ML20028A430

From kanterella
Jump to navigation Jump to search
Forwards Response to NUREG-0803, Generic SER Re Integrity of BWR Scram Sys Piping. Issue 61, Scram Sys Piping, Can Be Closed
ML20028A430
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 11/17/1982
From: James Smith
LONG ISLAND LIGHTING CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0803, RTR-NUREG-803 SNRC-792, NUDOCS 8211220141
Download: ML20028A430 (27)
v • d • e


Text

m 4;

_= -,

7-e  ! LONG ISL_AND LIGHTING COM PANY l I SHOREHAM NUCLEAR POWER STATION g g E = mwww=w w,-m. ' P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER. N.Y.11792 Direct Dial Number November 17, 1982 SNRC-792 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NUREG-0803, " Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping" SER Item Number 61 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

References:

(1) SNRC-703 dated 5/13/82 (2) Letter from NRC (A. Schwencer) to LILCO (M. S. Pollock) dated 10/28/82

Dear Mr. Denton:

The reference (1) letter provided LILCO's Shoreham specific response to the issues raised by the staff in NUREG 0803. Based on the staff's review of this information, the reference 2 letter was transmitted to LILCO forwarding nine (9) specific requests for information.

This letter, as supplemented by Attachment 1 thru 6 (forty copies of each are enclosed), presents LILCO's response to these requests as outlined below:

Request No. 1- The systems and equipment that would be used to detect a break in the Scram Discharge Volume (SDV) system consist of both safety related and non-safety related equipment as described in Attachments 1 and 2. Qualifica-tion of the safety-related equipment is discussed in Attachment 1.

Sool 1

8211220141 821117 PDR ADOCK 05000322 PDR g YD FC. 3 9 35.1

6. ,-

November 17, 1982 =

g SNRC-792 -

Page 2 Request No. 2 - A. description on how the control room indications and alarms provided by the qualified detection equipment would be used is included in Attachment 3.

Request No. 3- The SDV environmental profiles (temperature) are included in Attachment 4 for secondary ,

containment nodes. Peak temperatures an4 ,

pressures are listed in Attachment 5, which -

also describes the correlation between nodes '

and zones. Only for zones 2,3,4,7,18,and 20 '

do the peak temperatures exceed. those previously calculated and documented in the

" Environment Qualificati_on Report for Class IE Equipment" for Shoreham Nuclear- Power .

Station - Unit 1. ..

However, required equipment Is qualified',for thepe'> peak temperatures'as described in Attachment 1.

Request No. 4- Equipment essential for SDV failure detection, mitigation and safe shutdown is listed in Attachment 6. The discussion on qualification of this equipment'is included' in Attachment 1. As stated in SNRC-703, major components required for prompt depressuriza-tion are located inside primary containment ,

and are not affected by an SDV break.

1 Request No. 5- A review of.the-various'lcakage paths associated With SDV failures was performed to .N ensure there was n'o impact to safety related s equipment essential for safe shutdown and decay heat removal. This review supported the response encompassed in the SDV analysis submitted via letter-SNRC-703. Considered in the study were gotential wetting eff.ects- (by water up to 212 F) due to spraying,. dripping and/or cascading' water passing-through open hatches, penetrations or stairwells..

s n

w N

wW, *4

  • % g WW 4'

s e

D. %

, . e. .q .

e-

s ;

,- November 17 , 1982-SNRC-792 Page 3 Request No. 6- Equipment needed for detection and mitigation of, and safe shutdown and long-term cooling following a pipe break in the SDV system is presently included in the Shoreham Equipment f Qualification Program and is qualified as.

.s described in Attachment 1. As part of this overall . program justifications for interim j ~ operation have been submitted to the staff Y via Revision 3 and 4 of the " Environmental Qualification Report for Class lE Equipment s for Shoreham Nuclear Power Station - Unit 1",

N which were transmitted by letters SNRC-746 7-z;- dated 8/13/82 and SNRC-768 dated 11/3/82, respectively.

Request No. 7- As noted in ' 9>echment 2, alarm response procedures tready being revised to facilitatt .2gation of this event. LILCO will, however, integrate any future BWR Owners' Group (BWROG) emergency procedure

~ '

guidelines (EPC's) which improve the response to an SDV break, into the Shoreham Emergency Operating Procedures.

A submittal addressing the applicability of the BWROG EPG's with regard to SDV breaks at Shoreham will be transmitted to the staff

- within sixty (60) days after the staff review

,i of the BWROG report, and required modifica-U tions will be implemented in a time frame N/ L consistent with Shoreham operation.

i. -

Request No. 8- Stress analysis for the SDV piping has includeo the SRV and LOCA hydrodynamic loads and thq required load combinations as delineated in the DAR, up to an including Revisich 5.

i

.A o mn i

i k

7 .6

- ,a l y}. .

