ML20027D828
| ML20027D828 | |
| Person / Time | |
|---|---|
| Issue date: | 05/14/1982 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Aggarwal S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20027A669 | List:
|
| References | |
| FOIA-82-426 NUDOCS 8211100168 | |
| Download: ML20027D828 (22) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION j
W ASHINGTON, D. C. 20555 MY ) 4 SBb i
MEMORANDUM FOR: Satish K. Aggarwal Task Leader, Equipment Qualification Electrical Engineering Branch Division of Engineering Technology Office of Nuclear Regulatory Research FROM:
J. M. Felton, Director Division of Rules and Records Office of Administration
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SUBJECT:
DRR REVIEW 0F FINAL RULE CONCERNING ENVIRONMENTAL QUALIFICATION OF ELECTRIC EQUIPMENT FOR NUCLEAR POWER PLANTS; 10 CFR PART 50
~
The Division of Rules and Records concurs in the attached May 10, 1982, version of the rule noted above with the ' required format changes as indicated (those revisions which are marked with paper clips). The Office of the Federal Register may not publish the rule unless these changes are made.
You will note that other revisions are indicated in the Federal Register notice. We believe that you should give serious consideration to the incorporation of these changes as well since they clarify the existing language in the rule.
Please contact John Philips, Chief, Rules and Procedures Branch, on ext. 27086 if you have any questions concerning'this matter.
)
/,[ivision of Rules and Records
. F lton, Director Office of Administration
Enclosure:
As stated x
8211100168 821014
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MAY l 01982
[7590-01]
3 3
e NUCLEAR REGULATORY COMMISSION
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10 CFR Part 50 Environmental QL.alification of Electric Equipment for Nuclear Power Plants AGENCY:
Nuclear Regulatory Commission.
j ACTION:
T opvace Final Rule.
SUMMARY
The ".;1
. - T,c;;l;te ry Commission is p. weva i. 3 amending its
,o regulations app,licable to nuclear power plants to clarify and strengthen the criteria for environmental qualification of electric equipment.
Spe-cific qualification methods currently contained in national standards, regulatory guides, and certain NRC publications.for equipment qualifica-tion have b'eerr given different interpretations and have not had the legal force of an agency regulation.
This amendment r. e r ; 5 c d. u-1-s ww i d }codi';
Cod; ie_S t'._c environmental qualification methods and criteria which meet the o..
Commission's requirements k this area
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'j FOR FURTHER INFORM.ATION CONTACT:
Satish K. Aggarwal, Office of Nuclear
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Regulatory Research,-CI s..
1wo; E..w...ms..ng L... 1, U.S. Nuclear Regula-
-t tory Commission, Washington, D.C. 20555, Telephone (301)443-5946.
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SUPPLEMENTARY INFORMATION:
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a Previous Notics i
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~ On January-20, 1982,; NRC published in the Federal Register a notice
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of proposed rulemaking on environmental qualification of electric equip-ment for nuclear power plants (47 FR 2876).
The comment period eXDired Ms2.
March 22,1 A total of"69 comments!etter: were received by April 6, 1982,
'n 4
raising 10 major issues.
An additional 10 commentslette were received A
by April 21, 1982, but no new issues were raised.
The major issues are discussed below.
Nature and Scoce of the Rulemaking 3
Nuclear power plant equipment important to safety must be able to perform the safety functions throughout its installed life.
This require-ment is embodied in General Design Criteria 1, 2, 4, and 23 of Appendix A,
" General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50,
" Domestic Licensing of Production and Utilization Facilities"; in Cri-terion III, " Design Control," and Criterion XI, " Test Control," of Appen-dix B, " Quality Assurance Criteria for Nuclear Power Plants'and Fuel Reprocessing Plants," to 10 CFR Part 50; and in'10 CFR 50.55a(h), which 4
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incorporates by reference IEEE 279-1971,1'2 " Criteria for Protection 3
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Systems for Nuclear Power Generating Stations." This requirement is 3
applicable to equipment located inside.as well,as outside the containment.
~i The NRC has.used a variety of methods to gnsure that these general k'.fa o<ni le-J'{cjr requirements are met for electric equipment.
Prior to 1971, qualification ;
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was based on the fact that the electric components were of high industrial 1j quality.
For nuclear plants licensed to operate after 1971, qualification was judged on the basis of 'IEEE.323-l9' 71.
