ML20062F374

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For Comment Issue of Reg Guide 1.141,Revision 1, Containment Isolation Provisions for Fluid Sys. Summary of Public Comments Encl
ML20062F374
Person / Time
Issue date: 12/31/1978
From:
NRC OFFICE OF STANDARDS DEVELOPMENT
To:
Shared Package
ML20062F378 List:
References
TASK-EM-705-5, TASK-OS REGGD-01.141, REGGD-1.141, NUDOCS 7812180122
Download: ML20062F374 (4)
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[Senac%

o U.S. NUCLEAR REGULATORY COMMISSION Apsil 1978 MM.)o!REGULATORY GURDE o

OFFICE OF STANDARDS DEVELOPMENT

.g REGULATORY GUIDE 1.141 CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS

..n A. INTRODUCTION nis standard contains requirements indicated by the verb "shall" and recommendations indicated by

. General Des.ign Cr.itena 54, 55, 56, and $7 of Ap-the serb "should." The recommendations as well as pendix A, General Design Criteria for Nuclear the requirements of the standard were evaluated with Power Plan,ts, to 10 CFR Part 50, 'Licensmg of respect to importance to safety. All recommendations Production and Util,zation Facilities require that are considered to be of sufficient importance to safety i

3 piping systems penetrating pnmary reactor contain-to be endorsed along with the requiremen given in ment be provided with isolation capabilities that re-the standard.

flect the importance to safety of isolatmg these piping

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systems. His guide describes a method acceptable to' the NRC staff for complying with the Commission's k

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J requirements with respect to containment isolation ghe "

C. REGULATO ON fj r

fluid systems.

' Inment isolatifor r mbecon n?I that per.:trate th The requirements ndations"fo[ Eon'-

B. DISCUSSION primary cor aimg rQgf water-cooled reactors as Working Group ANS 'i6.2 of the American Nu-specified NS l-1 76, " Containment Isola-Ngd Systems," are generally ac-

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clear Society Standards Committee ANS-50, Nuclear tion lui Power Plant Systems Engineering, has prepared a cept ndtrovt an adequate basis for complying standard which specifies the minimum design re ' p h.e rtinTnt containment isola: ion requirements

/., quirements for containment isolation of fluid syste men Ix A to 10 CFR Part 50, subject to the Q. that penetrate the primary containment boundar godig:

light-water-cooled reactors. This standard wa p-

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proved by the American National Stand s

1. Secti n 3.6.4 of ANSI N271-1976 states.3 (ANSI) Committee N18, Design Criter for N 1 el sed system shall be leak tested m accordance with Power Plants,'and designated ANSI 71 76, 5.3 of this standard unless,t can be shown by inspec-i

" Containment isolation Provisions luid Systems."*

ti n that system integrity is being maintained,for those systems operating at a pressure equal; tg or The provisi i

271-1976 include above the untainment design pressure." His excep.

ti n t sptem leak testing is also applicable tol closed minimum des' nd maintenance require- -

systems inside the containment.

a; ments for e L lation i id systems that penetrate the pr' y y Lain t of light-water-cooled reac-tors.

c tWemWfor the design and testing of

2. Section 4.2.3 of ANSI N271-1976 states:

power s lies. 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. Dese areas are not the centrol room for valve status." Since the con-completely covered by 'the references given in ANSI tainment isolation valves are components of the con-N271-1976.

tainment isolation system, which is an engineered-

  • Copies may be obtained frorn th American Nue' lear Society.

safety-feature system, all power-operated valves 555 North Kensington Ascm.c. La Grange Park litinois 60525.

should have position indication in the control room.

USNRC REGULATORY GUIDES coa w. **.m t..* '. p. 5.a.

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3. Section 4.2.5 of ANSI N271 1976 states: "Di.

quirements of 3.7 and applicable requirements for versity in means of actuation of automatic isolation isolation barriers." Piping between isolation barricts valves in series should be considered to preclude should meet the applicable requirements of Section common mode failure." The NRC staff's position is 3.5 or Section 3.7.

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that there should be diversity in the parameters s.

sensed (i.e., types of isolation signals) for the initia.

D IMPLEMENTATION tion of containment isolat. ion.

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 all branch lines and their isolation valves ip closed' ~ using this regulatory guide, 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.'

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cant proposes an acceptable alternative method for

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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 guidme is revised as a result of sugges-termining radiation exposures for a loss-of-coolant tions from the public or additional stat'f review.

accident. More appropriate guidance is given in Reg-

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ulatory Guide.l.89,.",Qualifi. cation of Class IE l

For th. se plants for ich the second rouj/d of }

Equipment for Nuclear Power Plants.",

qu stions (Q2) on th onst crion permit op heation

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has een received y the te of issuan of this

6. Section 4.14 of ANSI N271-1976 states: "Ile guide, the recoy endations f this gu' e will be piping between isolation barriers or piping which conside d by Jne staff on a ca -by-c e basis pur-forms part of isolatiori barriers * 'shall meet the re-suant to 5 0.209 of 10 CFR Part

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Public Coments on Regulatory Guide 1.141, " Containment Isolation Provisions For Fluid Systems" The only public comment on Regulatory Guide 1.141, " Containment Isolation Provisions For Fluid Systems," dated April 1978 was received from Mr.

Glenn G. Sherwood, General Electric Co., dated June 1978. The above guide is an endorsement of ANSI Standard N271-1976, Containment Isolation Provisions for Fluid Systems."

