ML20137S329

Requests That Encl Fax Be Distributed to Docket File 52-003,PDR & to Project Manager for AP600 Review

ML20137S329
Person / Time
Site:	05200003
Issue date:	02/23/1999
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9906040061
Download: ML20137S329 (13)

Text

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.9L NOTE TO: Deshet N o 4340sx:-a

• Jerry . Wik=ry=(Senior Policy Analyst Ab FROM:

DMs iodulatory improvement Programs Office of Nuclear Reactor Regulation

SUBJECT:

FAX ON AP600 SCHEDULE Please distribute the attached fax, dated February 23,1999, to docket file 52 003, Public Document Room, and to me (project manager for the AP600 review). It is not necessat/ to distribute this document to the remainder of the normal RIDS distribution for AP600.

. oc w/o attachment: C. Grimes, RLSB/ DRIP /NRR IP' 2881 % s h! Mk n

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.0 Chris Grimes . NRC Following up on our telecon this moming, this note offers my thoughts on the schedule for completing certification of the AP600 design.

1. The DCDla complete and approved.

2. Rulemaking has been completed previously for GE and CE advanced plant designs. A copy of the final GE rule is attached, with items that require changes for the Westinghouse AP600 highlighted. Making the changes should not involvo more than a few days effort. We will draft the changes and provide them to you if that would be useful.

Subsequent NRC staff review, ACRS review, and Commission review should also require mlnlmal time and effort if presented as changes to previously approved rules supported by a previously approved technical document.

Seventy five days were allocated for public comment as mentioned in the 2/11/99 tasking memo status report. Assuming there are. no hearing requests, it should be possible to obtain the necessary subsequent reviews and approvals of the final rule within one week.

3. A strawman schedule for discussion.

Prepare proposed rule 3/5/99 Obtain NRC staff approvals 3/19/99 Submit to Commission 3/22/99 Obtain Commission approvals 4/5/99 lasue proposed rule for:

public comment 4/9/99 comment period ends 6/24/99 Issue final rule' 6/30/99 This success oriented schedule assumes little or no changes from the two previously appioved rules. It would also allow for completion under Chairman's Jackson watch.

A less aggressive draft schedula la also attached for your consideration.

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02/23/99 Tt'E 14:07 FAI 412 374 5535 AP600 @ 003 Appendix 4 To Part 52-Design Certincation Risle for the UMhhinsed Bollisg'WaiO Reactor

1. Introducuon Appendih 8 constitutes the standard design certification for the VfldM $7edvig% erMa'dcHABWR design, in accordance with 10 CFR part 52, Subpart B. He applicant for certification of ti,e U.S; ABWd DE Nuotsiif Jinsygy.

!!. Definitions A. Generic design control document (generic DCD) means the document containing the 'Her I and Tier 2 information and generic technical specifications that is incorporated by reference into this appendia.

B. Generic technical specifications means the information, required by 10 CFR 50.36 and 50.36a, for the portion the plant that is within the scope of this appendix.

C. plant specific DCD means the document, maintained by an applicant or licensee who references this appendix, consisting of the information in the generic DCD, as modified and supplemented by the plant specific departures and etemptions made under Section Vill of this appendix.

D. Tier 1 manns the portion of the design related information contained in the generic DCD that is approved and certified by this appendix (hereinafier Tier 1 information). ne design descriptions, interface requirements, and site parameters are derived from Tier 2 Information. 'ner 1 information includes:

1. Definitions and general provisions;

. 2. Design descriptions;

3. Inspections, tests, analyses, and acceptance ctheria (ITAAC);

4. Significant site parameters;and

5. Significant interface requirements.

E. Tier 2 means the portion of the design related information contained in the y,eneric DCD that is approved but not certified by this appendix (hereinafter Tier 2 information). Compliance with Tier 2 is required, but generic changes to and plant-specific departures from Tier 2 are governed by Section Vill of this appendix.