For plants whose Safety Evalua-tion Reports 1were issued since July 1,1974, the Commission has used
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Regulatory Guide 1.89, " Qualification of Class IE Equipment for Light-
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-j Water-Cooled Nuclear. Power Plants," which endorses IEEE 323-1974,2 1
1 "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power
.]
d-Generating Stations,". subject to supplementary provisions.
Currently, the Commission has underway a program to reevaluate the t
qualification.of e'lectric equipment in. all operating nuclear power plants.
j Asapartofthisprogram,moredefinitivecriteJraforenvironmental
' :j Jntf.4hr$- A-4 r.yy
'l qualification of electric equipmeng have been developed.by the NRC.
A j
document entitled " Guidelines for Evaluating Envirbnmental Qualification i
of Class 1E Electrical' Equipment. in Operating Reactors" (D0R, Guidelines) 4 was issued in November 1979.
In addition, the NRC has issued NUREG-0588,
" Interim Staff Position on Environmental Qualification of Safety-Related 1
Electrical Equipment,Iwhich contains two sets of criteria:
the first for plants original 1h' reviewed in accordance with IEEE 323-1971 and the.
second for plants reviewed in accordance with IEEE 323-1974.
a 1 Incorporation by reference approved by the Director of the Office of Federal Register on' January 1,1981.
2 Copies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., 345 East 47th Street, New York, N.Y. 10017.
3
[7590-01]
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By its Memorandum and Order CLI-80-21 dated May 23, 1980, the 1
Commission directed the staff to proceed with a rulemaking on environ,
't
'j mental qualification of safety grade equipment and to address the ques-
-l tion of backfit.
The Commission also directed that the 00R Guidelines and NUREG-0588 form the basis for the. requirements licensees and appli.
?
cants must meet until the rulemaking has been completed. This proposed rule is generally based on the requirements of the Division cf Operating Reactors (DDR) Guidelines and NUREG-0588.
Requalification of electric equipment in'accordance with this rule will not be reodired for equipment qualified or being qualified in accordance with 00R Guidelines and its supplements including IE Bulletin 79-018.or NUREG-0588 and generic letters including 82-09, provided the qualification of electric equipment has
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commenced prior toA90 days after the effective date of thF 0-4
/l The dates specif.ied in this rule iv' completion of environmental qualification of electric eouipment apply to all licensees and appli_
cants, and supersede.any date previously imoosed.
No changes to licenses or technical specifications are necessary to reflect these i
new completion dates.
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j The scope of the pnp.
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i equipment important to safety in its various gradations of importance.
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includes that portion of equipment.important to safety commonly referred to as " Class 1E" equipment'in IEEE national sta$dards and some additional I
non-Class 1E equipment and systems whose failure under extreme environ-4 mental conditions could prevent the satisfactory accomplishment of safety functions by accident-mitigating equipment.
Included in the p, e;d-final rule are specific technical require -
A ments pertaining to:(a) qualification. parameters, (b) qualification methods, and (c) documentation.
Qualification parameters include temperature, pressure, humidity, radiation, chemicals, and submergence.
Qualification methods include (a) testing as the principal means of qualification and (b) analysis and operating experience in lieu of testing.
fiMI The 7c;;;;;d-rule -J requirejthat the qualification program ~ include synergistic effects, aging, margin's, radiation, and environmental conditions.
- Also, a record of qualificati.on must be maintained.
_ Revision 1 to Regulatory Guide 1.89';
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will describe methods _ acceptable to the NRC for ineeting the provisions of hin d
this prop a)d rule and p include a list of typical equipment c sc
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NRC will generally not accept analysis alone in lieu of testing.
Experience has shown that qualification of equipment without test data may not be adequate to' demonstrate functional operability during design basis event conditions.
To ensure integrity.of a testing program, the same piece of equipment must be used throughout the complete, test sequence.
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-,,m The general requirements for seismic and dynamic qualif1 cation for electric equipment are contained in the General Design Criteria.
Pending development of specif.ic requirements in thi's area, the general require-ments will continue to apply.
NRC is considering expansion of the scope of this rule to include additional electric equipment important to safety.
