ML20072D339
| ML20072D339 | |
| Person / Time | |
|---|---|
| Site: | 05000447, 05000477 |
| Issue date: | 03/17/1983 |
| From: | Sherwood G GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| JNF-017-83, JNF-17-83, MFN-056-83, MFN-56-83, NUDOCS 8303210290 | |
| Download: ML20072D339 (58) | |
Text
{{#Wiki_filter:NUCLEAR POWER GENER AL $ ELECTRIC SYSTEMS DIVISION CENERAL ELECTRIC' COMPANY,175'CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 682 (408) 925-5040 MFN 056-83 JNF 017-83 March 17, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention: Mr. D.G. Eisenhut, Director Division of Licensing Gentlemen:
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) DOCKET NO. STN 50-447 REVISED DRAFT RESPONSES AND RESPONSES TO DISCUSSION ITEMS Attached please find revised final draft responses to selected questions of the Commission's October 5,1982 information request. Only modifications (new or revised) to the responses of the referenced letter are provided. Also attached are draft responses to discussion items. Responses are provided in the attachments as indicated below: Attachment Number 1 Draft Responses Quality Assurance Branch Questions 2 Draft Response; to Mechanical Engineering Branch Comments on Sections 3.2 and 5.2 3 Draft Responses to Instrumentation and Control Systems Branch Questions Discussion Items 4 Draft Responses to Structural and Geotechnical Engineering Branch Audit Action Items Sincer y,
'A n
) Glenn G. Shehwoo , Manager
' Nuclear Safety & Licensing Operation f cc: F.J. Miraglia (w/o attachments) C.0. Thomas (w/o attachments)
D.C. Scaletti L.S. Gifford (w/o attachments) 8303210290 830317 PDR ADOCK 05000447 A PDR i
7 s ATTACHMENT NO.1 DRAFT RESPONSES TO QUALITY ASSURANCE BRANCH QUESTIONS l
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, 1 260.3 Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) .._.
requires the identification of safety-related structures, systems, and components controlled by the QA program. You are requested to supplement and clarify the GESSAR II application for FDA in accord-ance with the following: , A. The following items do not appear in Table 3.2-1. Add the
-Q' --
appropriate items and provide a commitment that the remaining items are subject to the pertinent requirements of GE's QA
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program and Appendix B to 10 CFR Part 50 or justify not doing so. (1) Control rod grapple - - - (2) All containment isolation valves, piping within containment isolation valves, and piping forming isolation barriers (Ref. Table 6.2-25)
- 3) Drywell Drywell head region Drywell-to-suppression pool vents Reactor pressure vessel biological shield annulus (7) Containment steam tunnel
-]-- ._
(8) RWCU Rooms:
- a. Filter /Demineralizers Room
- b. Demineralizer Valve Nest and Holding Pump Room
- c. Precoat Room
. d. Demineralizer Drain Valve Room
- e. Backwash Receiving Tank Room
- f. Heat Exchanger Room
. _ -_ _ _ (9) Weir wall (10) RHR containment spray piping (11 RHR containment spray nozzles
_ _. _ _. (12 RHR strainers (13 Drywell vacuum relief
- 14) Containment isolation leakage detection system
- .._.._ Personnel air locks -
Equipment hatch
- g - ' -- - 6900 volt switchgear -
_ 480 volt load centers ~~ 480 volt motor control centers 120 VAC safety-related distribution equipment including - _ inverters and voltage regulators (21) Control and power cables (including underground cable system,cablesplices,connectorsandterminalblocks) wb-- @ r*-#Newge m w -p hasea e g -. We. .,g gm , , , , ,, _ N* " * * ' - - . - - . ~ . . _ - _ . _ . _ _ . . . . MM # 'm--6*'i$'3he am.-eh m e .-4 p.e.,,., , ,., % , . . , _,
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1 (22) Conduit and cable trays and their supports (Raceways containing Class IE cables and those whose failure could damage other safety-related items) Containment Electrical penetration assemblies Transformers
- Motors (26 Load sequencers (27) Protective relays and control panels (28) 125 volt batteries, battery rocks, battery chargers, and distribution equipment (29) Roof drainage systems (including drains and parapets) of safety-related buildings (30) Scram discharge volume header B. The following items are in Table 3.2-1 with indication that 10 CFR 50 Appendix B does not apply. Provide a commitment that the pertinent requirements of GE's QA program and Appendix B to 10 CFR Part 50 will apply or justify not doing so.
(1) Reactor internal structure - other (I.6) (2) Pipe restrainings - main steam (II.6) C. Add the following items under XLVI, " Diesel Generator System" in Table 3.2-1 or justify not doing so. (1) Lube oil system (2) Combustion air intake and exhaust systems (3) Fuel oil system (all components) (4) Diesel service water system (all components) (5) Starting air system (all components) D. Provide a commitment that the safety-related instrumentation and , controls (I&C) described in Sections 7.1 through 7.6 of the FDA application plus safety-related I&C for safety-related fluid systems will be subject to the pertinent requirements of General Electric's QA program and Appendix B'to 10 CFR Part 50. This can be done by a footnote to Table 3.2-1. E. Enclosure 2 of NUREG-0737, " Clarification of TMI Action Plan Requirements" (November 1980) identified numerous items that are safety-related and therefore should be in Table 3.2-1. These items are listed below. Add the appropriate items to Table 3.2-1 and provide a commitment that the remaining items are subject to the pertinent requirements of General Electric's QA program and Appendix B to 10 CFR Part 50 or justify not doing so.
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i' . l i t j l i i i i ! - NUREG-0737 (Enclosure 2) _. s.__ Clarification Item Plant-safety-parameter display console. I.D.2 Reactor coolant system vents. II.B.1 II.B.2 Plant shielding. Post accident sampling capability. II.B.3 Valve position indication. II.D.3 II.E.4.1 Dedicated hydrogen penetrations. Containment isolation dependability. II.E.4.2 Accident monitoring instrumentation. II.F.1 Instrumentation for detection of inadequate core-cooling. II.F.2
. ._. .... ___ (10) HPCI & RCIC initiation levels. II.K.3(13)
(11) Isolation of HPCI & RCIC. II.K.3(15) (12) Challenges to and failure of relief _( .
. valves.
ADS actuation. II.K.3(16) II.K.3(18) Restart of core spray and LPCI. II.K.3(21)
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__ _ . . ._. RCIC suction. II.K.3(22) Space cooling for HPCI & RCIC. II.K.3(24-Power on pump seals. II.K.3(25
. . (18) Connon reference level. II.K.3(27)
(19) ADS valve, accumulators, and associated equipment and instrumentation. II.K.3(28) _._ _ _. (20) Equipment and other items associated with the emergency support facilities. III.A.1.2
~~ '-"-- -
(21) Inplant 1,2 radiation monitoring. III.D.3.3
.-. _ ____ (22) Control-room habitability. III.D.3.4
_( .._.. . M 3poWSR _ _ _ _ ___ . . A JE . Awcl\ cAkMi w _Sd 3 e_ ek u . t C . 2 . I 7-f
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G'ESSAR II 22A7007 238 NUCLEAR ISLAND RIv. 4 l (}
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1C.2.12 Safety-Related Structures, Systems and Components Q-List) Controlled by the QA Program GUIDANCE (12)
, Staff requests for additional information regarding this issue have been sent to a number of OL applicants. A recent request i regarding Diablo Canyon is provided as Enclosure 11.