Compilance with Tier 2 provides a sufficient, but not tne only acceptable, method for complying with Tier 1.

Compliance methods differing from Tier 2 must satisfy the change process in Section VIII of this appendix.

Regardless of these differences, an applicant or licensee must meet the requirement in Section III.B to reference Tier 2 when referencing Tier 1. Tier 2 information includes;

1. Information required by 10 CPR 52.47, with the exception of generic technical specifications and conceptual design information;

2. Information required for a final safety analysis report under 10 CFR 50.34;

3. Supporting information on the inspections, tests, and analyses that will be performed to demonstrate that the acceptance criteria in the ITAAC have been not; and

4. Combined license (COL) action hems (COL license information), which identify certain matters that shall be addressed in the site specific portin, of the final safety analysis report (FSAR) by an applicant who references this appendix.These items constity'.e information requirements but are not the only acceptable set of information in the FSAR. An applicant may depart from or omit these items, provided that the departure or omission is identified and Puts 2 AppA. Doc I

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02/23/99 Tt'E 14108 FAX 412 474 5535 AP600 Q)004 justified in the FSAR. After issuance of a construction permit or COL, these items are not requirements for the licensee uniess such items are restated in the PSAR.

F. Tier 2* means the portion of the Tier 2 information, designated as such in the genetic DCD, which is su the change process in VIII.B.6 of this appendix. Als designation expires for some Tier 2* information under Vill.B.6.

G. All other terms in this appendix have the meaning set out in 10 CFR 50.2,10 CFR 52.3, or Section 11 of the Atomic Energy Act of 1954, as amended, as applicable.

Ill. Scope and Contents A. Tier 1, Tier 2, and the generi,, technical specificattor.: in the D;8lfABWR Design Control Document, DE Nucleas

[fa'er'gERjyl: IssiDadeWi!chil@h i are approved for incorporation by reference by the Director of the Office of theFederalReg$NaEisi(TeiGisiffWoodisel@ddih52$M1diidl obtained from ty oa ;%? 1$$22Mlidister Acopyis in accordance available for examination and copying at the NRC Public Document Room,2120 L Street NW, (Lower Level),

Washington, DC 20555. Copies are also available for examination at the NRC Library, i1545 Rockville Pike, Rockville, Maryland 20582 and the Office of the Federal Register, 800 Nordt Capitol Street, NW., Suite 700, Washington DC.

B. An applicant or licensee referencing this appendix,in accordance with Section IV of this appendix, shall incorporate by reference and comply with the requirements of this appendix, including Tier 1. Tier 2, and the generic technical specifications exce[qas otherwise provided in this appendix. Conceptt:al design information, as set forth in the generic DCD, and )@Iaphalda[SEpfortWf6dmEnifEtheMBNRO are not part of this appendix. Tier 2 references to the probabillstic risk assessment (PRA) in the hBWn Standard Safety Analvsis Report do not incorporate the PRA intoTier 2.

C. If there is a conflict between Tier 1 and Tier 2 of the DCD, then Tier 1 controls.

D. lf there is a conflict between the ABWl( design or NURE00iplM

• generic DCD and either the application for design certification of t Final Safet Evaluation Report related to the Certification of the $d'vancid BoitisWitsii)th6iiDisigni," (FSER)iIdd ""'TM.1, then the generic DCD controls.

E. Design activities for structures, systems, s*! components that are wholly outside the scope of this appendix may be performed using site-specific design parameters, provided the design activities do not affect the DCD or conflict with the interface requirements.

IV. Additional Requirements ud Restrictions A. An applicant for a license that wishes to reference this appendix shall,in addition to complying with the requirements of 10 CFR 52.77,52.78, and 52.79, comply with the following requirements:

L 1, Incorporate by reference, as part ofits application, this appendix;

2. Include, as part ofits application:

a. A plant-specific DCD containing the same information and utilizing the same organization and numbering as the generic DCD for the $%Mys design, as modified and supplemented by the applicant's exemptions and departures;

b. he reports on departures from and updates to the plant-specific DCD required by X.B of this appendix;

c. Plant-specific technical specifications, consisting of the generic and site-spcific techrical specifications, that are required by 10 CFR 50.36 ud 30.36a; l

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d. Information demonstrating compliance with the site parameters and interface requirements; .

e. Information that addmases the COL action items; and

f. Information required by 10 CFR 32.47(a) that is not within the scope of this appendix.