This matter will bedhe subject of a future rulemaking.-
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COMMENTS ON THE PROPOSED RULE
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The Commission. received and considered 69 ' th 3-from the n4blje f
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and A' staff responses to-qch comments are available for
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public inspection and copying for a fee at the Commission's Public Document Room et 1717 H Street, NW,' Washington, DC.
a Single copies of
'i the anslysis of the comments may be 'obtained_'hi'a
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V.S. h)0 dear Reiuls6 m C Document Management Branch,A Washingtbn, amm;55;owI DC 20555.
vwscA h h commeeds eMd +he NBC sfah" respn-20 Me A s
}lows:
The inafor issuesldthcf r :: Lt.e.. mi: di a :::d ":'
os (1) Seismic and Dynamic Qualification -k50.49(a)
Issue:
Seismic'and dynamic qualification e an ' integral:part of
_ environmental cualification.
It is, therefore, inaooropriate to codify these requirements separately.
l
Response
Electric equipment at operating nuclear power plants was generally qualified for environmental'and seismic stresses separately, i.e., by using separate prototypes for environmental and'se' ismic ouali-comide r,.ble.
The Commission has decided, after t' r.gt'y Mi : D:de, libera-h'o A) fication tests.
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A4.t.bhro d4tc, %<qh -ft( ismwc, yp" "
to purs,ue this issue d an advance no (tice ofArulemaking.
Any seismic l\\
gualification testing of equipment in operating plants that may be t
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j required by future rulemaking will not require retesting for environ-j mental stresses solely because a single prototype was not used during,
1 the original qualification.
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(2) Scope - Cold Shutdown Requirement -k5.49(c) i Issue:
The rule introduces a new requirement to qualify " equipment needed to complete one path of achieving and maintaining a cold shutdown I.
A change of this magnitude, at this advanced stage of h
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condition."
j A
l industry's qualification effort, most certainly introduces significant
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new costs an'd obligations with no demonstrated imorovernent in safety.
Response
The staff agrees and the requirement has been deleted.
(3) Scope - Equipment in a Mild Environment -k50.49(c)
.}
Issue:
The rule makes no distinction between equipment located in a harsh or mild environment.
The requirements for equipment in a mild environment are less stringent than for thdse in a harsh environment.
Response
The reouirements for equipment located in a mild environment are not covered by the final rulek(See650.49(a)). The
~
'E A operating plants are required to satisfy the provisions of IE Bu-11etin 79-01B and licensing generic letter 82-09 for eoui~or:ent located in a mild environment.
For' near-term. operating licensees and for applicants A
for future nuclear power plants, the regulatory guidance will be pro-vided in Regulatory Guide 1.89.
(4) Scope - Previous Qualification Efforts -[60.49(c8 dcN M *3 Issue:
The rule does not recognize that-eper-c*'. --
'--+e have just com-t pleted oualification of equipment to the DDR Guidelines en NUREG-0588.
Without such ecognition, industry efforts, manpower,and billions of
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'ollars will go down the drain.
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Response
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The statement of considerations has been expanded to
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alleviate this concern.
Also, 50.49(b) has been modified.
-1 l4i (5) Humidity -850.49(e)(2)
'.)1 Issue:
The effects of' time dependent variations of relative humidity 1
during normal. operation cannot be considered for all equioment.
There are
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no detailed standards for how this type of testing should be performed.
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Response
The staff agrees.
The words " Time dependent variation of l1 relative"-have been deleted fromh0.49(e)(2).
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(6) Aging-h50.49(e)(5)
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.ft.j Issue: The requirement that onaoing qualifications be done using
]9
" prototype equipment naturally aged".is overly restrictive.
Use of j
accelerated aging to define a qualified life is not technically feasible.
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Resoonse:
Paragraoh 50.49(e)(5) has been modified to alleviate this concern.
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(7) Margins-ESO.49(e)(8)
/
S Issue:
The margins aoolied in addition to known conservatiJns lead A
e7 to excessive stress which could lead to failures of eauioment is unrealis -
tic qualification tests.
This paragraph is in conflict with RegiJlatory 7.
-7 Guide 1.89.
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Response
The staff agrees.
The paragraoh has been accordingly, A
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\\ modified.I (8) Analysis and cartial test data - 0.49(f)(4)
Issue:
If partial type test data is available which adeauately
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supports the analytical assumotions and conclusions, their analysis I
should be allowed to extrapolate or interpolate these results for i
equipment, regardless of purchase date.
