ML20129E625
| ML20129E625 | |
| Person / Time | |
|---|---|
| Issue date: | 05/17/1985 |
| From: | Millman G NRC |
| To: | |
| Shared Package | |
| ML20127B699 | List: |
| References | |
| FRN-50FR20574, RULE-PR-50 AA83-1, NUDOCS 8507170014 | |
| Download: ML20129E625 (15) | |
Text
.
AA U-l Ce tified Original /J)yfhePDR
~
Date: g /
Draft Regulatory Analysis For Current Proposed Amendment Revision of 10 CFR 650.55a Codes and Standards
- 1. Statement of the Problem .
The General Design Criteria (Appendix A of Part 50) of the NRC Regulations require that structures, systems, and components of light-water-reactors be designed, fabricated, erected, constructed, tested and inspected to quality standards commensurate with the importance of the safety function performed. Without a set of specific rules to implement these quality standards, it would be necessary for each applicant / licensee to develop its own program for submittal to the NRC. Each program would have to be reviewed by the staff on a case-by-case basis. This would in-b crease significantly the licensing review time and would make inspections '
by the staff more difficult because of the nonstandard nature of each program. -
To provide a consistent set of rules, which the industry has participated in developing, 650.55a mandates use of Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for construction of Class 1, 2, 3 components, and Section XI of the ASME Code for inservice inspection of those components.Section III and Section XI are implemented by applicants / licensees of all light-water-cooled reactors. The NRC first endorsed the ASME Code by reference in 10 CFR 550.55a in 1971. The ASME publishes a new edition of the Code every three years and new addenda every 6 months. It has been a continuing policy of the Comission to update this section of the regulations to keep the references current. In those cases where an item in the ASME Code is inconsistent with NRC criteria, an exception may be taken to endorsing that portion of the Code, or supplementary criteria may be incorporated to make the item consistent with staff requirements.
Section 50.55a last endorsed the 1980 Edition and addenda through the Sumer 1982 Addenda. Since then, the Winter 1982 Addenda, Sumer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda, and 1983 Edition have been published by the ASME. The purpose of this proposed rule is to incorporate the new edition and addenda into the regulations.
The ASME Code is developed by the consensus process, which ensures that the various industry sectors (e.g., utility, NSSS suppliers, regula-tory) are represented on the standards writing comittees and that their viewpoints are considered in the standards writing process. Endorsement of the ASME Code by the NRC provides a method of incorporating rules into the regulatory process that are acceptable to the NRC and have received industry participation in their development.
If the NRC did not take action to endorse the ASME Code, the NRC position on the methods for construction and inservice inspection would have to be established on a case-by-case basis. If the NRC did not take I action to update the ASME Code references, improved methods for l construction and inservice inspection might not be implemented.
i 8507170014 850710 i l
k 1
- 2. Objectives The proposed rule would:
o Incorporate by reference into $50.55a of the NRC's regulations the Winter 1982 Addenda. Sumer 1983 Addenda. Winter 1983 Addenda, Sumer 1984 Addenda, and 1983 Edition of Section III, ;
Division 1, and the Winter 1982 Addenda, Sumer 1983 Addenda, and 1983 Edition of Section XI, division 1, of the ASME Code, o Incorporate revisions to corref t certain existing footnote and paragraph references; to simplify the language of the rule; and to delete two obsolete provisicus.
- 3. Alternatives b An alternative to incorporating 'oy reference into NRC's regulations 3 the latest requirements of Section III, Division 1, and Section XI, Division 1, and making certain editorial revisions would be to take no action. This would mean that the NRC position on the methods for construction and inservice inspection contained in the latest edition and addenda of the ASME Code would have _to be provided on a case-by-case basis; certain incorrect footnote and paragraph references would remain in the present rule; and obsolete provisions would remain to clutter the rule.
A second alternative to incorporating by reference the latest requirements of Section III, Division 1, and Section XI, Division 1, is to incorporate the entire text of these sections of the ASME Code into the NRC regulations. Because of the volume of these sections, this approach is not practicable.
- 4. Consequences Incorporating by reference the latest edition and addenda of the ASME Code will establish the NRC staff position on these Code rules on a generic basis for applicants / licensees thereby minimizing the need for case-by-case evaluations and reducing the time and effort. required for submittal preparations and license reviews.
The cost / benefit of ASME Code revisions is balanced by the manner in which these revisions are achieved through the American National Standards Institute (ANSI) consensus process. The ANSI consensus process ensures that participation in ASME Code development is open to all persons and organizations that might reasonably be expected to be directly and materially affected by the activity, and ensures that such persons and organizations shall have the opportunity for fair and equitable participation without dominance by any single interest. Consensus is established when substantial agreement has been achieved by the interests involved. Consensus requires that all views and objectives be considered, and that a concerted effort be made toward resolution. ASME Code proposed revisions are published for public comment in the ASME Mechanical Engineering and ANSI Reporter publications prior to being submitted for final ASME and ANSI approval. Adverse public coments are referred to the appropriate technical comittee for resolution.
2
The consensus process ensures a proper balance between utility, regulatory and other interests concerned with revisions to the ASME Code, and ensures that the cost of any Code revision is consistent with its benefit.
Implementation of the new ASME Code rules requires certain additional information collection requirements. The Supporting Statement for Information Collection Requirements in 10 CFR 550.55a is provided in Appendix A.
The proposed rule affects only the licensing and operation of nuclear power plants. The companies that own these plants do not fall within the scope of the definition of "small entities" set forth in the Regulatory Flexibility Act in the Small Business Size Standards set out in regula-tions issued by the Small Business Administration at 13 CFR Part 121.
Since these companies are dominant in their service areas, this proposed.
k rule does not fall in the province of this Act. The proposed rule willi have no significant effect on a substantial number of small companies.
- 5. Decision Rationale From the above analysis it is concluded that the proposed revision to incorporate the latest edition and addenda of the ASME Code will save applicants / licensees and the NRC staff both time and effort by providing uniform detailed criteria against which the staff can review any single submission. No significant additional cost to the applicants / licensees is expected as a result of NRC endorsement of the new ASME Code edition and addenda.
- 6. Implementation No implementation problems are anticipated. The framework for imple-mentation is already established in both the industry and the NRC.
3
Appendix A Supporting Statement for Infonnation Collection Requirements in 10 CFR 650.55a
- 1. Justification I
- a. Need for the Infonnation Collection NRC Regulations in 10 CFR 550.55a incorporate by reference Section III, Division 1, and Section XI, Division 1, of the American Society of Mechanical Engineers Boiler and Pressure
- Vessel Code (ASME Code). These sections of the ASME Code set forth the requirements to which nuclear power plant components are designed, constructed, tested and inspected. Inherent in these requirements are certain recordkeeping functions.