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~ Slbs5JRABWE9Cth B.%c Commission reserves the right to detennine in what nanner this appendix may be referenced by an ap for a construction permit or operating license under 10 CFR Part 50.

V. Applicable Regulations A. Except as indicated in paragraph B of this section, the regulations that apply to the MfhWWIl design are in 10 CPR Parts 20,50,73, and 100, codified as of May 2,1997, that are applicable and technically relevant, as described in the FSER (NURBOQ8$$fliid)dpiilesEM Np",Ji, B. De $ dish design is exempt from portions of the following regulations:

1. Paragraph (fX2Xiv) of 10 CFR 50.34-Separate Plant Safety Parameter Display Console:

2. $risidhdN%$N6MM312""IOiip%M$itiliMitlIMs,WINIAIMD5efs0IEj 2

$2KuInsr'idMD$D(tapy7f,777,175 VI. Issue Resolution A. The Commission has determined that the structures, systems, components, and design features of the Ifi/ BWR design comply with the provisions of the Atomic Energy Act of 1954, as amended, and the applicable regulations identified in Section V of this appendix; and therefore, provide adequate protection to the health and safety of the

public. A conclusion that a matter is resolved includes the finding that additional or alternative structures, systems, components, design features, design criteria, testing, analyses, acceptance criteria, orjustifications are not necessary for the U)iABWR design.

i B. The Commission considers the following matters resolved within the rneaning of 10 CPR 52.63(a)(4) in subsequent proceedings for issuance of a combined license, amendment of a combined license, or renewal of a combined license, proceedings held pursuant to 10 CFR 32.103, and enforcement proceedings involving plants referencing this appendix:

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1; All nuclear safety issues, except for the generic technical fications and other operational requirements, .

. associated with the information in the PSER W.M.i 7. Tier 1. Tier 2 (including referenced informntion

- which the context indicates is intended as requirements), and the rulemaking record for certification of the QM

. MlWM design;-

2. All nuclear sa' sty and safeguards issues associated with the information in proprietary and safeguards documents,

. referenced and 19 context, are latr.aded as requiremente in the genenc DCD for the (JEABWR design; E

3. All generic changes to the DCD pursuant to and in compliance with the change processes in Sections VIII.A.1 and l VDI.B.I of this appendix;

4. All exemptions from the DCD pursuant to and in compliance with the change processes in Sections VIII.A.4 and g' VIII.B.4 of this appendir, but only for that proceeding:

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5. All departures from the DCD that are approved by license anwndment, but only for that proceeding;

6. Except as provided la VIII.B.S.f of this appendix, all departures from 'ner 2 pursuant to and in compliance w the change processes in Vm.B.5 of this appendix that do not require prior NRC approval;

7. All envircamental issues concerning severe accident ation design alternatives associated with the information in the NRC's final envittsuneatal assessment' for the and$sjWl6e'1[ofndtj lidhlik DecemWr plants referencing this appendix whose

. slie narameters are within those specified in the Digisist'

- C, De Commission does not consider operational requirements for an applicant or licensee who references this appendix to be matters resolved within the meaning of 10 CFR 52.63(a)(4). De Commission reserves the right to require operational requirements for an applicant or licensee who references this appendix by rule, regulation, or or license condition.

- D, Except_ in accordance whh the change processes in Section VM of this appendix, the Commission may not an applicant or licenses who references this appendix to:

- 1 Modify structures, systems, components, or design features as described in the generic DCD; 2.

