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Forwards Rev 1 to Reg Guide 1.141,Containment Isolation Provisions for Fluid Sys, Pub Comments,Summary of Pub Comments & Their Resolutions, & value-impact Statement.Guide Endorses ANSI Standard N271-1976.W/encl ANO:7810140077
	ML20147C011
Person / Time
Issue date:	12/08/1978
From:	Arlotto G; NRC OFFICE OF STANDARDS DEVELOPMENT
To:	Fraley R; Advisory Committee on Reactor Safeguards
Shared Package
ML20062F378	List: ML20062F374; ML20147C011; ML20147C099; ML20147C107;
References
	RTR-REGGD-01.141, RTR-REGGD-1.141, TASK-EM-705-5, TASK-OS NUDOCS 7812180118
	Download: ML20147C011 (1)
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     ,....-                                                 cE0 0       1978 MEMORANDUM FOR:    R. F. Fraley, Executive Director, ACRS FROM:              G. A. Arlotto, Director, Division of Engineering Stds.

Office of Standards Development

SUBJECT:

REV. 1, R. G. 1.141, " CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS" Enclosed for the use of the Subcommittee on Regulatory Activities are fifteen copies of Rev. 1 of the proposed guide, " Containment Isolation Provisions For Fluid Systems," dated December,1978. Also enclosed are fifteen copies each of (1) the public comments, (2) a suninary of the public comments and the r resolutions, and (3) the value-impact statement. ACRS concurrence in the regulatory posit is reques . l G. A tto, Director Division o Engineering Standards Office of S andards Development

Enclosures:

As stated cc: PDR THIS DOCUMEN'. CONTAINS POOR QUALITY PAGES 0 11 % 781218stpky

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L.J l I,0 !: :o: Accessic.n Unit l Roor C50 Phillips ?uildint, l Fron: J. Norberg, EMSB Please niece .he attached document in the PDR using the following file ani file points:

                   .                                                                                        1 1

PDR File Additional Info (Select one and enter number) (Enter if appropriate) Proposed Rule (PR) _ ACRS Minutes No. Reg. Guide _ l .141, Rev.1 s Relate; to Proposed Rule (PR) ; Relates to Reg. Guide PetitionRule Effective (PRM) Tkti) ~~ Relates to Petition (PkM) ! l AilSI IAEA Relates to Effective Rule (RM) l

'                                                        Federal Register flotice                          !

SD Task No. EM 705-5 l NUREG Report Contract flo. l i

Subject:

Rev. 1 of R. G. 1.141, " Containment Isolation Pr nvicinns for Fluid Systeme". dated Dec. 1978 i CC: l Central Files 1 i

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                    ,4 ,4, REGULATORY GUIDE         OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.141 CONTAINMENT ISOLATION PROVISIONS                                                                                                                              ,

FOR FLUID SYSTEMS .- l A. INTRODUCTION This standard c%ntains requirements indicated by

                   ' General Des.ign Critena 54,55, 56, and 57 of Ap-                                                      the verb "shall" a~nd recommendations indicated by the verb "should." The recommendations as well as
                                                                                                                                                                                                                                  ]

pendix A, " General Design Criteria for Nuclear j the requirements of the standard were evahiated with Power Phrtts," to 10 CFR Part 50, "Licensmg of 1 respect to importance to safety.. All recommendations Pro, duction and Otilizat3on Facilities3 " require that pipmg systems penetrating pnmary reactor contam- are considered to be of sufficient imponance to safety ment be provided with isolation capabilities that re- to be endorsed along with the requiremen given in i the standard. . i . . g' ,c , .m: flect the ,mportance to safety of ,solating i these piping -

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systems. This guide describes a method acceptable to' ~

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the NRC staff for complying with the Commission ~ requirements with .espect to containment isolation er g's C. REGULATO Y' .ON ,'i ,l l fluid systems. The requirements 'om endationf,Yor con- .

B. DISCUSSION tainment isolati d'of syste . that penetrate the pnmary co sin f -water-cooled reactors as Working Group ANS 56.2 of the American Nu- specified }d 76, ." Containment Isola-clear Society Standards Committee ANS-50, Nucley tion is'n 3}id Systems," are generally a Power Plant Systems Engineering, has prepared a cept and rov e an adequate basis for complying .