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e
Response
The staff agrees.
Reference to "ourchase date" has been i
J deleted.
j (9) Requirement for a central file 50.49(J)
- q Issue:
The. requirement for a central file should be deleted, since
)
it is not cost effective and has no safety benefit.
Response
The staff agrees. The requirement has for a central file' has been deleted.
- }
(10) Justification of continued operation for operating plants.
s
- f Issue
The requirement to submit justification for the continued J
..j operation of operating plants, since this information has been previously
.j submitted to NRC.
.i
Response
This requirement has been satisfactorily met and m2; u;$50.49(j) * "-crend ri has been deleted in its
,i w
entirety.
In addition, 50.49(g) " "
- x:: d ;"A has been deleted from the final rule since it is too prescriptive.
It will be included in Regulatory Guide 1.69.
/
e (FFECTIVE DATE:[This rule is-b:f ; ":de effective upon oublicat' ion in W dfhe w,ned the Federal Register.
The Commission 4+hes that the <:"et_^ 2- ::c ti e.a l nAf dinV)d vih y AMdl,tiaA L
w i
-d f -tt rule.sm take "^di:M effectj because-tAeyfrelievesa restrictioF 0
A under subsection (d)(1)of Section 553 of the Administrative Procedure Act.
This is so because all operating reactor licensees are currently under a June 30, 1982, deadline to complete environmental qualification of safety-Shef related electric equipment.
TheArule's implementation schedule, as G
explained above, supplants this date and thus gives licensees additional
/
11 1
]I 4
q q
a
[7590-01]
5I i
t time to complete environmental qualification of thi
{
. ;d s equipment.
In addi-
,1 tion, ths Commission finds that there is good cause 3
- pursuant to subsec-tion (d)(3) of Section 553--to make the rule's req i
_upon publication.
u rements effective The first licensee actions under the rule are R
'I required until 90 days after the effective date of the rul 1
e.
This 90-day period is intended to include the statutory 30 d 4
h, w
ays and allow 60 Iit g' %0b guitional days to make the submittal required by c&ccti]c]r (q) 5 50.l 3
\\
' the rule.- The overall effect of makino the rule effective on publi
~
~
. on gid-Qt(sufficient period after the 1
tion is to relieve licensees of the. June 30 deadline F192 ca-a
- j
.i and to provide a l
a lg\\e#
1-)
1, '
gf to achieve compliance with the near-term requirements of the rule.
a i
- A'
"^
The proposed final rule contains recordkeeping requirem
/h subject to review by the Offic ents that are 0
5f of Management and Budget (OMB).
yt?
As Wall required by P.L.96-511, this-proposed rule wiii-be wa O
h submitted to OMB W
for clearance of the recordkeeping requirements ~ - %7, b
pC Regulatory Flexibiilty Statement -
In accordance with the Regulatory Flexibility Act of 1980
, 5 U.S.C.
605(b), the Commission hereby certifies that this rule
, if promulgated, will not have a significant economic impact on a substa ti l n a number o f.
small entities.
This g u
?_ final rule affects the method of qualifi-cation of electric equipment by utilities.
Utilities do not fall w' thin i
the definition of a small business found in Section 3 of the Sma'l Business l
Act, 15 U.S.C. 632.
In addition, utilities are required by Commission's Memorandum and Order Ct.I-80-21, dated May 23
, 1980, to meet the requirements 3
[7590-01]
~
.?
~1 contained in the DOR " Guidelines for Evaluating Environmental Qualification j
of Class IE Electric Equipment in Operating Reactors," (November 1979),and
,a j
NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,".which form the basis of this F 1
4 p r e., s.
4 rule.
Consequently, this rule codifies existing requirements and imposes
$.1 4
no new costs or obligations on utilities.
3 C
U Pursuant to the Atomic Energy Act of 1954, as amended, the Energy
.I Reorganization Act of 1974, as amended, and section 553 of title 5 of
.s6 9
the United States Code, notice i h reby giv n that s.Jy. : _.
he 3
W18Mr sub' d. TCD'hchiob j
following amendment to 10 CFR Part 50 is ::-t
.y hted.
