

or a July l, 1981 "Licensee Submittal". Additionally, where prior Commonwealth E~ison responses identified a July l, 1981 committment date, the enclosure provides the current st~tus of such items~ To the best bf my knowledge and belief, the statements contained herein and in the attachments are true and correct. In some respects,. those statements are not based on my personal knowledge but upon information furnished by other Commonwealth Edison employes. Such information has been reviewed in accordance with Company practice and 1 believe it to be reliable. Please address ~ny questi~ns you may have regarding t~is matter to this office.* P l e a s e* n ot e t h at n o re s p on s e i s p r o v i d.e d f or D r e s d en U n H. l, which is currently under~oing an extensive modification and d~contamination outage. The requtrements of NUREG-0737 will be addressed prior to startup of the unit, now scheduled for June, 1986. One (.1) signed original and seventy-n.i:ne (79)" copies of this transmittal are provtded for your use. Very truly yours, £~!{,~ Director of Nuclear Licensing cc: Mr. James G. Keppler, Director 2232N Riii Inspector - Dresden Riii Insp~ctor - Quad Cities* Riii Inspector - Zion

J ENCLOSURE COMMONWEALTH EDISON COMPANY Re. s p o n s e s To N U RE G. - 0 7 3 7 I t ems R e q u i r i n g. J u 1 y 1, 1 9 8 1 S u b m i t t a 1 Dre~den Units 2 and 3 Quad Ctties. Units l and 2 *

  • Z:-ion Un.its l and 2

II.B.l Reactor Coolant System Vents Dre*sden and Quad Cities Reseonse References A) Letter ffom D.B. Waters (BWR Owners G~oup) to D.G. Eisenhut date April 24, 1981. B) General Electric Report - NED0-24782 dated August 1980, titled "BWR Owners' Group NUREG-0578 Implementation: Analyses and Positions for Plant - Unique Submitials." Position,;, Item (2) Clarification - Items A(lL A(2) As stated in previous submittals concerning reactor coolant syste~ vents.there are several paths for reactor venting. The major systems* which in themselves provide adequate venting, however, are the Automatic Slowdown System and the HPCI System. The remainder of the paths. available which w o u ld pr o b ab l y n e v e r. b e n e e d e d f o r v e n ti n g ( t o pre v. e n t t h e postulated conditions) are considered* strictly as backup for the already adequate systems. Procedures specifically w~itten to in~truct reactor operators on using HPCI or ADS for venting purposes is not deemed necessary due to the inherent design of those ~ystems.

  • As. stated. by the BWR Owners Group (Reference A) and General Electric (Reference B) venting will be accomplished through the normat function of the ADS and HPCI syst~ms.

For small pipe breaks the HPCI pumps will maintain water level and there would be no subst~ntial hydrogen production. The HPCI system is capable of venting the noncondensibles under those conditions. For larger breaks where HPCI could not maintain water level the-reactor would be depr~ssurized by the ADS-system and the low pressure cooling systems would take over. ~enting would have been accomplished through the relief valves and the break itself if w~ter level were l.ow enough. Considering that l) the major objective *is to maintain water level, 2) the emergency procedures are written to insure this, and 3) ADS and HPCI

  • will provide for venting while performing their ECCS functions, no specific venting procedures are felt needed at this time.

Items A13la A(4), A(6l~ A(7), A(8), A{9) These items are felt to be adequately addressed in General Elect~ic report NED0-24782 (Reference B).

Item A(Sl Acoustic monitors have been added to the ADS valves to give an i n d i c.a t i on of val v e po s it ion ( Item I I

  • D
  • 3 )
  • These provide indication in the control room.

. Item A( 10) The seismic adeq~acy -0f the Target Rock valves and the Electtomatic relief valves were previously addressed in our response to _I.E. Bulletin 80-01. This response w'as transmitted in the 0. L. Peoples~ letters dated January 18 a n d 2 5, l 9 8 0 t o J

  • G. Ke. p p l e r, R e g i o n I I I a n d d i s c u s s e d t h e inspections and modtf icatians to be performed to assure*

seismic capability. It is felt t~at the actions tak~n to re s pond to the Bu l l et i n a ls 6 s at i* sf y the concern s of th i s NUREG re~arding seismic quafification. Also, as stated tn previous submittals, the* enviro_nmental qualification. of th.e

  • ADS va~ves will be addressed in the response to I.E.

Bulletin 79~01B wh.ich addresses. the environmenta.l q~alification of electric~l equipment. th~ acoustic monitors are undergoing a qualification program a,t this time *. As reported in a June 17, 1981 letter from J.S. A~el to D *. G~ Efsenhut the pragram will be completed by December 31, 1981 and a report wil.l be issued in February of 1982~ It em A ( l l ) The AD~ valves are already being tested as part of the ASME Sectiun XI pump and v~lve testing program as required by l 0 CF R 5 0

  • 5 5 a..

A l s o, t h e HP C I s y st em f a l l s u n d e r t h e s c o p e of the pump and valve testing program. The requirements of that testing program as submitted to the NRC are fulfilled during the periodic testing as. required by the Technical Specifications. Item A(l2) No new items were added as a iesult of the II.B.l requirements. Zion Response Position (1): The vent i~- a~ extensi6n of an existing v es s e r vent connect i on.