     ~,       standard which specifies the minimum design re-                                                       ..
                                                                                                                              'th - . -tinent containment isolation requirements
 /            quirements for containment isolation of fluid syste                                                                     pynYx A to 10 CFR Part 50, subject to the Q            that penetrate the primary containment boundar oh g>lo ing:

light-water cooled reactors. This standard wa ap- q *'""~^i' proved by the American National Stand ute iIH rN st(le (ANSI) Committee N18, Design Criter 1. Sect.i n 3.6.4 of ANSI N271-1976 statesphe Power Pla'nts,'and designated AN.Sl 71 76, el sed system shall be leak testeo in accordance wi,th

              " Containment Isolation Provisions                                                     luid                5.3 of this standard unless it can be shown by inspec-Systems. "*                                                                                                  uon. that system integrity is being maintained,for
                                                               ;                                                          those systems operating at a pressure equal to or The provisio                  of' [SDl271-1976 include                                                 .bove the containment design pressure." This excep-minimum desg'               n, #sin t,DndTnaintenance require .                                             tion to sqrstem leak testing is also applicable to closed id systems that penetr. ate                             systems inside the contamment.

f a; ments the pr' for. [tainme Esolation?nt of light-water-cooled reac. ~ tors. R dTem or the design and testing of . 2. Section 4.2.3 of ANSI N271-1976 states: power su *ies, qualifying of Class IE equipment, " Sealed closed isolation valves are under administra-and the de n and testing of protection systems are tive controls and do not require position indication in outside the scope of this standard. These areas are not the control room for valve status." Since the con-completely covered by 'the references given in ANS! tainment isolation valves are components of the con-N271-1976. tainment isolation system, which is an engineered-

Copies may be obtained from the American Nuc' lear Society, safety-feature system, all power-operated valves ,

             $55 Nonh Kensington Avenue,1.a Grange Park I!!inois 60323.                                                  should have position indication in the control room.

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                . 3. Section 4.2.3 of ANSI N271 1976 statzs: "Di.                                                                                            quirements of 3.7 and applicable requirements for wnity in means of actuation of automatic isolation                                                                                                 isnlation barriers." Piping between isolation barriers
         'sabes in series should be considered to preclude                                                                                                   3hould meet the applicable requirements of Section common mode failure." The NRC staff's position is 3.5 or Section 3.7.                                                                                         (      )

that there should be diversity in the parameters s. sensed (i.e., types of isolation signals) for the initia. -

i tion of containment isolation. D. IMPLEMENTATION

4. Section 4.4.8 of ANSI N271-1976 gives general The purpose of this section is to provide informa-design requirements for closed systems. In addition, tion to applicants regarding the NRC staff's plans for i using this regulatory guide.

all branch lines and their isolation valves in closed' systems both inside and outside the containment should meet the design criteria of Section' 3.5 or Sec- This guide reflects current NRC staff practice. tion 3.6.7 if the branch lines constitute one of the Therefore, except in those cases in which the appli-containment* isolatio~n barriers. cant proposes an acceptable alternative method for ; complying with specified portions of the Commis-

5. In Section 4.6.3 of ANSI N271-1976, reference sion's regulations, the method described herein is is made to Regulatory Guide 1.7, " Control of Com- being and will continue to be used in the evaluation bustible Gas Concentrations in Containment Follow. of submittals [or construction permit applications ing a Loss-of-Coolant Accident," for guidance in de- until this guidenee is revised as a result of sugges-termining radiation exposures for a loss.or. coolant tions from the public or additional staff review.

accident. More appropriate guidance is given in Reg- , ulatory Guidci.l.89, ': Qualification of Class IE I For those plants for ich the second roup'd of } Equipment for Nuclear Power Plants." qu tions (Q2) on th ons crion permit ap feation l

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6. Section 4.14 of ANSI N271-1976 states: "The guide, the reco endations f this gui e will be piping between isolatiori barrisrs or piping which conside d by J e staff on a ca -by-c e basis pur-forms part of isolatiori barr'ieri shall meet the re- suant to i OJO9 of 10 CFR Part ,

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G2N ER AL h ELECTFilC Nuct. EAR ENERGY PROJECTS DIVISION GENERAL ELECTRIC CCMPANY,175 CURTNER AVE., SAN JCSE, CALIFORNIA 95125 MC 682, (408) 925-5040 i MFN 265-78 ' WHO 151-78

l l

, June 26, 1978 U.S. Nuclear Regulatory Commission Secretary of i.he Commission , Washington, D.C. 20555 Attention: Chief, Docketing and Service Section Gentlemen:

SUBJECT:

GENERAL ELECTRIC COMMENTS ON REGULATORY GUIDE 1.141,

                                    " CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS,"

4 DATED APRIL 1978

References:

1) ANSI, " Style Mr.nual for Preparation of Proposed

                                       American National Standards," August 1972

2) ANSI, "American National Standards Inst.itute Proce-dures for Management and Coordination of American l National Standards," February 1975 The General Electric Company has reviewed the subject guide. As a result of this review, the General Electric Comoany has identified several deficiencies of sufficient importance to be of concern.