, RESPONSE (12) As indicated under Subsection 17.1.2.2, the Applicant has the responsibility for the identification of safety-related struc-tures, systems, and components (Q-list) controlled by the QA program. The Applicant will supplement and clarify its 0-list based on Table 3.2-1 in accordance with the staff's request on Diablo Canyon or a similar request on another docket (e.g., Grand Gulf, Clinton). O V 1C.2.12-1/1C.2.12-2 !
GESSAR II 22A7007 238 NUCLEAR ISLAND R;v. 4
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17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION _ I 17.1.1 Organization l See Section 1 of Reference 1. 17.1.2 Quality Assurance Program The identification of safety-related structures, systems, and components (0-list) to be controlled by the quality assurance program is the responsibility of the Applicant. The Applicant's 0-list will be based on the quality assurance requirements given in Table 3.2-1. The remainder of this subsection is covered in Section 2 of Reference 1. 17.1.3 Design Control See Section 3 of Reference 1. 17.1.4 Procurement Document Control See Section 4 of Reference 1. 17.1.5 Instructions, Procedures, and Drawings See Section 5 of Reference 1. 17.1.6 Document Control See Section 6 of Reference 1. 17.1.7 Control of Purchased Material, Equipment, and Services See Section 7 of Reference 1. 17.1-1
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l ! . 260.4 Item XLVIIL1 of Table 3.2-1 shows "R" under the Quality Assurance ~~ It appears this may be a misprint. Clarify.
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Requirement column. Similarly, item LIII.10 of Table 3.2-1 shows " " in the same column. . - - The meaning of this is not clear, and this also should be clarified. . k i _.- _ ___._ . _ _.. . _ -. . .- .
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w - . , , , +_ %, , _ .. pm, --w, g ee. -m-.e.--menee.w i* -.pgue- D *.rrame mm M .ee- . 4 weh-ee-. -ewe = e.4 * *e.--_g mmm=.me -p-4,,imm _= e w w-+ e-
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g - 4 m.g=. m.e. - . y . e -w _ , , , 4 __ ___ .-_ _ _. - - _ .. .w. m -==eme . . .e 4 - -- , -% e+-m.- -_.m ew.=m.w e -.e. - *" 4 4ieb-- .ema ah--em+-.m---.mme em .--. , -* -- wg he.m e m-.-sm u s=. -e.
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Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety ssurance , seismic g Principal Component Classb Iocation Classi d Requirement fication Category Comments XLVII (Continued)
- 7. Cables 2 D B B I
- 8. Containment /Drywell Atmosphere 2 D,C N/A B I Monitoring System N
Las cp XLVIII Fire Protection System g U 8 6 CQ 7
- l. Isolation valves and piping 2 C / / I h$
3* within outmost isolation valves Qy g ld :d
- 2. Other piping and valves Other A,R,C,X,S D B I (t) ww tn H
- 3. Pumps Other O D B I (t)
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- 4. Pump motors Other O D B I (t)
- 5. Electrical modules Other A,R,C,X,S D B I (t)
- 6. CO2 actuation modules 3 S N/A B I (t)
- 7. Cables Other A,R,C,X,S D N/A I
- 8. Sprinkles Other A,R,C,X,S D N/A N/A N
XLI'X Miscellaneous Components :U N (D l>
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- 1. Containment polar crane 3 C N/A B (x) o$
N
Tzblo 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety Classi- Assurance Seismic Principal Component" Classb Location # fication Requirement
- Category F m ts LIII Civil Structures
- 1. Containment 2 B I ,
- 2. Shield Building 2 B I
- 3. Auxiliary Building 2 B I u w
as
- 4. Fuel Building 2 B I U
EO
- 5. Control Building 3 B I O$
N Ng
- 6. Diesel Generator Building 3 B I (p) Nis HH
- 7. Radwaste substructure below 3 B I (p) 08 H grade h 2
O
- 8. Cooling water intake structure 3 B I
- 9. Diesel fuel storage facilities 3 5 I
- 10. Turbine Building other N/A N/A u
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. r 260.5 Note "t" in Table 3.2-1 speaks of a " United Quality Assurance Program" -
for the fire protection system. Clarify what is meant by a " United Quality Assurance Program." - . . , _ _. e_. _ . _ . _ _ . -_-._.__ - . ... _ D hM.sE _ __e_e____e. __.- ___ . . - __ _ _ _ .___ . _. . N.oET3K.h=- vedN wheMed m~ p C . 2.-- s.2._Aby T J k
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- S-@ a-me m ea maisN w re-.emrin=,me.- .$ -%. . %, emsmuy en m.. e,,memmam. g em - w ,, ea - - emmea m
.e+=. * . - + - .i,. e *%= = up--e.-4 -ew-,..a...-- -
. . - . . . .. -._ _- _-. . . m-- - . - - . _ . . - .-
e eilk--eu em-- -e%gss aw-.smes, eme ee.e= mis-ne we m.sese au-mmunea m .-e.m-,g h -er w- - e w- .mn.4*e g , eme e e e -mu e
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22A7007 238 NUCLEAR ISLAND Rev. 0 Table 3.2-1 $ EQUIPMENT CLASSIFICATION (Continued) NOTES (Continued)
- r. To comply with Regulatory Guides 1.26 and 1.29, the Emergency cooling Svstem is interconnected to the fuel pool, thereby providing a redundant Seismic Category I source of coolant to the fuel pool. Additionally, systems for maintaining water quality and quantity are designed so that any malfunction or a failure in such systems will not cause significant loss of inventory.
- s. The gaseous radwaste system piping, pumps, and valves contain-ing gaseous radwaste shall be constructed in accordance with the applicable codes of Code Group D.
h e.s e th e m f o E
- t. There is \ ag%de.d
" lica uality
.. ssurance rogram forpt4w Fire Protection System.
- u. The classification of the main steam and feedwater lines are shown in Figure 3.2-2.
- v. The following qualifications shall be met with respect to the certification requirements.