  • Th *e p i p i n g i s routed to the Control Rod Drive Mechanism (CROM) Seismic Platform where the solenciid val~es are mou*nted, and v~nts off -the platform

to the open ar~a of.the reactor vessel cavity. It is ~imed d-0wn at a 45 degree an~le away from any eq~ipment or obstructions *. The piping is one-hal*f inch diameter schedule 160 pipe (same piping *design table as the reactor coolant pipirig, "E-1"). The solenoid valves w~re purchased as ASME Class l valves (with N-.Stamps), environmentally qualified for Post-LOCA conditions and meeting the requirements of IEEE 323-*1974. The power supply to the so l en o i d val v es i s C l ass l E, w i t.h par al le l sets of valves w i r e d t o re d *u n d an t p 6 we r t r a i n s. S a r g e ri t & L u n d y* d r aw i n g s M-956 and M~959 show the line diagrams of the Unit l and Unit 2 systems~ respectively. Drawings M-957 and M-960 s h ow t h e U n T t l an d U n i t 2 i s 6 me t r i c d r aw i ng s, ** respectively. Drawtngs *M~958 Sheets l through 3 show the physical pipe rout~ng for both units. Draw.ings 22E-l-4840, ~ages RC12Z thru RC 1Z5 pr~~i~e the schematic diagrams for U,nit l. These* draw.ing.s have bee*n enclosed for your refer e n*c e * *. The: vent was p laced~ so th at d-1 sch a r g e of e i:t her gas., steam. or water wi 1 l not affect any e*quipment in the area and tha*t.any hydrogen relea.sed will not be trapped in the: CROM p la.tf orm *.

  • Position (2).:. *The.Westinghouse Owners Group*~ of which CECo~ is a m~mber. is working on guidelines and procedures for t*he* use of the ve*nt system.

Once comp.leted,, they wi.l T be i.ncorporated into. Zion Station emergency operating i n s.t ructions.* Clarification A.(l):* No.comm~nt required. Cl~rificatiori A.(2}: Procedure~ are.b~ing developed by the Westinghouse Owners group of which CECo. is a mem~er. Once developed, they will be incorporated into Ziori Station emergency operating instructions. Clarification A.(3): The vent was sized to keep the inside diameter smaller than* the siz~ corresponding to the definition of LOCA. When hjdrogen is vented from the r~actor vessel, the maximum rate of flow is determined by a choked.flow condition in the throat of the solenoid valve. Venting times will be addressed in the procedures described in item A.(2) above. Clarification A.(4): The,reactor coolant system vent is smaller than the' size corresponding to the definition of LOCA. Cl~rification A.(5): The open or closed v~nt valve position is shown by ~ed or green indicating li*ghts mounted on the control board. Clarification A.(6): Re~ctor coolant vent ~alves are controlled with control switches mounted on the main contra l board.

Clarification A.(7): The vessel vent piping was designed and instal.led as Clas5 l piping (Safety Related) and installed to the. latest addendum of ANSI B31. l. The vent pipe is schedule 160 pipe (same design table as the reactor coolant piping,* "E-l"). The solenoid v~lves were purchased as ASME Class 1 valves (with N-Stamps). Inadvertent operation will be ptevented by placing the vent valves under administrative control with key-lock control switches. Further,. two valves in series have to be opened to activ~te the vent system~ Clarification A.(8): The design of the vent system minimizes. the probability of failure in the open position. The vent solenoid valves are energized from the emergency buses. The valves are energized to open; a fai.lure of the pow e r supp Ty w i l l n o t prevent. the c l o s i n g of the vent p at h.. Clarificatio.n A.(9): The vent system discharges into an ope n are a. w he r e g o o d m i x i n g w i t h c o n t a i nm e n t a i r i s provided. Clarificati.orr A.(10}: The seismic and environmental qualification for the' system was provided to the extent possible. This documentation will be made available at the Zion Station for review. Clarification A.(11): We do not intend to do any tests of the valves under power. There are provisions for checking the operability of the reactor coolant vent valves. Clarification A.(12):

  • Human factor analysis will be taken into acc6unt in finalizing the station emergency procedures governing the use of vent system.

B) BWR Design Consideration: Not ap~licable to Zion Station C) PWR Vent Design Consideration: The design considerations listed in this section were taken into account in the design of RCS vent.

REV. A B c 1RC07J-1RC20 REACTOR VESSEl. <tRCOOt) ....,~ll't--.,..*,. au~b. f'LANG,E FOR <XlNSTRUCTICJN PIPE REROUTEO.(MOD. HO. M22-1-711-.43.) CON~Tlat.ICT10N AG.4 FCla ti 81-g9(ltf*11-l-1f ""t.,..RC.,..21__,.. -,....,,....E-+R...,,..;"

    • -**-*-----*-------~-~------------

VENT TO ' gJNl'AlflMEHT. NUCLIAI SAFETY IELAIED lllMS All SHOWN OH tias DIAweNG.

  • - WIJY QASllRCA-.......

-*,"" IOU9lll'!": VAlVI, OI -- U$TI. I REACTOR VESSEL HEAD . VENT ~YST!' DIAGRAM ZION STATION UN" CQMM()HWKALTH EDISON CQ. CHICAGO, ILLINOIS llmawrmY !I °"~ M-956 t-----,-iC

a.

