ML17193B503
| ML17193B503 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/17/1981 |
| From: | Rausch T COMMONWEALTH EDISON CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17193B504 | List: |
| References | |
| TASK-06-04, TASK-6-4, TASK-RR 0236A, 236A, NUDOCS 8106300202 | |
| Download: ML17193B503 (10) | |
Text
~~
t~-.
Co-;,,monweal-dison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 Dennis M.
Crutchf~eld, Chief Operating Reactor Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Dresden 2 SEP Topic Vl-4, Containment Isolation Systems NRC Docket 50-237
Reference:
a)
Dennis M. Crutchfield Letter of April 23, 1981 to J.S. Abel
Dear Mr. Crutchfield:
June 17, 1981 Item 1 of the referenced letter was a list of references.
In response to items 2 and 3 Dresden station uses several methods of ad~inistrative control on test coqnections, vent lines~ and capped branch lines.
Prior to power operations 1,a fter ~.a refueling outage, al 1 sys tern line~up~ are performed according to the: system valve. checklist.
Normally when operations require a valve position to be changed, an outage card is hung on the valve~ This helps to ensure the valve is returned to its normal position after the operation is complete.
There are no tags that identify valves as being administratively controlled.
There are some valves that are locked shut but these have no consistent basis for their selection.
Sbme remote-manual valves are* 1not monitored for leakage, but these valves are checked shut prior to plant power operation after an outage.
Item 4 - General Attachment A is an updated version of FSAR table 5.2.4.
Attachment B i~ a supplement to table 5.2.4 containing major penetrations not included in the original table.
It should be noted that an official and approved update of the table will be included in the updated version of the FSAR which is rjue to the NRC in approximately one year.
~(
Item 4a) b) c) d)
~ ~,.~
Attachment 'C are excerpts from section 5.2.1 of the Dresden -
1 (; 9 FSAR.
These paragraphs include a review of the general design philosoph used in providing containment isolation;*
Item 5 Isolation Attachment B.
retl6 3 oo Z02 valves for lines 2-9208 f
/
~
and 2-9207 are include~.,~
~**
11"'
GV'~,A
' cA
~,,,,.,, -
I.
". *J-
~~,.* !
Item 6a 2 -
Atta6hments A and B have what are felt to be the correct isolation valves.
item 6b Local manu~l isolation valves are considered acceptable for the purpose of containment isolation.
The service air and service water lines are strictly for support during maintenance and refueling outages.
These lines are isolated prior to closing the drywell.
Even if these lines were left open there would be strong indications of such *a
. condition.
With the service air line open, air would flow into ~he drywell. making it impossible to ke~p the drywell inerted with the nor~al makeup system.
With the service* water line open, water would *conb.lnue *to flow into the ~ry~ell and would be detected *during the vessel pressure test drywell inspection prior to startup or through excessive leakage to the drywell sumps.
The instrument air lin~ is a closed system within the drywell.
According. to the GDC having *one remotely opera~ed val_ve outside containment is an acceptable form of isolation (GDC-57).
The instrument air line~at Dresden has,an air operated valve outside ~ontainment which serves this purpose.
Therefore this i~olation is considered:acc~ptable.
Item 6c None are n~eded since this lin~ is outboard of the outeimost
. ~ontainment isolation valie (4607-501) on the service air line.
Item 7
- Line.2-2504-1" is the containment bleed line* for the.ACAD **
system.
The.isolation valves fo~ this line are listed 1n Attachment B.
Lines. 3316A, "B, C and D can not be located on our drawin.gs.
Item 8 Relief valve RV-2301-53 does provide an isolation function for the HPCI system.
The relief valve setpoint is 210 psig *which.is more than double the containment design pressure of 62*psi~~
Relief valve numbers RV-1501-85A, B, C and D have been changed to RV-1599~13A, B, C and D.
These valves do provide an isolation.
function for the LPCI system.
There ~etpoints are at 150 psig, again more than double the ~ontainment *design pressure.
