ML20115J673
| ML20115J673 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 07/23/1996 |
| From: | Brinkman C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| FRN-61FR18099, RULE-PR-52 61FR18099-00002, 61FR18099-2, NUDOCS 9607240264 | |
| Download: ML20115J673 (50) | |
Text
ABB 00CKElED ASEA BROWN BOVERI yglg July 23,1996 g
'% JUL 23 PS :48 Mr. John C. Hoyle, Secretary Office of the Secretary U.S. Nuclear Regulatory Commission
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Washington, D.C. 20555-0001 3W DOCKET NUMBER PROPOSED [RULEN ATfN: Docketing and Service Branch blPRITO9M RE:
Supplementary Notice of Proposed Rulemaking, Standard Design Certification for the System 80+~ Standard Design, SECY 96-077 (Apr.15,1996), noticed at 61 Fed. Reg.18099 (Apr. 24,1996),
comment period extended at 61 Fed. Reg. 27027 (May 30,1996),
Docket No.52-002.
Dear Mr. Hoyle:
Combustion Engineering Inc. (ABB-CE), a Connecticut-based U.S. corporation with nearly four decades of experience in the U.S. nuclear industry, is the applicant for design certification (Docket No.52-002) of the System 80+' Standard Plant Design described in the above-referenced Supplementary Notice of Proposed Rulemaking (SNOPR). With the issuance of SECY 96-077, the Nuclear Regulatory Commission (NRC or Commission) Staff presented a draft final design certification rule for the System 80+' Standard Plant Design. This letter contains ABB-CE's response to the request for public comments set forth in the above-referenced Federal Register notices.
ABB-CE has previously filed detailed comments, on August 4,1995, in response to NRC's Notice of Proposed Rulemaking (NOPR) for Standard Design Certification for the System 80+' Standard Plant Design, published at 60 Fed. Reg. 17925 (Apr. 7,1995). In addition to the specific comments contained in that filing, ABB-CE also expressed its full support of the extensive comments on the NOPR filed by the Nuclear Energy Institute (NEI) on behalf of the nuclear industry generally. In SECY 96-077, NRC Staff addressed some of the comments filed by ABB-CE and the nuclear industry, but ignored or disagreed with many others, including several comments regarded by ABB-CE and the nuclear industry to be the most important for ensuring the viability of the U.S. licensing regime for advanced light water reactors.
Now, therefore, ABB-CE finds itself at a critical juncture where the Commission's resolution of the nuclear industry's and ABB -CE's outstanding comments may well determine whether the System 80+' design certification rule will ever be used in the United States.
72 264 960723 l
52 61FR18099 PDR Atsts Lomoustion engineering Nuclear Power DSJO an. w "
i Mr. John C. Hoyle July 23,1996 Page 2 NRC's issuance of the SNOPR for System 80+" marks the penultimate milestone in a process that has consumed many tens of thousands of manhours of NRC and ABB-CE resources, cost approximately $100 million in ABB-CE and U.S.
Department of Energy funds and millions of dollars of NRC review fees, and has i
taken close to a decade to complete. In June 1994, that process resulted in the successful issuance of the Final Design Approval (FDA) for System 80+', signaling j
NRC approval of the System 80+~ Standard Plant Design itself. I jon FDA issuance, System 80+~ was offered for sale in the global marketplace and now represents one of the safest and most complete new nuclear plant designs in the world. ABB-CE has every expectation that the System 80+" Standard Plant Design will succeed in the foreign marketplace.
l Ironically, however, ABB-CE's ability to s.iccessfully offer the System 80+"
Standard Plant Design to the United States domestic market may well hinge on the Commission's resolution of the remaining licensing process issues that were intended, l
originally, to take full advantage of the technical merits of this advanced design. Part 52 was promulgated, and its principles reaffirmed in the Energy Policy Act of 1992 l
l (EPACT), in the hope and expectation that its licensing process advantages would i
parallel the substantial technical advantages expected with advanced light water reactors. The System 80+' Standard Plant Design, for example, represents an increased safety factor of approximately 100 relative to the nation's already safe operating nuclear plants, and offers significant cost and reliability advantages as well.
ABB-CE seeks to ensure that these advantages are appropriately reflected in the Part l
52 design certification rule for System 80+~ in order to successfully market the design l
to the utility industry in the U.S.
l ABB-CE participated extensively in, and fully supports, the nuclear industry's more detailed comments, separately filed by NEI, on the SNOPR. ABB-CE strongly l
urges NRC to review carefully and to adopt the industry's comments, and in particular, to utilize the proposed rule language represented by ABB-CE's attachments to this letter, as well as the detailed comments and tables prepared separately by NEI.
ABB-CE hereby incorporates by reference the NEI comments into its own comments.
No effort will be made here to address all of the important points raised in the NEI comments. Rather, ABB-CE will highlight in this letter certain specific issues that warrant additional comment or vendor-specific discussion.