,. h*.. --.........,,,.n..:..**"'*'*'* ~-" -~---*--*-* ****-... 17£M K.8.1 ~ION RESPONSE

~ \\,~~* ..U(llAI SAFETY RELATED lfEMS Mi SHOWN oN THIS DRAWING I - IAllH ClAHIHC:AflllN $111 _ ........,. -VI. Oii 1111_,.f llltl. I 1--;;~.&m:::N:.tl R VESSEL HEAD VENT SYSTEM. ISOMETRIC ZION STATION UNIT 1 CDMMONWE~TH EDISON CO. CHICAGO, I WNOIS 11 uaaT*WIDY II Ct"tlO.-...o M_-9_5_7 _ _. B °" 1 .i

t.'"JCUAI SAFITY lllATID llHU All UtOWN OM IMS DIAW91Q --*nA..o---*-M*- -*I *-*I --*-*-111 . -"~~:-*... ~--.

.::*.-:--.::.:.:=-~.

j ____ : -

  • -I --

1 .fl.~~--* ...,_.. ~,-....,....,,. 1*ou.1w11d'Faivt11111 --~-- ..I M*8~8 SH. 3

  • A*

~- ... j fil;At;!llft.YilS.ll.Ql!l£HJAJIQ!L .LI-.~ fi2!l~HE REACTOA vESSEL OAtENTATION FOR l.HT 2 IS ROTA.JED 1eo* W.TH R£FERENCE TO I.mil 1. REACTOR VESSEL HEAD VENT SYSTEM 'Pl.AN* EL.091"-1~ lK>N STAflOH l.HT 1 & 2 M-8~ C

I I I I I I '~*M NUCUAI 5AfllY lllAllD lltMI A&l '*>WH OH 1Hf1i 0.AW..0 1 * . -0 no* ---*-- - 7T

  • I I.
  • -Ep j

M*9~8 5H. l

  • A*

~ ~ ~~~~4~.;~~-*~,~~~*:':

  • REACTOR VESSEL HEAD VENT SYSTEM PLAN* EL.011'*0*

ZION STATION UNT 1 & :Z OlMMOHWEALTH EDISON CO. CHICAGO l..LINCWS .e* u-*-n

  • 1 NUCUAI *AflJY lllAllD llUU Ml 1HOWH OH..., DeAWIHO

... Ol-1-*uSU* i;.: *-**. M-Q~B sH. 2 r M-Qe8 SH.1 r _ S£C!tOttA*A* I~\\~~ ~11~ I& I 1.~ MACTOR V£UEL HE.AO VENT SYSTEM 5ECTIOH.. ~-~~ c

NUCLEAR SAFETY RELATED. IJEMS ARE SHOWN ON THIS DRAWING I fOll UflfY ClAUlflCAJIOH Ill PIPING, IGUIPMINI, VAlVI. OI INHIUMINf USU. I ~r-;:;==::=r-==c=::;:;c.--r--::=-:== A B J ~l.

  • 2SO\\/-RC10 250\\/-RCS C2Q6-1 E-1R

\\\\ g FOR CONSTRUCTION. MOD. NO. M*22*2-79-4l. FOR CONSTRUCTION. PIPE REROUTED.( MOD. NO. M22-2-79-43 .. l . *.., ~*!i'*.... ~: : ~. 1"x 12° RED. INSERT (TYP.) 4 REQ'D. C207-1 ~R 1R REACTOR VESSEL ( 2RC001) REACTOR VESSEL HEAD VENT SYSTEM DIAGRAM ZION STATION UNIT 2 COMMONWEALTH EDISON CO. CHICAGO. ILLINOIS DRAWlllO NO. UV. M-959 B SltHT 1

0.

1

NUCLEAR SAFETY RELATED ITEMS ARE SHOWN ON THiS DRAWING I fOll.U.fUY ClAHlflCATICIH Ill riftHO. -*NT. VAlV~. OI INUIUMIN1 Ulll. I REV. A B

c.

PUAPOSI FOR CECO CONSTRUCTION. MOD. NO.' M-22-2-79*43 FOR CONSTRUCTION. PIPE REROUTED. (MOO. NO. M22-2-79-<13.l REVISED PER FCR 80-43 (MOD. NO. M-22-2-79-43 REACTOR VESSEL REACTOR VESSEL HEAD VENT SYSTE::M ISOMETRIC ZION STATION UNIT-2 COMMONWEALTH EDISON co. CHICAGO, ILLINOIS ~ 11-~~~I DAAWlllCI llO. M-960 c SKI.IT-Of- .. :1 ,:-4. 'l e /,'

-.I I

I. i I.J j ./

w RC080 3A RC08G E-49 SOL. VLV. -na:-*- E.-49 RCOBRKj:, E-49 5 CLOSES WHlN VLV. 6 IS OPEil E-49 1 £JL [RC08N N -. -*- *--{[]}-- ----------+----__J l- ----~!_-~~~_Y.ENT VAL_VE _____ ~ __.;J

  • I-ISOV*RC08

-i . ~ *.. *. ~cl.Ass 1 ~ INSTALLATION ITC:M NC.!iOO lllS-RCl8 ~ F. V. SEE P. RCl99.0ET;065 FOR CS DEVELOPMENT MODULE

  • M02-F.-4 I SOV-RC08 REACTOR VESSEL VENT VAL VES-P \\RT. I SCHUIA Tl C 0 I AGRAM
    • oao.

