ML20006B530
| ML20006B530 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 01/26/1990 |
| From: | Scaletti D Office of Nuclear Reactor Regulation |
| To: | Marriott P GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9002050031 | |
| Download: ML20006B530 (5) | |
Text
p
^
't'
- 7 x m
a Docket No.lSTN 50-605=
January 26, 1990 L
1
- Patrick W.- Marriott, Manager Licensing & Consulting Services GE Nuclear Energy i
General Electric Company 175-Curtner Avenue I
San Jose, California 95125 1
1
Dear Mr. Marriott:
1 1
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE GENERAL ELECTRIC-q COMPANY APPLICATION FOR CERTIFICATION OF THE ABWR DESIGN-In our-review of your application for certification of.your Advanced Boiling Water Reactor Design, we have identified a need for additional information. Our request for additional information, contained in the enclosure, addresses the areas of SRP Chapter 10 reviewed by the Plant Systems Branch. We request that you provide your responses to this request by February 28, 1990.
If you have any concerns regarding this request please call
{
meon(301)492-1104.
Sincerely, dinoC.Scaletti,ProjectManager Standardization and Life Extension Project Directorate Ok AOO!d $00$$h D
Division of Reactor Projects - III, IV-PDC V and Special Projects A
Office of Nuclear Reactor Regulation
Enclosure:
As stated ~
-DISTRIBUTION:
Doctet File H D. Scaletti ACRS l
NRC~ PDR ~~"#
C. Miller C. McCracken PDSLE Reading T. Chandrasekaran L
- See previous concurrence l
i
- 0FC :*PDSLE:PM-
- "PDSLE:LA
- PDSLE:D l.....:............:...........:......_g@.:___.........:_...........:............:.........
- NAME :DScaletti:sg:PShea
- CMiller DATE-:01/25/90
- 01/25/90
- 01/ 6 /90 0FFICIAL RECORD COPY
. h JtSRmEWs55bt l
+
Enclosure RDQLTCT IM ADDITICNAL INmRMATION 430.59 Provide information on the followirg figures and tables:
(10.1)a.
Figure 10.1-2, Heat Balance for Guaranteed Reactor Rating b.
Figure 10.1-3, Heat Balance for Valve-Wide-Open 4
c.
Table 10.1-1, Summary of Inportant Design Features and Performance Characteristics of the Steam arri Power conversion System, with regard to:
Cordensate punps: total head (ft) and motor hp.
Ioa pressure heaters: Stage pressure (psia) and duty per shell (Btu /hr) for Heater Nos.1, 2, 3, ard 4.
High pressure heaters: Stage pressure (psia) ard duty per shell (Btu /hr) for Heater Nos. 5 and 6.
Iow pressure turbine exhaust pressure to condenser 430.60 Specify the value for tilne "T" in Figure 10.2-2.
~
(10.2) 430.61 Provide a description of the bulk hydrogen storage facility (10.2) mentioned in Section 10.2.2.2.
430.62 Provide a description of the speed control unit, the load control l
(10.2) unit and the flow control unit of the electro-hydraulic control (DiC) system. Your hiption should include how they perform their intended functions. Clarify whether the Dic system will fully eut p
off steam at 103 percent of rated turbirge apaul.
-430.63 For the turbine overspeed protection systaa ( h ibed in Section (10.2) 10.2.2.4), the SSAR referred to redundant electrical trip signals.
Provide information on the power source associated with each of the trip circuits.
430.64 As presented in Section 10.2.2.4 of the AIER SSAR, the closing time i
(10.2) of the extraction nonreturn valves is less than 0.2 secords, while it p
is 2 seconds at current BWR plants. Provide additional information on the design of these valves that supports the difference between the above closirg time values.
i 430.65 Clarify whether at least one main steam stop valve, control valve, (10.2) rohcat step valve ard reheat intercept valve will be irtW, at
- 1..
2-
]
1 approximately 31/3 years by dismantling them, and Whether visual and surface examinations will be conducted for the valve seats, disks-and sters (note that the above is an acceptance criterion for SRP Section 10.2).
430.66 Identify preoperational and startup tests of the turbine generator (10.2) in accordance with Regulatory Guide 1.68,=" Initial Test Freg a.
for Water Cooled Power Plants," as an interface requirement.
430.67 As stated in Section 10.3.2.1, "the four main steam lines are (10.3) cuus:cted to a header upstream of the turbine stop valves...".
However, according to Figure 10.3-2a, the main steam header is located downstream of the turbine stop valves.
Identify whether the -
statement or figure.is in error and revise the item in error so that the SSAR is consistent.
5 430.68 Provide information on the leakage detection system for steam (10.3) leakage from the MSSS in the event of a steam line break. Also provide information on the stated " safety feature designed into the MSSS" that will prevent radiation exposures in excess of the limits of 10 C m Part 100 in the event of a break of a main steam line or any branch line (SSAR Section 10.3.3).
430.69 For the following itens identified in SSAR Figure 10.3-1:
(10.3) h a.
Deaerating steam to condenser b.
Offgas system I
c.
'Airbine gland sealirq system e.
Reheater f.
Main steam bypass Provide the followirq information:
a.
Maxinum steam flow (lbs/hr) b.
Type of shut-off valve (s)
I c.