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Mr. John C. Hoyle July 23,1996 Page 3 DISCUSSION I.
F'-*v. An I==m of Control ABB-CE's continuing objections to NRC Staff's proposed resolution of disputed design certification process issues center on the finality (or lack thereof) of the System 80+" design, and with the " applicable regulations" proposed by the NRC Staff to be incorporated into the System 80+" design certification rule. In sum, ABB-CE views the remaining disagreements between the nuclear industry and the Staff as reducing to the basic issue of control. Specifically, the NRC Staff appears to desire more control now over various aspects of the standard design than the nuclear industry believes was originally intended by Part 52, the Energy Policy Act, and previous Commission guidance and positions.
When Part 52 was promulgated, the " balance of control" between NRC and the nuclear industry over the standard design was struck in Section 52.63, which provides protection against cost-benefit changes imposed by NRC Staff (i.e., the traditional backfit standard contained in 10 C.F.R. 6 50.109), but leaves open Staff's pruegative to backfit the design for adequate protection of the public health and safety. The Commission and the nuclear industry struck the balance of control represented by Section 52.63 with the full knowledge and understanding that it would reduce flexibility for both sides in making changes to the standard plant designs, but would offer in return a high degree of finality - and thus, standardization - to the designs.
He twin goals of finality and standardization, in turn, were to provide the requisite certainty to the licensing and review process that would restore investor confidence in the nuclear option in the U.S. and allow domestic utilities to realize the full technical benefits of the advanced designs.
Now, as articulated in the proposed resolution of many of the disputed process issues in SECY %-077, the NRC Staff has overtly retreated from the balance represented by Section 52.63, without any apparent safety benefit. He Staff has j
' plainly represented its position as stemming from its desire to regain control over the design. His justification, however, is unavailing. When ABB-CE embarked on the ambitious, expensive, and time-consuming task of design certification, it did so in the reasonable expectation - shared within the nuclear industry and by Congress -- that j
the System 80+" Standard Plant Design would have all the finality represented by the Section 52.63 balance. In retreating from that balance, the Staff has not articulated a single legal or safety-based rationale that would suggest the balance of control should be recast now, with the design complete, in favor of itself. Hus, far from being
l Mr. John C. Hoyle July 23,1996 l
Page 4 solely a process debate, ABB-CE regards the finality dispute to be one also of simple j
_ equity.
l ABB-CE implores the Commission to treat the various disagreements between
.the nuclear industry and the NRC Staff over finality issues as matters ofpolicy, not as j
matters of technical merit, legality, or safety. Not only does the System 80+~
Standard Plant present a substantially safer design, but the NRC Staff's ability to
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l ensure that such safety remains in place is firmly embedded in Section 52.63.
j Similarly, Staff objections to the proposals of the nuclear industry do not rest on legal l
or technical grounds, but rather, represent the Staff's " preference" that the balance of t
- control shift more toward the Staff. From ABB-CE's perspective, the policy questions presented by the various finality issues are interrelated, and thus can be addressed by answering two fundamental questions: Should the Commission reverse course, at the eleventh hour, and shift the balance of control articulated by Part 52, the Energy Policy Act, and previous Commission positions, so as to accommodate a Staff preference for augmented control over the technology (not the safety) of the design?
And, does this reversaljustify the resulting inequity to ABB-CE and the U.S.
taxpayer, who entered the design certification process with clear and diffemnt expectations concerning the design's overall level of finality?
Finally, ABB-CE notes that in most cases where disagreement remains between the Staff and the industry on issues of finality, the Staff's proposed resolutions will funher complicate an already overly-complicated licensing process for the advanced designs. The result would be a " swiss cheese" approach to regulation, with certain design aspects having one set of standards and backfit rationales, and other aspects having different standards and rationales. At this point, and particularly since safety is not implicated, ABB-CE believes it is imperative to simplify, not complicate, the rulemaking process, and to reduce any unnecessary regulatory burdens associated with the advanced designs. Hence, ABB-CE strongly urges the Commission to adopt the industry's proposed issue finality resolutions, returning the balance of control to that mpresented by Section 52.63.
H.
Annlicable Rerulations i
l ABB-CE suppons NEI's position that there should be no " applicable regulations." Applicable regulations, in whatever form, are unnecessary and destablizing, and do not comply with previous Commission positions and guidance.