- 1. The manufacturer of the turbine stop valves, turbine control valves, turbine bypass valves, and mainstream leads from turbine control valve to turbine casting shall utilize quality control procedures equivalent to those defined in General Electric Publication GEZ-4982A, General Electric Large Steam Turbine Generator Quality '
Control Program. ;
)
I 3.2-52 l l
a- m,- A se ATTACHMENT NO. 2 t DRAFT RESPONSES TO MECHANICAL ENGINEERING BRANCH COMMENTS ON SECTION 3.2 AND 5.2
238 NUCLEAR ISLAND R;v. 0 3 3.2.3 System Jafety Classifications (Continued) design requirements, the sections that summarize the requirements to be implemented in the design are indicated. 3.2.3.1 Safety Class 1 Safety Class 1 (SC-1) splies to components o the reactor coolant a 5 d eEwa.d t w l o cp fr go . '1 y)h f ailure could pressure boundarygor core support structure w ic cause a loss of reactor coolant at a rate in excess of the normal makeup system. 3.2.3.2 Safety Class 2 Safety Class 2 (SC-2) applies to those structures, systems, and components, other than service water systems, that are not Safety Class 1 but are necessary to accomplish the safety functions of: ) , (1) inserting negative reactivity to shut down the reactor;' . (2) preventing rapid insertion of positive reactivity; (3) maintaining core geometry appropriate to alliplant process conditions; (4) providing emergency core cooling; (5) providing and maintaining containment; (6) removing residual heat from the. reactor and reactor core; and J (7) storing spent fuel. b =It
- GG b g e.cha ho w ho.%c s a C %rk-Ae_ 7_ aT to C F F. FO.s5: C.
bec ws4 s2 4 d ev-s -S d co m po is d. , y Eaoh ake. 7
-t s-h t\ b.c s &A 3 ck y a m of evend cs e k s , AJ
+ % ns .s .5f CA ~ > s t. m u c.od <~~ u whk kk s UA) 3.2-4 I
si
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3 . . .~'+
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Table 3.2-1 x. EQUIPMENT CLASSIFICATION (Continued)
. Quality _
Group Quality . Safet Assur'ance Seismic Incation" Classi d . Requiremerit" Category # fication Comments ; Principal Co:nponent* Class N ' _-.- c I Reactor System , I - 1 D A B
- l. Reactor vessel ,
T I 1 D N/A B
- 2. Reactor vessel support skirt ,
D A B I- .U
- 3. Reactor vessel appurtenances - 1 c:.
pressure retaining portions z l D N/A S B I $ CRD housing supports 2 4. N.
- p D N/A B I'
'f 5. Reactor internal structudes - 2 W" engineered safety features " ,
[ Other D, N/A N/A N/A .
- 6. Reactor internal structures - 2 other ' O A^ I Control rods - 2 D N/A -
i 7. , e .;
- 8. Control rod drives 2 D ,
N/AO B I
! I 2 D N/.'. - B
- 9. Core support structure 2 D B ,. B I (g)
' -> 10 Power range detector. hardware D N/A B I Fuel assemblies 2 11
- i. ,'
k' *Q LPCT (Sb h )vgeve3 baudk kL%u ^M Eng* d' (CRO vakocsk $ t o w p h a g j j + p w m p s % .I a s m%\ , caa con s7, .u J, w,& a e M \? ,~m .ea uJ c.. A 3 t, % t- s sA,. e rv, o s
& Rev) ~ w- - ~ - _ (g ,
eg u-4 s s m 4\m % ra e a Mk; ~ dh s <- 7sugg Y T"9
= - - - - - - -
%ko--
idh a + w] C.Ov % e L , 3 A i s, w/A 1
Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety Assurance Seismic ' Classi d # Principal Component" Classb Location # fication Requirement Category' Comments II Nuclear Boiler System A B
- 1. Vessels - 1cvel instrumentation 1 D I condensing chambers 3 D C B I g
- 2. Vessels - air accumulators ta
- 3. Piping - relief / valve discharge 3 C,D C B I (h) 2 CC Piping - main steam and feed- 1 A,C,D,E A B I oe 4.
f water within outermost isolation E[
>3 N valve :xt p 8
- 5. Pipe supports - main steam 1 D A Bm I $[
Pipe restraints - main steam 1 D N/A , 6 I z
- 6. O
- 7. Piping - other within outer- 1 C,D ' 'E S I -' [ E
* $!. k"#b^td "J" PA i o A s r cm 9 . s . ., ,h m h a w .s i D,DE, A A B .I g)
- 8. Piping - other beyond outer- 3 C C ! -- (
most ie 3 D C 6-- - I ~ - - ~
- a. 4olation valves PVko.4vw4 - p, g g g, s , . ,+e am J~ s --
(g)
- 9. Piping - instrumentation 2/Other D B/D B/N/A I/N/A beyond outermost isolation valves t
1 D A B I 25 t
- 10. Safety / relief va:.ves (D 3
- 11. valves - main steam and feed- 1 C,D A B I *[
o-water isolation valves
- _ . _ _ _ _ _u __ - _ _ _ _ _ _
V Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Qur.lity Safety Classi- Assurance Seismic Principal Component" Classb Iocation# fication Requirement Category Comments II (Continued)
- 12. Valves, other - isolation valves 1/2 C,0 n /n n : M; -(
and within outermost isolation valves
\
r r
- 13. Valves - instrumentation beyond 2/Other A B/D B/N/A I/N/A (a) U outermost isolation valves g
- 14. Mechanical modulcs - 2 C N/A B I $h
. instrumentation with safety Qg yy i function NN B I HH
- 15. Electrical modules with safety 2 C N/A (i) us H function g 2
C,D,A,X N/A B I O
- 16. Cable with safety function 2 III Reactor Recirculation System 1 D AB B I (g)
- 1. Piping Pipe suspension - recirculation 1 D A B I 2.
line 2 D N/A B I
- 3. Pipe restraints - recirculation M line m p.
4" Pumps 1 D A B I .o
- 4. o
- n. gpv Lauf vw4vdv r i D A B _ __T_. _ _ (o L 0,A A B .I (a) b.Mer s b Avase va 6 I A I
[c. d.ww,4 Mc-.a s b ,Fo.u.J t "ve L 2. A B (a)
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Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) ~ Quality Group Quality Safety Classi- Assurance Seismic f Principal Component" Classb Location ficatio!. Requirement Category Comments III (Cont inued) 1 D B B I (g)
- 5. Valves 2 D N/A B I
- 6. Motor - pump M
2 X,C.A,X N/A B I y
- 7. Cable with safety function co Other T N/A N/A N/A z
- 8. IEMG Set CC O t' w u y$
7 w IV CRD Hydraulic System :D 2 cn 2 C B B I (g) y{
- 1. Valves - scram discharge volume lines g 2
D B I (j) O
- 2. Valves insert and withdraw 2 C lines Va ves - other Flos c_ M e,} Other A,C D N/A N/A (g) 3, va vt hJ pa s s(e can4*l v*
C B B I
- 4. Piping - scram discharge 2 volume lines
- 5. Piping - it:. sert and withdraw 2 C,/O B B I lines D N/A N/A (g) y[
- 6. Piping - oger (pwm 3 1ov , Other C , F.
MI _xNw e (k) k3
. c 2 C Special B I
- 7. Hydraulic control unit C c s s.s. au -% wi .g 7
h W w
Table 3.2-1 EQUIPMENT CLASSIPICATION (Continued) i Qudity Group Quality Safet **"#*"#*
- Classi d Requiremente Category f
Comments Principal Component Class Location fication X Process Radiation Monitor System C,T N/A B I
- 1. Electrical modules - main 2 steamline and reactor building ventilation monitors
- 2. Cable - main steamline and 2 A,C,T,X N/A B 1 [
ce containment ventilation 2 monitors CC O tt w E pU N XI RHR System w :t V B I H >-
- Heat exchangers - primary side 2 A B ,
Un > 1. A C B I
- 2. Heat exchangers - secondary 3 O
side 1,2 C A/B B I (g)
- 3. Piping within outermost isolation valves 2 A B B I (g)
- 4. Piping beyond outermost isolation valves 2 A B B I.
- 5. Pumps A N/A B I
- 6. Pump motors 2 t-5 r.