L
- ~.r:.. '
3 -
Item 9
- Attached i~ one aperture card of card of drawing B-24 Rev. W.
- Also, *attached are six copies of drawing B-25 Rev. z, Containment Vessels Supresiion Chamber Penetrations.
Please address any questions you may have concerning *this matter to: this office.
one (1) signed original and thirty-nin~. (39) copies nf this transmittal have beeh provided f6r y9ur use.
NPS/vhs 0236a
- cc:
- RI I I Resident Inspector, Dresden Very truly yours, T.J. Rausch
- Nuclear Licensing Administrator.
Boiling*w~ter Reactor~
.1
- l Valve Pt Number 103-iA, B, C, D ml-ZA. B, C. D
- Z?0-1 no-z llo-6ZA, B Z20-58A, B ll0-44 22045 301-95 301-98 lZOl-1.
1201-2 lZOl-3 1001-lA, B 1001-2A, B, C 1001-SA, B 1501-SA, B, C, D 1501 -22.A, B 1501-~ A.B 1501-illA, 'B l501-19A, B 1501-38A, B 1501-20A, B 1501-13A, B 1501-28A, B
%05-2-4 105-2-7 1101-16 1101-15 1301-1 1301-2 1301-3 1301-4 H02-3A, B H02-25A, B H02-9A, B H02-4A. B uo2-38 A, B
%301-36 2301-,,.
%301-5
%301-: 7'1
%301-34
%301-40 ZOOl-105
- 2001-106 1001-5 1001,-6 "310Z 3'1'-q-s;oo 3103 3706 1601-60 1601-61 1601-JlA, B 1601-20A, B 1601-23 1601-%4 1601-62 1601-21 1601-55 1601-59 1601-58 1601-56 1601-57 1601-22 MaLD Steain Main Steam Une laolated Main Steam Une Drain Maln Steam Une Drain Feedwater Feedwater RX Wat.er Sample RX Water Sample Crd Hyd Sya Ret Crd Hyd Sya Rel Cleanup Sys Sup Cleanup Sys &Ip Cleanup Sys Sup Shutdown Cool. Sup Shutdown Cool. Sup Shutdown Cool. Ret LPCI Pump Suet LPCI Core Flooding LPCI Core Flooding LPCI Suppression Spray LPCI Suppression Spray LPCI Teat LPCI Test LPCI Pump Min Flow LPCI ConWnment Spray RX Head Cooling
- RX Head.Cooling Standby Llquld Control Standby Uquld Control laolatlon Cond. Steam Sup Isolation Cond. Steam Sup laolat!on Cond. Cond. Rel.
laolattoo Cond. Cond. Rel Core Spray Pump Suet Core Spray to Reactor -
Core Spray to Reactor Core Spray Teat Core Spray Pump Min Flow HPCI Pump Suet Fr Torua HPCI Turb Steam Sup HPCI Turb Steam &Ip HPCI Turb Exhaust HPCI Cone!. Drain HPCI Pump Min Flow Drywell Floor Dr. Sump Disch Drywell Floor Dr. Sump Disch Drywell Equip Dr. Sump Disch Drywell Equip Dr. Sump Dlacb RX Bulldini Cloaed C. W. Sup RX Building Closed C. W. Sup RX Building Closed C. W. Ret*
- RX Building Closed C. W. Ret Suppressloo Chamber Vent SupproHIOD Chamber Vent Relief Suppression Chamber Vac Reller Suppre1alon Chamber Vac Relief Dryweti Vent Drywell Vent Drywell Vent Relief Drywell !nertlng and Purge
{)qtuJEL.L.. -.Z: AJ /5.~ T1.A.'4 Drywell N2 Mike-up Suppression Chamber N2 Mike-up Suppression Chamber Inert and Purge Drywell o.nd Suppr. Chamber N2 Make-up Drywall* o.nd &!ppr. Chamber Vent Fr RX Building 1601-63 Drywell Vent to Emer Ga.a Tr Sya 1601-55 N2 !nerUng