ABB-CE is panicularly concerned that several of the applicable regulations related l
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Mr. John C. Hoyle l
July 23,1996 Page 5 most specifically to operational (and not design) issues were simply " removed" from the applicable regulations section of the NOPR and relocated to another section in the SNOPR, an apparent new repository for all operational issues. In particular, ABB-CE agrees with NEI that the final rules should be revised to delete all of Section 4(b) and l
all of Section 5, which together represent all the applicable regulations. Mamover, ABB-CE concurs in the objections cited by NEI to the specific wortling proposals of each of the applicable regulations that apply to the System 80+~ Standard Plant Design.
l It is imponant to note that all of the Staff's proposed applicable regulations for System 80+~ were created after the design review had been fully completed. This design review was performed using Commission guidance provided in the SRMs for SECY 90-016 and SECY 93-027, which did not require " applicable regulations" for System 80+~. NRC's Final Safety Evaluation Report (FSER) for System 80+~
concludes correctly that the design satisfies and incorporates all of the Commission-approved additional technical requirements contained in SECY 90-016 and SECY 93-087. In attempting, after the fact, to reshape these additional technical requirements into broadly-stated " regulations" in the SNOPR, the Staff's proposed draft final rule has reduced the technical requirements to vague generalities that are subject to reinterpretation later. Thus, for no apparent safety benefit, Staff's proposal adds a highly destablizing process element, and substantial uncenainty, to the System 80+~
design cenification rule.
I Furthermore, in attempting -- after the design review had already been completed -- to add specificity to the broadly-stated applicable regulations proposed for System 80+~, SECY %-077 proffers language that is not supported by the System 80+~ Design Control Document (DCD) and FSER, creating errors that could become a focal point for future challenges based on allegations that the design does not meet the " applicable regulations." Indeed, in some instances, the System 80+~ design does j
not technically meet the " applicable regulations" that were proposed.
j For example, Section 5(c)(9)(i) of the proposed draft final rule requires that design features for certain severe accident sequences should incorporate "[a] minimum of 79 m2 of unobstructed reactor cavity floor space for molten core debris spreading."
In fact, however, the NRC approved the System 80+~ design for 64 m. Likewise, 2
l Section 5(c)(12) limits the System 80+~ " conditional containment fail. ire probability to l
less than 0.1" for cenain severe accident sequences. (This is an area where the NRC
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Staff is apparently proposing to convert an industry goal into a regulation.) In fact, l
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July 23,1996 Page 6 e
j however, there is one recorded calculation for System 80+~ for which the conditional j
containment failure probability of 0.1 is slightly exceeded.
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i Finally, the instability of applicable regulations will be compounded at the time of certification renewal if the Staff's current interpretation of the broad scope of a -
l certification renewal proceeding, as discussed in Section V. below, is adopted by the i
Commission. He existence and vagueness of the proposed applicable regulations make it probable that future NRC Staffs engaged in reviewing certified designs for j
renewal after 15 years will be tempted to bacrtit the design to conform with l
subsequent interpretations of the meaning and intent of the appli',able regulations. If so, this future Staff will not be constrained by the backfit provisions proposed in the SNOPR,' adding even more uncertainty to the long-term finality associated with the design.
IH.
Technical Specifications ABB-CE originally questioned the NRC's position'o 1 developing technical i
i specifications (Tech Specs) for the advanced plant desigra a the design certification stage. It was ABB-CE's view that certain aspects of the Tech Specs could not be developed prior to the time of an application for a combined license (COL). The i
NRC Staff, however, insisted that Tech Specs for each advanced plant be included in i
the DCD. Where numerical values could not be specified, ABB-CE was instructed to provide preliminary values or to leave such values blank, to be filled in at the time of a COL application.
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Consequently, ABB-CE, the U.S. Department of Energy, and the nuclear industry in general expended enormous resources in developing what are essentially standard Tech Specs for the System 80+~ Standard Plant Design. %ese Tech Specs were reviewed and re-reviewed by the NRC Staff and the Advisory Committee on Reactor Safeguards, and were fully approved by NRC with the issuance of the System
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80+" FSER and FDA.
He NRC Staff does not now take issue with the content of the System 80+~
Tech Specs, but rather suggests that the Tech Specs should lose their finality and be essentially removed from the DCD. The Staff's rationale for this position is not based on any articulated safety concern, but rather on a concern over the level of control that NRC will later have to impose backfits over operationally-related issues, including those addressed in the DCD. In particular, the Staff wants to apply the cost-benefit
l Mr. John C. Hoyle J
July 23,1996 Page 7 backfit standards in 10 C.F.R. I 50.109 to all operationally-related aspects of the Tech Specs rather than the enhanced backfit protection standards of Section 52.63 that j
would otherwise be applicable to the Tech Specs as an integral component of the DCD's Tier 2. This result is directly contrary to the Commission's SRM on SECY i
90-377, which provides that finality should attached to all information reviewed and l
l approved by the Staffin the design certGcation rule:
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The Commission agrees with the staff that the process [i.e., the design l
certification procecs] provides issue finality on all information provided
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in the application that is reviewed and approved in the design certification rulemaking. Information obtained during the staff's review process that forms the basis for a safety decision should be formally l
docketed as part of the application. Only this information will have l
regulatory significance for the design certification process.