Incorporation of the Winter 1982 Addenda, Sumer 1983 Addenda, ;
Winter 1983 Addenda, Summer 1984 Addenda, and 1983 Edition for '
Section III, Division 1, of the ASME Code would add the y following recordkeeping requirements. 3 Section III o Winter 1982 Addenda NB-2125, Fabricated Hubbed Flanges - New provision for surface examination requires documentation of l
+ examination results.
o Summer 1983 Addenda No additional recordkeeping o Winter 1983 Addenda NCA-3650, Design Documents for A>purtenances -
l Requires Design Document for eac1 appurtenance that is to
' be attached to a component unless it is already included in the component Design Documents.
i o Sumer 1984 Addenda NB/NC-7240, Review of (Overpressure Protection) Report After Installation - Addendum to report required to document any modification of the installation from that used for preparation of the Overpressure Pro-tection Report.
ND-7200, Overpressure Protection Re) ort - Requires overpressure protection report for class 3 components to define the protected systems and the integrated
! overpressureprotectionprovided,and(ND-7240) documentation of any modification of the installation from that used for preparation of the Overpressure Protection Report.
I o 1983 Edition All requirements, except those for Winter 1982 Addenda, previously incorporated in separate amendments to 10 CFR 550.55a.
IThe 1983 Edition of Section III is equivalent to the 1980 Edition, as modified by the Summer 1980 Addenda Winter 1980 Addenda Sumer 1981 Addenda. Winter 1981 Addenda, Summer 1982 Addenda, and the Winter 1982 Addenda.
A-1
-,+--,~,c ,,-m.n-- , _ - - - - - - - . , - , , , - ___.,__,___.c.,._,_.___,.,_._,,,__,,,,_,p..,n___,_. , , _ , - _ . _ _ _ _ , -n._,__,_._,.y..
Incorporation of the Winter 1982 Addenda, Summer 1983 Addenda, and the 1983 Edition of Section XI Division 1 of the ASME Code would
, add the following recordkeeping requirements.
Section XI o Winter 1982 Addenda IWA-6220Lb), Preparation (of Records and Reports) - Requires preparation of Owner's Report for Repairs or Replacenients (Form ~
NIS-2).
o Sumer 1983 Addenda No additional recordkeeping j 2
o 1983 Edition All requirements, except those for Winter 1982 Addenda, previously incorporated in separate amendments to 10 CFR ,
k 550.55a. T I The Winter 1982 Addenda of the ASME Code references ANSI /ASME NQA-1-1979,
" Quality Assurance Program Requirements for Nuclear Power Plants."
NQA-1-1979 is based upon the contents of ANSI /ASME N45.2-1979, " Quality Assurance Program Requirements for Nuclear Facilities" and seven daughter standards. These standards are referenced in Regulatory Guides 1.28, 1.58, 1.64, 1.74, 1.88, 1.123, 1.144, and 1.146 as providing methods acceptable for implementing certain NRC quality assurance program requirements. NQA-1-1979 incorporates no recordkeeping beyond that originally required by the N45 standards upon which it is based. There is, therefore, no additional recordkeeping burden associated with the endorsement of NQA-1-1979.
- b. Practical Utility of the Information Collection These records are used by the licensees, National Board j inspectors, insurance companies, and the NRC in the review of a variety of activities, many of which affect safety. The records are generally historical in nature and provide data on which future activities can be based. NRC Inspection and Enforcement personnel can spot check the records required by the ASME Code to determine, for example, if proper inservice examination test l methods were utilized.
- c. Duplication With Other Collections of Information ASME requirements are incorporated to avoid the need for writing equivalent NRC requirements. The final rule will not duplicate
' the information collection requirements contained in any other generic regulatory requirement.
i d. Consultations Outside the NRC i
No consultations.
i
- 2 The 1983 Edition of Section XI is equivalent to the 1980 Edition, as
- modified by the Winter 1980 Addenda, Winter 1981 Addenda, and the Winter 1982 Addenda.
A-2 i
- e. Other Supporting Information NRC applicants and licensees have been complying with the infomation collection requirements of the ASME Code since 1971.
No problems with these information collection requirements have been identified to the NRC by the applicants or licensees.
- 2. Description of the Infomation Collection l
- a. Number and Type of Respondents In general, the information collection requirements incurred by i 650.55a through endorsement of the Code apply to the owners of the 34 nuclear power plants under construction and to the owners of the 93 nuclear power plants in operation. The actual number of plants that would implement the edition and addenda addressed by the proposed revision, and thereby be affected by their s k infomation collection requirements, is dependent on a variety .
of factors. These factors include whether the application is for Section III or Section XI, the class and type of components involved, the dates of the construction permit and construction permit application, the schedule of the inservice inspection program, and whether the plant voluntarily elects to implement updated editions and addenda of the ASME Code.
- b. Reasonableness of the Schedule for Collecting Infomation The information is generally not collected, but is retained by the licensee to be made available to the NRC in the event of an i NRC inspection or audit.
- c. Method of Collecting the Information
- See Item 2(b).
- d. Adequacy of the Description of the Infomation I
i The ASME Code provides listings of information required and
( specific foms to assist, where necessary, in documenting j required infomation.
- e. Record Retention Period The retention period for information is in accordance with a schedule provided in Table NCA-4134.17-1 of the ASME Code. The retention periods for information keeping requirements specified j in Item 1.a above are:
A-3
Infomation Retention Period (3)
Design document for appurtenances Lifetime Overpressure protection report Lifetime Reports for repair and replacement Lifetime Final nondestructive examination report Lifetime Lifetime retention of the above records is necessary to ensure adequate historical infomation on the design and examination of l components and systems to provide a basis for evaluating degra- '
dation of these components and systems at any time during their service lifetime. ,
, i i
- 3. Estimate of Burden
- a. Estimated Hours y The infomation collection requirements inherent in incorporating ~
by reference the latest edition and addenda of Section III, Division 1, and Section XI, Division 1, of the ASME Code are identified in Item 1.a above. These requirements may be categorized in tems of Section III requirements that document component / system design and the results of construction examinations, and Section XI requirements that document repairs and replacements.