! November :17 , 1982 SN RC-7 9 2 ,

i Page 4

.,, ,j ' ', ' N ',

,  ; r 6 ,'

Request No. 9 - For small diameter piping (less than 2

. inches nominal size), the piping and supports have been designed for the seismic and LOCA

'{ hydrodynamic load design. In addition, the t actual piping and support installation is in the process of being, verified to assure the validity of the piping analyses. .This task is scheduled . to be completed prior to fuel load. ,

This submittal provides sufficient info'rmation such that Issue No. 61, Scram System Piping, can' > be ' closed on the Shoreham docket. '

y Should you have any questions, please contact this' office.

Very truly yours, f

t

. J. L. Smith

-Manager, Special Projects Shoreham Nuclear Power Station asWG:mp i

i cc: J. Higgins

, All parties t,

4 I

,_,- .,- . . , . - - - . - _ . , , - . - - - - . - . . , , . . . . .- , .. _ , ._,. .. - ,, - _ ,,-.- - ~, - - .- -- - . - -

Attachment 1 SNRC-792

' Qualification of the Equipment Required for Identification and Mitigation of an SDV Break:

In the unlikely event of an SDV break the Reactor Building Area Radiation Alarm would immediately be initiated. This would be followed by initiation of the following safety related alarms:

o Reactor Building Flood Level Alarm, (lGll*LE645 A,B) o Reactor Building Ventilation High Radiation Alarm, (lDll*PNLO68, ID11*PNL126) and, o Reactor Building Differential Pressure Alarm (IT46*PDT043 A,B).

Initiation of these alarms would be sufficient for the operator to identify and take immediate action to n'_tigate the event. The operator would also have additional information from the following sources which are not safety related but would aid in identifying the problem:

o CRD High Temperature Alarm, o CRD Drift Alarm, o Reactor Building Ventilation Isolation Alarm, o Reactor Building Area Radiation Alarm, o Reactor Building Ventilation High Radiation Alarm, o Reactor Building Floor Drain Sump Level Alarm , and

o Personnel Observation of Leakage.

The calculation of environmental conditions in the Reactor Building due to an SDV break assumes that the operator would not

! take any action for 30 minutes after initiation of the event.

Depressurization of the reactor 30 minutes into the event would I result in peak temperatures which are below those previously calculated for high energy line breaks for most zones. The peak temperatures in the SDV break scenario would occur a few seconds after actuation of the ADS to depressurize the reactor.

l

  • Only 1Gll*LE642C is safety related. This level element serves Reactor Building Floor Drain Sump 1Gll-TK-056C, from which the suppression pool leakage return pump draws suction.

i

~.

. Attachment 1 (continued)

SNRC-792 The temperatures would return to the maximum normal within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, which is less than the approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> identified for the limiting break in the " Environmental Qualification Report for Class lE Equipment for Shoreham Nuclear Power Station - Unit 1" (EOR).

The equipment identified in Attachment 6 and located in the Reactor Building either is or will be qualified for the peak SDV break temperatures calculated for its spatial zone.

A review was performed for such equipment which was identified in the EQR Revision 4 either as qualification status "EQ" or as not requiring jt tification for temperature. This review confirmed that the eg.ipment qualification temperature exceeded its zone's peak SDV break temperature in all cases. This review also confirmed that the qualification time period included a segment which e nvelopes the relatively long '(30 minutes) rise to the SDV break .emperature peak.

For equipment for which temperature was identified in EQR Revision 4 as a parameter requiring justification, a similar review will be incorporated into the evaluation described in Section 4 of the EQR.

I l

l l

l l

[

l

Attachment 2 SNRC-792 NON SAFETY ITEMS USABLE FOR SDV FAILURE DETECTION Item Mark Number Description Location 1D21-RE08 Reactor Building Area Radiatic7 RB el 78 Monitor 1D21-PNLO8 R.B. Area Panel RB el 78 ID21-RE09 R.B. Area Rad. Mon. RB el 78 1D21-PNLO9 R.B. Area Panel RB el 78 ID21-RE37 R.B. Area Rad. Mon. RB cl 78 1D21-PNL37 R.B. Area Panel RB el 78 1Cll-TE100 CRD IIigh Temp. Alarm P.C.

IC11-TR100 CRD Temp. Recorder RB el 78 11111-P016 CRD Drift Alarm C.R.