L Staff Requirements Memorandum, "SECY-90-377 - Requirements for Design Certification Under 10 CFR Part 52," Feb.15,1991, at p. 3. ABB-CE submitted its System 80+~ Tech Specs as part of its design certification application (Tier 2 of the DCD), and NRC Staff reviewed and approved those Tech Specs as discussed in Chapter 16 of the FSER, and in the subsequent issuance of the System 80+~ FDA.
At the NRC Senior Manager's workshop on July 15,1996, the Staff suggested l
that it could develop a new standard whereby assurances would be provided, in the l
final design certification rule, to the effect that the Staff could not backfit " design features" through mandated changes to the Tech Specs. However, all " operational features" could be changed if justified under the backfitting standard contained in 10 l
1 C.F.R. I 50.109. Tr. at pp.17-28. This result is incongruent with Part 52 and, in i
particular, with Section 52.63, which provides enhanced backfit protection to all aspects of the standard plant design. When asked specifically at the July 15 workshop why a Section 52.63 backfit standard could not be applied to the Tech Specs - thereby realizing the finality of the agreed text - Staff could articulate no compelling answer other than its preference for increased control over the design post-COL, and its desire i
to avoid "three sets of books." Tr. at pp. 13-14, 40-42.
Industry concurs that during the post-COL phase the backfit standard contained in Section 50.109 would be applicable to all non-design-related changes to the Tech Specs. That fact, however, does not justify extending the same standard to earlier time frames. Indeed, the Staff's proposed protection standard, Section 50.109, does j
not even apply to license applicants, thus leaving the COL applicant with absolutely no l
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l Mr. John C. Hoyle j
July 23,1996 l
Page 8 legal protection against NRC changes or intervenor challenges to material which, in fact, has already been approved by the NRC and has been subjected to a heariq l
opportunity. Moreover, the burden of maintaining two sets of books, to the extei;t I-this is a genuine burden, will fall largely on the industry, and not on the NRC.
l Therefom, ABB-CE sees no compelling reason that the Tech Specs should not now be afforded the level of finality associated with every other aspect of Tier 2 of the DCD.
IV.
Tier 2* Ernirada=
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Section 8(b)(6) of the SNOPR establishes another process by which the NRC l
l Staff seeks to assert more control over certain aspects of the System 80+~ Standard l
Plant Design, this time even well after an advanced plant has actually been built and licensed to operate, contrary to long-standing industry positions.
i Specifically, the Staff proposes that for the life of the COL for a System 80+~
l plant, any change to one of four specific issues designated as Tier 2* information must receive prior Staff review and approval and, in essence, be treated as a license j
amendment. (Those issues are (1) methods for seismically qualifying equipment, (2) l acceptance criteria for pipe design, (3) limits on fuel burnup, and (4) control room i
factors human engineering.) All other Tier 2* information will revert to Tier 2 information after the plant achieves first full power, which permits the licensee to j
make changes to such information without prior Staff review and approval provided j
only that the change satisfies the 50.59-like change process.
The reason behind the application of heightened NRC scrutiny for changes to Tier 2* information before first full power stemmed from the fact that in certain specific areas the design could not be fully developed anydme earlier due to lack of as-procured or as-built data or because of rapidly changing technology. This concern, however, disappears upon plant operation. Once a plant is built and operated, the design will have been finalized and thus the need for heightened NRC scrutiny (i.e.,
the need for Tier 2*) will have expired. Unpersuaded by this fact, the Staff now rationalizes that maintaining Tier 2* change restrictions is warranted because the Staff considers some Tier 2* information "more significant" than other Tier 2* information.
Tr. at pp. 97-98.
1 The onerous effect of the Staff's position on Tier 2* expiration, however, is not i
j limited to just the four specific Tier 2* issues. Throughout ABB-CE's System 80F Design Control Document there are at least 141 design features that will fall subject to 1
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Mr. John C. Hoyle l
July 23,1996 1
Page 9 a heightened level of Staff scrutiny, and thus additional NRC control. Beyond these, i
many secondary documents referenced in the DCD contain uncounted additional l
bracketed sections that will also require prior NRC approval to be revised.
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i Of even greater burden, however, is the fact that any change in design aspects related to the four non-expiring Tier 2* issues will require not only prior NRC review and approval, but also a license amendment and an opportunity for a hearing, even if l
the change would not otherwise rise to the level of an unreviewed safety question (and j
thus, could ordinarily be changed using the 50.59-like change process). This burden, j
moreover, will persist through the life of the plant.
Another effect of this Staff position is the resultant loss of finality of Tier 2*
information. Specifically, in response to Question 7 of the NOPR the Staff stated that any changes to the DCD in the four Tier 2* areas will trigger a license amendment requirement and offer an opportunity for a hearing. The resource requirements and licensing uncertainty associated with this approach is an onerous and unnecessary regulatory burden, particularly when a proposed design change would not have i
constituted an unreviewed safety question.