"'+3:27-.500 Service Water Supply
't ~
-.sO~rvtce Water Supply
<./bOf-6'Dl---servtce Air Supply H 1 ~EL-' 4AUWrl&rvtce Air &lpply "7 ::i..:i Instr Air Supply
/60/-t/B--.. Instr Air &lpply Closure Signals B
Reactor Low Wtr Level c
Main Stmllne High Radlat!OD D
Main Stmllne Break (high temp. high flow)
F High Drywell Presa G
Reactor Low Wtr Level - lnltlate ECC System*
H Hlgl> Reactor Pre11 K
ISO Condenser Line Break (ateam or cond high flow)
L HPCI Une Break (ateam or cond high flow)
P Main Stmllne Low Prell (run mode only) 8 Low Drywell Preeaure A
TABLES.2.4 f
. "TT/lCll/-f.E,UT A PRINCIPJr PENETRATIONS OF PRIMAR~ CONTArn NT AND ASSOCIATED ISOLATION VALVES Drywell(D Location Ref Penetration To Drywell X-lOSA, B, C, D lnalde X-105A. B, C, D Outside X-106 Inside X-106 Outside X-107A, B Outside X-107A, B ln.!lde X-122 Ina Ide X-122 Outelde x-i'#-a+
\\
Outside X-J.'lf -*-
Inside x-.113.*
ln.!lde X-113 Outside X-113 Outside X-lllA, B Ina Ide X-lllA, B Outside X-116B,A Outside X-303A, B, C. D Outside X-1168, A Outside X~l16B 1 A Inside X-311A, B Outelde X-311A, B Outside X-310A, B Outside X-310A, B Outside X-JlOA, B Outside X-l50A, 'J-11/S Outside X-H7 Outelde X-147 Inside.
X-130 Outside X-130*
lnalde X-lOSA Ina Ide X-lOSA Outside X-109 B Outside X-109 B Inside X-303A *. B, C, D Outside X-l'+"I A,P>
Outside X-I 'l"l.A, f3 Inside X-310A, B Outside X-JlOA, B Outside X-303A. B. C, D Outside X-llSA Ina Ide X-115A Outside X-317A Outside X-312 Outside X-J10A Outside X-117 Outside X-117 Outside X-118 Outside X-118 Outside X-123 Outside X-123 lnalde X-124 Outside X-124 lnaldo X-318 Oltslde X-318 Oltslde X-304 Oltslde X-304 Qltslde X-125
- Oltslde X-125, ~- 319 Qltslde X-125 QI ts Ide X-126 )C-30~ <J Oltalde
>< - i.:JJo r-_-
0 0..rr.S.**E X-126,
- 30 L/
Qltslde X-304 1
~JD.J,,
Qltalde X-304, X-J~(p Oltslde
'X-304, X-126 Oltalde X-304, X-126 QI ts Ide X-125, X-.119 Outside X-126 )'.-Jo>t Outside X-119 I Qltslde X-119 Inside X-120 QI ts Ide X-120 lnalde X-121 Oltslde X-121
.0.. -r>>DE Minimum@
Valve Valve
- Cloeure Cl<>atng Nor Type Size Power Signal Rate Sta AO Globe 20 In.
.AC/DC SOL (aprlng.cloae)
B.C.D,P 3-10 aec*(Total)
Clp AO Globe 20 In.
AC/DC SOL (spring closel B,C,D,P 3-10 sec (Total)
~
MO.Globe 2 In.
AC B,C,D.P Standard
. Cl<
MO Globe 2 In.
DC B.C.D,P Standard Clo Check lS lo.
Self Rev. Flow ClP Check lS In.
Self Rev. Flow
~
Solenoid 3/4 In.
AC B,C,D,P
. Standard CIO Solenoid 3/4 In.
AC B,C,D.P Slandard CIO Check 4 In.
