ML20070U610
| ML20070U610 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 04/01/1991 |
| From: | Marriott P GENERAL ELECTRIC CO. |
| To: | Chris Miller NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| EEN-9122, MFN-034-91, MFN-34-91, NUDOCS 9104090190 | |
| Download: ML20070U610 (5) | |
Text
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i GE NucIcer Encryy April 1,1991 MFN No. 034 91 Docket No. STN 50 605 EEN 9122 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Charles L Miller, Director Standardization and Non. Power Reactor Project Directorate Sulject:
GC Responses to Discussion items of March 29, 1991, GE/NRC Perfermance & Quality Evaluation liranch Conference Call Enclosed are thirty four (34) copies of the GE response to the sulicet discussion items.
It is intended that GE will amend the SSAR, where appropriate, with this response in a future amendment.
Sincerely, 0
/W \\
P. %
arriott, Manager Regulatory and Analysis Services M/C 382, (408) 925 6948 cc: F. A, Ross (DOE)
D. C. Scaletti (NRC)
J. G. Spraul (NRC)
D. R. Wilkins (GE)
J. F. Quirk (GE) l
- emnua, A
Gr RESPONSES TO MARCH 29, 1991 CONFERENCE CALL WITH NRC PERFORMANCE & QUALITY EVALVATION BRANCH DISCUSSION ITEM 1 The response to Question 260.4(4) is acceptable except that it appears that items V3.7, Cables and U3.8, Sprinklers (p.3.2 30) in Table 3.2-1 should have note t.
RESPONSE 1 Items U3.7 and U3.8 will have note "t" added as on page 3.2 30 attached.
DISCUSSION ITEM 2 The response to Question 260.4(5) is acceptable except that it appears that the radioactive drain transfer system items not safety-related (p.
3 ?-21, System Kl) should have note p.
RESPONSE 2 Items Kl.1, Kl.2 and Kl.4 will havc note "p" added as on page 3.2-21 at-tached.
DISCUSSION ITEM 3 The response to Question 260.4(6) states that the SPDS is part cf "the procer,s computer system, item C12 on Table 3.2-1."
However, the response lette-includes page 3.2-13 which shows principal components in order of C5, Remote Shutdown System; C6.
Reactor Protection System; then 01, Process Radiation Monitoring System.
Clarify the reference to "the process computer system item :2 on lable 3.21."
RESPONSE 3 The reference to "the process computer system", is item C7 on page 3.2-13 a t t a t.h ed.
(The reference to item Cl2 was incorrect in the response letter.)
DISCUS $10N ITEM 4 The response to Question 260.4(8) indicates that no other ABWR plant items have been identified which require rovisions beyond normal industry practice, in the area of civil structures, it appears that the radwaste building, the firewater pump house, the ultimate heat sink pump house, and the power cycle heat sink pump house should be identified under System V4 in Table 3.2-1.
RESPONSE 4 The radwaste building will be added to the civil structures as on page 3.2-30 attached.
The firewater, power cycle heat sink, and ultimate heat sink pump houses are not in the scope of the ABWR standard plant.
F:jnfl040ll:tjm
-ABWR mame RfV D Standard Plant TABLE 3.21 CLASSIFICATION
SUMMARY
(Continued)
Quality Group Quality Safety Loca.
Classi.
Assurance Seismic Princloal Comnonenta gggb ge ficationd Reaulrement' Catenorvf D'Etu C5 Remote Shutdon System Components of this system are included under B2, E1, E4, G3, H2, and P2.
1.
Electrical modules with 3
C,5C,RZ, -
B 1
safety related function X
B I
2.
Cable with safety related 3
RZ function C6 Reactor Protection System B
1 1.
Electrical modules with 3
SC,X,T, safety related function RZ B
1 2.
Cable with safety 3
SC,X,T, related functions RZ (u)
E 3.
Electrical Modules, other N
T,X
.A (u)
E N
T,X 4 Cable other I
c1 r;;ogn,uyg{ef r c!"oes e
n x
DI Process bdiation Mo61toring System (includes gaseous and liquid amuent monitoring) 1.
Electricalmodules with 3
SC,X,RZ -
B with safety related functions (includes monitors) 2.
Cable with sahy related 3
SC,X,RZ --
B 1
funClions (u) 3.
Electrical Modules, other N
T,5C,RZ, E
X,W (u) 4.
Cable, other N
T,SC,RZ, -
E X,W 3143 Amendment
i MN 21A610:AE Standard Plant m,n TABLE 3.21 CLASSIFICATION StBDIARY (Continued)
Quallry Group Quality Safety Loca.
Classt.
Assurance Seismic Prineinal Comnonenta g'b ge
[leationd Reautremente Catenonf h
H1 Main Control Room Panel B/E 1/-
(aa) i 1.
Panels 3/N X
n B
I 2,
Electrical Modules with 3-X
~
safery related function B
1 3.
Cable with safety related 3
X function g
E 4.
Other mechanical and N
X electrical roodules H2 Local Control Panels (aa)
{
B/E 1.-
Panels or Racks 3/N C,5C,X
~
B I
2.
Electrical modules with 3
C,5C,X safety related function B
1 3.
Cable with safety related 3
C,5C,X, function l-E
- 4. 'Other mechanical and N
C.SC,X electrical modules K1 Radioacthe Drain Transfer System n
( P) -
1.
Drain piping including supports
-N ALL D
E and valves radioactive (except)
RZ,X) -
(p) 2.
Drain piping including supports N
ALL D
E pf and valves. nonradioactive
~
3.
Piping and valves. contain-2 C,SC
-B B
1 l
ment isolation (p)
{
4 Other mechanical and N
ALL E
electrical modules 3001 Amendment s
-_._m-..,
m,,r.-.,,.,.__,_,_-_,,_-,,,._,_,,..,..,~.....,..O..._.~.__-
.__.__...____._.._.__._._________..________7____
MN 04104t; rit n Standard Plant TAllLE 3.21 CLASSIFICATION
SUMMARY
(Continued) 1 Qualit)
Group Quality Safet4 Loca.
Classi.
Assurance Selsmic Prineinal Comnonent" gang ggg' fication Reautrement' Catecord figigg i
U3 Fire Protection System (Continued)
(t) (u) 6.
CO actuation modules N
RET 2
(t)(u) 7.
Cables N
SC.C,X, RAT,W h)(u) 8.
Sprinklers N
SC,X D
U4 Civil Structures B
I 1.
Reactor Building (Secondary 3
SC,RZ Containment and Clean Zone)
B I
2.
Control Building 3
X 3.
Service Building N
H
- 4.. Radwaste Building substructure 3
W B
1 4 8. R oal w o s4e 8 %+ld m 3 N
W E.
(v)
- 5. Turbine Building N
T t
t t
l 3130 Amendment 13
,,,.. _.~._.._.--;-,___.,.,, _ _ _ _. _.. _ _ _-
._u..,.._._,,..,...._..,__.,._.,,_.._..~._,..,._._.,......_