N
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10 CFR Part 50 g,.;
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f L i e [7590-01) g-o 2. A new 9 50.49 is added to read as follows: S 50.49 Environmental qualification of electric equipment for nuclear, I power plants. i .s (a) Requirements for se'ismic and dynamic qualification of electric i j equipment are not inc7ude'd.in this section. Also not included are the requirements for electric eguipment located in a mild _ environment. A mi1d_,nvironment fs_ar: e i _env ro_nment.that..would.at no.. time.be..sjgrti.f.icantly,
- g more severe than the environment that-would occur during normal plant e
- - - - -. ~... _ _..... -.. _..... _ ~
~~ -
operation or during an_t..ici.p.ated. operational occurrences.
(b) Each holder of or each applicant for a license to operate a
'3 nuclear power p] ant shall establish a program for qualifying the electric equipment as defined in paragraph (c) of this section;aj
l (1) The performance specifications o...
..wusarai inscui.e,
._qo...
l[j
--... under conditions existing during normal and abnormal operation and during design basis events and afterwards. ec.J th :-n3Lha vf th r-.;vd.
- .; h ihm i n um3c i tj. _:t-b r:2 -t ri n;d.
(2) T:.. m. 3c ur Voltage, frequency, load, and other electrical characteristics, for which the performance specified in accordance with paragraph (d)(1) of this section can be ensured. (3) The environmental conditions, including temperature, pressure, humidity, radiation, chemicals, and submergence, and th; p.;dictsd.mii;- t4 h mesto uvnJ..
- u...th t.me at the location where r
the equipment must perform as specified in accordance with paragraphs (d)(1) and (2) of this section. i (e) The electrical equipment qualification. program must include the following: (1) Temperature and Pressure. The time-dependent temperature and pressure at the location of the equipment must be established for the i most i...m rns severe of the applicable pc;t 1 t J _.m.m design basis events and must be used as the basis for the environmental qualification of electric equipment. 1 \\~ (2) Humidity. T :..-- J;p e..J _,... a.1 a vi o n s ui.mimt'r e Humidity during normal operation and design basis events must be considered. h 13 4
(7590-01) 6 f (3) Chemical Effects. The composition of chemicals used must be 3 at.1. east as severe as that.resulting from the most limiting mode of plant i operation (e.g., containment spray,.emerg,ency core cooling, or recircula-tionfromcontginmentsump). If th,e_ composition of the chemical spray ,y J
- 1 can be affected by equipment malfunctions, the most severe chemical spray
'3 3 environment that results from a single failure in the spray system must 1a be assumed. i ~ (4) Radiation. .The radiation environment must be based on~the type 73, of radiation the total dose c.nf J.;- ...s o f v-, .mJ.um.vu en.;.vo-mus 2 expected during normal operation over the installed life of the equipment j -p+we and the radiation environment, including dose-rate effects, associated with the most severe design basis event during or foTlowing which the equipment is required to remain functional, including the radiation resulting from recirculating fluids for equipment located near the recircu-lating lines. (5) Aging. Equipment qualified by test must p.e t.meLie be preconditioned by natural or artificial (accelerated) aging to its installed end of-life condition. Eicd. ...m-nan d ; cf.r..co. A. % ..c g;. ;t;J t; t!..~.:.5 1 ~m. ..Jmi.m.,, _ '. 4. mL L.. ,cucu au.2og Where a p Mn*<i-/.?*e -e--v.vpreconditioning to an installed end-of-life 4 m. -i. % (,:./-1.fc- ~~ condition 'is not practicable and technically meaningful, the equipment a n-i .w s..r may be preconditioned to a shorter designated life. ,,b ^ ,The equipment must - n.-i ;-lU. 7 - ~~ be replaced or refurbis_hed at the end of this designated life unless A +o,- ongoing qualification demonstrates pce; 1,,;;
- _ - p o n. t, ; t ; - ;' 1,
, _ J 'rs 1 d. ~ i3 c.il.. so yr ou, ling that the item has c.;..W /- -3.,.3 -.m c addition'ai life. e .? 16 I
i [7590-01] i 'y. s s ] (6) Submergence (if subject to being submerged). (7) Synergistic Effects. The preuvuuiu vo...s -..J i;;i! 5 Af;;-Je~ l 3
- ,.t
- t ;;..;
- J-. moLon Synergistic effects must be considered when these
'lerstw > effects are,believt.1 to have a significant effec't on equipment performance. 4 3 (8) Margins. Margins must be applied to account for production variations and inaccuracies in test instruments. These margins are in addition to :..r;;i. oggiicu ...:_: ;f .om u n.. w m.m. 2 ww...3 muu um. any conservatisms applied during the derivation of environ- - wunuiu v....- ~ mental conditions unless these conservatisms can be quantified and shown to contain appropriate margins. - (f) Each jtem of electric equipment must be qualified by one of the following methods: (1) Testing an identical 1 tem of equipment (manufactured to the same design) under identical conditions, or under similar conditions with a ~ supporting analysis to show that the equipment to be cualified is acceptable. (2) Testing a similar item of equipment with a supporting analysis to show that the equipment to be qualified is acceptable. (3) Experience with identical or similar equipment under s,imilar conditions with a supporting analysis to show that the equipment *to be qualified is acceptable. --( ' '
- 1,...