The additional Section III requirements incur a one-time burden on plants under construction. The information collection requirements associated with the proposed edition and addenda are generation of the design documents for appurtenances and the overpressure protection report. Section 50.55a specifies that the Code Edition, Addenda, and optional Code Cases to be applied to reactor coolant pressure boundary, and Quality Group B and Quality Group C components must be detemined by the provisions of paragraph NCA-1140 of Subsection NCA of Section III of the ASME Code. NCA-1140 specifies that the owner (or his designee) shall establish the ASME Code edition and addenda to be included in the Design Specifications, but that in no case shall the Code edition and addenda dates established in the Design Specifications be earlier than three years prior to the date that the nuclear power plant construction permit is docketed. NCA-1140 further states that later ASME Code editions and addenda may be used by mutual consent of the Owner (or his designee) and Certificate Holder. The earliest Section III addenda being addressed in the proposed rule is the Winter 1982 Addenda. Since the last plant to be docketed that is still under construction was docketed in October 1974 (Palo Verde Units 1, 2, 3), there is no plant under construction for which implementation of the Section III edition and addenda specified
' in the proposed rule is a requirement. Plants may implement these improved rules on a voluntary basis, but unless they make that choice, there is no additior.al paperwork burden associated with incorporating the proposed Section III edition and addenda.
3 Service lifetime of the component or system.
A-4 I__, . ._ - .
The additional Section XI requirements incur a burden associated with the documentation of component repairs and replacements.
To facilitate this documentation Section XI provides Form NIS-2, " Owners' Report for Repairs or Replacements."
Information required by this fom relates to identifying the owner and facility; identifying the components repaired or replaced and replacement components; identifying the type of work, the repair organization and by whom the work was perfomed; and identifying the type of tests conducted. A l portion of this infomation, such as that to identify the owner, !
facility and components is already required by Fom NIS-1, "0wners' Data Report for Inservice Inspections," (Form NIS-1 was part of an addenda previously incorporated by reference into 550.55a). Most of the remaining information required by Form NIS-2 can be obtained from the previously prepared component work / repair order. It is estimated that the time required to complete the required documentation on Form NIS-2 is ten hours. y Nuclear power plants are required to update their inservice inspection programs by incorporating into their initial 120-month inspection interval requirements of the latest edition and addenda of Section XI, Division 1, that have been incorporated by reference into 650.55a as of 12 months prior to the date of issuance of the operating license; and by incorporating into successive 120-month inspection intervals requirements of the latest edition and addenda of Section XI that have been incorporated by reference as of 12 months prior to the start of a 120-month inspection interval. On this basis, many plants will at one time be required to implement the Section XI, Division 1, edition and addenda specified in the proposed rule. The number of plants that will be implementing the specified edition and addenda will grow gradually as each plant updates its inservice inspection program at the 10-year interval. Therefore, conservatively, the total number of plants that may ultimately be required to implement the specified edition and addenda is 127 (i.e., 93 operating plants and 34 plantsunderconstruction).
Inservice inspections are typically performed at the time of refueling (i.e., approximately every 18 months). The need to complete an NIS-2 form would occur as a result of a repair required by the results of an inservice inspection, or as a result of an unanticipated repair between refuelings. It is estimated that 2 NIS-2 foms are completed for repairs resulting from the inspection and 2 for repairs required during operation.
Assuming applicability to 127 plants, and the completion of 4 NIS-2 foms by each plant every 18 months, with ten hours required to collect information and complete each form, it is estimated that the total time required by all utilities to complete the NIS-2 form is approximately 3400 hours0.0394 days <br />0.944 hours <br />0.00562 weeks <br />0.00129 months <br /> / year (i.e.,
4 forms x 127 plants = 508 foms per 18 months, 508 forms x 2 =
1016 forms per 3 years,1016 forms / 3 = 339 forms per year.
I 339 forms x 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per form = 3390 hours0.0392 days <br />0.942 hours <br />0.00561 weeks <br />0.00129 months <br /> per year). The time required to maintain these repair and replacement records for A-5
i f . . e the period noted in Item 2.e is estimated to be 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / year for
, each plant. Thus, the total time required by all utilities to complete and maintain the NIS-2 form is approximately 3517 hours0.0407 days <br />0.977 hours <br />0.00582 weeks <br />0.00134 months <br /> / year.
- b. Estimated Cost Required to Respond to the Collection Based upon the hours specified in Item 3.a. it is estimated that the cost of responding to the information collection required by the Section III, Division 1, and Section XI Division'1, edition and addenda specified in the proposed amendmeht to 650.55a is a total of $211.020/ year (3517 hrs x $60/hr) for 127 plants.
- c. Source of Burden Data and Method for Estimating Burden Estimates of the number of NIS-2 forms that are completed during a year and the time required to collect the necessary ,
T im information and to complete the forms, were obtained from utility staff inservice inspection specialists and NRC staff in the Office of Inspection and Enforcement (regional and headquarters) engaged in inservice inspection activities.
- d. Reasonableness of Burden Estimate The estimate of the burden is considered reasonable because of the reliable source of the burden data.
- 4. Estimate of Cost to the Federal Government NRC inspection personnel who audit plant quality assurance records would include in their audit verification of the proper implementation of the NIS-2 form. The time associated with NRC inspectors verifying use of the NIS-2 form would be extremely small when the activity is performed as part of a normal quality assurance audit.
G 5
A-6 g- - '
+e-+.,. . - . , , - , , - ------.-m-mw- -- -, e- ---
q ; p_ ,y. y .
.A A E3 -1 7
s w . i. :. w .. -s. r r m .. h m .8 . e ... .-. a... P D R, . . .
j .. .. . .:. .
i .. .
M:
asonday.
April 2b,1985
. . . . . . . _ ._ , _ _ ____ _.. 4. . . _ - _ _ . .. .. .
~~
'G #1 D. -
,u
' ~
, . c,. ,
- e
- k . . . ,
^
- e .
' t .
l l -
a si ' -
. .. , . . d. *
- t .
- I / *
- .' g.
F ,.
, e L ."d' ' . .' . E . ., , ,gy. , ,
!.' P. art LVil a
- . .om.
'.r.,.. ,
- an , .s V. -
,, ., j, A. .3 *'#- .i , .- , ..
.a ..- -. -
1
-Nuclear.RegulatoYY
~
, . . ~ . .. . . . .
~
T. . ." : Commission
. ~ . .. -
4 m . .. . _ ... . S.emia,nnual Regulatory Agenda .. . .
~. -
.r . , .- .. . ,: . ;. -
' #. ' , l 3.
- T 7! !".'.
. u .,.-~...