D,A A/B B I (g) m3
- 7. Valves - isolation, LPCI line 1 4-
- c I (g) c 2 D,A B B '
- 8. Valves - isolation, other (go,I3 chu% vdv es, fool 4 , -}- J n vdm o.J yv a.
p )b6 gnag.9-(ulA*- _ _ _ _ _ _ _ _ _ _ _ _ - - - -- m
Tcble 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety Classi- Assurance Seismic Classb Incation# fication Requirement Category Comments Principal Component" XI (Continued) Valves beyond isolation valves 2 A B B I (9) - 9. 2 A B B I
- 10. Mechanical modules B I N
- 11. Electrical modules with safety 2 A N/A function Z
- 12. Cable with safety function 2 'A,X N/A B I Cj
,N.!
N, M W! XII Inw Pressure Core Spray ' Ht (g) m> 1,2 D,C,E,A A/B B I
- 1. Piping within outermost h isolation valves 2 0
2 A B B I (g)
- 2. Piping beyond outermost isolation valves 2 A B B I
- 3. Pumps 2 A N/A B I
- 4. Pump motors owker 1,2 C A/B B I (g) 5.
Valves 4 isolation and within A B B I (g)
- 6. Valves beyond outermost 2 isolation valves WI e:
Electrical modules with safety 2 A N/A B I ,4 *
- 7. c function o-w V -
. 1 Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued)
Quality Group Quality Safety Classi- Assurance Scismic d Requiremente Category f Comments Principal Componenta Classb Locationc fication XII (Continued) A,X N/A B I
- 8. Cable with safety function 2 w
XIII High Pressure Core Spray co 1,2 C A/B B I (g) g
- 1. Piping within outermost Cg isolation valve t (n w
Other O D N/A N/A . y' y y 2. Piping - return test line to :O W condensate storage tank beyond ss [ second isolation valve in m r A B B I (g)
- 3. 2 Piping beyond outerm6stM; $
isolation valve - other .
&) 2 A B B I'
- 4. Pump A N/A B I
- 5. Pump motor ,2 1[2., \ A,C A/B B I (g)
- 6. Valves - outer isolation and withir.
XIV Leak Detection System N
- 1. Temperature sensors 2 A N/A B I (1) hh
=o B I (1) o
- 2. Temperature switches 2 X N/A 5wo dW .3 w Dh P f' Ev *
- e-o *= 4. Sh e kN y Po.l p s {s n ,
y ] es r 9 d ab- W4o wt cAs h 9a. e ssh yl > }e q =Lgs.u c k
~
g,.- F i Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued)- Quality Group Quality Assuance , Seismic safetg Classi d Requirement Category f Copunents Principal Component" Class Location fication XIV (Continued) C N/A B I (1)
- 3. Pressure transmitters 2 2 X N/A B I (1)
- 4. Pressure switches w
- 5. Differential pressure trans- 2 A,C N/A B I (1)- g mitters (flow) 2 CC B I (1) Ot W Differential pressure switches 2 X N/A L
6. Ei
- 7. Square root converters 2 X N/A B I (1) y*
e'o ra
- 8. Differential flow summers 2 X N/A B I (1) $
h 2 X N/A B I- (1)
- 9. Differential flow switches 2 0 2 X N/A B I (1)
- 10. Timer switches ,
2 X N/A B I (1)
- 11. Power supplies C N/A N/A I (1)
- 12. Radiation monitor Other 2 C,A,D B B I (1)
- 13. Instrument lines C,D C,D B I (1)
- 14. Sample lines Other
- 15. Flow transmitters Other C N/A N/A N/A (1) . g 4-b hW % gp Yb k hk hM
_ _ A g P ~ b " ' 2 *Lb b b - hk \
. a Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued)
'I Quality Group Quality Safety Classi- Assurance Seismic Principal Component" Classb Location fication Requirement" Category ' Comunents XV Main Steamline Isolation Valve Positive Leakage Seal System A
- 1. Piping and valves up to the 1 / A B I ,
first isolation valve of the inboard subsystem eJ W 2 A B B I 80
- 2. Piping and val.ves
. 1v Wa.o- oth rup rSea- of g (e.I.
l' u h.h e e v- v*M .F n. mbo.J smbasb) A N/A B I ec
- 3. Electrical module = . tith 2 O
" safety function 'Y{U
- 4. Mechanical modules with 2 A B B I hh
" safety function pg en >
- 5. Cables with safety function 2 A B B I h 2
0 XVI RCIC System 1,2 D A/B B I (g)
- 1. Pipine within outermost isolation valves 2 C,A,E B B I (g)
- 2. Piping beycad outermost isolation valves Other 0,A D N/A N/A (g)
- 3. Piping - return test line to e
condensate storage tank beyond second isolation valve and gg vacuum pump discharge line from *$ vacuum pump to containment o-isolation valves
h. Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safetg A**"##"# s'i""i# Principal Component. Class Location Classi d fication Requirement e Category f
. Comments XVI (Continued)
- 4. lo;mps 2 A B B I
- 5. Pump motors 2 A B B I
- 6. Valves - outer isolation and 1,2 D, A A/B B I (g) w W
within w 7. Valves - return test line to Other 0,A D N/A N/A (g) $c condensate storage beyon.1 0y i second isolation valve.In b tr Z vacuum pump discharge line to $$ ontainment isolation valvas , g g4 I (n >
- 8. Valves - other N 2 hA B B I (g) h 2
- 9. Turbine 2 A N/A B I (m)
- 10. Electrical modules with safety 2 A,X N/A B I function
- 11. Cable with safety function 2 D,A,X N/A B I XVII Fuel Servicing Equipment
- 1. Fuel preparations machine Other C,R N/A B N/A cN es (D :>
- 2. General purpose grapple Other C,R N/A B N/A <g o
.O 4
% RQQ k , -) kkp fwWf g SM C V \M 3 th GC MiIJ\ 6 W %/ a M O h g/ ck s-vw cav.hs~~.1 & s-ky4 a w\ek O e Mxk d w - u d- - _
. Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued)
Quality Group Quality Assurance SeMc g Classi d Raquirement, Category Safetg Principal Component Class Location fication Comunents XVIII Reactor Vessel Servicing Equipment
- 1. Steamline plugs Dther C N/A. N/A N/A f .w) "C C -eM/A B I
- 2. Dryer and separatdrg % and 2 head strongback ,
N W co XIX In-Vessel Servicing Equipment ,
+
p- g
/
CC U Control rod grapple 3 C,R --BH! jN/A 6 I N/A O N l. J .- j 0[8 27 2 gp XX Refueling Equipment in n -
- 1. Refueling equipment platform 2 C N/A B 'I h assembly $
- 2. Refueling bellows Other D N/A N/A N/A i
- 3. Fuel transfer syst.em 2/Other- C,R B,D,N/A B N/A (n)
- 4. Penetration sleeve OM C,R B/D B I (o)
XXI Storage Equipment
- 1. Fuel s orage racks h ew "b 2 C,R N/A B I o IP" $
- 2. Defective fuel storage 3 R N/A B I ,4 {
container c o ~. _ _ _ _ _ _ - - _ _ - _ _ - - _ _ _ - _ _ _ _ ~
Table 3.2-1 EQUIPMENT CLASSIFICATION-(Continued)- Quality Group Quality Safety Assurance' SeMc g Classi d Requirement, Category Principal Component Classb Incation fication Conenents XXV Fuel Fool Cooling and Cleanup System
- 1. Vessels - filter /demineralizers Other R C B N/A (r) m.