Size, quality, design code, closure time, actuation mechanism and associated motive power of the valve (s).
430.70 Provide information on the followirg items:
~(10.3)
(a) Analysis for steam hanner and relief valve discharge loads i=m.
(b) Ibwer source to the solenoid valves for the inboard and outboard main steam isolation valves.
(c)
Iocation of seismic interface restraint (e.g., interface of which buildings?)
(d) Route which the main steam lines, incitriing the branch lines, pass up to the turbine stop valves.
-w
- =-, -
m
i.
a.
l.
(e) Specific design features prwided to protect safety-related portions of the main steam supply systan, including the main steam isolation valves, against extemally an$ internally generated missiles and adverse natural phencunena such as floods, hurricanes and tornadoes.
430.71 hibe prwisions for operation of the main oordenser with (10.4.1) leaking condenser tubes.
430.72 Provide the permissible cooling water inleakage rate and the allowed j
(10.4.1) time'of operation with inleakage.
430.73 Prwide information on the following items:
(10.4.1)
(a)
Provisions incorporated into the main oordenser to preclude cwweit or tube failure due to steam blowdown frun the turbine bypass systers.
(b) Worst possible flood level in the applicable buildings due to complete failure of main condenser and provisions for protecting safety-related equipnent located in the M41dhgs against such flooding (note that AS4R SSAR Section 3.4 does not aM e= the turbine building),
i 3
430.74 Discuss how the m vorsits of the main w.%nser evacuation system (10.4.2)
(MCES) conform to the guidelines of Regulatory Guide 1.26, 1.33 ard 1.123 with respect to quality group classification and quality assurance prvpaus.
430.75 Provide the design pressure and normal operational absolute pressure (10.4.2) for the MCES wweits that could contain potentially explosive gas mixtures.
430.76 Identify the radiation monitoring provisions for the mechanical.
(10.4.2) vacuum punp exhaust. Is the exhaust filtered by charcoal ad erbar ard HEP.$ filters prior to release?
430.77 Identify the number, location and functions (i.e., recortling and (10.4.2) annunciatirq alarm) performed by the hydrogen analyzers. Clarify whether they can withstard a hyivymi detonation.
430.78 Clarify whether the air ejectors are redundant in the sense that (10.4.2) one of them is a stan3by.
430.79 Identify the ocmponents ard portions of the MCES that are designed (10.4.2) to withstand a detonation in the system.
430.80 Discuss how the design of the turbine gland sealing system (TGSS)
(10.4.3) conforms to the gnidalines of Regulatory Guide 1.26 as it relates to the quality group classification for the system, ard Regulatory Guide 1.33 and 1.123 as they relate to the quality assurant programs.
430.81 Provide a description of the exhauster blower provided for the 'IGSS.
(10.4.3) t
'+
- w s-w+-
-v-e
r
.l 4
a 8
i
'430.82' AIER SSAR Snhaartion 10.4.3.1.2 states that the 'IGSS exhausts the l
k (10.4.3) norx.udeiE.able gases to the turbine building agii==nt vent systa; however, Snhaetion 10.4.3.3 states that the 'IUSS exhausts the noncondensable <Jaaaa eventually to the main vent. Clarify how the
'IGSS exhausts are acnitored. Also, clarify whether the main vent mentioned above is the plant vent referred to in SSAR Section 11.5.
t 430.83 What is the source for the auxiliary steam? Justify why an advanced (10.4.3) design will use s==antially radioactivity free auxiliary steam (see SSAR Section 10.4.3.2.2) as a backup sealing source rather than i
'as normal' sealing source. Note that the use of a process steam l
supply for sealing purpose can result in significant operational 4
radioactivity relaaaaa.
I 430.84 For the turbine bypass system:
(10.4.4) l l
(a)
Provide figures whict1 delineate the system and its cum auds.
cr
[
(b)
Clarify whether the system includes pressure-reducer assemblies for the bypass valves to reduce steam pressure prior t> steam discharge into the condenser.
430.85 For the circulatirg water system:
I' (10.4.5) l (a)
Describe the function of the watidiux fill and drain subsystem mentioned in AIMR 9ihaa' tion 10.4.$.2.1.
Also, describe th.3
" makeup water" shown in SSAR Figure 10.4-3.
(b)
Provide the worst possible flood levels that can occur in the applicable plant buildirgs as a result of circulating water system failure and indicate how safety-related aqtim =nt l
located in the buildings is protected against such flooding.
t 430.86 How is the remote manual notor-operated shutoff valve (gate valve F 282 powered?
430.87 Describe the design features provided to protect the safety-related portion of the cuderssate and feedwater system frun internally I
generated missiles.
430.88 Provide a sumary of the analysis of a postulated high-energy pipe break for the feedwater piping in the steam tunnel including the design features provided (e.g., pipe whip restraints) for preventing adverse effects resulting frun pipe whip, jet ispirgement arri floodirg.
430.89 Provide information on the analysis that shows that the entire feedwater system piping can an--.-- ^ ate water hamer events and the means to prevent water haminr loads due to hydraulic transients.
403.90 Provide detail information on the feedwater control valve and controller design, including the features that ensure the design will be stable ard carnpatible with the system arx1 imposed operating corditions.
.