1D11-RE029 R.B. Vent IIigh Rad Alarm R.B. Vent 1Dll-PNLO29 R.B. Vent Panel RB el 100 IG11-LT-255A R.B. Floor Drain Sump Level RB el 8 IG11-LT-255B R.B. Floor Drain Sump Level RB el 8 i

I d

a

a

s. _

Attachment 3 SNRC-792 The Shoreham operators are trained to use all available information to diagnose abnormal events. Thus, their response to an unisolable leak in the secondary containment is not predicated solely upon safety-related detection equipment. Shoreham Alarm Response Procedures for both safety and non-safety related detection equipment have been modified to assure a prompt depressurization. Specifically, response procedures for the Reactor Building Area Radiation Alarm (non-safety related), the Reactor Building Differential Pressure Alarm (safety related),

and the Reactor Building Floor Drain Sump Level Alarm (non-safety related except for 1Gil*LE642C) all refer the operator to the Abnormal Performance Section of the Suppression Pool Leakage Return System Operating Procedure, SP.23.704.04. The Abnormal Performance Section of SP.23.702.04 describes conditions for which a rapid depressurization, in excess of 100 F per hour cocidown, is warranted. Further, it refers the operator to the i

BWR Owners' Group Procedures Level Control, and Cooldown.

The anticipated operator response to the SDV event was delineated in Sections 3.3.6 to 3.3.11 of the Shoreham Evaluation Report Regarding Integirty of Scram System Piping previously submitted.

In these sections all the alarms anticipated for this event were described. Many af these alarms direct that personnel be sent into the Reactor Building to assess the problem. Hence, early personnel observation of the problem is anticipated. Here the emphasis is on how the safety related alarms would contribute to the diagnosis of the event.

Immediately after the postulated scram and SDV failure, the Reactor Building Area Radiation Alarm would be initiated. In response the operators would direct the Health Physics Department to validate the alarm and determine the source. Then, they would refer to the Abnormal Performance Section of SP.23.702.04.

Based upon GE estirates in NEDO-24342, within minutes after event initiation the Reactor Building Ventilation High Radiation Alarm would sound followed within a few seconds by the Reactor Building Differential Pressure Alarm. Since floor drains in the SDV-HCU area would carry most of the leakage to sumps, the Reactor Building Floor Drain Sump Level Alarm would also sound within minutes of the event's initiation. As noted previously the alarm response procedures for the Reactor Building Differential Pressure and Floor Drain Sump Level Alarms refer to the Abnormal Performance Section of SP.23.702.04.

Attachment 3 (continued)

SNPC-792 i Ucing information from the safety-related detection equipment the operator would know that there is a high radiation source in the reactor building and that something is causing the loss of the building's differential pressure. The viable conclusion is that there is a break in a line with high temperature radioactive water, i.e., primary system coolant water outside the primary containment. Therefore, following the directions in

. SP.23.702.04, the operator would initiate a rapid depressuriza-tion and effectively terminate the event.

However, it must be emphasized again that as noted in the previous response several other alarms would be initiated and these would support the conclusions described above. Further, many of the alarm response procedures direct that personnel be sent into the reactor building to assess the problem. Thus, personnel observation of the leakage very shortly after the start of the event is anticipated.

i l

(

O l

[

l

, r . _ . _

..e Attachment 4 s . i.- .-

- .- . ig u

. . r. .\~-

o x

o e

M Q

U

{

h w :

- 5a .=.

o. -=

- w oz-

+ -

was e to w

. f _

rua u N ee N m wm

-c.

1 - a con 2 3 a o .-

u o e ..

O u g 25n:

\ -- W ncdas

- m f -

w r

~

a b

i

~

l

~

1 o

023 012 003 061 081 061 091 O S I O t l O C'l 021 011 001 -

l l u 030) aanisasawai l

l -

l usa a r m x m ---- - - _ _ _ _ .

4 8 e e e= , e' ,

e .

_f * ,

9 0

  • Oe  % . e

. . .:be fj t.bs

- % . v .

W O

~

l I me em Re 99 NG W

9 u"

u E

E e

\

M U >

O =

- y:

y -

a a

o -1 e

- - W I

t 0- - o MO z$

e n-g *s 2: Nun

~

y m W N af O ne2=='

w OE

- O Ow==

k l Z x s ta O

\- - w mm.

5 2-

~ .

. l

  • H .

O

~

l .

pub O

um W

e e e

O O

I m OZZ O12 003 0610910L10910S10t10E1031011001 (d 0301 3801883dW31 9

8 e

v et

. .e .

e e

e 1k00. 7;  :,:

.  ?

Y 14D pp IIB MB IIIB se G

e

=

u

=

,, E .,

u

'. O

.~ y* -

a Y g u,s m o5 ce n w h T. N " r.

\- -

~

m MME.-

.- o .

. O O W$.

2 rson Q E

\\ _

~

l3 tu w

men

\ l e

w w-N

. \. _ =

~ .,

~

O

.-n._*

\ -

MG sum sus I'W pup e

O O

e 023 013 003 061091 OLI 091 OSI Ott OEI 031011 Odl (J 030) 3801883dW31 9

9 b

.,y_,g .

mw' ' rP r- s-

(- ~

. . . r1 %,

-l--

L:V2 .

o o-

'/l r.

=

u e

, y.

o

\ ' ~

E ="

- S .

o :

- g2

- > =

/

Ez-:

1 E S!2:

_ zw a

- u~--

g W ==0a

=Oa-(

_ a z

o ne.