- 2. Vessels - e4her m b v- 3 R C Bi I
- 3. Heat exchangers ' 3 R C B I y cc
- 4. Piping 3 R,C C B I/N/A g 3 R C B bt g 5. Pumps and pump motors I b 6. Valves and piping - containment 2 C B B I Stl e
isolation '> cn > I/N/A (r) - 7. Makeup system 3/Other R,0,C C B.N.A O
- 8. RHR connections - emergency 3 A,R C B I cooling
- 9. Electrical modules and cables 3 R C B I XXVI Suppression Pool Temperature Monitoring System
- 1. Electrical modules with safety 3 C,X N/A B I functions . :c I (D :
- 2. Cable with safety function 3 C,X N/A B I <;
c O *.
f Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety Classi- Assurance Seismic Principal Component Classb Location fication Requirement
- Category Comments XXXI Standby Gas Treatment System
- 1. Filters 2 R N/A B I
- 2. Valves - ductwork 2 A,R,C N/A B I
- 3. Cable with safety function 2 R,A,C,X N/A B I N w
co
- 4. Fans and motors 2 R N/A B I y cO w 0 t9 gen yy XXXII NI Chilled Water Systems MW
- 1. Control Building 3 D,C,A C B I yy tn H
- 2. Electrical switch gear 3 A C B I O
- 3. Other buildings Other A,R,W D N/A N/A XXXIII HPCS Service Water System This system is included under group /MPL XXXIV/P41.
XXXIV Essential Service Water System
- 1. Piping 2,3 0,A,C B/C B I N Ww a>
- 2. Pumps 3 P C B I ,4 y o
- 3. Pump motors 3 P N/A B I l 8 4
Tablo 3.2-1 EQUIPMENT CLASSIFICATION (C:ntinued) Quality Group Quality Safety Classi- . Assurance Seismic Principal Comionent Classb Mcation" fication Requirement
- Category Ccaments XXXIV (Continued)
C,A B B I Valves - isolation 2 4. OM"O A,C,R,S C B I
- 5. Ives = _..__ O
- 3 is o\ a4% ew vo<t W I 3 A N/A B g
- 6. Electrical modules with safety w function B I 2 Cable with safety function 3 A,0,P,X N/A cO
- 7. OM w
Other A,C,R,W D N/A N/A Q$ y 8. Nonessential portions >> WW s HH mg XXXV Closed Cooling Water System h 2 A,C,R B B I Piping and valves forming part 2 O 1. of primary containment boundary h\\ ^ Other A,C,D,R,W D N/A N/A
- 2. //i in and valvesr n ok < m s -3 p a d . *.Y-n w o r g c.o v v M w m d pb e w d A M .
XXXVI Condensate and Demineralized Water Storage and Transfer 2 C B B I
- 1. Piping and valves forming part -
of the containment boundary MN
- 2. Condensate storage tank Other O D N/A N/A (w) $#
- C q
C O4 w v l
Tablo 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Safety ****"#* Classi d Requirement e f Comments Principal Componcat Classb Incation fication Category XLIV Plant Electrical Systems (Applicant to Supply) XLV Auxiliary AC Power System N
- 1. All components with safety 2/3 A,C,X N/A B 1 $
function g CO " OM XLVI Diesel Generator Systems $ puel oil stom b*f MW
- 1. pDaf tar.k; s$ s4be ov d 4va aJ 3 S C B I (3) yy Co a\ s v.
- 2. t.Pipi 3 :w.d 1: 1::: br 39 -55" fucl cil 3 Sh C B I h}
, - . . o
$ g. p n. _ r _f. 2, '_^ ' t 98. U 5 Y.w m '.
.._ . m 3 S C B I servicc watm. 1 ic-
^ ?
(o / $. 0 ?.e _ . ~ . S ,".F. , _ 'f_.e~ on twhawJ 3 g .5
- 3 S C B I
. r _.y a cie;cl 2.. .x. wa ta .- : : : :
,. . . g -
coe%' g
- 74. Pumpmotors[r'ueloilsystemi -f 3
water A,o system med N/A B I N and diesel e l o b e o d >-) s 4
- m gy 9/. IDiesel generators 3 S N/A B I (3) ,4 y o
b4 l- 8
- v _
~ Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) Quality Group Quality Assurance c. Seismic f Safety Classi d Requirement Category Conunents Principal Component Classb Location fication XLVII (Continued) 2 D B B I
- 7. Cables D,C N/A B I
- 8. Containment /Drywell Atmosphere 2 Monitoring System u W
co g XLVIII Fire Protection System CO P 1. Isolation valves and piping 2 C KB KO I (t). O$ Qy within outmost isolation valves :o :c
.c D B I (t) HH H O
- 2. Other piping and valves Other A,R,C,X,S (n N )
Other .O D. B I (t) Z
- 3. Pumps , 0 Other O D B I (t)
- 4. Pump motors Other A,R,C,X,S D B I (t)
- 5. Electrical modules I l
S N/A B I (t)
- 6. CO2 actuation modules 3 Other A,R,C,X,5 D N/A I
- 7. Cables Other A,R,C,X,S D N/A N/A
- 8. Sprinkles N
lc N m l> XLIX Miscellaneous Components <4
- O C
3 C N/A B (x) g ,J
- 1. Containment polar crane i
'w v
OLbbMK 11 sensuus 238 NUCLEAR ISLAND Rev. O Table 3.2-1 . EQUIPMENT CLASSIFICATION (Continued) , NOTES (Continued) O. B,=-the equipment shall meet the quality assurance require-ments of 10CFR50 Appendix B in accordance with the quality assurance program described in Chapter 17. N/A = Quality Assurance Requirements not applicable to this equipment.
- f. I = shall be constructed in accordance with the requirements of Seismic Category I structures and equipment as described in Section 3.7, Seismic' Design.
N/A = The seismic requirements for the safe shutdown earth-quake (SSE) are not applicable to the equipment. ) Equipment that provides no safety function but which could damage Seismic Category I equipment if it failed is analytically checked and designed to confirm its integrity against collapse when subjected to seismic loading resulting from the SSE.
- g. 1. Lines one inch and smaller which are part of the reactor coolant pressure boundary shall be o Class 2 and Seismic Category I. S de.
- 2. All instrument lines which are connected to the reactor coolant pressure boundary and are utilized to actuate and monitor safety systems shall be Safety Class 2 from the outer isolation valve or the process shutoff valve (root valve) to the sensing instrumentation.
)
i 3.2-44
unssan.AA eensuut 238 NUCLEAR ISLAND R:v. O Table 3.2-1 EQUIPMENT CLASSIFICATION (Continued) NOTF;S (Continued)
- g. 3. All instrument lines which are connected to the reactor coo.l. ant pressure boundary and are not utilized to actuate ow
-end monitor safety systems shall be Code Group D from the outer isolation valve or the process shutoff valve (root valve) to the sensing instrumentation.