DCD; Provide or - additional or ahernative structures, systems, components, or design features not discussed in the generi

' 3, Provide additional or alternative design criteria, testing, analyses, acceptance criteria, or justification for structures, systems, components, or design features discussed in the generic DCD.

E.1. Persons who wish to review proprietary and safeguards information or other secondary references in the DCD for the D,$dM design, in crder to request or participate in the hearing required by 10 CFR 52.85 or the provided under 10 CPR 52.103, or to request or participate in any other hearing relating to this appendix in whic Interested persons have adjudicatory hearing rights, shall first request access to such information from @MhAI lishY, he request must state with particularity:

a. %e nature of the proprietary or other information souglt;

b. he reason why the information currently available to the public in the NRC's public document room is insufficient;

c. He relevance cf the requested information to the hearing issue (s) which the pei:nn proposes to raise; and

, d. A showing that the requesting person has the capability to understand and utiliae the requested information.

2.1f a person' claims that the information is necessary to propero a request for hearing, the request must be filed no

later than 15 days after publication in the Federal Register of the notice required either by 10 CFR '

$2.85 or 10 CFR 52,103. lf MWij$i@iE6 declir es to provide the information sought, dB3Gii$$%iItEIhall send a wrluen response within ten (10) days of receiving the request to the requesting person setting forth with

!_ particularity the reasons for its refusal. De person may thea request the Commission (or presiding officer,if a

' proceeding has been established) to order disclosure. De person shall include copies of the original request (an subsequent clarifying information provided by the requesting party to the acoliernt) and the applicant's response.

no Commluloa r,M palding o!!!cer shall bare their decisions sob on the s ' inal (including

_ any cla_rifying Information provided by the requesting person to "Baije6sl b' ' he C= '% and presiding officer may order to provide access to some or allof the requested information, subject to an appropriate non. disclosure agreement.

VII. Duration of his Appendix Parts 2.AppA DOC 4

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o-his appendix may be referenced for a period of 15 years from fais}@b'3 except as provided for in 10

. - 52.55(b) and $2.57(b). This appendix remains valid for an applicant or licensee who reference,

- the appbcation is withdrawn or the license espires, including any period of extended operation under a re license.

Vill. Processes for Changes and Departures

. - A. Tier 1 information.'

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1. Generic changes to Tier ! Information are governed by the requirements in 10 CFR 52.63(aXI),

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P j 2. Generic changes to Tier 1 information are applicable to all applicants or licensees who refence this

' A,4 of thisthose except for whk.h the change has been rendered technically irrelevant by action taken under paragra

• sectionc i

i 3. Departures from 11er I is. format!on that are required by the Commission through plant specific orders are governed by the requirements in 10 CFR 52.63(aX3).

- 4. Exemptions from Tier 1 information are governed by the requirements in 10 CPR 52.63(bX1) and $32S7(b).

Commission will deny a request for an exemption from Tier 1, ifit finds that the design change will result in a significant decrease in the level of safety otherwise provided by the design.

B. Tier 2 information.

l. Generic changes to Tier 2 information are governed by the requirements in 10 CFR 52.63(aX1).

2. Generic changes to Tier 2 information are applicable to all applicants or licensees who reference this appe except those for which the change has been rendered technically irrelevant by action taken underparagraphs B.3,

' B.4, B.5, or B.6 of this section

3. De Commission may not require new requirements on Tier 2 information by plant-specific order while this appendix is in effect under $152.55 or 52.61, unless:

a.'A modification is necessary to secure compliance with the Commission's regulations applicable and in effect at the time this appendix was approved, as set forth in Section V of this =M. or to assure siequate protection of the l public health and safety or the cornmon defense and security; and

b. Special circumstances as defined in 10 CFR 50.12(a) are present.

4. An applicant or heensee who references this appendix may request an exemption from Tier 2 information. The -

Commission may grant such a request only ifit determines that the exemption will comply with the requirements

'10 CPR 50.12(a). De Commission will deny a request for an exemption from Tier 2, if it finds that the design

. change will result in a significant decrease in the level of safety otherwise provided by the design. He grant of an

. exemption to an applicant must be subject to litigation in the same manner as other issues material to the license hearing. De grant of an exemption to a licensee amst be subject to an opportunity for a hearing in the same manner as license amendments.