One area of considerable concern is the application of Appendix A,

                  " Typical Boiling Water Reactor System Diagrams," of ANSI N271-1976,
                 " Containment Isolation Provisions for Fluid Systems."       The purpose of Appendix A is to _ illustrate the application of isolation provisions to BWR designs. A second area of concern is the application of the footnotes of ANSI N271-1976.      The references in the footnotes are cited to identify guidance. General       Electric has determined, however, that the figures of Appendix A and the footnotes associated with the main text of the standard are not representative of current SWR designs approved by the NRC in licensing documentation. In fact, the information contained in Appendix A and the footnotes is substantially obsolete when compared with current designs. Examples of corrected figures and footnotes are provided in Attachment 1. Therefore, the application of Appendix A and the footnotes should be clarified.

Attached is a copy of comments submitted to Jim Mallay, Chairman of tne . ANS-50 Committee. The comments are considered nem asary to provide clarification on the main text of the standard and te rectify the oosolete-ness of Appendix A and the footnotes, ts12182>0 ppe ?& low" 7 7

      ;c                                       -  -

GENER AL h ELECTRIC ' U.S. NRC June 26,.1978 Page 2 The' NRC has taken the position (Section B, last sentence) that all recommendations of ANSI N271 are considered to be of sufficient importance to safety to be endorsed along with the requirements given in the standard. This position has fostered some uncertainty as to the nature of the application of Appendix A and the footnotes in the guide. Appendix A and the footnotes are not officially a part of the standard, and this fact is explicitly stated in the preamble to Appendix A and references 1)'and 2). Further, the information contained in Appendix A and the footnotes was provided for illustration purposes only, and this purpose + is explicitly stated in the second to the last paragraph in the foreword to the standard and references 1) and 2). General Electric believes that Appendix A, primarily, is acceptable for illustrating containment isolation provisions conceptually or in principle. However, the NRC should clarify that Appendix A and the footnotes are not mandatory and are not necessarily representative of SWR designs acceptable for meeting regulatory position on containment isolation. Recommended wording to satisfactorily address this concern is provided in Attachment 1. '

Other substantial comments relate to: (1) position requirements for motor operated valves, (2) requirements for indicatien circuits and. associated actuation circuits, (3) guard pipe guidance, and (4) test provisions on 10CFR50 Appendix J. These subjects are discussed in detail in Attachment 1. If you have any questions regarding this letter, you may contact Robert J. Mur.illo of my staff, (408) 925-3406. l

l Glenn G. Sherwood, Manager Safety and Licensing Operation GGS: cc/148, 144 Attachment cc: G. A. Arlotto (NRC)

4. Ofab (NRC)

R. Kirkwood (NRC) L. S. Gifford (GE) . W e

~ ATTACHMENT 1 General Electric Company Comments on Regulatory Guide 1.141,

                     " Containment Isolation Provisions For Fluid Systems,"

Dated April 1978 l

1. ANSI N271-1976, Accendix A i

Procosed Chance: The following position should be incorporated in the guide as Regulatory Position C.1, and the other positions numbered accordingly:

               "The footnotes and appendices in ANSI N271 are not part of the            l standard. The information contained in the footnotes and appendices is illustrative guidance, and adherence to such information is not        '

mandatory .in order to comply with 10CFR50, Appendix A." J0stification: The last sentence in Section D of the Regulatory Guide, which reads: "All recommendations are considered to be of sufficient importance to safety to be endorsed with the requirements in the standard," has lead some reviewers to believe that the guidance of the footnotes and appendices are mandatory. This interpretation has occurred since the last sentence in-the discussion section of t,he guide was interpreted to overrule the second-to-the-last para-graph in the foreword of the standard, which reads: "The appendices are provided to illustrate application of the standard, but are not mandatory or part of the standard." Examples of areas where Appendix A is deficient are the following: A. The guidance on guard pipes inside the containment, such as Figures A-1, A-2, A-4 and A-5:

a. The guidance for guard pioes and the associated criteria are not within the scope of ANSI N271-1976.

b. The criteria applied in ANSI N271 are not consistent with currently applied criteria, such as SRP 3.6.1, SRP 3.6.2, nd Regulatory Guide 1.29. For example, Figure A-2 iows a guard pipe on the RHR system shutdown return line iich is not required by current regulatory criteria,