Self Rev. Flow o~¥'Eoy~~-o.
Check 4 In.
Set(
Rev. Flow 13"/mTn Of".
Clp MO Gate S In.
AC B,W,Y,E,1..1 MO Gate 8 In.
DC B,W,Y,E,1,.1 23"/mln MO Gate 8 In.
DC B, W, Y,E,1,.1 23"/mln MO Gate 16 In.
AC*
B,U Z6/mln MO Gate Hin.
DC B,U
. 26/mln MO Gate H In.
AC B,U Standard MO Gate H In.
- AC RM Standanl MO Gate 16 In.
AC RM Standard AO Check 16 In.
AC G-
~~~MR.D MO Gate 6 In.
AC G
MO Globe Hin.
AC G
Standard MO Gate H In.
AC G
Standard MO Gate 3 In.
AC G
Standanl MO Gate 16 In.
AC G
Standard MO Gate 2-1/2 In.
AC BJE=
Standard Check 2-1/2 In.
Se!(
Rev. Flow Check 1-1/2 In.
Sel(
Rev. Flow Check 1-1/2 In.
Sell Rev. Flow MO Gate Hin.
AC K
26/mln MO Gate H In.
DC K
28"/mln MO Gate 12 In.
DC K
2S"/mln MO Gate 12 In.
- K 26/mln MO Gate 16 In.
- MO Gate 10 In.
AC RM Standard AO Check 10 In.
AC G
Standard MO Gate 1-1/2 In.
S'(t.11!11 FLDUJ MO Gate 16 In.
DC L
Standard MO Gate 10 In.
AC L
ZS.5'!/mln MO Gate 10 In.
.L 2S.5"/mln
- Stop Check 24 In.
Sell Rev. Flow Check 2 In.
Set(
Rev. Flow Check 4 In.
Set(
Rev. Flow AO Gate 3 In.
AC SOL B,F Standard AO Gate 3 In.
AC SOL B.F Standard AO Gate 3 In.
AC SOL B,F Standard AO Gate 3 In.
AC SOL B,F Standard MO Gate 6 In.
RM Standard Check 6 In.
Sell Rev. Flow!,
MO Gate 6 In.
RM Standard MO Gate 6 In.
RM Standard AO Butterfly. 18 In.
AC SOL B,F Standard AO Gate 2 In.
AC SOL B,F Standard Check 20 In.
Sell Rev. Flow AO Butterfly 20 In.
AC SOL Standard AO Butterfly 18 In.
AC SOL B,F Standard A 0 Butterfly lS In.
AC SOL B,F Standard AO Globe 2 In.
AC SOL B,F S!andard AO Butterfly 18 In AC SOL B,F Standard AO ~-n.EIU'O' °Lii~.
AL ~01..
&,r
$Tlll-'A~ IV)
AO Butterfly
- ~-
AC SOL B,F Standard AO Butterfly f
In~
AC SOL B,F Standard AO Butterfly AC SOL B,F Standard MO Globe I ~tn.
AC B,F
.Standard AO Butterfly 18 In.
AC SOL B,F Standard AO Butterfly 6 In.
AC SOL B,F Standard AO Butterfly 6 In.
AC SOL B,F Standard Hand Gate 3 In.
Hand Hand Globe 3 In.
Hand HandGtP/J.1!-
1 In.
Hand Hand Gate, Pl~!J. I ;.11.*
Hand go Globe l In.
Hand and G-A n=
l In-
.Hand NOTES:
100 aerlea are drywell penetrattona 300 aeries are suppreaalon cha.m.ber*penetrauona
- Standard closing rate Cor MO Globe va.lvea
- 4 tn./mln Standard cloalng rate Cor MO Gate. valvea
- 11 tn./mln
°"
Clc CloC Clet Clo
°""
Clcl Ciel cc~~
Clcl Cle Cl c Cl(
Cit Cl ct Cl ct Cl ct Oi>4
()p4 Cl(
~
cw C1<c Cit; Clct c~,
C!"
