6
. _ ' p(w) ' , . - . .. GE Nuclear Energy | . + ama new.c cem . I?5 catw Avve, San Juse Ct W?S MFN No.087 90 - Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission , Washington, D.C. 20555 - ; 1 Attention: Charles L Miller, Director i Standardization and Non Power Reactor Project Directorate Subject: Submittal of Responses to Resolve Safety Evaluation Issues as Requested in . NRC Letter from Dino C. Scaletti, May 1,1990. Reference: 1. . P.W. Marriott to Charles L Miller, same subject, MFN No.' 061-90 ! May 31,1990. 2. P.W. Marriott to Charles L. Miller, same subject, MFN No. 088 90, July 16,1990. ! Enclosed are thirty four (34) copies of GE responses to resolve two additional subject safety evaluation issues for the Advanced Boiling Water Reactor (ABWR), Reference. I provided the majority of the responses. The specific issues covered by this transmittal are: (1) The method of attachment of the level instruments that facilitate the automatic switch - over of the HPCF and RCIC pumps from the CST to the suppression pool. (PDSER Section 9.2.9). 3 (2) Final sizing of the RCW heat exchangers, (PDSER Section 9.2.11). OE believes that the modifications to the ABWR SSAR provided in the attachment will resolve ' these issues. It is intended that GE will amend the SSAR with these responses in a future amendment. Resolution of the final issue pertaining to the remaining portions of the MUWP system that are. j within the scope of the SSAR will be provided by Reference 2. L ' Sincerely, , | , - P.- W. Marriott,- Manager Re ulatory and Analysis Services M 382, (408) 925-6948 F. A. Ross (DOE) | cc: D. C. Scaletti (NRC) D. R. Wilkins (GE) nk J. F. Quirk (GE) Q/ L 9007180280 900713 * PDR ADOCK 05000605 .P PDC --- -

I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

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Page 1: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

. _

'

p(w)'

, . - ...

GE Nuclear Energy |.

+

ama new.c cem .I?5 catw Avve, San Juse Ct W?S

MFN No.087 90-

Docket No. STN 50-605EEN 9041

Document Control DeskU.S. Nuclear Regulatory Commission ,

Washington, D.C. 20555 - ;

1

Attention: Charles L Miller, Director iStandardization and Non Power Reactor Project Directorate

Subject: Submittal of Responses to Resolve Safety Evaluation Issues as Requested in.

NRC Letter from Dino C. Scaletti, May 1,1990.

Reference: 1. . P.W. Marriott to Charles L Miller, same subject, MFN No.' 061-90 !May 31,1990.

2. P.W. Marriott to Charles L. Miller, same subject, MFN No. 088 90,July 16,1990.

! Enclosed are thirty four (34) copies of GE responses to resolve two additional subject safetyevaluation issues for the Advanced Boiling Water Reactor (ABWR), Reference. I provided themajority of the responses. The specific issues covered by this transmittal are:

(1) The method of attachment of the level instruments that facilitate the automatic switch -over of the HPCF and RCIC pumps from the CST to the suppression pool. (PDSERSection 9.2.9). 3

(2) Final sizing of the RCW heat exchangers, (PDSER Section 9.2.11).

OE believes that the modifications to the ABWR SSAR provided in the attachment will resolve' these issues. It is intended that GE will amend the SSAR with these responses in a futureamendment.

Resolution of the final issue pertaining to the remaining portions of the MUWP system that are.j within the scope of the SSAR will be provided by Reference 2.L'

Sincerely, ,|

,- P.- W. Marriott,- ManagerRe ulatory and Analysis ServicesM 382, (408) 925-6948

F. A. Ross (DOE)| cc:D. C. Scaletti (NRC)D. R. Wilkins (GE) nkJ. F. Quirk (GE) Q/

L 9007180280 900713 *

PDR ADOCK 05000605.P PDC

--- -

Page 2: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

_ _. . _ __. _ . . __ __. _ _ _ _ __

L. ., essewriew os: issunO)cABWR

'

wiet sleanAmed Plant arv. n.-

o m. .

P 9.2 WATER SYSTEMS 9.2.9 Makeup Water system (Condensate) 1

9.2.1 Station Service Water System 9.2.9.1 Dwign nues,

The functions normally performed by the (1) The makeup water condensate system (MUWC)station service water system are performed by the shall provide condensate quality water forsystems discussed in Subsection 9.2.11. both normal and emergency operations when i

9.2.2 Closed CoolingWater $ystem(2) The MUWC system shall provide a required

| The functions normally performed by the closed water quality as follows: 1

cooling water system are performed by the systems. S/cm) 10.5 at 25'Cdiscussed in Subsections 9.2,11, 9.2.12, 9.2.13, Conducth -

h and 9.2.14. Chlorides,3 c. (ppm) s 0.02l

pH 5.9 to 8.3 at 25'C9.2.3 DemineralizedWaterMakeup Conducthity and pH limits shall be applied |

System- after correction for dissolved CO . (The !2

above limits shall be met at least 90% ofThe functions normally performed by the demin. the time..)

eralized water makeup system are performed by thesystems discussed in Subsections 9.2.8, 9.2.9 and (3) The MUWC system shall supply water for the |9.2.10. uses shown in Table 9.21.