'llOll STATIOll Ii';; . ~] DWG.NO. 22£-1-4840 t011MOOwt~~\\IJ~o1soil co. ~~~~~~ll---' 6 1 02 '--+--------1 . CIHCAGO, ILLlllOIS RCI 22

~ ~RCIOP ITEM NO.SOI A P- ~~ IHS-Ar.1.9 CLOSE OPEtl J~ ~ ~ F.V. fl "'r SEE P. RCl99,0ET.065 0 FIJI CS OEVELll'llENT fl lilO\\JLE.

  • 1112-F -*4 R

~ii:' . B.;. L ~,; ~*M'j u"' 0 RC1 uO ---.b RCIOG -,, ~ (Sl £-49 > *:{ ~E-49 E-49 I IL OPENS 5 CLOSES SOl.VLV.,; _ ~ ETD~ 7 - WllEN VLV. -- WHEN VLV. 2 IS OPEN 6 IS OPEN (~ E-49 ll! 4( H-49 c~ E-49 I+- f.lL lRCION _ ~ ~ JA N - v RX VESSEL VENT VALVE ... 1 J ISOV-RCIO ~ ~* 5l ci f**~ 0 1~ CLASS 1 *~r u INSTALLATION ISOV-RCIO I DAU f".UHf*OttC fhM... DAil l"UOPDt.a fllM 1,:°f~....... \\) at=c.V Q(. For c.o..... Tc P*ll 1*Hl.PAHIO dl\\ /Ja.ftlA,;. OA1'*C _~/- lf.*80 REACTOR VESSEL VENT VALVES-PART 2 11'tt' 19 4!' 1u*v11.Wt:od Ck ;.,.;. &-12-<!1) SCHEMATIC DIAGRAM "'OJ HO. ZION STATION IL~~~;..~~~~~~I DWO NO. 22E-1-4840

  • ~-~,"..

UNIT I 6102 ~*.(.*:~ CCloolllfALTH EDISON CO. ,.,.,.,,ov1,.-,

  • .
    (* * ~ ":::"""'D,..TI.

CHICAGO. ILLINOIS .PAGI: RC12l t

~ r*..,, I TEii N0.502 IHS*RC20 £Y. r09P ~ 3A p - --{[.Jr- / -1 J~ £ f.V. SEEP. RCl99,0ET.065 I FOR CS OEVELm>il:NT 0 fl 'l ICOULE

  • ICZ-F -4 s

R ~ !J ii: L ';;'. -'j ... ' 'i u 0: 0 RCO 1 RC09G ~1> E-21 E-21 ~{ ~ E-21 I SOL. VLV. OPENS 5 CLOSES +- . -~WHEN VLV. -~ WHEN VLV. ---no- "' 7 fil 4 IS OPEN 6 IS OPEN 2 (~ E-21 ~ ( ~E-21 (~ E-21 fli. rRC09N

I 3A H*

I* R_X VESSEL VENT VALVE I SOV*RC09 0., 0 ~ CLASS1 ~1 ~ ~ INSTALLATION. 0... u I SOV*RC09

.j
  • REACTOR VESSEL VENT VALVES-P4RT 3 PUHPOltlE:

fllM... OAfE fo'UfllPOtil!: FILM l*ftl[PARkof.!O:tWe!de: DAT.: ~l-16*~~ plt()J NO

  • c*

DATE SCHEMATIC DIAGRAM OWG HO. 22E,l -4840 Ql r.>~,.,. '*°".:I. I a.Jk. f'-ll-8." ZION STATION ((!ARG!!!,3 6102 A. 1,*ll)~ Ec...v pc.* Ht'Z :-1"1*4~ '* UEVll:Wt. ~ATIE . 7. UNIT I RCl24 ~,__ ii--*~ ' /. Jo? 2~~-f~ COMMONWEAL TH EO I SON CO. .:...,.C:AOO P~GI: r--* CltlGAGO. ILLINOIS APf'nrivt.rl.. ~- \\~,...--:.r&A"TI' ~ 7 J t

  • -:;.~- -

W:. [RCllP p -

{[JJ--~---1...._ ___ _

I / Ar' "' ::r £ 0 fl 8 ~-".'.'.. L~ 0

  • .1 fl

~ "' 0.. u.. 0 Cl' ~ R R~j 10 lE-21 "'; ~;E-21 ""'"~ E-21 I "!{] i.L OPENS ~+/- CLOSES SOLT~h'!:. IJ: 7-WHEN VLV. WHEN VLV. E e 4 IS OPEN 6 IS OPEN E-21 ~ (~E-?I (~E-21 ~ ~ N-* -* -iC .. RX VESSEL VEtH VALVE ~ ~---l-SO-V--R-C-11-.---~--~ t

  • I

~CLASS 1 ~1 INSTALL.t.TION I TEii NO. 50] lllS-RC21

  • .~

F.'v *. SEE P. RCI 99.0ET. 065 Fm! CS* OEVELCl'~NT . !a>ULE ~ 1112-H ISOV-RCll REACTOR VESSEL VEUT VALVES-PART" 4..