~ '
I 1 , . J a ir, , . . far'! aM '
6 9-ih.\
b
. ...e
- 8
- s% ! u, .
- s. s . , , ,
.'='.*
! I n
, h ,.
. , ._s o i '
- * ' i 5, .- ,
, ,, ,t
.- * ." ~# :i. . t* - . '. . , .
~*.. -
' * ~
, , . , . - . 3 4." .
, . e, ,
7 s . . , . .
, .* * .#' .* Y Ja'
=- ... .
c . . . . . , . .. .c.
Je._ .
.>- .,g.. .
'* .' y ;; l n , a . .
. :T'. : ~v:. ? > : ..T e e.:t. si .. r .
. .s-
. wi,1.: w .w.. .. a .. . .. v. . . . . . ... . - . .
. .2:sru.: :.w i: 1:;. n s.. ', -
u.. ,- e.: v. ..e )..J y ,; ;- ., c: ,
.. . . . . .wr us.t.n3 .= F. d..:.*. u. . :- r. e . ; a: t. y'. : ~%
9 e
G
1_
Fadesel Radster / Val go No.42 /. Mand 2y. April as, ness / timia.a @ .T/. ,
1
.c .. _ . ,. . . . . .. - . . . . . . . - . . . . . . - - . -
blC. .e - .a -- t i .:% tv. t, .
Current anci W %
= *
- 4 haposed by license conditions, the met TensteMe: . CFR Chation: 10 CFR so '
increase in cost would be about Aseen Date 941Este A. bstract:De proposed rule would -
3350 000 per year for the industry or chout taooo per licensee.ne proposed MPnu w oo/es gQg by se emnos jnte ,*
. rul3w K ish g a e g g Small Entity: No A0ency
Contact:
June Robertson.
Winter 1983 A AdanAm Summn 1984 Addenda,and the 1983 F/ition of would minimise the effort requiE to SectionIII, Division L of the American ,
Nuclear Reguletory Counmission: OlEce obtain reciprocity for NRC licensees to - et Neclear Material Safety, and' Society of Mechanten1 Engineers Boiler 8pomh (cent) and pressure Vessel Gode (ASME Safeguards. Wasidngton. DC, Set egy.
Code), and the Winter 1962 Addenda.
Theetable: Sees Summersees Addanda and the 1983 Asema sans en same ggg. sim Edi6on of Sectica xI. Division I, of the '
MPW 04/qo/85 ASME Code.he ASME Code sets 70.EXTEletott OF CRitetNAL - standards for the construcuan oflight.
emeB Engly: No .
water-reactor nuclear power plant PEIRALTIES s in '
Agreement Ste ce L89al Authodty: 42 USC 2 rot co7an
, en &
. versa.He rule would CFR Cateten: 10 CFit 50 inurvice inspcum d be a-i- w air-se- s ruie.In . m ,o m is M S.co . xi.oivisi t by MRC. A,,,,ect
,,,,,4 ,,,,%e,g_ , tine provisions ofIbe De proposed rule would te the existing refasence to the Code Agency
Contact:
Anthony N, Tee, . NRC Authorisation Act for FlecefYear Nuclear Regulatory Comminolon, Office sego, would extend b appHoeHan g and would thereby permit the use of gie eramen=1 penalties i,..,C d the improved methods for the construction of Nuclear Regulatory Researdt AtomicEnerEY Act(AEA) of1864,es and inservice inspection of nuclear C.
Washington, DC 3D555,30144Mtet -
amended, to any indiYidual director, power plant components. ,
, . , 3 ,
- Ritt: 3166 A835 f i. officer, or employee d a Srm -.
Incesporadas by afssenca the latut .. -
- ' edition and addenda of the ASME Cede ggy 4.o g m.g ' :.
- constructingorsupplyingthe components of a nuclear paw will save applicants / licensees and the .
m . , .m. a . r.e z who knowingly and wlDfnEy tes fetCstaff both thne and effort by W: e.
.- . . . , . 4 .. .
providing miform detailed ersteda ,A..
Legal Autherty: At bec spot; 42 MBC any NRC esgulation, seder, er Bcense
- e841 : J ~ c--. . t.
conditlen during construction of a' against which the staff canseelew eary nuclear power plant Secum 223(b) of - single submissien; Revisions to the '
CFR Citation: 10 CFR 40; 10 CFR 7tt, le ASME code are achieved thmugh the"
.w the AEA essentiaHy directs Gne '
CFR 150 -
- Commt,aton to establish a lhnit for ^ ' (cont) u a , -) w- *h.
80880'*8U N r'~, - - , "I' -
potential unplanned off site releases of D"M' '~~'
T ' ' '
i emend the seguirements applicable to f . tige ==h==f==ta= elsoume amater radioactive material which would il a and: trigger consideration of possible : Acuen e Egees < t g41 cas ..
,i
'special nuclear asalarial lmatory '. L -criminal penalues. As directed ins ~-' """" - -
) ist 94/00/e5a,,,,,,, -
- reports. %e proposed rule would . . , Secum 223(bp),& propoud rde d mh-An=te h requiramt to nport establishes,in its definition of a " basic
- SmeE EnSty: No + a . eW T.W ~
~~"
l inventories on Form y42 for all
.; component." the ihnits for potential , 'ABSHACT
'f"' " "" .
me - '- utBfly, regulatory, ed othe interests .
! foreB neces except fhose for Timetable:
concemed with the code and ensures
! ruclear reactors and those reporting Aseen . sines en cas that the vaine of any revisions to the .
ender the agreement.%e NRC would -
codeis emaistent wi& tts impact. -
l NPW -
01/co/86 ,,
'. generate an equivalent invetitory report. Agency
Contact:
GGhert C. ham-an
!- based on the data submitted by each Smau Entity: No NuclearRegulatory cnemiazion. Office
! cffected licensee; and the licensee A0mcy W M UW' d Nuclear Regulatory Ruearch -
j ,
w uld verify the accuracy of the report. Nudear Regulatory Commlasion OfBoe - Washington E20655,30144b
%Is amendment would reduce the - ' of Nuclear Regulatory Researdi. .
the- WasMagton, E 20555,301443NS
' M MM f Bcensee a y reely ff domestic safeguards program on that RIN: 3150-AAso . '
- y2. PRIMARY REACTOR .
t 'tbility to satisfy international ..
CONTAINMENT LEAKAGE TESTING .
commitments.%e proposed reduction -
would result in a total cost savings of 78. + CODES AND STA8tDARDS FOR - FOR WAN POWER A., - _j ,
NUCLEAR POWER PLANTS (1983 - REACTORS
.j
$39.000 for affected licensees.' " . c. s: EDITION, WINTER 1932 THROUGH ".. . y5,3 , , .