The NRC Staff has stated that license amendments lose the backfit protections.
contained in Section 52.63 and that the Section 50.109 backfit provisions would become applicable. In the public meeting of July 15,1996, Mr. Russell of the NRC Staff held out the possibility that a licensee could apply for an amendment (at the COL stage or beyond) that would articulate certain parameters under which, with prior NRC approval, site-specific information could be substituted for Tier 2* issues and that further changes in this site-specific information could be implemented without prior NRC review and approval, i.e., without license amendments. Tr. at pp.92-105.
ABB-CE believes that, even if Mr. Russell's approach were to be adopted, licensees would nevertheless be forced into a position of having to file for amendments, even for changes having no safety significance.
Thus, ABB-CE fully supports the recommendation made by NEI that all Tier 2* requirements should terminate at first full power, at which point all Tier 2*
information should revert to Tier 2 information and be subject only to its attendant controls and restrictions.
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j Alternatively, ABB-CE notes that NRC Staff could revise its proposed response to NOPR Question 7. The justification that Tier 2* changes should perpetually be treated as license amendments because they involve a licensee departing from l
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l Mr. John C. Hoyle July 23,1996 Page 10 J
significant mquirements of the DCD is sharply inconsistent with the manner in which l
Tier 2 changes are otherwise handled. Tier 2 information in the DCD constitutes i
I significant " requirements" just as much as Tier 2* information, and for those Tier 2 I
changes that do not involve an unreviewed safety ouestion there is no provision in the design certification rule for a license amendment or a hearing opponunity. A similar rationale could be applied for Tier 2* changes that do not involve a change in Tier 1 information or the Tech Specs, and that do not create an unreviewed safety question.
In short, if no unreviewed safety question is involved, the Tier 2* change should be treated as any other Tier 2 change except for the requirement to first obtain MAC t
myiew and approval.
V.
has of Cedi&M'en R::;wsl Proceedi==
1 As noted above, approximately $100 million in ABB-CE and U.S. government funds, and nearly a decade of work, were expended to produce the System 80+~
Standard Plant Design. This is an exercise that, from a policy perspective, ought not j
to be repeated unnecessarily, even in small part. Yet, the effect of the Staff's l
proposed approach to design cenification renewal is to do precisely that.
Section 52.59 states that the Commission shall issue a rule granting renewal of the cenification if the design " complies with the Atomic Energy Act and the l
Commission's regulations applicable and in effect at the time the certification was issued...." Regmttably, Part 52 and its rulemaking history do not provide additional guidance for determining precisely what any such Commission determination of compliance, at the time of renewal, should entail. As stated in NEI's letter to Chairman Shirley Jackson of May 31,1996, the industry - and cenainly ABB-CE -
l has always envisioned that the scope of any such renewal proceeding would be limited l
to a review of changes proposed to the design by either the vendor or the NRC Staff.
Presumably, any regulatory non-compliance associated with the original design would, by the time of mnewal, have been backfitted if a genuine issue of adequate protection or noncompliance with regulations in effect at the time were involved. Thus, apart from review of NRC and vendor changes, ABB-CE envisioned the certification renewal proceeding as no more than a "due diligence" process to ensure that intervening developments between the time of original certification and the time of renewal did not reveal a previously undiscovered noncompliance. In no respect, j
however, did ABB-CE ever foresee that NRC Staff could reopen the entire design to a wholly new review.
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Mr. John C. Hoyle July 23,1996 l
Page 11 At the May 2 public workshop, to the considerable surprise of the industry, Mr. Malsch of NRC suggested that a renewal proceeding might actually involve a de l
novo review of the standard design, a proposition ABB-CE finds to be unacceptable.
At the July 15 public workshop, Mr. Malsch reaffirmed that there were, in his view, 1'
"no legal limits" on the scope of Staff's (or the public's) review at the time of renewal. Tr. at p. 50. ABB-CE finds this position to be nothing short of astonishing, l
since it suggests that ABB-CE's, the Department of Energy's, and NRC's efforts to date were directed at developing a standardized design with merely a 15-year life.
ABB-CE believes that, although Part 52 does not precisely delineate or limit the scope of a mnewal proceeding, neither does it do the opposite, i.e., open the door to an entinly new review. Thus, ABB-CE views the issue of the scope of a certification renewal as strictly a policy issue that the Commission should' decide now. ABB-CE strongly encourages the Commission to adopt the specific proposal offered in the NEI i
comments, which reasonably constrains the scope of a certification renewal t
proceeding, while leaving open the potential for any genuine challenges to the certified l
design based on adequate protection of the public health and safety, non-compliance.
with regulations in effect at the time, and prescribed Staff cost-benefit tests. At the j
very least, the Commission is mquested to defer expressly its decision making on the j
scope of certification renewal, so as not to signal unwittingly that the entire certified design is open to re-review or challenge in 15 years.
- VI.
Conclusion Appropriate resolution of the outstanding System 80+~ design certification regulatory process issues is essential to nuclear power's future in the United States.