  • ,(.

SCllEllATIC OIACRAll ZIOtl STATION UNIT I COMllJNWEALTH EDISON CO. ..ClllCACO. ILLWOIS 22E - I -4840 RCl25

  • I.r.D.l.

Relief and Safetx ~alve Test Reguirements Dresden and Quad Cities Response

References:

l) Letter from T. J. Derite (BWR Owners' Group) to D. G~ Eisenhut (NRC), "Transmittal of Preliminary Data from Generic BWR. Safety/Rel~ef Valve (S/RV) Test Program" dated July l, 1981 2}

3) letter from D. B. Waters (BWR Owners' Group) to R. H. Vollmei (NRC), "NUREG-0578 Requirement 2.1.2-Performance Testing of B WR and PW R R e l i e f and S a*f et y Va l v e s "

dated September 17, 1980. Letter from D*.B. Waters (BWR Owner's Group) to 0. G. Eisenhut (NRC), "Responses to NRC Questi*ons on.the BWR S/RV Test Program" dated March 31, _1981 (Response to NRC Que~tion No. 1) Th i s. response provides the. res u lt s of a p_r e l i mi nary rev i e w of the seneric BWR S/RY test pro~ram results (Reference l) in order to confir~_the ad.equacy*of the S/RV's for the Dresden and Quad Cities Plants for all test conditions as defined in the test de~crip~ibn (Reference 2).

  • The Dresden and Quad Cities Plants employ the Dre.s~er EJectromatic, Model No. 6-1525 VX (four per unit),. and the Target Rock 3-stage, Model No. 7467F (one per unit) S/RVs.
  • The test results for the 6-1525 VX Electromatic and 3-stage Target Rock 7467F valves are -applicable to:'these plants' val~es (Reference 3):

A preliminary review of the generic BWR S/RV test program results* demonstrates that the tested val~es satisfy the acceptance criteria f-or operability;* Consequently, based.on this preliminary review, the operational adequacy of the S/RV's for the *Dresden and Quad Cities Plants has been demonstrated.

Zion Respon.se

References:

1)

Letter from R. C. Youngdahl (Con~umers Power) to D. G *. Eisenhut (NRC) dated December 15, 1980 2} Letter from R. C. Youngdahl (Consumers Power) to H. R. Denton (NRC) dated July 1, 1981

  • By l et t er dated Ju Ty l, l 9 81. R
  • C Young d ah l (Consumers Power) transmitted the Interim Data Report for the EPRI PWR Safety and Relief Valve Test. Program.

This report summarizes the t.est. data collected. to date on. relief valves (safet*y v:alve*data is still no.t available).* Our* Zion Plant:- has Copes-V.ulcan.Model D'-10.0-160 2" ai:r operated, globe re* l i e f v a l v e s ( l7 - 4 P H. P l u g* arid C a g:e ) a n d C r o s by Mod e l HP-BP-86', si*ze 6M6 safety va*Tv*es *. Results provided in Section 4.7 of the EPRI Interim Data* Report are *applicable to our plant.. Our preliminary. eva.luation. of the d.a.ta indicates that our reli~f valves will-perform-their fnten-ded function for steam inlet cond.itions. Commonwealth Edison will submit prelimfnary and final evaluations, and other plant s*peci.fic d:ata for all relief and. safety va*lve in' l et con d i ti on s yet to be. tested on a sch e d:u le cons i st en t with the R. C. Youngdahl letter* of December 15, 1980 and modified on July l, 1981.

..,J,. 9, II.E.1.1 Auxiliary Feedwater System Evaluation Dresden and Quad Cities Response This item ts not applf~able ~o Dresden or Quad Cities. Stations.

  • Zion Response See.Refe~ence (b), W. *f. Na*ughton letter to D. G. Eisenhut dated Marth 18~ 1980.

In our judgement, w~*have sufficiently complied with this NRC request and have provided the necessa:ry,i nfocrmat i-on for the NRC to conduct th i s system e v a 1 u at i on-.' To date, CE Co

  • h as rec e i v e d no d,estgn. revfew response from the NRC.

l"herefore.,, in our

  • opinio,n no further resp.on.se. is. re,quired. at this time *.

J

  • e II.E.l.2 Auxiliary Feedwater System Automatic Initiatton and Flow Indication Dresden and Quad Ci,ties Response This item is not applicable to Dresden or Quad Cities Stations.

Zion Response See Reference (a) D. L. Peoples l~tter to D. G. Eisenhut dated December.14,

  • 1979.

This submittal provided justification that the existing automatic ini~iation and flow indication does not require modification and that Technical Specification ch_a_nges were als.o unnecessary. To date, CECo. has received no de~ign review response from the N RC

  • Therefore, ** i. t i s our j u*d gem en t th.at no further response is required at -th i*s time *.