SUMMER 1984 ADDENDA)
Legal Authority: 42 USC 2133; 42 USC y
. . .c .
r . m . . i t.
. E : . s . : - c . sa.- Legal M .42"E '2201; 42 M' ";"*" ' rh . 7 1 I
.. ...e,.
"ar,w "
.t.x. 6641
^ '-
' ~
. g' CFR Cltation: .S173 go.,,,',,,,,,,,,*;,
r . m ..m. e
.. n. .
b s
a y ,. - - ~
AA23-1 '
?
20574 PhR 1 Federal Register / Vol. 50. No. 96 / Friday. May 17, 1985 / Proposed Rules- i ?
cction is not taken. State agencies shall Code (ASME Code), and the Winter 1982 the construction of Class 2 and Classa
? j g not enter into an agreement with any Addenda. Summer 1983 Addenda.and components.
f i V. go, , e p,
)j T.=
t institution included on this list of 1983 Edition of Section XI. Division 1. of Since publication of the last ASME inillgible lastitutions and shall the ASME Code.The sections of the Code addenda incorporated by trrminate any participating institution ASME Code being incorporated provide ir reference in i 5055a. the Winter 1982 i included on the list within 15 days of the rules for the construction oflight-water- Addenda. Summer 1983 Addenda.
cc receipt of notification by FNS of the cooled nuclear power plant components Winter 1983 Addenda. Summer 1984 A \ the cc institution's ineligible status. Once and specify requirements for inservice Addenda, and 1983 Edition, to the Ragd included on this list, an institution shall inspection of those components.
be iniligible to participate in the ASME Code have been issued.'Ihe 1983 h g Adoption of these amendments would Edition is equivalent to the 1980 Edition. v.
progr:m until such time as FNS,in permit the use of improved methods for I I' as modified by the Summer 1980 2 consultation with the appropriate State construction and inservice inspection of Egency, determines that the serious '
Addenda. Winter 1980 Addenda, t Z ; .cos nuclear power plants. Summer 1981 Addenda. Winter 1961 d;ficitncy which resulted in the iniligible status has been corrected. Any carts: Comment period expires July to . Addenda. Summer 1982 Addenda, and Winter 1982 Addenda.The Commission j Q [g!
1985. Comments received after this date g institution which is identifiable with a proposes to amend i 5055a to i
, , seriously deficient institution through its will be considered ifit is practical to do i 9 g 33 so, but assurance of consideration incorporate by reference all editions corporate organization, officers, , cop; cannot be given except as to comments through the 1983 Edition and all "
employees, or otherwise shall also be ~ fron h ceived on or before this date. addenda through the Summer 1984 I considered to be ineligible unless it is Eng d;menstrated to the satisfaction of the Addenda that modify Section III. ~
ADDRESSES: Written comments or "*'
Stata agency, with FNS concurrence, suggestions may be submitted to the Division 1. and all editions through the d ^
Secretary of the Commission. U.S. 1983 Edition and all addenda through thit good cause exists for considering the Summer 1983 Addenda that modify the institution distinct from the seriously Nuclear Regulatory Commission.
Washington, D.C. 20555, Attention: Section Xh Division 1.of the ASME -
dificient institution. Denial or Docketmg and Service Branch. Copies of Code.The Summer 1983 Addenda for termination actions taken on the basis Section XI does not include any N 'C' of FNS notification ofineligible status comments received may be examined in an.
shril not be subject to administrative technical requirements related to the Commission's Public Document **
Room at 1717 H Street NW., Division 1. but is being included in the 0 review as provided in i 226.6(j). # E IlowIver, an institution which FNS Washirgton, D.C. . reference to avoid confusion that might occur with a lack of continuity in the he d;tirmined to be seriously deficient and FOR FURTHEN INFORsfATION CONTACT: addenda references.
which has not taken acceptable Ps Mr. G.C. Millman, Division of Editorial revisions are proposed to corrective action nay request an Engineering Technology, Office of correct certain existing footnote and cdministrative review of this Nuclear Regulatory Research, U.S. I" determination by an FNS review official paragraph references that are ,
Nuclear Regulatory Commission. inconsistent with the last amendment ai in cccordance with the appeal A procedures set forth in i 226.6(i) and Washington, D.C. 20555, Telephone (301) (49 FR 9711) to this rule and to simplify 443-7800. the language.These editorial revisions "
will not be included on the list of h in ligible institutions unless FNS* SUPPLEssENTAAY INFORMATION:On are contained entirely in i 50.55a(g).
February 7,1983, the Nuclear Regulatory For facilities whose operating licenses t determm,at,fon is upheld by the review Commission published in the Federal were issued prior to March 1.19766 this '
", , , , Register (48 FR 5532) amendments to its rule provides the effective date for I M e s sy H. m regulation.10 CFR Part 50, " Domestic implementing the inservice inspection Licensing of Production and Utilization requirements and for defm' ing the
- h *"L Facilities " which incorporated by effective edition and addenda of the l Administmfor, FoodandNutrition Servica reference new addenda to the American Code for the start of the next one-third *
(FR Doc a5-12002 Filed 5-16-85; 8.45 am) Society of Mechanical Engineers Boiler of a 120. month inspection interval after y saisie coca swas September 1.1976. Since this one-third and Pressure Vessel Code (ASME Code). The amendment revised i 50.55a of an inspection intervalhas already to incorporate by reference the Winter been completed for all applicable NUC W HREGULATORY 1981 Addenda to Division 1 rules of. facilities,it is proposed that the part of
~ " ' Section IIL " Rules for the Construction the rule addressing it in i 50.55a[g)(4)(iii) of Nuclear Power Plant Components." be deleted.
"E S, and Division 1 rules of Section XL Power reactors for which a notice of
" Rules for Inservice Inspection of hearing on an application for a Codes and Standards for Nuclear Nuclear Power Plaot Components," of Power M provisional construction permit or a the ASME Code. On November 4.192, cons,truction permit had been published AGENCY: Nuclear Regalatory the Commission published in the Federal on or before December 31.1970L were Commission. .
Register (48 FR 50878) an amendment to - permitted to use the rules for ACTioec Proposed rule.. I 5055a to incorporate by reference the construction required by power reactors .
