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{{#Wiki_filter:2/17/72 SUPPLEMENT TO SAFETY GUIDE 11 INSTRUMENT LINES PENETRATING PRIMARY REACTOR CONTAINMENT BACKFITTING CONSIDERATIONS D. Introduction                                                     loss are within the capability of the reactor coolant makeup Safety Guide 11 describes the regulatory                       system, position concerning instrument lines penetrating               (3) the integrity and functional primary reactor containment for present and                         performance of secondary future reactors. The purpose of this supplement                     containment, if provided, and is to provide guidance to applicants and licensees                 associated safety systems (e.g.,
{{#Wiki_filter:2/17/72 SUPPLEMENT TO SAFETY GUIDE 11 INSTRUMENT LINES PENETRATING PRIMARY REACTOR CONTAINMENT BACKFITTING CONSIDERATIONS D. Introduction Safety Guide 11 describes the regulatory position concerning instrument lines penetrating primary reactor containment for present and future reactors. The purpose of this supplement is to provide guidance to applicants and licensees concerning possible backfitting with regard to these instrument lines. This supplement does not represent a requirement for backfitting; such requirements will be formulated on an individual case basis pursuant to § 50.109, "Backfitting,"
concerning possible backfitting with regard to                     filters, standby gas treatment these instrument lines. This supplement does not                   system) will be maintained, represent a requirement for backfitting; such                       and requirements will be formulated on an individual               (4) the potential offsite exposure case basis pursuant to § 50.109, "Backfitting,"                     will be substantially below the of CFR Part 50.                                                    guidelines of 10 CFR Part 100.
of CFR Part 50.
E. Regulatory Position                                 b. For each instrument line penetrating containment, including
E.
: 1. Plants for which a notice of hearing on             those connected to the application for construction permit was             containment atmosphere, some published on or after January 5, 1970,             method of verifying during should conform to the regulatory                   operation the status (open or position in the safety guide.                       closed) of each isolation valve
Regulatory Position
: 2. Plants for which a notice of hearing on             should be provided.
: 1.
application for construction permit was     3. Licensees of plants for which a notice published between January 5, 1967,             of hearing on application for and December 30, 1969, should meet             construction permit was published on.
Plants for which a notice of hearing on application for construction permit was published on or after January 5, 1970, should conform to the regulatory position in the safety guide.
the following criteria as soon as              or before December 30, 1966, should practicable:                                  furnish to the regulatory staff a suitable
: 2.
: a. Each instrument line connected to          analysis of the effects on the secondary the reactor coolant pressure              containment, if provided, and boundary and penetrating                  associated safety systems of a containment should be sized or            postulated failure of the piping or of include an orifice such that if a        any component in an instrument line postulated failure of the piping or      outside primary reactor containment.
Plants for which a notice of hearing on application for construction permit was published between January 5, 1967, and December 30, 1969, should meet the following criteria as soon as practicable:
of any component (including the          With respect to plants for which the postulated rupture of any valve          integrity and functional performance of body) in the line outside primary        the secondary containment building reactor containment occurs during        and associated safety systems cannot be normal reactor operation:                maintained under these postulated (1) the leakage is reduced to the        conditions, the licensee should provide maximum extent practical            protection equivalent to that described consistent with other safety        in regulatory position 2.a.(3) above as requirements,                        soon as practicable consistent with the (2) the rate and extent of coolant        reactor shutdown schedule.
: a.
Each instrument line connected to the reactor coolant pressure boundary and penetrating containment should be sized or include an orifice such that if a postulated failure of the piping or of any component (including the postulated rupture of any valve body) in the line outside primary reactor containment occurs during normal reactor operation:
(1) the leakage is reduced to the maximum extent practical consistent with other safety requirements, (2) the rate and extent of coolant loss are within the capability of the reactor coolant makeup
: system, (3) the integrity and functional performance of secondary containment, if provided, and associated safety systems (e.g.,
filters, standby gas treatment system) will be maintained, and (4) the potential offsite exposure will be substantially below the guidelines of 10 CFR Part 100.
: b.
For each instrument line penetrating containment, including those connected to the containment atmosphere, some method of verifying during operation the status (open or closed) of each isolation valve should be provided.
: 3.
Licensees of plants for which a notice of hearing on application for construction permit was published on.
or before December 30, 1966, should furnish to the regulatory staff a suitable analysis of the effects on the secondary containment, if
: provided, and associated safety systems of a
postulated failure of the piping or of any component in an instrument line outside primary reactor containment.
With respect to plants for which the integrity and functional performance of the secondary containment building and associated safety systems cannot be maintained under these postulated conditions, the licensee should provide protection equivalent to that described in regulatory position 2.a.(3) above as soon as practicable consistent with the reactor shutdown schedule.
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Latest revision as of 21:38, 11 January 2025

Safety Guide 11, Supplement: Instrument Lines Penetrating Primary Reactor Containment Backfitting Considerations
ML12298A118
Person / Time
Issue date: 02/17/1972
From:
Office of Nuclear Regulatory Research, US Atomic Energy Commission (AEC)
To:
References
SG 0011
Download: ML12298A118 (1)


Text

2/17/72 SUPPLEMENT TO SAFETY GUIDE 11 INSTRUMENT LINES PENETRATING PRIMARY REACTOR CONTAINMENT BACKFITTING CONSIDERATIONS D. Introduction Safety Guide 11 describes the regulatory position concerning instrument lines penetrating primary reactor containment for present and future reactors. The purpose of this supplement is to provide guidance to applicants and licensees concerning possible backfitting with regard to these instrument lines. This supplement does not represent a requirement for backfitting; such requirements will be formulated on an individual case basis pursuant to § 50.109, "Backfitting,"

of CFR Part 50.

E.

Regulatory Position

1.

Plants for which a notice of hearing on application for construction permit was published on or after January 5, 1970, should conform to the regulatory position in the safety guide.

2.

Plants for which a notice of hearing on application for construction permit was published between January 5, 1967, and December 30, 1969, should meet the following criteria as soon as practicable:

a.

Each instrument line connected to the reactor coolant pressure boundary and penetrating containment should be sized or include an orifice such that if a postulated failure of the piping or of any component (including the postulated rupture of any valve body) in the line outside primary reactor containment occurs during normal reactor operation:

(1) the leakage is reduced to the maximum extent practical consistent with other safety requirements, (2) the rate and extent of coolant loss are within the capability of the reactor coolant makeup

system, (3) the integrity and functional performance of secondary containment, if provided, and associated safety systems (e.g.,

filters, standby gas treatment system) will be maintained, and (4) the potential offsite exposure will be substantially below the guidelines of 10 CFR Part 100.

b.

For each instrument line penetrating containment, including those connected to the containment atmosphere, some method of verifying during operation the status (open or closed) of each isolation valve should be provided.

3.

Licensees of plants for which a notice of hearing on application for construction permit was published on.

or before December 30, 1966, should furnish to the regulatory staff a suitable analysis of the effects on the secondary containment, if

provided, and associated safety systems of a

postulated failure of the piping or of any component in an instrument line outside primary reactor containment.

With respect to plants for which the integrity and functional performance of the secondary containment building and associated safety systems cannot be maintained under these postulated conditions, the licensee should provide protection equivalent to that described in regulatory position 2.a.(3) above as soon as practicable consistent with the reactor shutdown schedule.

11.4