~
ClpC Clct
°"
Ct ct oP.;:*tJ a P... H_
of'EM"'
PL4'1~
~
~
<>iii Qi>C CIAC*
Clf*
Cl4 c14 C14 Clf*
Clf*
CIC l?J" C14*
C14*
.C14 Cl4 Cl, Clf*
CIC Cl<
CIC Cl;
- a.
~
~
T Low Reactor Pre11 - Q>en Core Spray and LPCI Va!vea U
Hlgfl Reclrc Line Temp W
His!> Temp Non Regen Heat Exchr O.tlet Y
SIAndby Uquld Control Syot.em Actuated Z
High Radl*Uon. Proceaa RadlaUon. RX Bulldlng Vent E>:bauat RM Remote Manual Switch (control room)
I His!> Cool Wtr Temp from Aw< C. 0.. Pump I
Low f"low Tbroqb C. 0. Filter J
Hip Pnaa no-.tream C. o. Preaa Red Sta
Attachment.a.Sh~e~ ( l ) of 3 Location Valve Line Drywell Ref. to Valve Valve Closure Normal*
Number Isolated Penetration Drywell Type Size Power:
- signal Status 1916-500 Service Water X-119 Ins i.de
- Hand 211
- Closed, Supply Globe 4720 Drywell Pneumatic X-1390 Outside AO l "
AC 8, F Open 4721 Gate So 1.
(Fails Closed) 220-112A CRD to Recirc.
X-1398 Inside Hand 3/4 11 Closed 220-1128 Globe 399-504 CRD to Recirc.
X-1398 Outside Hand Globe 111 Closec9*
399-506 CRD to Recirc.
X-1398 Outside Hand 111 Closed Gate 9205A, 8 Drywell Air X-143 Outside AO l /2 II AC 8, F Open 9206A, 8 Sample Gate So 1.
{Fails 8501-5A, 58 Closed) 8501-3A Drywell Air x-:2 04 Outside AO 111 AC 8, F Open
-38 Sample Gate So 1.
(Fails Closed) 8501-lA Drywell Air X-309A Outside AO l I 2 II AC 8, F
- open
-18 Sample
. Gate So 1.
(Fails Close~
9207A, 8 Drywell Air X-101 Outside AO 111 AC 8, F Open 9208A, 8 Sample Gate So 1.
(Fails Closed) 1501-27A Containment X-150A Outside MO 16 11 AC G
Closed Spray Gate 1501-278 Containment X-145 Outside*
MO 16 11
. AC G
Closed Spray Gate
- Refer to Table 5.2.4
- Sheet ( 2 ) of 3 Location Valve Line Drywell Ref. to Valve Valve Closure No rma.l
- Number Isolated Penetration Drywell Type Size Power Signal Status 2599-28 ACAD *
'X-2048 Outside*
AO l "
AC Drywell Closed Globe So 1.
Pressure (Fa i 1 43L8~
Closed}
2599-238 ACAD X-2048 Outside Check l "
Closed 2599-2A.
ACAD"***
X-202V Outside AO l "
AC Drywell Closed Globe Sol.
Pressure (Fa i 1 43L8.
Closed) 2599-238 ACAD.
X-202V
AC Drywell Closed -
-38 X-3168 Globe Sol.
43L8.
(Fa i 1 Closed) 2599-24A ACAD X-3l6A Outside*
Check l "
Closed
-248 X-3.l 6A 2599-4A AC.AD X-125 Outside AO l "
AC Drywell Closed
-48
.Globe Sol.
Pressure (Fa i 1 43L8.
Closed) 2301-14 HPCI Pump Min.
X-3 lOA Out~ide MO 411 DC System Closed Flow Globe Flow 2301-53 HPCI Pump Min.
X-310A Outside Re 1 i e'f 411 Close.
Flow
- ***Valve 2301-71
. HPC I Cond.
X-312 Outside.