I o n..

& e .

\ s I(s h N "o-u w

g ggy n e--

s @

x N -

{ _

w r

+ .

\ N s ,

o

- x ,

\ o 033 013 003 06108' OLI 091 OSI Os t OEI 031 011 001 s

tJ 030) 3801883dW31 s

_A v #%N W_W* , ,,A.- *

,7" ' . . .

P .

1 3**

b: q, g - -.s.

o

( k

  • 5 h~ a 5:

, \ 3 gi C \ yj w t:

ex-N ( /_

= a5 a: m w

- E N"

- uu.

@ we=

= O 5.

- o Z

e ns-o c .t:

e ec .

\ o o

U voz;o.g x

M K ri a 1 .

w w

r i

~

"O

_~

O o

i 0 3 3 0 1 3 0 0 3 0 6'l 0 8 1 O L I 0 9 1 O S I O i l O E I 031 011 001 (d 030) 3801883dW31 l

1 l

I I

e

V...:

1 l

, I I

e 1 s .3 N

O I

J m.

  • RE e
  • um 1

1 E 1

E .

M U a.

- O .

( \

- g:

\a s o

a .I.

.- - o ;

- W E o z-r c

emwo5

< T. NG e U N ec O o e

- o o wn-Z aAU w O c z.

O U $ gpg

- tu o mag 1

- VJ

  • e E

, . ~

B.

O

~

W .

I -

e e

W D

O

~

. ,. m . . .

OB3 013 003 0610810610910S10tI DE1031011001 I

J (d 030) 3801883dW31 l

l =

s b

f ,*.

o 3

. :. h 's O C 2. U3!01 & '0 o

~

x u

  • G".

E M U I o -

N w N -

E a -

- o

_ > _=

w o z-m cc n -

as e

rua a N a:

W m oe

-. c a

/. o z a n:

T c.-

. o e

= =,-

o a -

- w ME!!

w g

r

_ ~

~ -

o O

o 0 3 3 0 1 3 0 0 3 0 6 1 0 8 1 O t. 1 0 9'l O S I O t l O E I 031 011 001 r (3 030) 3801883dW31 i

W-

-~-~ s '"W 4 , 6. - -in- _.m . , _ , _

r l

PEAK PRESSURES AND TEMPERATURES FOR SDV BREAK CORRESPONDING NODE ZONE NIDGER PRESSURE TIME TEMPERATURE TIME NUMBER (AS DEFINED IN EQR) (PSIA) (SEC) (DEG F) (SEC) 1 1 15 54 185.460 1h6.69 213h.000 2 2 15.52 185.399 159.61 1986.000 3 3 15.52 185.389 159.45 2061 500 4 h 15.52 185.39h 161 90 2089 500

  • 5 5 15.52 185.411 166.55 2074.000 6 6 15.52 185.h02 166.62 2037 500 7 7 15 52 185.396 179 70 1966.500 '

8 8 15.51 185.416 139.23 114.200 9 9 15.50 185.376 154.46 1957 500 10 10 15.50 185 364 1h9 91 1926.500 11 11 15.50 185.368 180.00 1943.000 12 12 15 50 185.382 169 20 2061.500 13 15 15.h9 185 350 152 36 2170.000 14 16 15.h9 185 341 137.05 2300 500 15 18 15.47 185.32h 152.19 2225.500 16 19 15.47 185.323 137,65 2300.500 17 20 15.45 185 315 317.81 2300 500

18) 15.53 185.L2h 161.63 2053 500
19) 2 15.53 185.h05 159.61 2005 500
20) 15,53 185.41h 163.1h 2009 500 21 1 15.54 185.h32 1h6.43 2242.000 8

ii a

.+

1 u

Atttchment-6 e

..~ ,

SNRC-792 EQUIFvEIT ESSEiTIAL FOR SDV FAILURE DI.TECTICN AND MITIGATICN AND SAFE SHUTD0'44 NUREG-0588 Ecuicsent Item No. Description Location Operability Code 1321*ACV0dlA M.S. Line A H-08 A 1321*A07C813 M.S. Line S H-08 A 1321*A07081C M.S. Line C H-C8 A 1321'A0V081D M.S. Line D H-08 A 1321*A07082A M.S. Line A H-08 A 1321*ACVG23 M.S. Line B H-08 A 1321'A07:32C M.S. Line C H-08 A 13214A0VC32] M.S. Line D H-08 A 1321* LITCC7A Fuel Zone G-09 A 1321"LITCC73 Fuel Zone G-ll A 1321* LT154.A Reae.Lvl Trips G-10 A 1321*LT1543 Rese.Lvl Trips G-10 A 1321* LT154C Reac.Lvl Trips G-12 A 1321* LT15!.D Rene.Lvl Trips G-12 A

, 1321* LT155A *'ide a Range G-10 A id21'LT1553 Wide Range G-10 A

1321*IT;55C *~ide

- Range G-12 A -

1321'LT155D Wide Range G-10 A 13215LT157A Reae.Lvl Trips G+10 A 1321'LT1573 Reac.Lvl Trips G-12 A 1321* LT157C Reac.Lvl Trips G-10 A 1321* LT157D Reae.Lvl Trip.s G-12 A 1321*LT159A Auto Depressur. G-10 A 1321* LT1.593 .

