ML20205F495

Requests Addl Info Re Chapter 10, Auxiliary Sys, of CESSAR-DC Sys 80+.Info Requested by 881230

ML20205F495
Person / Time
Issue date:	10/20/1988
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
PROJECT-675A NUDOCS 8810280075
Download: ML20205F495 (5)

Text

October 20, 1988 p

s Project No.: 675 Hr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 10, AUXILIARY SYSTEMS, CESSAR-DC, SYSTEM 80+, PLANT SYSTEMS BRANCH Our Plant Systems Branch has reviewed Amendment C of Chapter 10 of CESSAR-DC, System 80+ transmitted by your letter dated June 30, 1988 and has identified the need for additional information. The enclosed Request for Additional Information describes the needed information. Our schedule calls for the infonnation to be received by December 30, 1988.

Sincerely, Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III,

!Y, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As rtated cc: See next page

. DISTRIBUTION

Central Filei NRC PDRs FDSNP R/F' GHolahan LRubenstein EHylton GYissing WHouston, RES CFerrel, RES OGC-Rockville EJordan EGrimes ACRS (10>

JCraig JRaval J i' /D g' fp Df4iP-PH-

,P D:PDSNP Gl u L y/ en l

EF if O'l ing:jc Chiller l

10// //88 10////88 10/ic/88

)bFCS ggo g 5 831020 Q[7 b 675A PEC

[{g

j

'o UNITED STATES 8'

",t NUCLEAR REGULATORY COMMISSION t

-l W ASHING TON, D. C. 20655 k.,...**/

October 20, 1988 Project No.: 675 i

Mr. A. E. Scherer, Director I

Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 10 AUXILIARY SYSTEMS, CESSAR-DC, SYSTEtt 80+, PLANT SYSTEMS BRANCH Our Plant Systems Branch has reviewed Amendment C of Chapter 10 of CESSAR-DC, System 80+ transmitted by your letter dated June 30, 1988 and has identified the need for additional information. The enclosed Request for Additional Infomation describes the needed information. Our schedule calls for the information to be received by December 30, 1988.

Sincerely, uyS.y$

g, Project Manager Standa zation and Non-Power l

Reactor Project Directorate Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page J

l l

r

/

Combustion Engineering, Inc.

Project No. 675 Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue, Suite 1310 Bethesda, Maryland 20814 Mr. Ernest Kennedy Manager of Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

j REQUEST FOR ADDITIONAL INFORMATION PLANT SYSTEMS BRANCH COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT DESIGN CERTIFICATION (CESSAR-DC), CE SYSTEM 80+

PROJECT NO. 675 410.17 Provide large size legible copies of Figure 10.4.9-1 Sheets 1 and 2.

(10.4.9) 410.18 Denonstrate that the Emergency Feedwater System (EFWS) is designed (10.4.9) to have sufficient flow capacity to remove decay heat during various i

reactor operations, and to cool the plant to the Shutdown Cooling Systemcut-intemperature,by(G)and(J)ofSectionproviding sumary of analyses supports the design criteria 10.4.9.1.2 of 3

the submittal.

410.19 As stated in Section 10.4.9.3, "all EFW System components are located (10.4.g) in Seismic Cate Are the Emergency Foedwater Storage Tanks (gory I structures...".EFWSTs) also covered and protected from 4

1 environmental hazards by these structures?

If they are, demonstrate that the EFWST failure or leakage will not adversely affect other essential components housed in the same structures.

[

410.20 As described in the submittal, the stean-driven pumps are designed (10.4.9) to provide emergency feedwater in the event of a station blackout.

However, the length of the battery-backed power for the turbine governor speed control and the steam generator (SG) water level is not specified (i.e., designated as "later").

Thus, the length of the i

battery-backed power is to be addressed, and supporting technical information should be provided.

i 410.21 With regard to the EFWSTs, each tank has the storing capacity of 50%

i (10.4.9) of the total volume of emergency feedwater required for plant opera-l tions(about 350,000 gallons).

The two tanks are connected and sep-t arated by a normally locked closed, local manually operated isolation valve. Since the operation of the EFWS is essential to the plant

)

safety, provide the information on the timing of the switchover i

l between the EFWSTs.

Also, justify the lack of automatic swithchover i

j between the tanks.

i 1

410.22 Provide information on the cooling requirements for the motor-driven (10.4.9) EFW pumps, i

410.23 As per design criterion (B), "all components and piping essential to (10.4.9) the emergency function are designed to Seismic Category I require-ments..." However, it is not clear whether or not the turbines for the steam-driven pumps and associated equipment are safety grade.

Clarify the above.

1 410.24 The steam-driven pump turbine exhaust is designed to release directly (10.4.9) to the atmosphere via vent lines through the roof.

Are these exhaust t

lines equipped with devices that can be used to monitor releases of i

j activity to the atmosphere?

I L

- ~.

r j

410.25 The automatic actuation of the EFWS is provided by the Emergency (10.4.9) Feedwater Actuation System (EFAS) or the Alternate Protection System (APS).

Provide the interface requirements for these systems.

410.26 The EFWS reliability analysis is scheduled for a later submittal.

(10.4.9) Demonstrate that the EFWS meets the design criterion (N) of Section 10.4.9.1.2.

In particular, provide detailed information on the analysis, including methodology, scope, model and data used in the reliability assessment of the system.

410.27 Provide information on the Inservice Inspection and Performance Test-(10.4.9) ing Program and associated surveillance testing schedule for the EFWS.

410.28 Verify that the EFWS has capability to detect, collect, and control (10.4.9) system leakage. Also, provide the interface requirements for the Equipment and Floor Drainage System.

410.29 Based on the Generic Letter 88-14. "Instrument Air Supply System (10.4.9) Problem Affecting Safety-Related Equipment," the provision of a safety-grade instrument air supply is highly desirable to minimize the adverse effects of loss of air to safety-related equipment.

The consideration should be given to provide a safety-grade instrument air supply for the EFWS active pneumatic valves (EFWS control valves, steam supply isolation valves and steam supply bypass valves). Also, i

provide the corresponding interface requirements for the safety-grade instrument air system.

410.30 Discuss conformance with the requirements of 10 CFR 50.63, "Loss of i

(9.26, All Alternating Current Power," as related to the support systems 10.3, regarding 1) sufficient amount of water (condensate storage system),

10.4.7,

2) sufficient flow path (condensate and feedwater system), 3) sufficient and flow delivery (EFWS), and 4) capability of operating main steam 10.4.9) supply system atmospheric dump valves either locally or remotely t

to assure that core is cooled by removing decay heat independent of

) referred and onsite emersency ac power in the event of a station

)lackout for the specifiec duration in accordance with the guidance of Regulatory Guide 1.155 " Station Blackout," Positions C 3.2 through C.3.5, as applicable.

410.31 Provide the following information (now shown as "later") in order (5.1.4, to permit the staff to perform an integrated review of the EFWS:

5.4.7 and 1)

Table 10.4.9-4, "Emergency Feedwater System Instrumentation

)

10.4.9) and Control" - Remote Shutdown Station Information 2)

Sections 5.1.4.G.5through5.1.4.G.8(AmendmentB,datedMarch31, 1988) - Interface Requirements for the Nuclear Steam Supply System 3)

Table 5.4.7 Shutdown Cooling Heat Exchanger Data on Shell Side t

d)

Table 5.4.7 Interface Requirements for Component Cooling Water i

i

..