Summer 1982 Addenda to Section III, that had received their construction suesasARY:"Its Commission proposes to Division 1.of the ASME Code. The permits prior to January 1.1971. It is cm:nd its regulations to incorporate by ASME did not publish a Summer 1982 proposed that i 50.55a(1) which covers refirence the Winter 1962 Addenda. Addenda to Section XL On March 15 this provision be deleted because it is no Summ:r 1983 Addenda. Winter 1983 1984, the Commission published in the longer necessary, Section 50.55a(c)(4)
Addenda, Summer 1984 Addenda and Federal Reg [ ster (49 FR 9711) an provides that for these and other 1983 Edition of Section IIL Division 1. of amendment to I 5055a to among other facilities that received a construction th3 American Society of Mechanical things, incorporate by reference those permit prior to May 14,1984, the Engineers Boiler and Pressure Vessel - subsections of Section III which apply to applicable Code Edition and Addenda
- .. . 1
- 4 20575 Federal Register / Vol. 50. No. 96 / Friday. May 17, 1985 / Proposed Rules does not fall within the purview of the Paragraph (g)(4)(iii)is removed and ' I
" for o component of the reactor coolant reserved; and ,
i
- pressure boundary continue to be that Act. Paragraph (i)is removed.
' Coda Edition and Addenda that were Ust of Subjects in 10 CFR Part 50 -
required by Commission regulations for 150.55a Codes and stamients, Antitrust. Classified information. Fire ,
th3 component at the time of issuance of prevention. Incorporation by reference. ;
'th] construction permit Intergovernmental relatione. Nuclear (b) * * ,
i Regulatory Analysis power plants and reactors. Penalty. (1) As usedin this section. references Radiation protection. Reactor siting to SectionIII of the ASME Boiler and L Thi Commission has prepared a draft Pres ure Vess Code r a criteria. Reporting and recordkeeping regulttory analysis on this proposed requirements.
regulation.The analysis examines the Pursuant to the Atomic Energy Act of' through the Summer 1984 Addenda.
' cost cad benefits of the alternatives considered by the Commuasion.N 1954 as amended, the Energy (2) As used in this section. references 4 dr-ft entlysts is available for inspection ReorganW= Hon Act of 1974. as ===aM to Section XI of the ASME Boiler and #
-in the NRC Public Document Room.1717 and 5 U.S.C. 553, the NRC is proposing Pressure Vessel Code refer to Section 11 Street NW., Washington. DC. Single to adopt the following amendments to 10 XI. Mion 1. aM indade edides ;
& rough the 19a3 Edition and@nde .' - '
copits of the analysis may be obtained CFR Part 50.
from Mr. G. C. Millman, Division of through the Summer 1983 Addenda. gt*%
EngineeringTedmology Office of PART 50--DOMESTIC UCENSING OF subject to the following limitations and Nuclear Regulatory Research.U.S. PRODUCTION AND UTIUZATION modifications.
FACTUTIES 9 Nucle:r Regulatory Commision.
Waahington, D.C 20555. Telephone 1.The authority citation for Part 50 (g) + a + b D
(301) W 8 M. continues to read as follows: (3) * *
- Commission mqueste puh (i) Components which'are classified
[W E comment on se dran mgulatwy Authadry: Secs. tas,104, tot, ts2,183, tee, 1as, es seat. 936,937,948,964 SSE,968, as as ASME Code Class 1 shall be designed l f.h '
entlysis. Comments on the draft amended. sec. 234, sa Stat.1244, es amended and be provided with access to enable i me pufomance of h ;
- O' ana}ysis may be submitted to the NRC O
! - as indicated under the ADDRESSES (a UAC 2133, 2134,2'01. 2232, 2223. 223a, 2239. 2282): secs. 201. 202, 200, e8 Stat.1242-1244,1248. as amended (42 UAC 5841. sa42-examination of such components and shall meet the preservic'a aammation
[
hsading.
m se rth in Sec XI of p ,
Paperwork Reductlas Act Statement 5e48) 3 , p, , g ,5, '
'this proposed rule amende e01 sec.E 92 Stat.2 set (42UAC Sast).
Sections 50.57[dk 50.5a,60.91 and sa92 also Presaare VesselCode and Mderula * [-
inforuntion collection requirements that alssued under Pub. L 97. 416,9e Stat. 2er1. , applied to the construction of the particular component ! [J cre subject to the Paperwork Reducdon Act of 1980 (44 U.S.C 3501 et seq.). ' Itis 2073 (42 UAC 2133,2239) Section 5a58 also
- * * * .W M
- issued under sec.122, ce Stat. 930 (42 U.S.C l rule has been submitted to the Office of 2152). Seceane caso-so.st also issued unde ' (iii) Pumps and valves which are Management and Budget for review and sec. toe es samt. 954, u amended (42 UAC clannihd as ASME Code Ciass 1 shall approvalof thepaperwork 2234). Sectness satos-se.to2 also +=a w be dmW aM be provided wis N'#b* M
'*9"I" "*"'** d "pN ise,es * 's access to enable the performance of Nf
, sa of se S a a inservice testing of the pumps and M&
Regulatory FlaxIbility CarH&=Hn=
la c~ccordance with the RegulaN amended f42 S C 2273), il sato(a). (b),
and (c),50.44,5a46,5a48, sa54 and 50.80(s) are issued under see telb. es stat. 948, as valves for assessing opefational readiness set farth in Section XI of p;
Flexibility Act of 1980. 5 U.S.C. eOS(b), amended (42UAC2201(b));11saio(b)and ' editions of the ASMEBoilerand
. ibr$( M tha Commission bereby certifies that Pressure Vessel Code and Addenda 8 p C.?
this rule wul not, if promulgeted, have (c) and 50.54 are issued under sec.101L se Stat. 94s. as amended (42 U.S.C 2201ti)) and applied to the construction of ths , ,W:*
significant economicimpact on a lI so.55(e). 5ase(b), so.70, 5071. Sa72. 5073 particular ump or valve or the Summer substantial number of small entittee. and soJs are issued under teto, es Stat. 9so, 1973 Addenda, whicheveris later" i@N fC 3 U
as amended (42 UAC 2201(c)). , , ,
. 'this proposed rule affects only the licensing and operation of rnaclear I4) . . .
[bMh l
- 2. Secuon 50.55a is amended as rogown.
.G power plants.The companies that own these plants do not fall withis the scope Paragraph (b)(1) and the introductory .
N, ***"gI.