9.2.4 Potable and SanitaryWater (4) The MUWC system is not safety related.Systems

|(5) The condensate storage tank shall have a-

| Out of ABWR Standard Plant Scope, capacity of 2,110 m3. This capacity wasdetermined by the capacity required by the

9.2.5 Ultimate Heat Sink uses shown in Table 9.2 2.

Out of ABWR Standard Plant scope. See (6) All tanks, piping and other et nipmt at shallSubsection 9.2.17.1 for interface requirements. be made of corrosion resistant materials,

9.2.6 Condensate Storage Facilities (7) The HPCF and RCIC instrumentation,whichand Distribution System initiates the automatic switchover of HPCF ,

and RCIC suction from the CST header to the'

The functions of the storing and distribution suppression pool, shall be designed to . |of condensate are described in Subsection 9.2.9. safety grade requirements (including |

Installation with necessary seismic I

9.2.7 Plant Chilled Water Systems support). %pThe functions of the plant chilled water 9.2.9.2 System Description

system are performed by the systems described inSubsections 9.2.12 and 9.2.13, The MUWC P&ID is shown in Figure 9.2 4 This j

system includes the following: 79.2.8 Makeup Water System (Preparation)

(1) A condensate storage tank (CST) is provid.- Out of ABWR Standard Plant scope. See ed. It is of concrete construction with a

Subsection 9.2.17.2 for interface requirements. stainless steellining. The volume is shownin Table 9.2 3.

(2) The following pumps take suction from theCST:

Amendment 11 9.21

0 . -- _____1 - ~- '

_ _ _ _ _ _ _ _ _ _ _ _ . - 1.1.'

Page 3: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

mogn cm

*i... ;

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,

bA The instrumen?ation~is mounted in'a safety gradeYtandpipe located in the reactor building secondarycontainment. With no condensate flowing, the water level.is*

the same in both tho' CST and-the standpipe - A suitable.,

[ correction will be made for the effect of flow upon water

{ 1evel in'the. standpipe,.

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Page 4: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

E E W o d 0F 1S390 iZ)JABWR _** Standard Plant av a

*

. tant materials. (3) ability to prevent or mitigate the conse.quences of events which could result in ,

(6)' The system shall be designed to prevent any ' potential offsite exposures.radioactive contamination of the purified,

water. The MUWP system is not safety related.However, the systems incorporate features that

9.2.10.2 System Description assure reliable operation over the full range ofnormal plant operations.

Si The MUWP system P&lO is show in Figure 9.2 5. >

l This system includes the following: 9.2.10.4 Tests and inspections

'(1); A purified water storage tank shall be The makeup water purified distribution syster. ;

provided outdoors with adequate freeze is proved operable by its use during normal.protection and adequate diking and other plant operation. Portions of the systemmeans to control spill and leakage. normally closed to flow can be tested to ensure

operability and integrity of the system.(2) Two MUWP forwarding pumps shall take suction -

from the purified water storage tanks. They The air. operated isolation valves are capableshall have a capacity of 308 gpm and a of being tested to assure their operatingdischarge head of 114 psi. Integrity by manual actuation of a switch .;

5located in the control room and by observation_(3) Distribution piping, valves, instruments and of associated position indication lights,

controls shall be provided.Flow to the various systems is balanced by

|: (.1) Any outdoor piping shall be protected from means of manual valves at the individual takeofffreezing. points. ,

(5) All surfaces coming in contact with the 9.2.11 Reactor Building CoolingWater ,

purified water shall be made of corro. Systemsion resistant materials.

L 9.2.11.1 Design Bases(6) All pumps shall be located at an elevation

such that adequate suction head is present- 9.2.11.1.1 Safety Design Bases i

at all levels in the purified water storagetanks. (1) The reactor building cooling water (RCW)

system shall be designed to remove heat fromE -(7) Instruments shall be provided to indicate plant auxiliaries which are required for a| purified water storage tank level in the safe reactor shutdown, as well as those

main control room, auxiliaries whose operation is desiredi .

following a LOCA, but not essential to safe

h| 9.2.103 Safety Evaluation shutdown.

Operation of the MJWP system is not required (2) The RCW system shall be designed to performto assure any of the following conditions: its required cooling functions following a

LOCA, assuming a single active or passive- (1) integrity of the reactor coolant pressure failure.

'

boundary;(3) The safety related portions and valves

(2) capability to shut'down the reactor and isolating the nonsafety related portions ofmaintain it in a safe shutdown condition; or *

Amendment 6 9.23

*__

Page 5: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

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Page 6: I?5 catw Avve, San Juse Ct W?S · I?5 catw Avve, San Juse Ct W?S-MFN No.087 90 Docket No. STN 50-605 EEN 9041 Document Control Desk U.S. Nuclear Regulatory Commission, Washington,

. _ _ _ _ _ . _ . ._ _ _

,

ABM . . 2346ioorn*'.4 L','. Standard Plant, REV D

t'

. TABLE 9.2 4d'-

fy~ '

DESIGN CHARACTERISTICS FOR REACTOR |BUILDING COOLING WATER SYSTEM COMPONENTS '

RCW PumpsRCW (A)/(B) RCW (C)

4840 4- -@Discharge Flow Rate - 5,720 gpm/ pump A,da&gpm/ pump .

Pump Total Head 82 psig 75 psig

iDesign Pressure 200 psig - 200 psig

r:esign Temperature 1580F 1580F

RCW Heat ExchangersRCW (A)/(B) .RQVR

6Capacity J0x10 BTU /h J6ka6B*iU/h68 63

RCW Surge Tanks

(w Capacity - Equal to 30 days of normalleakage

-

,

Design Pressure Static Head

| Design Temperature 1580F f

RCW Chemical Addition Tanks'

,

L Design Pressure 200 'psigi-

- Design Temperature 1580F :.

i?

RCW Piping

Design Pressure 200 psig

Design Temperature 1580F

|>.

||.

Amendment 7 9.219a'

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ . _ J~ '