( eference 238NI GESSAR).

c. Guard pipe requirements are, in general, containment-drywell-system / operation unique and therefore cannot be applied " generically" as implied / required by ANSI N271. ~

v

Attachment 1 page 2 June 26,1978 B. The guidance on valve testing, such as Figures A3 (TC on Inboard Valve (1)) and A-6 (TB on th'e inside of the suppress-ion pool): The subject of valve testing is not a principal topic of the standard, and therefere the information on valve testing is piecemeal and does not represent optimum test provisions. For example, the TC provision on the inboard of valve (1) indicates that valve (1) is tested. The TC provision is in direct contradiction with NE00-21424, "238 Nuclear Island Containment Bypass Leakage Sealing and Testing Methods," which specifies that valve (1) need not be tested because of closed loop exemptions and 10CFR50, Appendix J criteria. . Acceptable criteria and requirements for valve testing are contained in 10CFR50, Appendix J. The guidance of ANSI N271 on valve testing should be set aside until more up-to-date and comprehensive valve testing guidance, for example, draft ANSI-56.8 N274, " Containment System Leakage Testing Require-ments," is officially promulgated. '

2. ANSI N271-1976, Section 3.3.2(4).

Procosed Chance: 6b The following position should be incorporated in the regulatory [Cf position of.the guide: ,

                    "When a single active failure is assumed, at least one isolation                ..J valve per pipeline shall take the position of greatest safety."                 y{.

sus

.?

(mJustification: .O Section f ANSI N271 specifies that automatic isolation ' I ;; ) , valves sha esigned to take the position that provides the ' ?s ! greatest safety. This requirement could be interpreted to mean ? !~ i that all valves shall move to their safest position following loss l of motor power. The inherent design of motor-operated valves dces not provide for closure upon loss of electrical power. The key safety objective is not necessarily assuring specific valve posi-tions, but rather assuring the proper isolation of pipelines. The proper isolation of pipelines when using motor-operated valves is achieved by redundancy and single-failure considerations, for l example, providing redundant motor-operated valves powered from - l different electrical divisions. Thus, the proposed change is ! required to preclude the unjustifiable interpretation that each motor-operated valve shall move to its safest position following loss of electrical power.- .

o '. la 1 !> : '

                                                    .,,-;~..               b e d.
                                                                              .~

IAttachment 1 4 - '

             -Page 3 June 26,-_1978

3. ANSI N271-1976, Section 4.2.3 .

Proposed Chance: . The second sentence of Section 4.2.3 should be modified as follows: p "The indicating circuit shall be classified IE unless a failure of. the indication circuits could not cause a failure of the actuation Q), ! . circuit." ir(jk Justification j Class IE indication circuits.are connected in some instances to isolation valve control circuits. These indication circuits. provide positive indication of the power availability of individual control circuits. Further, redundant Class IE circuits are physically separated and environmentally qualified. Seismic testing of finished-panels, where the lights and circuits are mounted, has substantiated that failures of indication circuits are unlikely as a result of a Seismic I event. Also, a single failure of an indication ~ circuit in one valve is acceptable because the isolation function wculd still be carrted out by the redundant valve. Thus, the proposed change is necessary to permit positive indication of control circuits and to preclude an overextension of the single-failure criterion. . p RJM: pat /1177-ll79 I