. . ' ! WC $N
> cf th2 deGnition of "susall entities ** set text of ar ph (b)(2) are revised; D forth in the Regulatory Flexibility Act o' Refe nc footnote 2 in paragraph gPril 985. y a. .
the Reall Business Size Standards set (g)(1)is deleted; References to footnote 3 in paragraph For the Nuclear Regulatory Co==udna g9 cut la regulations issued by the Small (g)(2) and in paragraphs (g)(3) (ii) and Jack W. Res. - NQ Business Administration at t3 CFR Part (iv) are removed; Acung Executive Duectorfor Operudans. 3, 121.
(FR Doc. 85-11998 Filed 5-16 45: a:45 aml F,,f Paragraphs (g)(3)(1) and (iii) are Since these companies are dominant in their service areas, this proposed rule revised; =n =ia coca rese*4s ]{
]<f
< 1,,
$ v!
2 M
\ _____-. _ _ _ _ _
. ,.4- s
~
^1 .
pg34
. PDR
- floderal Register 1 Vd. so. No. g6 f %uredty, May to.1985 / Natices 35513 Ordere of the Conw-a newer . associated with Appendix R has teen IV hereafter la effect. - ~ completed.%e routing of the fire weich Acewdingly.Se Commission has ne facility - A two wSI be established so that the petrol .pumuant 2 to Cm T - __ ; d water reactors at the observes each area at a frequency of Mennind 50.12, an exemption is authorised by law consee's riteloosted la Goodbue about every 20 minutes to ensure that a an ad av W pmW w County Minnesota fire could not dem'8e redundant safe the common defense and security and is H shutdown related equipment. If a fire otherwise in the publicinterest and
""' CC"#* * ""I"I MOM * ' hereby grants the fouowing exemption By lettses dated Deoseber 31.1984 immediately notified and the Bre and janaary 30,1985, the hoonm wnh mpact b b requirements d brigade response initiated.P=ndmp the subsection IH.G.of Appendix R to 10 requested an exemption from the arrival of the Bre brigade the fire watch CFR Part 50t schedulari- ' -
,ts of to CFR so.48(c), which establishes deadhnes for patrol will be trained in the proper use F end Maplememahn datMo CFR of Portable fire extinguishers in ee completion d Ere protection 80.48 (c)(2) for instaBation of modification in modifications required by Appendix R suppressing the fire before significant Fire Areas st.sa. sa, se 7s and 74 requir-d by to 10 CPR Part 50 Specifically, the damage could occur. On this basis,if a Appendix R subesction ELG for both ur .s.
licensee requested that the current fire would occur within an area from December 31.1ges to lene 1.19e5.
deadline of Decesiber 31,1984 for the provided with a fire watch, there is Pursuant to 10 CFR 51.32, the installation of one-hour barriers reasonable assurance that it will be detected in its indpient stage before Commission has determined that the pursuant to section HLG.2(c) and the issuance of the Exemption will have no axemptionissued by letter dated April significant flame or temperature rise significant impact on the environment 38,1984, be extended to June 1,1985, for occurs-both Prairie Island units. %e request .h licensee's efforts to complete the (50 FR 18333) applies toFire Areaa31,32,Jia,59.73 Dated at Bethesda, Maryland this 7th day ane. hour barrier installation have been of May, seas.
and 74.in which areas certain
- delayed somewhat by the late delivery shutdown < elated cables are being of wrapping material and unforeseen For the Nuclear Regulatory Comuniesion.
wrap to provide the sequisite one- Harold E. Dentes, "
interface problems between har .
-- - .uiuvumental qualification work going Dimeror. Offim ofNuclearJteoctor on at the same time as Appendix R Jtegulation.
Hg efforts were being planned.De delay in [yR Doc. 85-11s08 Filed 5-15-85: Etes am]
%elicensee states that the - material delivery was due to t'io large me.una eaos resw e installation of cable wrapping in these fire areas is the only remaining influx d mders which the mmfacturer received after approval of the material Appendix R modification for the Prairie Documenta Containing Reporting or Island units.1n the fire areas mentioned, by the NRC sehff. A design hold was all other Appendix R measures have placed on the associated cable wrapping Recordkooping R-t a r.O; Office -
in Fire Areas 31 & 32 until the potential of Management and Budget Revlww been taken to the extent required. i.e.,
suppression and detection capabilities. Issue of relocating the auxiliary Aemsev: Nuclear Regulatory Specifically,in Fire Areas 31 and 32 the feedweter pumps related to Conugission.
1 shutdown related systems are m62d environmentalqualificatim was by automatic fire detection an[ fire ' resolved. Acviost14otice of the Office of
%e only remaining activity in Bre Management and Budget review of suppression systems.lf a fire should occur in eese amas. R would be protection at the Prairie Island Nuclear infenstia collection.
detected in its initialstages and Generating Plant is the installation of aussesany:%e Nuclear Regulatory suppressed by the suppression systems the cable wrapping in the affected fire Cornrnissim has acendy subrained b i
to allow time for the fire brigade to areas Moreover the staff has judged se Mim M Managenwnt and Budget attend the fire during its infancy, before tlist tiie delays encountered by the i B) fw mvim me foHwing pmpmal
' algnificant propagation occurs. lf a rapid licensee were unforeseen and could not tempersture rise occursbefore the for the collection of information under i
be avoided.In addition,the interim ee provisima d te Papawork arrival of the fire brigade, the fire c MPensatwy measums cornmined to Reduction Act (44 U.S.C. Chapter 35).
suppression systent would actuate to contml&e Em and pmtect tlm shutdown systems. We therefore have
,,,,) ,, 'Y oi y ,,
U
- 1. Type of submission.new, revision, or extensi n: Revision.
level of safety that is equivalent to that reasonable assurance that, pending intended by Appendix R.
2.W ude d the infamaHon completionof thelicensee's AppendixR collection:10 CIR Part 50, Domestic relat,ed modification, a fire in either of ne staff finds that eelicensee has Licensing of Production and Utilization these two areas will not result in proceeded diligently to implement Facihdes disabling the shutdown systems to the Appendix R at the Prairie laland units 3.ne form numberif applicable:Not and that the fire protection sneasures appBcable.
extent that the safe abatdown could not be achieved and maintained.
required by Appendix R have been hastalled with the sole exception of the 4.How often the collection is In the semaining areas (i.e.,58, so.78, required:3 times / year.
cable wrap forwhich the extensionis and 74) that do not have a fim 5.Who will be required or asked to suppression system,thelicensee .. requested. Under these circumstances, the public health and safety will not be report: Owners of nuclear power plants.
committed by letter dated January 30.
adversely affected by the extension of S. An estimate of the number of 1985 to implement a roving fireweich the deadline for a period of 5 months. responses: 830 per year.