). 11.E.~.1 Dedicat~d Hxdrogen Penetrations Dresden*and Quad Cities Reseonse The ACAD System has been furrcti-0nally tested at both stations ~nd performs as designed. The QA do~umentation is in final stages of review and resolution. The system was destgned to ASME Section 111, Class 2 and the electrtcal equipment is qualified to IEfE 323, 1974 and IEEE 344, 1975, ~xcept f-0r some Rochester Instruments .which are q~alified to 1971. Due to the *1arge v61ume of qualification documentation~ it was not feasible to submit the inform.ation at this time. The documentation is available for review at Dresden and Quad Cities Stations. Zion*Response The modi"ftcations, making the Hydrogen Recombiner single fai:lure proof 'are complete at Zion. These included m.odifying the 10 11 suction path so that. it could be used* either as a. suction or discharge* path, automating the dra:in on that line to prev.ent format.ion of loop sea.ls,, a*nd upgrading both suction_ paths to. withstand 10 p_sig. The only pieces of equipment that required environ.mental qualifi*cation were the automatic dra.in valves on the 10 11 suction path. The qualification test records to IEEE 323-74 will be available at Zion Station for review by August 1,, 1981.

.. ~ . II.E.4.2 Containment Isolation Dependability~ Position (7) Radiation Signal *on Purge Valves 2232N Dresden and Quad Cities*Response See Reference* (e); J. s.. Abel letter.to 0. G. Eisenhut letter dated *oecember 15, 1980. CECo. c.ommitted to the installation of automatic high radiation closure of the containment purg~ and vent valves. Since that time, the BWR Owner's Group* has performed an evaluation of the need for this i.so.lation signal which was transmitted to.the NRC by Mr. T~ J. Oente's letter to Mr. 0. G. Eisenhut dated June 29*~ 1981. This evaluation has been determined to be generally ap.p.l i*cable to Dre.sden Uni ts 2 and J and Quad Cities LJ:nits. land 2, and based on its conclusions, Commonwealth Edison Co.. doe.s not believe* that installation of *the high rad.fa*tion closure is required. The modification has been completed at Dre~d~n ~ and will remain operational, but operability of.the trip will not b e m ad e* a Te c h n i c a 1 S p e c i f i c at i on r e q u i r em e n t

  • Zion Response See Refer e n*c e ( e ) J.. S
  • Abe 1 l et t er to D
  • G
  • E i sen h u t dated frecember 15, 1980.

1*n our judgement, no additional response is required~.

11.F. l Accident Monitoring Dresden ~nd guad Cities Response

2.

Sam~ling* and Analysis pf Plant Effluents The final design details are being drafted and will be available 8/1/Sl. The system.is expected to be in service by l/l/82.

3.

Coptainment High-R~nge Monitor T~e designs are available for review and installation is expected to be compl~te by l/l./82.

6.

Containment Hydrogen The function of the monitors which.Dresden and Quad Cities have in place has been changed to a "go-no-go" m6nitor by the desigrier. This new fun~tion will indicate when H2 concentrations are present, but not exact percentages. Operating procedures for the system reflect the use of the "go-no-go" monitors for containment hydrogen. control. CECo. is e~aluatfng bids from seie~al v~ndo~s to replace t*he existing monitors. The installation of the new monitors is scheduled during the *refueling* outages commencing ~fter l/l/82. The new monttors and systems will me~t.all requirem~nts of NU.REG-0737.

    • Zion Response

.3. Containment High-R~nge Monitor The designs are available for.review and installation is ~xpected to be complete by 1/1/82. The following description of the monitors is provid~d:

1.

The description oi on name of ~anufacturer and model number of the monitors;

Response

General Atomic Model R~-23 high range radiation monitor.

2.

Verification th~t the monitors meet the ... specificatioQs of T~ble Il.F.1-3;

.L .e Resgonse REQUIREMENT-The. capabi 1 ity to detect and measure. the. radiation level within the reactor containment durfng and following an accident.

Response

Comply RANGE . 1 rad/hr to ldB rads/hr (beta an~ gamma) or ~lternativelJ 1 R/hr to lO (gamma only). Responsa:. Comply RESPQNSE - 60 keV to 3 MeY photons~ ~ith lin~ar energy response +*20%) for photons of O.l MeV to* J MeV. Instruments must be accurate.e.nough to prov.ide usable REDUNDANT inform~tion~

  • Response~ Comply A minimum* of two physica,lly separated* monit.ors

(: L e *, mo n it or i n g w i de* l y s e p a rated s p aces within containment) *. Respo~se~ Comply DESIGN AND QUALIFICATION-Category 1 instruments as described in App~ndix A, except as listed below.

Response

We assume that this reference is to Appendix B instead of Appendix A. The.Radiation Mo~itors are Gen~ral Atomic~ RD-23 which have been tested to* IEEE 323-1974. The review of the Environmental Equipment Qualification Test Report has been completed. Presently there are no outstanding deficiencies in the report, however, there are a few areas which are being investigated further before complete acceptance of the Report.

L SPECIAL CALIBRATION SPECIAL In situ ca.libratio:n by electronic signal substftution is acceptable for all range decades above 10 R/hr. In situ calibration for at least o~e decade below 10 R/Hr shall be by means of calibrated radiati-0n source. The, ori gi:na l laboratory calibration ts not an acceptable positi-0n due to the possiblJe differences after in si*tu installation. For high-raQge calibrat.ion, no ad~quate sources exist, so an alternate was

  • pzrov i ded.