- 4. All other instrument lines -
e Through the root valve the lines shall be of the same classification as the system to which they are attached. or m owsMe r e Beyond the root valve, if used to actuatega safety system, the lines shall be of the same classification as the system to which they are attached. e Beyond the root valte, if not used to actuate a l safety system, the lines may be Code Group D. I
- 5. All sample lines from the outer isolation valve or the process root valve through the remainder of the sampling system may be Code Group D.
, b. Relief valve discharge piping shall be Quality Group C and Seismic Category I. Safety / relief valve discharge line piping from the safety / relief valve to the suppression pool consists of two parts: the first part is attached at one end to the safety / relief valve and attached at its other end to the structural steel just below the main steam header through a pipe anchor. This portion of the safety / relief valve discharge piping, is analyzed with the main steam piping as a complete system. 1 The second part of the safety / relief valve discharge piping extends from the anchor (located below the mainstream header) 3.2-45
tst:.b bnM 11 44A/UU/ 238 NUCLEAR ISLAND R v. O Table 3.2-1 EQUIP!1ENT CLASSIFICATION-(Continued) NOTES (Continued)'
- 2. A certification shall be obtained from the manufacturer of these valves and steam leads that the. quality control program so defined has been accomplished.
- w. The condensate storage tank will be designed, fabricated, and tested to meet the intent of API Standard API 650. In addi-tion, the specification for this tank will require: (1) 100% surface examination of the side wall te bottom joint and (2) 100% volumetric examination of the side wall weld joints.
a b m -k h sc b m b e M .ca p a b
- x. The cranes are designed top.21f @ J. i; 1:2f *u der ondi-tions of 1/2 SSE and to maintain their [$ 5 SS o9er lhe units under conditions of SSE.
- 3. N k W Co
- b\ W AA N*'
f -C. u b liy2 oke. rekow Ac ss uh ~ 6b v 3 Ac ai hd W jaVlJckstkow CHASM 6 Sukm I A n c"k A t he:tjJ, ts h on g s u(,{M 'O JVow Y li no 5- - (h\ A \ \ c t \M CM f D f C. o h J NC D Asus sco m ,et w 3 3.2-53/3.2-54
%nr -
Table 3.2-2 QUALITY GROUP DESIGNATIONS - CODES AND INDUSTRY STANDARDS FOR MECHANICAL COMPONENTSa,b ASME Section III Code Applicable Subsections Pressure Metal , ASFtB Core Quality Group Section III Vessels and Pumps, Valves, Contairutent Storage Tanks Storage Tanks Atmospheric Supports Support and Piping Components- 0-15 Classification Code Classes Heat Exchangers NA and NB - - - NF and NA A 1 NA and NB TEMA C NA and NC 'NA and NC NA and NC NF and NA NG B 2 NA and NC TEMA C MC NA and NE
.s NA and ND NA and ND NA and ND NF and NA C 3 NA and ND .~. =
TEMA C cC ASME Piping and - API-620 API-650 O[ ht f D Section VIII valves or AWWA-D100 3p 3 y B31.1.0 equivalent, ANSI B96.1 i Div 1 or N m equivalent
- gp W
0 TEMA C Pumps
=
0 i t Wt S*
- C C
O~ i
uuoonn AA tan,vus .-- 238 NUCLEAR ISLAND R v. O Table 3.2-2 , s QUALITY GROUP DESIGNATIONS - CODES AND INDUSTRY STANDARDS FOR MECHANICAL COMPONENTSa,b (Continued) NOTES , 1
- a. With options and additions necessary for service conditions and environmental requirements.
- b. In compliance with 10CFR50.55a, application of code and addendauat t b4 for the reactor coolant pressure boundary equipment (Class .1)gies provided in Table 3.2-4. All other components shall satisfy codes and addenda in effect at the time of component order.
- c. (oA44 ) ,
applicable subsection NB,
. ivt pumps classitieu, a, s, or C, NC, or ND (respectively) in ASME Section III, Boiler and i Pressure Vessel Code, shall be used as guides in calculating the thickness of pressure-retaining portions of the pump and in sizing cover bolting. -
)
- d. For pumps classified in Group D, Section VIII, Division 1, shall be used as a guide in calculating the wall thickness for pressure-retaining parts and in sizing the cover bolting.
- e. Tanks shall be designed to meet the intent of API, AWWA, and/
or ANSI 96.1 Standards as applicable. i
)
3.2-56
unconn.AA -22A7007 y 238 NUCLEAR ISLAND- Rev. 0 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY ~ This section' discusses measures employed to provide and maintain the integrity of the reactor. coolant pressure boundary (RCPB) for the plant design lifetine. 5 . 2 .' l Compliance with Codes and Code-Cases 5.2.1.1 Compliance with 10CFR50, Section 50.55a tudk Y Table-3.2-4pshowf compliance with the-rules of 10CFR50, Codes and Standards. Code edition, applicable addenda, and component dates wil be.
.meegin accordance with 10CFR50.55a.
~5.2.1.2 Applicable Code Cases The reactor pressure vessel and appurtenances and the RCPB piping, - pumps, and valvesp..d sq2 ::b4 cc.. designed, fabricated, and tested in accordance with the applicable edition of the ASME Code, including addenda that were mandatory at the order date for the applicable components. Section 50.55a of 10CFR50 requires code case approval only for Class 1 components. These code cases contain requirements or special rules which may be used for the construction of pressure-retaining components of Quality Grou Classification A. The various ASME code cases thatweeefahpliedtocomponentsintheRCPBarelistedin Table 5.2-1.
Regulatory Guides 1.84 and 1.85 provide a list of ASME Design and Fabrication Code Cases that have been generically approved by the Regulatory Staff. Code Cases on this list may, for design purposes, be used until appropriately annulled. Annulled cases are considered active for equipment that has been con-tractually committed to fabrication prior to the annulment. 5.2-1 9
Table 5.2-1 REACTOR COOLANT PRESSURE BOUNDARY COMPONENTS - APPLICABLE CODE CASES Number Title .