A.

Sumary of Coments 1.

Mr. Sherwood is concerned about the application of the appendices and the footnotes of the standard. He suggests adding words in the Regulatory Guide 1.141 to explain that neither appendices nor footnotes of the standard are parts of tha standard and therefore are not required for compliance with the guide.

2.

Section 3.3.2 of the standard (General Design Criterion 55, of 10 CFR 50) specifies that upon loss of actuating power, auto-matic isolation valves shall be designed to take the position that provides greater safety. Mr. Sherwood comments that this requirement could be interpreted to mean that all valves shall move to their safe position upon loss of actuating power which is difficult to meet if motor-operated valves are used. Mr. Sherwood suggests different words:

"when a single active failure is assumed, at least one isolation valve per pipe line shall take the position of greatest safety."

3.

In section 4.2.3 of the standard Mr. Sherwood suggests that an indication circuit shall be classed lE if its failure cor.ld cause a failure of the actuation circuit.

B.

Discussion and Resolution of Comments 1.

The purpose of adding appendices and footnotes to the ANSI Standard is clearly identified in several ANSI documents as for illustration and not to be included as part of the standard.

At the top of the first page of Appendices A, B, and C in the subject standard a parenthetical sentence states that the material in the appendix is not part of the standard but is included for information only.

Similar statements for appendices and footnotes appear in ANSI, " Style Manual for Preparation of Proposed American National Standards," August 1972, and in ANSI, "American National Standard Institute Procedures for Management and Coordination of American National Standards," February 1975 Since the purpose of adding appendices and footnotes is so abundantly clear, it is thought than any more clarification in the text of the regulatory guide would be redundant and un-necessary. Therefore no revision to the text of the guide was made as a result of this comment.

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. 2.

It is the position of the NRC that the isolaticn of any fluid line penetrating the containment boundary depends on the need for that line following the accident that required the isolation.

If the fluid line is not needed for post-accident emergcncy operation it is isolated at a speed depending on the nature and quantity of flow in that particular line.

Furthermore, it is the NRC's position not to require a particular type of operator on a particular valve whether it is motor operated or otherwise.

Section 3.3.2 in the standard merely requires that if a valve is to operate automatically, it has to be designed to move to the position of greater safety upon loss of its actuating power.

It is not until the application of the single failure criterion that at least one valve per fluid line taking the position of greater safety will be required as a minimum.

That is, all automatic valves in a fluid line are designed to function properly upon loss of their actuating power. Then by postulating a single failure due to unforeseen causes, at least one valve shall take the position of greater safety.

Since Section 3.3.2 of the standard does not contradict the above rationale, no revision to the regulatory guide is necessary as a result of this comment.

3.

The Instrumentation and Control System Branch (ICSB) of the Office of Nuclear Reactor Regulations reviewed this GE comment and did not concur with their rationale. The ICSB based their conclusion on the fact that the instrumentation for the con-tainment isolation system should satisfy the acceptance criteria for engineered safety features actuation systems and essential auxiliary support systems. The indication circuits being part of the containment isolation system (an engineered safety feature) must meet the IEEE-279 requirements, as discussed in SRP 7.3.

Therefore no revision to the regulatory guide is thought necessary as a result of this comment.

Ms At

i VALUE/IMPACiSTATEMENT I.

The Proposed Action A.

Description - The proposed action will provide guidance to applicants in meeting the minimum requirements for containment isolation of fluid systems.

B.

Need for the Proposed Action.

The SRP gives current staff

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practices.

For this important topic,'it would be desirable to issue a regulatory guide in order to afford a wider public review of this topic.

A national concensus standard has been developed which could provide the technical basis for this guide.

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C.

Value/ Impact of the Proposed Action 1.

NRC operations

'Since the guide reflects current licensing

' _ practice, no impact on NRC operations is anticipated.

2.

Other Government Agencies - Not Applicable.'

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Industry - Same as for NRC operations.

4.

Public - Not Applicable e

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Decision. on the Proposed Action Guidance should be furnisfied on containment isolation of fluid f

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Technical Al.ternatives.l' i,

Since the guide gives the current methods used to meet the t

1 regulations'., no technical. al.ternatives are now being considered.

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4 Regu1ation

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Value/ Impact of Procedural Alternatives The endorsement of the standard is the most efficient alter-native since it requires the least amount of time and effort to accomplish the task.

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L Decegber 13, 1978.

i.W.0 : fccessior. Unit fiam-C50 Niillips :uildin:;

Fro..:

J. Norberg, EMSB Please elece the attached docn.ent in the PDR using the following file aci file points:

PDR File Additional Info (Selectoneandenternumoer)

(Enterifappropriate)

Proposed Rule (PR)

ACRS Ninutes fio.

Reg. Guide 1.141 s

Relates to Proposed Rule (PR)

Petition (PiiM)

Relates to Reg. Guide 1.141 Effective Rule (Rtt)

Relates to Petition (PRM) _

~

Ai!SI Relates to Effective Rule (R:i)

IAEA Federal Register f!ctice SD Task rio.

EM 705-5 f!UREG Report Contract flo.

Subject:

Ltr. to Glen G. Sherwood, Mgr. Safety &

Licensing Operation, GE, concerning nis comments on R. G.

1.141, "L,ontainment Isolation Provisions for Fluid Systems" l

Central Files l

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