Auto Depressur. H-12 A 1921'Pr004A Reactor Fressure G-10 A l

l

1921*FIC04B Reactor Pressure G-10 A 1821*Pr153A RVO92A Monitor G-Ol A RV0923 Mcnitor G-01 A 1921*PT1533 RV092C Monitor G-01 A 1B21* PT153C RV092D Monitor G-01 A 1321*Prl53D 1B21*SCV81AX 1821*ACVC81A Ctrl D-22 A 1E21*ACV081A Ctrl D-22 A 1B21*SCV81AY 1321*SCV81AZ 1B21*ACVC81A Ctrl D-22 A 1321*SCV81BX 1321*ACVC813 ftn2 . . D-?Oy A 1321*SOV813Y 1B21*ACV0813 Ctrl D-22 A 1321*SGV813Z 1321*ACV0813 Ctrl D-22 A Lb21*SOV81CX 1321*ACVCSIC Ctrl D-22 A 1921*SCV81CY 1B21*ACV081C Ctrl D-22 A 1321*SCV81CZ 1821*ACVC81C Ctrl D-22 A IS21*SOV81DX 1321*ACVC31D Ctrl D-22 A 1821*SOV81DY 1821*A07081D Ctrl D-22 A 1B21*SOV8102 1B21*A0V081D Ctrl D-22 A 1B21*SOV82AX 1321*A0VOS2A Ctrl T-08 A 1321*SOV82AY 1921*A0VC82A Ctrl T-08 A 1321*SCV82AZ 1321*A07082A Ctrl T-03 A 1321*S07823X 1821*A0VC82B Ctrl T-08 A 1321*SCVd23Y 1921*ACV082S Ctrl T-08 A 1821*SOV823Z 1321*ACVC82B Ctrl T-08 A 1B21*SOV82CX 1321*ACVC32C Ctrl T-08 A 1921*SCV820Y 1321*A0VC82C Ctrl T-08 A 1B21*SCV82CZ 1321*ACVC82C Ctrl T-08 A 1321*SOV82DX 1321*A0VC82D Ctrl T-08 A 1321*SOV82DY 1B21* A0VC82D Ctrl T-08 A 1B2l'SOV82DZ 1921*ACVC82D Ctrl T-08 A IB21*SCV92AX ADS VLV 1321*RV- B-22 A 92A SOV A 1321*SOV92AY ADS VLV 1921*RV- 3-22 A 92A SCV B 1321*S0V923X ADS VLV 1321*RV- B-22 A 923 SCV A 1321*SOV923Y ADS VLV 1321*RV . B-22 A 928 SCV B

1321*SCV922X ADS VLV 1821*RV-92E SCV A B-22 A IB21*SC-V92EY ADS VLV IB21*RV-92E SOV B B-22 A 1821*SOV92HX ADS VLV 1821*RV-92H SCV A B-22 A 1521*SOV92.T! ADS VLV 1321*RV-92H SOV B B-22 A 1321*SOV92JX ADS VLV 1321*RV-92J SCV A B-22 A 1321'SOV92JY ADS VLV 1321*RV-92J SOV B B-22 A 1821*SCV92KX ADS VLV 1821'RV-92E SCV A B-22 A 1321*SCV92KY ADS VLV 1821*RV-92X SOV B B-22 A 1921*SOV92LX ADS VLV 1821*RV-92L SCV A B-22 A 1321*SCV92LY ADS VLV 1321*RV-92L SCV B B-22 A 1B21'SCV313A SAMPLE PP SUPPRESS FOOL EETURN d-09 A 1921*SCV3133 SAMPLE PP SUFFRESS PCOL RETURN G-09 -A 1D11'FN' l 68 R.B. STA. VDT PAD ALARM TB D

'1D11*FNL126 R.B. STA. VENT RAD ALARM TB D

1E11'FTC01A RHR MAL'i FLOW G-01 A 1E11*FTC01B RER MAIN FLOW G-01 A 1E11'MCV034A RHR HX SHELL BYPASS G-01 A 1E11*MCV0345 RER HX SHELL BYPASS G-01 A 1E11*MOV036A RHR CUTBOARD VV G-03 A 1E11*MOV0368 RHR CUTBOARD VV G-07 A

)

RHR CUTBOARD VV G-03 A 1E11*MCV037A RHR 00TBCARD VV G-07 A 1E11*MC70373 RHR FLCV TO SUPP PCOL G-03 A 1 Ell *MOV040A RER FLC'4 TO SUPP PCOL G-CT7 A 1E11*MC704C3 1