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_ L _ _ t _ A L _ _,.-. 1_A. s, ,oc a ci..c picwc v. cy m i r..cu w w..._..._,.__ -. _ - t;;t ;;, w..we _a;;. 2------ = f49 {gl Each holder of an operating license issued prior.to (insert the effective date of this amendment) must, by (insert a date 90 days after the effective date of this amendment), identify the electric equip-ment alrea'dy qualified to the provisions of this rule and submic a schedule for the qualification"EE2wo.J or replacement of the remaining electric equipment. This schedule must establish a goal of final environmental qualification by the end of the second refueling outage after March 31, 1982. The Director of Nuclear Reactor Regulation may grant requests for extensions of this deadline to a date no later than November 30, 1985, -%s e.. for specific pieces of equipment if-sesh requests are filed on a timely. 18
[7590-01] 4, -4 s basis and demonstre.te good cause for the extension, such as procurement lead time, test complications, and installation problems. In exceptional i
- 5 cases, the Commission itself may consider, and grant extensions beyond i
November 30, 1985 for compit: tion of environmental qualification. \\ .i fH (h) Each licensee shall notify the Commission of any signifi-4 3 cant equipment qualification problem that may require extension of the Completion date Within 60 days of its' discovery. m efs t_ st_ ___Al__ a 12____r - 9 '1 sw, r-i t _sJ__. r----s'***'- -- __ _;.aam32___.m i m _; - - 1 t t-ss r-- r-"' 'w w+*wwb* *h "GbG W* 5'** 8 w==
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1 gw, --=w n.m J G We 6 al 4 a 64 a. 4 9w b V444,3 Ul h 'W b G4 G Q Ql he3G ij b w w.1 h e e tii4.s 444 4-TTV "^ 6v wg g g]} wgg g g gg ,w ) w[ sraww.was .,4 : s a3 4. wy 4 we.w.6 .w. ""*'** N w Ur_^ w....-- D . - _ _ _ ;,s. _1 i 23 .e, ....a. ...w %6 4u av c3 casw--_ i w 3 u 4 c..... i _ ; M S
- 44.. -,, wi mm e
r r l I %df b he b 4 tes N '% wag .TV E V bg ~TVe&ULIO$h Od e.h i ) l C h Q-- 1 _ Ul Q w ga w wy&T $e 19
v 4' l (5).. a :3.. : T... mc31 ado..vu vi ...,.. f .y ionsuon or m12im J~ug r u... . ~... ., _ _..... ~..... <m m m I s o... v..... s u u. (k3f()11}Theapplicantforanoperatinglicensethatisgranted f j on or after)fbh $f ctive date of this amendment, but prior to November 30 -tj 1985, must perform an analysis to ensure that the plant can be safely operated pending completion of environmental qualification. -tn-- osuv.uonus -.uu poiam opn tas w T ti. :. .mm :....ed rt now m. m '., _ '. ; .n.. This analysis must be submitted to the Director of Nuclear Reactor {g Regulation for consideration prior to the granting of an operating 'i license and must include, where appropriate, consideration of: (1) Accomplishing the safety' function by some designatec alternate equipment if the principal equipment has not been demonstrated to be fully qualified. (2) The-validity of cartial test data in support of the original qualification. (3) Limited use of administrative controls over equipment that has not been demonstrated to be fully oualified. ~ (4) Completion of the safety function prior to exposure to the ensu-inq accident environment and the subsequent failure of the equipment does not degrad'e any safety function or mislead the operator. (5) No significant degradation of any safety function or misleading of the operator as a result of failure of equipment under the accident environment. (i) fjd ill A record of the qualification _ including documentation f in paragraph (d) of this section must be maintalned in m. m... a '. i. ic 20 ? .s
a Tq *. /,.,.,.,. [7590-01] d ] an auditable form to permit verification that each item of electric equip-i ment covered by this section (1) is qualified for its application and, (2)meetsitsspecifiedperformancerequiremenEswhenitissubjected to the conditions predicted-to be present when it must ' perform its safety function up to the end of its qualified life. Dated at this day of 1982. ' For the Nuclear Regulatory Commission. i Samuel J. Chilk j Secretary of the Commission k e ? e 9 9 6 ) O i a s 21