. Applicable Equipment Remarks
# Reactor pressure vessel RG 1.85, Rev 8 1141-1 Foreign produced steel Requirements for steel Reactor pressure vessel RG 1.85, R 15 h 13 forgings ,
1361-2 Sock welds Control rod drive RG ,.84, Rev 15 ts or minor Globe and check valves RG 1.84, Rev 14 1516-2 Welding of U$ internal perma t (2-1/2 inch and larger) attachments in va s for Section III applicatl gg nm 1557-2 Steel product refined eactor pressure ssel RG 1.85, Rev 15 $$ y, by secondary remelting gg N 1 1567 Testing lots of carbon or Safety / f valves globe RG 1.85, Rev 12 (( c low-alloy-steel-covered and eck va (2-1/2-Inch g electrodes, Section III larger) .z o 1572 Fracture toughness, Reactor pressure vessel Section III, Class 1, components 1578 SB-167 nickel- romium Control rod drive 1.85, Rev 15 iron (Allo 00) pipe or tube, Se ion III s Criteria, Section Piping for HPCS, RCIC, LPCS, RG 1.84, Re 11 1606-1 St N I, Classes 2 and 3 NBS, SLC, RHR, RWCS piping subject to upset, e>
<4 emergency, and faulted 6 ,0
, o operating conditions -
o
- x. -
1
Table 5.2-1 REACTOR COOLANT PRESSURE BOUNDARY COMPONENTS - APPLICABLE CODE CASES (Continued) Number Title Applicable Equipment Remarks i nyurostatic testing at nela test of ASME Code III RG 1.84, Rev l piping prior to or fol- piping l lowing the installation of spray nozzles for Section III, Classes 1, 2, and 3 Piping Systems C N-61 I) TfriN- Stress category for Reactor pressure vessel RG 1.84, Rev tt y partial penetration w welded penetrations, Section III, Class I % yg a construction / . oM t-* w
. M U1 w
Globe and check valves (2-1/2- RG 1.85, Rev 15 >> i 1621-1 Internal and external # (for 1621-2)
$ valve items, Section III, inch and larger)
Division 1, Class 1, 2, mU and 3 line valves y z U RG 1. 8 5, Rev 'i -1444 7 Additional materia g fo g Pipe snubbers and struts 13 N-7l_to component supportsgerd^ Pipe supports alternm.e denigr rat?irc- NF structural steel yuQ ,) mcnts fcr britc:' j c i 7thdsd*" NF structural supports Section III N f:, Ck s J l s d.Div t , S*- d 3 ,o d M C u % r, swppod,3 ' Clarification of flange Venturi tubes - M G 1.84, Rev 1 [1677 Globe and check valves (2-1/2- k I design loads, Section III, Class 1, 2, and 3 Inch and larger) Globe and check valves (2-Inch and smaller) y" m> 1682 Alternate rules for Recirculation pump RG 1.85, Rev 5 f$ material manufacturers o$ and suppliers
- V ...
m - -
~
Table 5.2-1 REACTOR COOLANT PRESSURE BOUNDARY COMPONENTS - APPLICABLE CODE CASES (Continued) Number Title Applicable Equipment Remarks-e Recirculation pump RG 1.85, Rev 11 1690 l Stock materials for ' construction, Section III, Div. I 19 . Pressure relief valve Safety / relief valves RG 1.84, Rev W
--l+ H t4 - LO O design rules, Section III, Division 1, Class 1, 2, and 3 _
w-RG 1.84, Rev 15
- 1745 Stress indices for struc- Piping for HPCS, RCIC, LPCS, Z tural attachments, NBS, SLC, RHR, RWCS, RWR
" Section III, Division 1, $$
y$ y Class 1 >> co ## Globe and check valves ( 2-1/2 - RG 1.85, Rev 11 q 1773 Use of other product e forms of materials' for inch and larger) j; yt< [ valves, Section III, Div. 1 f $ O E _ w ttti20 Alternative ultrasonic Recirculation pump RG1.85,Revisik N-t y 7 examination technique, Section III, Division 1 , S RG 1.85, Rev W I 9 I N207-1 Use of modified /;A-479 Control rod drives type XM-19, Section III, Div. 1, Class 1, 2, or 3 or C S construction to
*s o3
==
c' i* ATTACHMENT NO. 3 l l DRAFT RESPONSES TO INSTRUMENTATION AND CONTROL SYSTEMS BRANCH QUESTIONS AND DISCUSSION ITEMS l l
i . g I i
) p 4, r 3-?G-E3 ,.Q- #
beesTHH i , 421.50 A In Section 7.4.1.4 of your FSAR, you provide information on the remote (7.4.1) shutdown system (RSS). Attachment 2 provides the Instrumentation and
' Control Systems Branch guidance for remote shutdown capability (i.e., -- guidance for meeting the requirements of GDC 19). Indicate the extent - -_.
to which your proposed destyi of the RSS conforms to the guidance
-s provided in Attachment 2. -- - ;-----
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.- 11 .
, ;t aj [N([ 3-/ Y&) ! . ICS8 POSITION GESSAR II RSS DESIGN -10CFR50 Appendix A GDC 19 (As interpreted in S.R.P. Section 7.4) , ;
- 0 Provide redundant safety grade capability o f7 g . ,7 9/c m/,47 ; for remote shutdown assuming no fire damage y g j e p . ,:g ,./ or accident has occured - [
,y pf): k j en W M M
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i o RSS equipment should be seismically 8 N NSStrvtM P 'O k quali fied. 5 y ,tff4 y ftr (hete Y d' O W d""'Y ( i Mffc4 jpwnty NM wa/ I Y - Q-x Pr : o Provide redundant instrumentation /< ~ r (indicator 4 for verification of W4 ! safe shutdown conditions, p M 2p & a m" dx't'* o loss of offsite power should not negate O(/%r M 7 h/MP l shutdown capability from RSS l o LPCT n et RHR Jeep, Rcic e dde t n j f m ulasepp f o.p,e ow h b4/ j o Transfer of control to RSS should not 4yy p gg gr. (Afg , disable any automatic actuation of ESF functions unless such systems can be f Q f manually placed in service from the RSS. o See Figure 7A.4-3b. Eeylock ! switches are not used on the RSS panel . SJw ee o RSS access via keys or keylock switches the g,varon ./jparne/ /e /ocq/sd f shall be administratively controlled and /n a rwom whicA M nor/ne// Au shall not be precluded by the event ygn f.,,/ pmg, ; n ssitating evacuation of the control ,
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Wv e-v p h) of 3-1033 ICSB POSITION (continued) GESSAR 11 RSS DESIGN (continued) o 94 2de M14 dSE aj f , o The design.should comply with the requirements of Appendix R to 10CFR50. M g -pfs Kr /kule $ d j
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^ * - r l f, ,.' ' k'Q(p.-3 -l /i sj -)?. 3 421.50 a GUESTION , ) -
Provide the following additional information in your discussion
. using drawings as appropriate:
A
- a. Design Criteria for the remote control station ec,aipment including the transfer switches and separation requirements
- for redundant functions.
421.50 a RESPONSE The Remote Shutdown System (RSS) provides remote manual control of normal and nuclear safety-related systems necessary for Prompt shutdown and subsequent cooldown of the reactor from outside the control room.
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The remote sh own capabilit n itself doe not perform any safety r ated function Those RSS co . nents that ; interface th safety rel ed systems ma tain the inte ity and chan I separation o those system ( _ j (also ee part di . h a p i.1 z?M i d*
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421'.50b QUESTION
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Discuss the separation arrangement between safety-related and non-safety-related instrumentation and controls on the auxiliary shutdown panel. 421.50b RESPONSR
. Inside the remote shutdown panel physical barriers between redundant division), and between safety related and non-safety related equipmenWrevents the propagation of fire or effects of electrical faults from one division to another p&& '_ ; .McAs f N Yf4' W da m. W gf Ah h. **'***f"'*
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. 3- lh-D 421.50 c QUESTION Discuss the location of the transfer switches and the remote control stations.
421.50 c RESPONSE The transfer switches are located at the Remote _ Shutdown panel.