1 Ell *MOV045A R'IR PP MIN FID'd BYPASS G-Ol A RHR PP MIN FLOW BYPASS G-01 A 1 Ell *M070453 1EllaPol4A RER PUMP G-01 A RHR PUMP G-01 A 1E11*P0143 G-01 A 1E11*P014C RHR PUMP RHR PUMP G-01 A 1E11*P014D VALVE DITERLOCE G-01 A 1 Ell *PLSC01A 4

lEll*?DSC013 VALVE INTERLCCE G-01 A lE11*PNS031A POS SH CN 1 Ell'MOV031A G-01 A G-01 A 1 Ell *RiSO31B PCS SV ON 1E11*MOV0313 POS S*4 CN lE11*MCV031C G-01 A 1E11*FNS031C lEll*RiS031D PCS S'a' CN 1 Ell *MOY031D G-01 A POS SW C?i 1 Ell'MOV032A G-Ol A 1E11*RiS032A POS SV CN 1 Ell *MOV032B G-01 A j lEll'HIS0323 POS SV CN lEll'MOV032C G-01 A 1E11*PNS0320 POS SW CN lE11*MOV032D G-01 A 1E11*PNS032D POS SV CN 1 Ell'MOV037A G-03 A 1EllaRIS037A G-03 A 1 Ell *RIS0373 POS SV CN lE11*MOV0373 G-03 A 1E11*PNSO40A PCS SW CN 1E11*MOV040A 1 Ell *PNSO403 FCS SW CN 1 Ell'MOVC403 G-07 A D-22 A 1Ella RISO47 1 Ell'MOV047 PCSITICN SV G-03 A 1 Ell *PNSO48 1 Ell *MOV048 POSITICN SV lEll*RISC61A ON 1E11*A0VC61A G-01 A RER PUMP DISCHARGE G-01 A 1 Ell *PS134A G-01 A 1 Ell *PS1343 RER PUMP DISCHA".GE G-01 A 1E11*PS134C RER PUMP DISCHARGE G-01 A 1 Ell *PS134D RER PUMP DISCHARGE lEll*PS135A RER PUMP *:ISCHARGE G-Ol A RHR PUMP DISCFARGE G-01 A lEll*PS1353 1E11*PS135C RER PUM? DISCHARGE G-01 A lE11*PS135D RHR PUMP DISCHARGE G-01 A 9

1Gll*LE645A react BLD FLOOD LEVEL G-01 A 1G11*LE645B REACT BLD FLGOD LEVEL G-01 A 1H21*RiL15 MAIN STEAM FLCW RACK A G-01 A IH21*FNLl6 CS/HPCI LEAK DET I RK G-01 A 1H21* PNL17 RCIC INST RACK G-01 A 1H21*RIL18 RHR INST RK CH A G-01 A 1H21*PNL19 CORE SPRAY RK CH B G-01 A 1H21' PNL21 RER INST RK C4 B G-01 A 1H21*RiL22 RECIRC PUMP B RACK L-02 A IH21*RiL26 RV LEVEL & PRESS INST H-12 A 1H21*R!L35 CS/RCIC LEAK DET RK B L-02 A 1H21*RiL36 HPCI LEAK OET RK B G-01 A 1H21*PNL37 RCIC LEAK LET RK A G-01 A 1H21*PNL38 RCIC LEAK DET RK B L-02 A 1P41*MCV034A RER HX E-34A DISCH G-01 A 1P/.l*MOV034B RHR HX E-34B DISCH G-01 A.

1P50*MCV114A COMPA SVCE EMERG SPLY VV D-22 A 1P50*MOV114B CCM?A SVCE EMER SPLY VV D-22 A 1P50*PS113A SERV AIR HER A NCRM SUP H-18 A I?50*PS1133 SERV AIR HER B NCRM SUP H-18 A 1P50*P"116A SERVICE AIR HEACER A H-18 A IP50*PT1163 SERVICE AIR HEADER B H-18 A 1R24*MCC111V MOTOR CO!T?.0L CDiTER N-21 A

l

~

1R24*MCC111% Mor0R CQ! TROL CEiTE-LCP1 N-21 A 1R24*MCCll2W MOTOR CC:iTROL CEiTE N-21 A 1R24*MCC112Y MOTCR CCNTRCL CEiTER-LCPI N-21 A 1R24*M::Clll2 MOTOR CCNIROL CEiTEP.-EER N-21 A i