4,
- 2.,
'6 jf q UNITED STATES { (f,,g NUCLEAR REGULATORY COMMISSION g / 'e E WASHINGTON. D. C. 20555 eV 8 N .. / MAY 191982 y a ~ MEMORANDUM FOR: William J. Dircks Executive Director for Operations e FROM: Victor Stello, Jr., Chainnan 4. f Committee to Review Generic Requirements
SUBJECT:
MINUTES OF CRGR MEETING N0.13 The Committee to Review Generic Requirements met on Wednesday, May 12, 1982, from 3:30 to 5:30 p.m. A list of attendees is enclosed. Mr. Aggarwal (RES) presented the proposed final rule on the environmental qualification of electrical equipment. The Committee recommended that the rule be modified to address the following' comments: 1. The rule should state in clear language that if a licensee has qualified or begun to. qualify his equipment in accordance with the DOR Guidelines or NUREG-0580, he will not have to requalify equipment urider the rule. 2. NRR should ensure that the language describing the scope of equipment to be qualified is not inconsistent with current staff policies and definitions for safety related equipment as outlined in the November 1981 memorandum from Harold Denton to NRR Staff, Standard Definitions for Commonly-Used Safety Classification Terms. 3. The rule should not be silent on replacement parts in light of CLI 80-21 (pg. 7). The rule should include clear language stating that replacement parts that are the same model as the part already qualified to the DOR Guidelines, or NUREG-0580, or the rule need not be requalified. All other replacement parts must be qualified in accordance with the rule unless there are sound arguments to the contrary as to why lesser qualification standards should be applied. 4. The Committee noted that the proposed final rule includes qualifi-cation for both harsh and mild environments. The language concerning qualification of equipment subject to mild environments should be revised to indicate that technical requirements for this equipment are already covered by other existing requirements in NRC's regulations that call for quality operating, administrative, and engineering practices. OELD should be consulted as to the rule language to assure that this is properly accomplished considering the outstanding technical specifications resulting from CLI 80-21. 001532 n O ? bV jk.+ 4
k s q. I MAY 191982 ~ ; William J. Dircks 4 e ) The Committee noted that there was insufficient information presented to assess the costs and benefits of the rule. Nevertheless, it was the Committ'ee'- judgment that the rule addressed a significiant safety issue and t W ue rule should be sent to the Comission after CRGR comments have been addressed to the Committee's satisfaction. In view of the need for expeditious CRGR review, the Committee has designated the CRGR Chairman to assure that the Comittee's aforementioned comments have been adequately addressed. i t l Y ctor Stel o, Jr., hairman Committee to Review Generic Requirements
Enclosure:
List of Attendees cc: Commission (5) Office Directors Regional Administrators CRGR Members G. Cunningham, ELD e 6 A v~ l l e mm. +a-. so
.a..L_
..7.......-_--..----
- . q l
List of Attendees 1 CRGR Meeting No. 13 (May 12,1982) CRGR Members ..i Victor Stello, Jr.. '1 Jack Heltemes Ed Jordan i Joe Scinto Darrell Eisenhut .j Bob Bernero .i t Others i >j Walt Schwink, DEDROGR Mat Taylor, DEDROGR s Tom Murley, DEDROGR .i Bob Erickson, NMSS Dick Vollmer, NRR Satish Aggarwal, RES Jose Calvo, NRR Donald Sullivan, RES Harold Gregg, RES Al Hintze, RES John Phillips Steve Stern, NRR Zoltan Rosztoczy, NRR Bill Johnston, NRR Mark Williams, NRR B. D. Liaw, OCM O 8 P* UP'8 g .8", '[ 9,,__ _w
- _g'**,
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