5.a. An applicant or licensee who references this appendix may depart from Tier 2 information, without prior NRC

. approval, unless the proposed departure involves a change to or departure from Tier I information Tier 2' information, or the whaim1 specifications, or involves an unroviewed safety question as defined in paragraphs B and B.S.c cf this section. When evaluating the proposed departure, an applicant or licensee shall consider all matters described in the plant-specific DCD.

b. A proposed departure from 11er 2, other than one affecting resolution of a severs accident issue identified in the plant-specific DCD, involves an unreviewed safety question if-

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- (1) De probability of occurrence or the consequences of an accident or malfunction of equipment impo

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safety previously evaluated in the plant 7 specific DCD may be increased; (2) A possibility for an accident or malfunction of a different type than any evaluated previously in the pl

- DCD may be created;or i (3) *IM margin of safety as defined in the basis for any technical specification is reduced.

c. A proposed departure from Tier 2 affecting resolution of a severe accident issue identified in the plant-specific DCD, involves an unreviewed safety question if-

. (1) Dere is a substantial increase in the probability of a severe accident such that a particular severe accident previously teviewed and determined to be not credible could become credible; or (2) Dere is a substandal increase in the consequences to the public of a parucular severe accident pr-Mously reviewed.-

d. If a departure involves an unreviewed safety question as defined in paragraph B.5 of this sectior.,i~. is governed by 10 CFR 50.90.

e. A departure from Tier 2 information that is inade under paragraph B.5 of this section does not require an exemption fmm this appendix.

- f. A party to an adjudicatory proceeding for either the issuance, amendment, or renewal of a license or for operation under 10 CPR 52,103(a), who believes that an applicant or licensee who references this appendix has not complied

with V111.B 5 of this appendix when departing from 'Iler 2 infarmation, may petition to admit into the proceeding such a contention in addidon to compliance with the general requirements of 10 CFR 2.714(b)(2), the petition must

- demonstrate that the departure does not comply with VIII.B.5 of this appendix. Further, the petition must demonstrate that the change bears on an asserted noncompliance with an ITAAC acceptance criterion in the case of a 10 CFR 52.103 preoperational hearing,'or that the change bears directly on the amendment request in the case of a hearing on a license amendment. Any other pasty may fde a response, if, on the basis of the petition and any

- response, the presiding officer determines that a sufficient showing has been made, the presiding officer shall certify the matter directly to the Commission for determination of the admissibility of the contention. De Commission may

- admit such a contention ifit determines the petition raises a genuine issue of fact regarding compliance with Vill.B.5 of this appendix.

6.a. An applicant who references this appendix may not depart from Tier 2* information, which is designated with

! italicized text or brackets and an asterisk in the generic DCD, without NRC approval. De departum will not be considered a resolved issue, within the meanin6 of Section VI of thi: appendix and 10 CFR 52.63(a)(4).

b. A licensee who references this appendix may not depart fiom the following Tier 2* matiers without prior NRC approval. A request for a departure will be treated as a request for a license amendment under 10 CFR 50.90.

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c. A licensee who references this appendix may not, before the plant fint achieves full power following the finding required by 10 CPR 52.103(g), depart from the following Tier 2* matters except in accordance with paragraph B.6.b of this section. After the plant first achieves full power, the following Tier 2* matters revert to Tier 2 status and are

_ thereafter subject to the departure provisions in paragraph B.5 of this section.

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d. Departures from Tier 2* information that are made under paragraph B.6 of this section do not require an axemption from this appendix.

C. Operational requirements.

IfGeneric changes to generic technical specifications and other operational requirements that were com reviewed and approved in the design certification rulemaking and do not require a change to a design feature in the generic DCD are governed by the requirements in 10 CFR 50.109. Generic changes that do require a change to a design feature la the generic DCD are governed by the requirements in paragraphs A or D of this section.