1R24*MCClll3 MOICR CONTROL CEiTE-EMER N-21 A 1R24*MCC1122 MOTOR CCNTRCL CE;TER-EER N-21 A 1R24*MCC1123 MCTCR CCNTRCL CE!TER-EMER N-21 A 1P24*MCCll28 MOTOR CCNTROL CENTE-EER N-21 A 1R245M001131 MOTOR CONTROL CEITE-EER N-21 A 1R24*MG111 480V MOTOR GD;EATCH (RED) N-21 A 1R24*MG112 4807 MorCR GETEATCR (SLUE) N-21 A 1P24*MGll3A 4807 MorCR GEiERATCR (CRANCE) N-21 A 1R24*MG1133 4BCV MOTOR GDIERATOR (CRANGE) N-21 A l 1R24* PNL-31 SP.EAXE DIST PNL (BLUI) N-21 A

! 1R24* F!!L-R1 BREA ER DIST PNL (RED) N-21 A 1R24' P';L-R2 3REAKER DIST RiL (RED) N-21 A a=-- .

l 1R24* PNL111 H-G 327 CCNTROL CABINET N-21 A l 1R24* RiLil2 H-G SET CONTROL CABINET N-21 A l

j iP24* PNL113 A H-G SET CCNTROL CABINET N-21 A 1R24 *PNL1133 H-G SET CONTRCL CASINET N-21 A IP24*TRSil1X 430V AUTO TRANSFER SWITCH N-21 A 1P24*TRSil2Y 480V AUTO TPs'uNSFER SWITCH N-21 A l 1R31*NFM02 POWER CABLE ALL A 1331*NFN03 PVR CABLES ALL A 1R32*NFPO44 INST CABLE ALL A 1R32*NFP-63 INST CABLE ALL A 1R32*NFF010 INST CABLE ALL A l

l t

l

(

\ .'. .

1R32'NFP097 INST CABLE ALL A 1R32*NF?C20 INST CABLE ALL A 1R3 5' mil-22 12CVAC DIST FNL REAC BLDG N-21 A DER 120V FUL 01-REL RM RR D 133 5* PNL-01 l

1R35'FNL-R2 1207AC DIST FNL REAC BLEG N-21 A 1335+T-22 480-120/240V TRriS N-21 A 1R35*T-B2 480-120/240V IRANS N-21 A 1R42*MCCCA2 125VDC MMCR CCNT CDITER N-21 A 1R42*MCCCB1 125VDC XOTOR CCNT CDiTER N-21 A IT46'AOD040A P3 REFUEL LEVEL EXHAUST H-18 A IT46'AOD040B RB REFUEL LEVEL EI4AUST H-18 A IT46*AC0041A RB PCI CCfiTMI 4.REA EXH K-15 A 1746'ACD0413 RB PCT CONTAM ARIA EI4 K-15 A IT46*AGV035A P3 AIR EXHAUST G-01 A IT46*ACVC353 RB AIR EXHAUST G-01 A IT46'ACV037A RB DISCHARGE ISOLATICN H-12 A i

1746*A07037B RB DISCHARGE ISOLATICN H-12 A

1746*FLT01A FILTER TP.ADI REHEAT CCIL P3SVS K-15 A IT46'FLT01B FILTER T?.AIN REHEAT COIL P3SYS K-15 A IT46"FNC03A RBSVS EXH FMI K-15 A IT46*RiCO3B RBSVS ZI4 FAN K-15 A IT46*FNCO3C P35VS EIi FAN K-15 A 1746*FN07 ?A RB EXHAUST BCCSTER FAN E-15 A 1T46*FNC79B RB EI4AUST BCCSTER FAN K-15 A IT46*FN333A 1T46*UC-002A FAN G-01 A IT46*FN8333 IT465UC-0023 FMi G-01 A IT46*FN834A 1T46*UC-003A FAN G-Ol A

. . . . . . . __ ~ . - . . . . - . . . . - . .

1T46'Hi334B 1T46*UC-003B FAN ,

G-01 A IT46* FN335 A 17465UC-004A FAN H-20 A 1T46*FN835B 1T465UC-004B FAN H-20 A IT46*FN836A 1T46*UC-005A FAN H-20 A 1746'Mi836B 1T46"UC-005B FAN H-20 A IT46*FN837A IT468UC-020A FAN J-16 A IT46*FN8378 1T46*UC-0203 FAN K-15 A IT46*FN838A IT465UC-021A FAN H-19 A IT46*FN3385 1T465UC-021B FAN H-19 A l?46*FN839A IT46*UC-022A FAN H-19 A IT46' nib 393 1T46*UC-0223 FAN H-19 A IT46"FT004A RSSVS EXH AIR FLCV H-18 'A lI46*FTCC43 RBSYS F19 AIR FLCW H-18 A 1T46* MOD 031A RSSVS INLE TO MIXED PLEI K-15 A 1746*M00031B RESVS IKLE TO MIXED PLSI K-15 A IT46' MOD 034A ESSVS FILTER TRAIN DISCH H-20 A IT46* MOD 0343 RBSVS FILTER TRAIN DISCH H-20 A IT46*MCD036A MO: DAMPER FCR FN 1T46*FN-CO3A K-15 A 1T46* MOD 0363 MCP DAMPER FOR FN 1746*FN-C033 K-15 A 1746* MOD 036C M0r DAMPER FCR FN IT46*FN-003C K-15 A IT46* MOD 047A FN-79A DISCHARGE AIR K-15 A 1T46*MODC47B Mi-79B DISCHARGE AIR K-15 A IT46*MCDC43A FLT 1A K-15 A 1T46*MOC0433 FLT la K-15 A IT46*PDT003A FLT-1A DIFF PRESSURE K-15 A IT46*PDIC033 FLT-1B DIFF PRESSURE K-15 A 1T46* PUr043 A REACTCR BLDG DIFF H-20 A 1T46'PDT0433 REACTCR SLOG DIFF H-20 A IT46*PN3031A POSITICN CN MCDO31A K-15 A 1T46*PNS0313 POSITION CN MCD0313 K-15 A IT46*PNS034A POSITION CN MOD 034A H-20 A IT46*PNS0343 POSITICN CN MCD034B H-20 A