- patrolin the remaining fire areas for -
which the schedularmilef has been especially considering that the worls will 7. An estimate of the totalnumber of be accomplished steadily throughout hours needed to complete the requested.ne fire watch will continue until all fire protection related work this period. requirement or request: 3517 hours0.0407 days <br />0.977 hours <br />0.00582 weeks <br />0.00134 months <br /> / year.
- jo I kG A0Sl.3
30514 Fedesel Registee / Vcl 50, N3. 95 / Thured y, May 18, 1985 / N:tices g -
- 4. An indication of whether section In accordance with the licensee's (vi), a change widch either may result in 3504(h). Pub.L 96-511 applies:Not application dated February 14.1985, the some increase to the probability or applicable. proposed amendment would revise the consequence of a previously. analyzed
- 9. Abstract:ne proposed rulemaking Technical Specifications to incorporate accident or may reduce in some way a updates existing references to specific design changes to the Control Room / safety margin, but where the results of sections of the ASME Boiler and 'ISC Emergency Mltering System and the the change are clearly within all Pressure Vessel Code that set forth Air Supply System which are acceptable criteria with respect to the requirements by which nuclear power subsystems of the new Control Room / system or component specified in the plant components are constructed and 'ISC Emergency HVAC System. Standard Review Plan (SRp): for inspected.These requirements provide Specifically, the amendment would: (1) example, a change resulting from the that plant owners maintain records of Change the name of the Emergency application of a small refinement of a certain safety related activities.The ControlRoom Filtering System to previously used calculational model or remrds can be used by NRC to audit the Control Room /TSC Emergency Filtering design method.
performance of these activities.ne System. (2) change the 1.imitirig The change in name of the Emergency ret.ordkeeping applies to the owners of Condition for Operation (LCO) for 6e ' Control Room Filtering System to
. nuclear power plants and does not Filtering System to reflect the new Control Room /TSC Emergency Filtering affect the general public. . design. (3) revise the surveillance testing System is the same as example (i) of an Copies of the submittal may'b'e . of the Air Makeup System to reflect new administrative change because it inspected or obtained for a fee from the design flow rates and Control Room / involves only a nomenclature change.
' NRC Public Document Room.1717 H TSC positive. pressure requirements, and The modified Control Room /ISC Street NW., Washington. D.C. 20555. (4) revise surveillance testing of the Emergency HVAC System including the Comments and questions should be filtering system to reflect proposed Control Room /TSC Emergency Filtering directed to the OMB reviewer Jefferson reduced removal efficiencies for testin8 System and the Air Makeup System B. Hill, (202) 395-7340. of the charcoal and HEpA filters and to satisfy the acceptance criteria of SRP - ,
NRC Clearance Officer is R. Stephen reflect new' design flow rates. The NRC Section 8.4 and Ceneral Design Criterion Scott, (301) 492-8585. -
staff earlier reviewed the pro sed 19 of Appendix A to 10.CFR Part 50.
l Technical Specifications for ese four
-l Dated at Bethesda. Maryland shis 13th day Since the changes proposed to the of May tees. Items and foun'd the proposed reduced Technical Specifications are necessary For the Nuclear Regulatory Commission. removal e!!iciencies for testing charcoal . to reHect design changes to the Control
,,m,g and HEpA unacceptable. Subsequently, Room /ISC Emergency HVAC System.
by letter dated May 8,1985, the licensee this change is similar to Example vi.
Dinictor OfficeofAdministmtion. ,
p1t Doc.11s07 Filed.5-1545;si 45 am) Therefore, since 6e application for app catio od proposed p '
,"" ch the reduced an !
"",'", ",entin
})ar t examp
. U"8I no significant hazards considerations (Docent too. 50-3121 . original tech specs remain unchanged.) exist, the Commission's staff has ma~de a Before issuana of the proposed that the l
l Sacramento Municipal Utsity District; Consideration of laanance of ,.
license amendment, the Commission will have made findings required by the
] ed d tion y es significant u
Amendment to Faciuty Operating Atomic EnerEy Act of1954, as amended omsideraum.
Ucense and Proposed Dio Significant - The Commission is seeking. public -
(the Act) and the Commission's
, i Hazards Considerenon DeterminsUon~ regulations. . . comments on 61s pmposed
-and,Oppatung for % ein y da of de n a ed n publication of this notice will be
%e U.S. Nuclear Regulatory request involves no si:;nificant hazards Commission (the f'.ammiasion)is consideration. Under the Commisison's considered in making any final coesidering issuance of an amendment regulations in 10 CFR 50.E2, this means determination. %e Commission will not to Facility Operating License No. DpR- that operation of the facility in- normally make a final determmation .
54, issued to Sacrammto Municipal accordance with the proposed unless it receives a request for a Utility District (the hcensee), for hearing. -,
amendment would not:(1) Involve a -
operation of the Rancho Seco Nuclear significant increase in the probability or Comments should be addressed to the Generating Station locatedin . consequences of an accident previously . Secretary of the Commission, U.S.
Sacramento, California- evaluated; or (2) aente the possibility of Nuclear Regulatory Commission, .
To satisfy the habitability - a new or different kind of accident from Washington, D.C. 20555 Attn: Docketing sequirements of NUREG-0737. Item any accident previously evaluated; or (3) and Service Branch. .
-III.D.3.4, the Control Room Emergency involve a significant reduction in a By June 17,1985, the licensee may file Heating. Ventilsting and Air margin of safety, a request for a hearing with respect'to e Conditioning (HVAC) System was ne Commission has provided - issuance of the amendment to the
- changed from a single train systeminto guidance concerning the s'pplication of - subject facility operating license and a two-loop redundant full-flow system. - the standards in to CFR 60.92 by . - ' any person whose interest may be In addition, the Control Room providing certain example (48 FR 14870). affected by this proceeding and who Emergency HVAC System was Examples of actions likely to involve no wishes to participate as a party in the expanded to include the Emergency significant hazards considerations are proceeding must file a written petition HVAC requirements for the Technical Example (1), a purely administrative forleave to intervene. Request for a Support Center (TSC).ne new Control change to the Technical Specifications: hearing and petitions forleave to Room /TSC Emergency HVAC System is for example, a change to achieve intervene shall be filed in accordance j designed to satisfy the habitability - consistency throughout the Technical with the Commission's " Rules of requirements of both the Control Room Specifications, correction of an error, or Practice for Domestic Ucensing and the 15C. ,
a change in nomenclature; and Example Proceedings"in to CFR Part 2.If a N
- W
-, ____. _ .