Without a fluent and workable licensing regime to accompany the substantial technical and safety advantages achieved by advanced designs like System 80+~, potential users of such promising new designs will opt for more certain, if less desirable, supply alternatives. It would be tragic indeed if, having worked conjunctively for years to achieve an exemplary technical result - an FDA consistent with longstanding industry and NRC goals - the industry and the NRC Staff were to fail in the end to realize the regulatory process advantages that each understood to be the very stimulus that would (and indeed, did) in large part foster the approved design improvements.
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1 Mr. John C. Hoyle July 23,1996 l
Page 12 l
ABB-CE requests that the Commission exercise its policy-making prerogatives in such a manner as to reaffirm Part 52's original vitality in the final design l
certification rule for System 80+~. To that end, ABB-CE respectfully requests that the Commission adopt the proposed rule changes specified in Attachments A and B to this letter, and as further described in the comments submitted by NEI.
Respectfully submitted, COMBUSTION ENGINEERING, INC.
1
/wau l
Charles B. Brinkman, Director l
Nuclear Licensing j
Attachment A ABB-CE's Suggested Revisions to the Language of the Draft Final l
Design Certification Rule for the System 80+' Design i
(red'ine/ strikeout) t l
Attachment B ABB-CE's Proposed Design Certification Rule for the System j
80+~ Design (clean version)
I cc (w/ Attachments):
Chairman Shirley A. Jackson l
Commissioner Kenneth C. Rogers i
Commissioner Greta J. Dikus l
Mr. James M. Taylor, EDO l
Design Certification Senior Managers Committee:
Mr. James Milhoan Mr. William Russell Dr. David Morrison Mr. Martin Malsch, Esq.
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1 ATTACIIMENT A ABB-CE's SUGGESTED REVISIONS TO THE LANGUAGE OF THE DRAFT FINAL DESIGN CERTIFICATION RULE FOR TIIE SYSTEM 80+ STANDARD PLANT DESIGN l
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l This attachment provides ABB-CE's suggested changes to l
the language of the draft final design certification rule for l
the System 80+ Standard Plant Design. This attachment identifies ABB-CE's suggested additions through use of
@i$ and suggested deletions through use of strik=t.
Each change has an associated footnote which explains ABB-CE's reasons for the change (with the exception that i
the first footnote is contained in the rule itself).
1 l
L Appendix B To Part 52 Design Certification Rule for the System 80+ Design l
1.
Introduction.
l Appendix B constitutes design certification for the System 80+* standard pit at i
l design, in accordance with 10 CFR Part 52, Subpart B. The applicant for certification j
of the System 80+ design was Combustion Engineering, Inc. (ABB-CE).
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2.
Definitions.
i As used in this part:
(a)
Generic design control document (generic DCD) means the document i
that contains the generic Tier 1 and Tier 2 information that is incorporated by reference into this appendix.
(b)
Plant-specife DCD means the document, maintained by an applicant or l
licensee who references this design certification rule, consisting of the information in the generic DCD, as modified and supplemented by the plant-specific departures and exemptions made under Section 8 of this appendix.
l (c)
Tier 1 means the portion of the design-related information contained in the generic DCD that is approved and certified by this design certification rule l
L (hereinafter Tier 1 information). The i; iga i;;ripha;, int;';;c regier. cat, ad
- it p==;tr; r.r iid frc= Tier 2 ins;;;Sn.8 Tier 1 information includes
(1)
Definitions and general provisions; (2)
Oc; iga Q@@ldiiiijg2 descriptions; (3)
Inspections, tests, analyses, and acceptance criteria (ITAAC);
- ' System 80+" is a trademark of Combustion Engineering. Inc.
This language is replace by language provideo slow to conform to the 2
provisions in the DCD Introduction.
This addition clarifies that Tier 1 includes only the certified design descriptions.
2
(4)
Significant site parameters; and (5)
Significant interface requirements.
1h,e._tified.de ig_n.y%,uonst sigmfic_ ant %.ie,_p_a_ra_nuae_rst and_si_ m_.6c_ ant cer s
g indirface equirements am derived firam Tier 2 information, but may tie aume genedd.
than the provisions in lier 2.' Ca=ph with tlw more detailed Tier 2 maennial himnie s'sufBcient, but'act the only, acceptable, method forfcceplying wish the~axire seaeral'oroWeiens'im^11er 1,0acinding Ibo RTAACh Compuance aseeds diShrfug from 11est2 material must smalsfy she clungs process provisions speci8ed in Sectice 8(bh and such Afterescos shaB act negate a COL applicants er_ hold _er's'ge_neral_
- - - _ _ _ _ -. - ~. _ _ _ _.-_
er4 rperima.pyw*y,ly.y.y.ungs.b.y.rp;d-ag4nyy.yrsdW,, yggsy.vyyny.y)g yygy 1'1s%%:Dy*W. n cr hons:noi_:llm4vp1.psn49 on ;so,t e esign'e ructures iiilsiiiRWesig-W%W Des &Ns,l_p% 44+ %w>WyptemissentsWhiis M
9 Wa.mmenk #gstmi&iserationd G"MMMri'# ncosiitEM/bideeinMir@M^
i
%2ETisdistidt govsrn.' Desijn. actikidsOdiFstructures![hp"si$ns/sds,,5EZ3 6utside%!s, cope?bf thESyste.ni80R.s,tandme.mm.igr_i'm.ay beA _.M_._iss_ini.s.~i dss
- M?