Stop 2"
Closed Drain
-Check 2301-45 HPCI Turbine X-317A Outside Check 24 11 Closed Exhaust.
Valve Number 2301-35 1599-13A 138 13C 130 NPS/vhs 0236a Line Isolated HPCI Pump Suction From Tor.us LPCI Pump Motor Cooling Line Attachment B Sheet ( 3 ) of 3 Location Drywell Ref. t ff Valve Valve Closure Normal Penetration Drywell
- Type Size Power Signal St at.u.s.
X-303A Outside MO.*
16 11 AC L
Closed B
Gate c
D
. X-303A Outside Relief 2"
Closed B
Valve c
D
/*.
J~_).
LI-.,'?:;-'* ** '>
- "~*
Isolation valves are provided on lines pen.etrating the drywell and pressure suppression chamber to assure foteg-rity of the.conta_inment when required during emergency and post-accident periods. Isolation valves which must be closed to assure containment_integrity immediately after a inajor accident are auto-matically controlled by the reactor protection system described in Section 7.
Pipes which penetrate the containment vessel ancl whiCh connect to t11e nuclear steam !!Upply system, arid pipes which open into the free space of containment vessel arc equipped with two isolation valves in series.
As a general rule, one of each pair of isolation valves in series is located inside the containment, the other outside as close to the containment as practical.
On lines which open to the free space of the containment :.1nd have two valves normally closed, the valves are located outside the containment, e.g., vacuum relief fro~1 atmosphere, and suppression chamber
, water makeup lines. Lines. forming-a closed loop inside the containment but which; as a result of pipe fail-ure inside the contained area, may carry radioactive fluids outside arc generally provided with.*one isolation
- valve outside the containment, cithe1; n self-actuating check valve or.:1 remote, manually controlied motor-operaterl valve.
Systems which con.nect to the nuclear steam supply system and may be required to have now after an accident are provided either with. two check valves or a check and. a remote manually controlled valve in series. These are the feedwater, the control rod drive hydraulic, and the standby liquid control systems.
In general, the closure time of all isolation valves is such that the release of fission products to the environment is minimized. The closure times of all valves on lines in systems connecting to the nuclear steam supply system are based ori preventing fuel damage from overheating with no feedwater makeup follow-ing a line break in the particular system. The valve closure time for the main steam line is ba:;ed on the main-steam-line break accident discussed in Section 6. By keeping the valve closure time less than about 10 xcconds, sufficient coolant will remain in the reactor vessel to provide adequate core cooling. The valves
- !~i'
- iii~E!~~~d:e~_s~i:gn~e=d~t~o-~l~~-e _and to be leak-tight during the worst conditions of pressure; temperature n_n_d_~~~m. _
flow following a break in the main s.team line outside the pressure suppression system.
A list of all isolation valves on lines penetrating the _containment vessels an~_their pertinent modes and characteristics is given in Table 5. 2. 4.
On inflowing lines citl1er of two valve arrangements is used. Either both isolatiOn valves in series are self-actuated check valves, one inside and one outside the.containment, or one is a check valve and the other ls a power-operated valve (electric motor or air).
On lines where flow may be in either direction,
I
\\~
,'.""t';
All containn~ent isolation valves, induding their power operators, are designed to operate under the most extreme ambient conditions of pressure, temperature, etc., to which they may be e:\\.-posed after a major accident. All isolation valves in lines connecting to the nuclear steam supply system and all pipe-welclecl connections were fully radiographecl to assure their integrity. They are built to the applicable ASME Codes and all nuclear interpretations applying to. these codes. All power operators on valves inside the containment am a--c and those outside the containment are d-c power-operat~d valves.
~
The reactor building serves as secondary containment, and its ventilation system is provided with twp leak-tight.isolation valves in series in both the supply and exhaust ducts.. These valves automatically close from a signal of high radiation in the reactor building, as described in Section.. 7, Instrumentation and Contr=ol'"".-------------
I
.I I