Response

A" l R/Hr rad tat io.n sou.rc:e is provided insi.de* the dete.c.tor for cali-bration. Additionanl.y,

  • . e.lectronic cali.bration hs provided by mean s' of an i n t e r n a l

~c;u r r*e n t source*correspondin.g t~ ~-05 R/Hr. E NV IRONME NTAL QUALIFICATIONS - c*alibrate a.nd type..:test re*pres.entat'ii v.e specimeris :o.f detectors at sufficient points to d em on s tr at e l i n e a r i t y t h r*O u g h a l l' Respons~:

s. C*a l e s. u p. t o l 0 6 R I h r *

~p r i o r t o i n i t i a l u s e, c e rt if y c a l :i'b r a t i on of each detector for at least one point .Per decade of rang~ between l R/Hr and 103 R/Hr. The Radiation Monitors have been tested over. a range of 43.5 Kev to 4.5 MeV and at 14 different test value~ from.6625 R/Hr to 5.17xlo& R/Hr. Although, there w~s not a test point:in the 103 decade and 105 decad~~~ it appears that , sufficient tests were performed to demonstr'ate linearity. The calibration for each detector at

  • one point p~r decade of ~ange
  • b et wee n l R I H r a n d l O 3 Rf H r w i l l
  • be implemented by C6mmonwealth
  • Edis.on Company *

. 3

  • Ver if i c qt ion that the mo n,i tors w i l l
  • be opera b le on January 1, 1982; and,

Response

Monitors for both units will be in service b~fore January 1, 1982.

4.

A plant layout drawing showing the location of the mon.itbrs. Re~pons~ Attached drawing M499 SH139 illustrates location of detec~ors.on inside wall of Unit l reactor building *. The ~etectors for Unit 2 are presently installed 1800 apart and at elevation 671'. Th~se detectors will b.e lowered about 42.' to faci.litate in situ calibration~

300°

  • PLAN 3 [4.1 HORIZ. LEAK TEST CHANNEL'.

...,... ". ;:-:- *' *~. REF. DWG.: CB & I. UNIT 1 NO. 16, REV. 2 * .HOLE FOR M6* BOLT.(TYP.)... AND 2~X2"Xl/.(l --L.A.-~.A-1~-Ef-+--.---,.--..- EXISTI~.,' EXISTING.. N EXISTING -.. ~. -l--1----U--' PIPE '. 120° LOCATE 2 INEACH UNIT 1eo* APART AT APPROX-. IMATE ELEVATION 6 2 ~o* SEE ENLARGED VIEW AT RIG... T.. 8 ~ttr-->.:-- E XIS Tl NG ~~'--'---__,.-< E XI sr'1 NG PIPE SUPPORT LINE PLATE

  • (CONCRETE ELEVATION*

.. Pff9POSED RADIATION.MONITOR SUPPO~T N-'CLEAR SAFiTY RELATED n~~s ARE SHOWN ON THIS PRAWING C PO. SAPITY CLAHlflCAllON SH. "PING. ~IPMINT. VAlyt. ()I INSllUMINT LISTS. I /T~M.::JZ. F. I Z/Oltl RE.5"PONSE SIDE)

i:, .*l I I.. F

  • 2 I n s t r um e n t a t i o n f o r De t e c t i *O n
  • of I n ad e g u at e C or e C o o l i n g Dresden and guad Citi~s Response
  • S e e R e f e r e n c e ( e ) J
  • S
  • A b e l l e t t e r t o D
  • G.
  • E i s e n h u t d a t e d December 1.5, 198-0~

In our judgement, no -additional i nf o rm at i on i s. re q u. i red

  • Zion*Response See Refe.rence (g) J. S *. _Abel letter to D. G. Eisenhut dated Apr i l l, l 9 8 l
  • The
  • 11 Su mm a r y Report -

We st i n g ho u s e Re actor Vessel Level Instrumenta.ti.on System for M.onitoring rnadequa.te C:ore.*Cooling 11 is. currently bei'ng edited t.o re~l~ct t~e specific design. installed at li6n Station. ~o~ever, d~e to it's proprtetary classif.ication, the submittal o.f this d*esign information will b.e handled under** separate c.over and in accord:ance with sta.ndard pr act ices to ha.ndle such propri-etary documents.* Thi.s submittal will be made by August l,. 1981. I.

II.K. 3.1 Installation and Testing of Automatic Power~Operated Relief Valve Isolation System and II.. K.3.2 Re~ort on Overall Safety Effect of Power-Operated Relief Va ve Isolation System Dresden and Quad Cities Response. These items are not applicable to D~esden or Quad Cities Stations. Zion Response Se~ Reference (g) J. S. Abel letter to D. G. Eisenhut dated Aprtl 1, 1981. The Westinghouse Owner's Group letter

  1. OG-52 dated March 13, 1981 (R~ Jurgenson letter to J. R.

Miller) was submittted recommending against the installation of automatic PORV isolation (Item II.K.3.l). Commonwealth Edison concurs tn that recommendation *. Therefore, in ~ur judgement~ no f~rther action is requir~d at this time.

£..

e.