4
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7 specifaides,gn paradmmysr i
(d)
Tier 2 means the portion of the design-related information contained in the generic DCD that is approved but not certified by this design certification rule (hereinafter Tier 2 information). Ccmpii; ace wie Tier 2 is rcquired, but gcacric changes c ard plan: ;p;ciS; iparturcs from Tict 2 are goveracd by Scctica 8 cf iis apperd'a.* Tier 2 information includes:
(1)
Information required by 10 CFR 52.47, wis oc caccpuca of :cchcica!
speciSca:icas and concep:;;! isign inform:dca; (2)
Information required for a final safety analysis report under 10 CFR 50.34; (3)
Supporting information on the inspections, tests, and analyses that will be performed to demonstrate that the acceptance criteria in the ITAAC have been mett-end7C6iiplian6FWitli^Td2iiiWNiME6iiiTini
_iiii_isii_Ei_iFiljTdisi"6iild_in_eth_o_d*fo_r?co_rnp_iy_ihgM_ih* tG T_r$_X_CM1%
m -_
.m Then additions reflect provisions in the DCD Introduction that have been 3
approved by the NRC. These provisions are needed if the NRC does not ino>rporate the DCD Introduction into the O.eign certification rule. Sec NEI Coinments, i VI.
This language was deleted because it is inconsistent with the DCD Introduction.
- i
.-s c..v
.w e-nesow wasesi acertincationwfedes inoe.m. specired,4.+vshww,eena.v.vhjwv;.&%w> mum.wwe+.s.mamev,A+M*-mbxv+,ia.cyn,mm<m4*v>nW ma
/ /"* Of I.I.w~b. 0w_ _. I _ f..,...._.a f.- \\
+
'O_
L*__J I.I, _ _ _ _ /P OT \\._.w.*.._ _.. *. a.w._..a_
(4)
+
..)
gw vas w.... u...w.
.ww..ev gw v asj
.. Info.v.w.w.vy.,y.sw.g. Items, wh,ch identi certa,n
..w,mg ws-nnahon i
i Coyn,..bieum.wdyLa.pwvw-uq m ne conso s
vs.munnanna,.anu.va mym.w.
ww.+w youam. ~nns ex.amama
.! a m.~,,~w.C...m a.f.
.m.f a.l..~.C._..._.1 matters that._L_19 L
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i 5.r.:.t r.t2:4. ~aisiidT6Widdniiiied bi'ai'if@lisnt'hiifli6siins
~isi5iiiiMdsiliiiihettificanon rule for tile Sjstein 8%atsindant, se IlesignETho'parpose of these COL Ucenselaformadas feeins isto identify:the type ofinformadon that must be ikirssssd bs ? Ep' ~
DCDs that reference the design:cerdficadon rule'for We; System,80+,'
'standant design,These COL Ilcense Information Items dd'aot' establish imup'ussments; inthesthey identify"an% cop;stde' set)'of W%but i
'not the only acceptable set of informananl for, inclusion in' a'plaatj j
specific DCD. %i applicant may deviate futun' or omit these COL Ucense Informadon items, provided that the deviation or ' omission ii identified and justified in the plant +pecific DCD1 'AAer le==mara of a
' construction perniit or license,' the ' COL License Information Items hav6 iso further effect to that liceis. e';1instead=the_' orrespu_d_ing provis. ions in i
nMeiam specine DCD'aHFappil6abisfaiid'
- id c
MEProposed wenicas pe'cifications foF the poitidn'of the^pisnt'iirithin"ths s
scope of'the standard design. These proposed technical agw1Readamp
$pplicable to an' applicant for a combiried license ci a
i fenical erwineatiaan in the license, ixcept sis changed pursuant to'the patwisions,in Section,8 of this design certification' rule that apply to changes to Tier 2 information. Changes in the proposed technical siwincadone byg.a license applicant:are subject to NRC revicMand w
r_o_ceed_. nA_fter_<is_~su_a_nc_e,
,.__an,d,~.a_~ b_ean.u n,ng'_as p_ art.,o_f_the_;h.o_ ens _e:pns aw nw n
w mg_a This language was added to clarify the role of Tier 2 information in complying 5
with the ITAAC.