- - . . - - . - -- a n -

)

G-Ol 'A I 1T46? PNS035A ' RBSVS INITIATICI SIGNAL RBSYS ElITIATICN SIGNAL G-01 A IT46*FN'S0353 RUSVS INITIATICN SIGNAL H-12 A 1T46* F:XS037A RBSYS INITIATICN SIGNAL H-12 A IT46*FUS0373 _

POSITICN Qi A0D040A H-18 A IT46*FNSO40A POSITICN CN A0D040B H-18 IT46*FNSO408 POSITICN CN A0DC41A K-15 A' 1T46* PISO41A' POSITICN CN A00C41B K-15 A 1T46* F!!SO41B 1Tt.6* OV035A OPERATES ACV035A G-01 A 1T46*SOV0353 OPERATES ^A0V035B G-01 A 1T46*S0V037A OPERATES A0V 037A G-01 A IT46*SOV0378 G-01 A OPERATES A0V037B . . . . . - .

1T46*SOV040A 0FERATES ACD040A H-18 A

[ H-18 A IT46*SOV040B OPERATES A0E04CD OPERATES ACD041A T,-15 A

1T46*S0V041A OPERATES A0D041B K-15 A

. 1T46*SOV041B i

i l

f

, , _ , _ - . , , _ . . , , _ . , , -- ,a -,- - . - ,

--n , ---,--_ , _ , , , , , , , , - - - , ,,, , , , -

, ,,. 4 _ _ _ _ . _ _ .

. _ lo _

1T46*TCV022A RB STANEBY VDiT UC 2A b-01 A 1746*TCV022B RB STMiDBY VEIT UC 2B G-01 A IT46*TCV023A RB STMIDBY VDIT UC JA G-01 A 1746*TCV023B RB STANDBY VDIT UC 3B G-02 A 1746*TCV024A RB STANCBY VDIT UC-4A H-20 A IT46*TCV0245 RB STANDBY VDiT UC-4B H-20 A IT46*TCV025A RB STANDBY VDIT UC-5A H-20 A IT46*TCV025B RB STANDBY VUIT UC-5B H-20 A IT46*TCV026A RB STANDBY BEIT UC-6A K-15 A IT46*TCV026B RB STANDBY VDIT UC-6B K-15 A IT46*TCVC28A MCC RH UNIT CCOIE N-16 A 1T46*TCVC28B MCC RM UNIT CCOI23 K-15 A IT465ICVC59A UC-21A UNIT CI2AR H-19 A IT46*TCV059B UC-21B UNIT CIJAR H-19 A IT46*TCVC60A UC-22A UNIT CIIAP. H-19 A IT46*TCV060B UC-223 UNIT CIIAR H-19 A IT46*TE001A RBSVS RECIRC AIR TEMP K-15 -

A 1T46*TE0018 RBSVS RECIRC AIR TEMP K-15 A 1746*TEC22A AIR RETUPli TO UC-2A 0-01 A IT46*TE0223 AIR RETURN TO UC-2B s G-01 A 1T/.6*TEC23A AIR BETURN TO UC-3A G-01 A IT46*TE023B AIR FITURN TO UC-3B G-02 A IT46*TE024A AIR RETUPE TO UC-4A H-20 A 1T46*TE024B AIR RETURN TO UC-4B H-20 A 1T46*TE025A AIR RETURN TO UC-5A H-20 A IT46*TE025B AIR RETURN TO UC-5B H-20 A IT46*TEC28A MCC RM UNIT CCOIIR H-16 A 1746*TE028B MCC RM UNIT C00I2R J-15 A IT46*TE059A UC-21A UNIT CI2AR H-19 A IT46*TE059B UC-21B UNIT CI2AR H-19 A ITM*TeC6CA UC-22A UNIT CI2AR H-19 A IT46*TE060B UC-22B UNIT CIZAR H-19 A

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20028A430&oldid=2494315"