2. Generic changes to generic technical specifications and other operational requirements are applicable to all applicants or licensees who reference this appendix, except thoes for which the change has been rendered tech Irislevant by action taken under paragraphs C.3 or C.4 of this section.

3. *Ihe Comsalssion may require plant-specific departures on generic techmcal specifications and other operationa

requirernents that were completely reviewed and approved, provided a change to a design feature in the generic DC is not required and rpecial circumstances as defined in 10 CFR 2.758(b) era present. 'the Commission may mod or supplement generic technical specifications and other operational requirements that were not completely reviewed

- and approved or require additional technical specifications and other operational rquirernents on a plant specific basis, provided a change to a design feature in the generic DCD is not required.

4. An applicant who references this appendix may request an exemption from the generic ucal specifications or

- other operational requirements. The Comrnission may grant such a request only ifit determines that the exemption

' will comply with the requirementa of 10 CFR 50.12(a). The grant of an exemption must be subject to litigation in the

' same manner as other issues material to the license hearing.

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( $. A party to an .? % sy proceeding for either the issuance, amendment, or renewal of a licens

. under 10 CPR 52.103(a), who believes that an operatinnal requirement approved in the DCD or a technical s

spacincation derived from the generic technical specincations must be changed may petition to admit into the proceeding such a contention. Such petition snust comply with the general rm'_ ..:.nts of 10 CFR 2.714(b

( must demonstrate why special circumstances as denned in 10 CFR 2.758(b) are present, or for complia

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- Commission's ragulations la effect at the time this appendix was approved, as set forth in Section Vi

Any other party may Ale a response thereto If, on the basis of the petition and any response, the pres determines that a sufficient showing has been made, the presiding officer shall certify the matter direct)

Coaunission for determination of the admissibility of the contention. All other issues with respect to the a specific technical specincations or other operational requirements are subject to a hearing as part of the license l proceeding. '

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• 6. After issuance of a license, the generic techancel specifications have no further effect on the plant-specific

. technical spccifications and changes to the fr :;+1fic technical specifications will be treated as license amendments under 10 CPR 50,90.

' 11 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC)

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A.I' An applicant or licenses who references this appendix shall perform and demonstrate conformance with the 1 ITAAC before fuel load With respect to activities subject to an ITAAC, an applicant for a license may proceed at i i own risk with design and procurement activities, and a licensee may proceed at its own risk with design, procurement, construction, and preoperational activities, even though the NRC may not have found that any r particularITAAC has been setianedc 2,'the hcensee who references this appendix shall notify the NRC that the' required inspections, tests, and analyse i

the ITAAC have been successfully compleeml and that the corresponding acceptance critorim have been met. .

3, In the event that an activity is subject to an ITAAC, and the applicant or licenses who referen!.es this appendix h not demonstrated that the TTAAC has been satisAed, the applicant or licensee may either take corrective actions to successfbily complete that ITAAC, request an exemption from the ITAAC in accordance with

.Section VIII of this appendix and 10 CFR 52.97(b), or petition for rulemaking to amend this appendix by changing .

the requirements of the ITAAC, under 10 CPR 2.802 and 52.97(b). Such rulemaking chan6es to the ITAAC must  ;

. meet the requirements of paragraph VIII.A.1 of this appendix.

B.1 - The NRC shall ensure that the required laspections, tests, and analyses la the ITAAC are performed. The NRC i-

- shall verify that the inspections, tests, and analyses referenced by the licensee have been successfully completed and

- based solely thereon, And the prescribed acceptance criteria have been met. At appropriate intervals during construction, the NRC shall publish notices of the successful completion of ITAAC in the Federal Register.