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t . Z y-, - - , , - , . - ,v..,. . , - , 4 6 2 W W t 9
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m z , 3 E '# l I E %- J C
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4 MM M 2G WH Z o ! ! W Em x .,$ 2 e . CL. m < s- , 5 N 'N H w " o 2 e . 4 % g Z m c- 0,> < WQ Uy , D 3 '
E* -
s '# e 3
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s s 2 U- N '# o l ) U & 3 3 1 ., : m 5
~ $ 5l 4 c E- U 3l t y - <
M O r 2 3j j , J y b 6d l 4 40
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3 3l
':J mw \ 4 1
QQ h G %* 1 1 2 G ' % ~
"r> u s v .- , \
4 C % =p A='. .)' 3
$ \ i., b dj = #c,;'** , + gah e
v i y ,4s.% g x-. r.. ,. t
~
7 'p "$ . b. 4 4 o # 0 r 0 3 3l. l .l ,l - 6 -lal' ll
=
.i nw.7
TYPICAL LINES WHICH CONNECT TO SUPPHESSION POOL -[ , Pump Suction Line ANNULUS OHYWELL CONTAINMENT SHIELD WALL INSIDE OUISIDE INSIDE GUTSIDE INSIDE OUTSIDE
@L iv ^
r + 1 g 10 EMEHGB NCY Cont Q- COOLINii S VSTE M
$. PUMP SuCTBON h TC .b s SUPPittiSSION POOL v asman flEACTOil TYPE: HWil , s .. f Acronison f vai vs cos.Y.on f ,p ,3 js s4 .,
h( 2
#e'#* , =0"[9 ,p E s"O s ,# s'"' , s' 8 s[.
o tTs u p* *
,#- p* e '/ +]g },s., s'/ 4 , v' e f ne uanns . . .. ... 0;=: : .i. .-. .... . . . . .s .s .
2 .. ... , si . . . . . LEGEND New Change
TYPICAL CONTAINMENT VENTILATION SYSTEM Effluent Line ANNULUS DilYWELL CONTAINMENT SillELO WALL INSIDE l' 00TS10E INSIDE OUTSliiE INSIDE l OUTSIDE
?
I t stuu OHYwt t t
Anis CONI AtNMENs E UttePME NT AHE A5 '
Ye 9 l 9 gos,,uooy Xin4,4^ b - r Ma -mik uAsvntAvueNr sysitu tiv $ Tcf,y Tc l Tc V m -
ACTOH 1YPE: BWR I . L f Ac u A nun f v As.vr ensiieON [ ,p%- p g 4 ,,s ' r+ '
f' . o,$ f g#"" +' ' +' ,of'" p s* s "?' '1 's ' vd' w ........ gi=1; c. ou a A. ..u o
. . , . . . . . - . - ...a ' A. t. ='r T .. a .-. .
LEGEND New Change 1 w + - ....e _
TYPICAL INSTRUMENT SYSTEM . liistruiltent lirte ANNULUS DilYWELL CONTAINMENT SHIELO WALL INSIDE ! UU TSIDE INSIDE OUISIDE INSIDE OUTSIDE s 1
^
e nou ss Nson y-{ ' y ~
, io sus a nuut N ,,, s?-
3
vE G e
e now se nson i b o [ X jg l su r % io ensinuurnT IIEACIOlt TYPL: I BWil s r./ / Aclu A f tun [ VAL E $*O$. I SON [ ,b g .g
) , no / ,9 ,,
0**~
,sd ' f"d f* *,f , ,,, s' d$ o, $l$ p' neuanas , ,. v....... - - - - - - -
o ,
, . . . , . :::::1; - m. . .n . . . os. . ...o - , s. .... ..... - -.. ... . _. . _ ... .
w N, LEGEND New Change k -
6
** S cm ay + ; 2 s
c a E<$
** $ I. 2 U cC 6 < .i I w 3 -O # 2 8 : C * $ e - ig w .J 2
D .- I 1Y.cc. v Q Ik *4 0*~* v
+ 5 E
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2 a * <g%
m .s m -
> o 3 $gc45 5 s' -
z A. E- ,g% g
$ g ,,
Z ww ,
<=c g i a GG 5
t. D
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w t H >h ') m 'o*
> R * \. g t o e 's \
W
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2 C e; f/"J w G. p z 2: C 2 m c 4 l
<t 2 c +
c c: = < a , g to H - ' 5
e. 4 a$ $ w*
U y 5 3, h w$
3

u. u.
n Vtao so < l
C;L <3 0 \ g, ,
o i y 3., c . 2, o " '#
> 23E & :Z2 2 -
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=
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am zo 2 a M'
= -
s&#
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3 _ - - l 53; , cw \ cc 3 1s #
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j 3 ?,. 7i #
2 *g 1
.. tgo d g - > 4s <
[
- N,'"'r -\
S 's 2!iI!l . O
< .: i i I l ~
l I I I l Figure A 11
~
TYPICAL CLOSED LOOPWATER SYSTEM - Effluent And influent Lines ANNULUS DRYWELL CONTAINMENT SHIELD WALL INSIDE iDUTSIDE INSIDE OUTSIDE INSIDE ! OUTSIDE i
! i
l 6 A 7 EHOM
?! . ' 14 ; E 4 i* cesita to wATEn
.}.- h 'c you, k
~ j. h n iv o, -- 7s
?~ D -
V/ p - ygTO To s d' To MISSitE HEAClOR TYPE: HWH - L Tc
g. f ACIUAllON [ V At yt POSeisON
/ pc g g ga h'
e, f ,v+' # sy ,/ ,f"
,,s* '" s ' ~
of'" s, f' er ,'$' 6' s ,
/ y d e neumans . .. m .,.. .o......<
l ... .. i . m. .. . . . ,
r(cT e . 2. , LEGEND
. New Change}}

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