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The RS pa'nel sh be located the ,e, e. :i. '" tM4s df p'that accesscoK and function o the panel wil not be affecte y the event c sing] the control om evacuation It is suggest that the pane be located n a local RHR stem control bo d where co enient conununic ion can be ma tained with the R switch gea and where failur of any other uipment will no damage the eq pment on e rem shutdown pane . The panel sha be located i a contro ed (env)o tonment similar to that of the c trol room. h**
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v n ?: r i _'Q, , , , u f?vg 3-/t43 421.50 d QUESTION Provide a description of your isolation, separation and transfer
. override provisions. This .should include the provisions for preventing electrical interaction between the control room and the remote shutdown equipment.
421.50 d RESPONSE The functions needed for the remote shutdown control are provided with manual transfer switches located at the remote shutdown panel, which defeat the controls from the control room and transfer the controls to the remote shutdown control. Remote shutdown is not possible without actuation of the transfer switches. , fsf o W syyvdP &, N M j *1Y N g M &*
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p, , , , , , se>c* - 421.50 0 QUESTION
' Provide a descript!1on of the administrative and procedural control features to restrict and to assure access, when necessary, to the displays and controls located outside the control room.
. 421.50 e RESPONSE
/ o t is the c'd'dpplicant[' responsibility describe administ[nanal-ve and procedpfal control on ess to remo hutdc r.-
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**j;;;.L PF iFF 421.50 f QUESTION 1
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Provide a description of any consnunication .ystems required to co-ordinate operator actions, including redundancy and separation. 421.50 f RESPONSE O ti t . 5 A YM &m M J i c m e g' ' M 1.s.22.23. & 4
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t Kr-f'MJ1 l v n .- , l= 3'(('b 421.50 a 00ESTION 3 ,. Discuss the means for ensuring that cold shutdown can be accomplished.
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42i.50 a RESPONSE
, The RSS design includes a panel and associated controls, indicators, .
and monitors for interfacing with the RHR, RCIC, Main Steam, and Condensate and Feedwater Systems. In the event the reactor vessel is isolated, the feedwater su l sinks (turbine and condenser)pply are is unavailable, lost, the normal.. and evacuation of theheat ! control room is necessary, remote manual control of normal reactor cold shutdown sytems is taken as follows: Reactor pressure will be controlled and core decay and sensible heat will be rejected to the suppression pool by releasing steam through the safety relief valves. Reactor water inventory will be maintained I by the RCIC system. The suppression pool will be cooled as required ! by operating the RHR system in the suppression pool cooling mode. - 1 i- This procedure will cool the reactor and reduce its pressure at a j controlled rate. The RHR system will than be operated in the j shutdown cooling mode to bring and maintain the reactor to the cold , I shutdown condition. l hp h I
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[ ': ' ,' L hpy 7 421.50 h OUESTION f
- . Provide a description of the control room annunciation of the status
, of remote control or override status of devices under local control.
421.50 h RESPONSE Operation of any of the transfer switches causes an annunciator alarm in the control room. t t i 4 l 1 i i
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f- 3-{6 ~0 421.50 i QUESTION Discuss your proposed startup test pr;. gram to demonstrate remote
. shutdown capability in accordance with the guidance provided in Regulatory Guide 1.68, Revision 2.
4 421.50 1 RESPONSE ^ The startup test program for the RSS shall be performed after the completion of the preoperational testing of the RSS, and the establishment of remote shutdown operating procedures and test procedures, and the communications between the control room and l remote shutdown locations. 1 i The reactor shall be scrammed and the MSIV's closed from outside i the control room while the reactor is in a normal steady state j- condition. l Reactor water level an'd pressure shall be controlled from outside the main control room.
- Data shall be obtained and recorded at locations outside the control l room to verify that the plant has achieved hot shutdown conditions j and can be maintained at stable hot shutdown for at least 30 minutes.
i Manual operation of the safety relief valve (s) and the suppression j pool cooling mode of the RHR system from outside the control room i i
~
) shall be demonstrated. From outside the control room, water level shall be controlled in the normal range and reactor pressure shall i be lowered at a rate not to exceed the technical specification i limits.
l j The reactor coolant temperature shall be reduced 50'F by controlling ! the shutdown cooling mode of the RHR and/or the Reactor Core Isolation i Cooling Systems from outside the control room at a rate not to exceed 1 technical specification limits.
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, A test report shall document the results of all tests performed and a j summary of any significant deviations from the required system performance. - - - - - - i The demonstration of cold shutdown capability need not be performed ~ k
- immediately following the demonstration of achieving and maintain-
! ing safe hot standby from outside the control room. Rather, l this cooldown portion of the test may be combined with another j j . startup test requiring the reactor to be cooled down, as long ' I l as the procedures and acceptance criteria for the combined test meet all the elements of each individual test. ' f L.
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' j .;v. w / td .']'r.j: ? l' - l [ - f '2 421.50 i QUESTION , ) ,
Of scuss the testing to be performed during plant operation to verify the capability of maintaining the plant in a safe shutdown condition from outside the control room. 421.50.i RESPONSE It is the plicant's responsibility to discuss testing performed during plant operation in accordance with their plant technical specifications. , ifl( () esp fr,t' l} ' ? " ' ' l b^-l '
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Draft Response 3/17/83 ICSB Testing of the Backup Scram Valves Although not associated with the formal ICSB questions, the staff requested additional justification supporting the testability of the design and the frequency for testing the backup scram valves, I and their associated solenoids. ' I
Response
The following applicant interface requirement has been added to Table 1.9-19 in GESSAR II, Section 1.9:
" Revise technical specifications to include functional testing of back-up scram valves each refueling outage. Also, add method for confirming back-up scram valve operation following each scram occurence."
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' ATTACHMENT NO. 4 DRAFT RESPONSES TO STRUCTURAL AND GE0 TECHNICAL ENGINEERING BRANCH AUDIT ACTION ITEMS
20 jy Audit Action Items No. 12 and 13 Item-No. 12 Investigate the effects of not accounting for torsional interaction between soil and structures. Provide results and conclusiont.e Item No. 13 Provide a discussion as to how a potential exceedance in response spectra beyond the envelope spectra included in GESSAR II due to discreet site specific soil parameters is considered.
Response
Responses to audit actions No.12 and 13 will be provided as part of the results of the additional soil structure interaction analysis (SSI) using the lumped parameter approach with input motion at the foundation level in response to NRC Questions 220.09 and 220.44. Since this SSI analysis is considered confirmatory by the staff, the information submittal for audit action items no.12 and 13 should also be confirmatory. d i s 1 I i l h i i 4 1
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' ATTACHMENT NO. 4 DRAFT RESPONSES TO STRUCTURAL AND GE0 TECHNICAL ENGINEERING BRANCH AUDIT ACTION ITEMS 1
{ 4.
- Audit Action Items No. 12 and 13 Item No. 12 Investigate the effects of not accounting for torsional interaction between soil and structures. Provide results and conclusions.
f Item No. 13 Provide a discussion as to how a potential exceedance in response spectra beyond the envelope spectra included in GESSAR II due to discreet site specific soil parameters is considered.
Response
Responses to audit actions No.12 and 13 will be provided as part of the results of the additional soil structure interaction analysis (SSI) using the lumped parameter approach with input motion at the
- foundation level in response to NRC Questions 220.09 and 220.44.
Since this SSI analysis is considered confirmatory by the staff, the information submittal for audit action items no.12 and 13 should also be confirmatory. _}}