II.K.3.5 Automatic Trig of Reactor Coolant Rumps Duri~g Loss*of-Coolant Accident. Dresden and* Q~ad Cities Response Thi.s it.em is not app,licable to D.resden or Quad Cities St at ions. Zion*Reseonse Respons.e to this item was mad~ by the Westinghouse Owner's G r o u p i n t h e J u n e l 5, l 9 8 l l e t t e r f r om R

  • W
  • J u r g e n s e n t.o P
  • S
  • C h e c k
  • A d d i t i o n a l s u b m i t t.a l s c o n c e r n i n g t h i s it em, if necessary will be made tn accordance w.ith the sch~~ule provided in the Owner's Group. June l5., l98l letter above:.

II.K.3.13 Separation of HPCI an*d RCfC *system Initiation Levels Quad Cities Response See Reference (f) J'. S. Abel letter to 0. G. Eisenhut dated December 31', 1980:. BWR Owners Group concluded. tha-t HPCI and RC I C tn i t i at i on.1 eve 1 s e.p a rat i on was u n n e c es s a r y

  • Due to equipment delivery delays, installation of th~ RCIC automatic lqw water level restart by July 1, 1981 will not be po~sible.

Although* projected deltvery schedoles would perm i t i n st al l at i on by August, l 9 81, we be l i eve i. t i s more. prudent to insta~l the equipment.during a unit out~ge to* prevent taking the RCIC system out of service with the units op~rating. Therifo~e~ the installations.will be made* on Quad Cittes. Unit 2 *during the refueling outage beginning in September 1981 and on Q_uad Citi~s u*n;-t l during a planned outage in September or October, 1981. Dresden and Zion Response~.** This item is n'ot applicable to Dresden and Zio.n Stations.

II.K.3. 14. Isolation of Isolation Condensers on High Radiation . Dresden* Reseonse

  • See Referen~es (c) and (e) D. L. Peoples letter to D.

G~ Eisenhut dated June 12~ 1980 and J. S. Abel letter to D. G. Eisenhut dated December 15, 1980 indicating our intention to install shell vent high radiation trips on the i so 1 at i on condensers at* Dresden 2 and 3. After further consideration of this item and discussions with the BWR Owner'~ ~roup, we do not beli~ve that this installation i's desirable. The NRC staff position concerning vent high *rad trips emphasized the need for increased availability by relocating the high rad trip from the steam line to the shell vent. Our isolation condensers da not current)y have a steam line high rad trip. Also~ the addition of a vent line trip is judged not to tncrease the availablity but may actually decrease availabil°ity due to the potential of inadvertent trips. In addition, the isolati*on condenser can be isolated manually by the operator if necessary, after evaluatirrg existing vent radiation monitor alarms and indications and the availabitity of core cooling systems following any actident. Based on the above. a vent line high radiation trip of *the isolat1on condenser will not be installed. guad Cities and Zion Response This item is not applicable to Quad Cites or Zion Stations.

II.K.3.15 Modify Break*Detection Logic to Prevent Sgurious Isolation of HPCI and RCIC Dresden and Quad Cities Response This tnstallation will be in accordance with the General .Electric Co. "Conceptual Design for Modifications of the HPCI/RCIC Break Detection Logic". The i~olation relay ~ill be replaced with a safety rel~ted, Class. tE time

  • delay relay.

These relays w~ll.be set for the shortest delay time preventing spurious. isolation, from a minimum. of 3 ~econds to a maximum of 13 seconds. The installation is complete at Dresden. At Quad Cities, however, vendor QA documentation problems hav~ de*layed equi*pmen.t. availability. Although the eq*uipment. is e x p e c t ed. t o. b e a v a i l ab 1 e i n t h e n e a r f u t u. re, we b e l i e v e i t i~* more prudent to delay installation until a unit outa~e occurs. The equipment wi1*1 be installed on the same schedule as in. Item II.K.3.13, above. Zion Response T~is item is not a~plicable to Zion Station.

tt II.K.3.25 Effect of Loss of Alternating

  • Current Power on Pume Seals Dresden. *guad Cities Response The BWR Owner's Group Evaluati:on of this topic, transmitted: to the NRC by the o.. B. W-aters letter to D.

G. Eisenhut dated May 22, 1~81, has been reviewed by Commonwealth Edison Co. and has been determined to be applicable to the re~irculation pumps at Dresden 2/3 and Q.u ad C it i es l/2'. Based. on the. con c l us ions, of the O~ner's Grou~ evaluation~ n-0 changes or modifications ~re required. Zion Response. Se:e: R.efer*en~.e (e). J.: *. S. Ab.el; letter to D. G *. Eisenhut date.d December 15, l980. In ou*r judgement, no. addttfona.l ~espon~e i~ r~quired.

ILl<.3.27 2232N Provide Common Reference Level For Vessel Level Instrumentation Dresden and guad Cities Response S e e R e f' e r e n c e (" f ) J.. S

  • A b e l t o D
  • G
  • E i s e n h u t d a t e d December 31, 198-0.

In our judge~ent, no additional tnformation i.s required at this time. Zion Response This *item is. not applicable to Zion Station. r.}}

Retrieved from "https://kanterella.com/w/index.php?title=ML17252A719&oldid=5111248"