2. In accordance with 10 CFR 52.99 and 52.103(g), the Comnussion shall find that the acceptance criteria in the ITAAC for the license are met before fuel loed,

3. After the Commlanion has made the finding required by 10 CPR 52.103(g), the ITAAC do not, by virtue of their

! isclusion within the DCD, constitute regulatory requirements either for licensees or for renewal of the license; excep

. for specific ITAAC, which are the subject of a Secnon 103(a) hearing, their expiration will occur upon final Com.nission menon in such proceeding, However, subsequent inodifications must comply with the Tier I and Tier 2 design descriptions in the plant-specific DCD unless the licenaec has complied with the applicable requirements of e 10 CPR 52.97 and Section VIII of this appendix.

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_ l. The applicant for this appendix shall maintain a copy of the generic DCD that includes all generic cha

. I and Tier 2. The applicant shall maintain the proprietary and safeguards information referenced in the generic for the period that this appendix may be referenced, as specified in Section V11 of this appendix.

• 2. An applicant or licensee who references this appendix shall maintain the plant specific DCD to accurately both generic changes to the generic DCD and plant-specific departures made pursuant to Section VIII of this

appendix throughout the period of application and for the term of the license (including any period of renewal).

3. An applicant or licensee who references this appendix phall prepare and maintain written safety evaluations whi provide the bases for the determinations required by Section VIII of this appendix. Dese evaluations must be

retained "iroughout the period of application and for the term of the license (including any period of renewal).  ;

-1 B. Reporting.

.1. An applicant or licensee who references this appendix shall submit a report to the NRC containing a brief F description of any departures from the plant-specific DCD, including a summary of the safety evaluation of each, This report must be filed in accordance with the filing requirements applicable to reports in 10 CFR 50.4.

2. An applicant or licensee who references this appendix shall submit updates to its plant-specific DCD, which reflect the generic changes to the generic DCD and the plant specific departures made porsuant to Section VIII of this appendix. %ese updates shall be filed in accordance with the filing requirements applicable to final safety-

. analysis report updates in 10 CPR 50.4 and 50.71(c).

3. De reports and updates required by paragraphs B.1 and B.2 of this section must be submitted as fol'ows:

- a. On the date that an application for a license referencing this appendix is submitted, the application shall include the report and any updates to the plant-specific DCD.

t b. During the interval from the date of application to the date ofissuance of a license the report and any updates to the plant specific DCD must be submitted annually and may be submitted along with amendments to the application.

c. During the interval from the date ofissuance of a license to the date the Commission makes its findings under 10

CFR 52.103(g), the report must be submitted quarterly. Updates to the plant-specific DCD must be submitted annually,

d. After the Commission has made its finding under 10 CPR 52.103(g), reports and updates to the plant. specific DCD may be submitted annually or along with updates to the site specific portion of the final safety analysis report -

for the facility at the intervals required by 10 CFR 50.71(e), or at shorter intervals as specified in the license.

- [62 FR 25827, May 12,1997; 62 FR 27293, May 19,1997)

I e

Pen 52-AppA. DOC 9

,y .- ,;

.02/23/99' TUE 14:17 FAI 412 374 5535 AP600 @ 012 y

e

. AP600 DESIGN CERTIFICATION SCHEDULE Milestoneo -

Duration Qgtg FSER issued

' 9/3/98(C)

Design Controi Document (DCD) submitted 11/30/98(C)

Comments on DCD provided 1/20/99(C)

Design Control Document revision submitted 2/10/99(C)

DCD approved 2/18/99(C)

Draft proposed rule 15 days

. 3/5/99 ACRS review of proposed rule 7 days 3/12/99 Commission review of proposed rule 14 days 3/19/99 Issue FRN for proposed rule 15 days 3/31/99 Receive comments on proposed rule 75 days 6/15/99 Evaluate comments on proposed rule 15 days 6/30/99 Develop final rule 15 days 7/15/99 ACRS review of final rule 7 days 7/21/99 Commission review of final rule 14 days 7/29/99 lasue FRN for final DCR 15 days 8/15/99 0007BAM.DOCD2/23/99 1 s_