These changes and additions reflect the provisions in the DCD Introduction which have been approved by the NRC. These provisions are necessary if the NRC does not incorporate the DCD Introduction by reference into the design certification rule. Scc NEI Comments, 6 VI.
iftliiUnsidaad licsinis~ sift 6periitiiifliassiis' tliiijw[iiijiss f
incluscal specificatio lin stE license become effectivs?
(6Lgtefannoes%ao:Is!Syste(80BStanlard Safety 'AnalisifRijisKf
,iiii.u w sir _.ed.d_ m _w__g_a _ e._ec_n_6._.7_h_m_rerii.m_t_ia_
i r
m thereinM~IETa.eirt,w.un i
wa..uwwx-a.?mmm%.u.w),
(e)
Tier 2* means the portion of the Tier 2 information, idgs::d ;; :=h
-~...~._.,,.....1._._.m__._.t_~.....y._.1_... _c _ _.1._._. y,t m,._,..e _
_e _t x___
o 1_
.t _
,w api ~; dix. Ei; id;2:ica spire; for ;cs; iithicli disiiOliE"liiiiiiiiiiiillilllinliQiii6if C
l.. iMEE5..iiPd~ dis,i,f,;iinitiEiiFdari%,TiesilifdEiniisaTidisilfiedli N..~R,7.. Jiibsmii.iiiF<
i
. sosialeticasissilhenge(.,,,g.a..m, e.. : u,,?wann:.we, a& ym;w.nwes,wan.a.,,m,,>
- n.-
s...
.u
. 1,q.,
ad Tier 2* information ;mrr-.: :: E-:-:dc y
x n
w lhe:DCD g
g w
. iiissg>n,.ae. n,ege aTie,. m, formatio =n?.t_ies%hMion_tratiesiWE h gM M2iinfess l
i er.
an
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a,n her r2m c
ntaannerla ot
- - - ~ ~ -
(f)
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.
i l
3.
Scope and contents of this design cenification.
(a) Tier I ad Tier 2 of :he System 80+ Design Control Document, ABB-CE, dated are ;yyre s,.,cris mcmps by;se,m_, w,Jihn.ss incorporat. ion by
.__u,,
l reference i_iiii~iigijiii6G_iid by thTDIidct876f" die Dffi2Edfi$ Ederal Register on x
~
[ Insert date of approval) in accordance with 5 U.S.C. 552(a) and 1 CFR Part 51.
Copies of the generic DCD m;y be cS ;!=d frc= [In-d.==: =d iirs; cf i
pylica: cr c;; air;.dca isiga::d by :h :pplian:] Sysisisil80EDCDjiisy[liis jii.i.ii.iicliii_iiiilT,_nisiiNi_iiH6_Eiiil2Ts_sh_ni.6_iF16mf6if.i_li_iitioiii'5_6i91_6e_nsinis.sfield6V_M2_21_~
mm m.
_mm
.~m x
l Copies are also available for examination and copying at the NRC Public Document l
Room,2120 L Street NW. (Lower Level), Washington, DC 20555, and for 1
' This pec.agraph was added to indicate that Chapter 16 Technical Specifications will remain pan of Tier 2 of the design certification. Sec NEI Comment, 6 II.
This addition clarifies that only NRC approval is required for changes to Tier 8
2* 7md also indicates that all Tier 2* restrictions expire at first full power. See NEI Comments, ) VII.
This change identides the organization from which the DCD may be purchased.
5
A l
examination at the NRC Library,11545 Rockville Pike, Rockville, Maryland 20582-2738.
l (b)
An applicant or licensee referencing this appendix, in accordance with Section 4 of this appendix, shall comply with the requirements of this appendix, including Tier 1 and Tier 2, except as otherwise provided in this appendix.
l (c)
If there is a conflict between Tier 1 and Tiet 2 of the DCD, then Tier 1 l
controls.
l (d)
If there is a conflict between the generic DCD and either the application for design certification for the System 80+ design or NUREG-1462, " Final Safety l
Evaluation Report related to the Certification of the System 80+ Design," dated August 1994 (FSER) and any supplements thereto, then the generic DCD controls.
l l
(e)
Csaap;ad design ir.for.T.cdsr. cc.d gcacdc :canical apccincansa;, a; sci 4
52T47(iXIXii)T6 sib &ipuiiilidsiighii:^jisividedff6EtbuisiisitionRaf[t1E) feri la ic gcr.cric DCD, r.2 r.c: pr.r: cf 11: cpper.dic. N'TiNRMiidWIO l
isope oihlisf5ystonil80$standsd^diNijhbindi$Qssidthidiinijniertificintioiinisle Intisiysteine190M@WeasafsidM56t3asiselsfusgsifemesiis applicable to a iiiii' )MjdMapMga]ijeMMyfeij@gMMpertijcajos M
l l
4.
Applications and licenses referencing this design certification: additional i
requirements and restrictions.
l l
(a)
An applicant for a combined license that wishes to reference this Appendix shall, in addition to complying with the requirements of 10 CFR 52.77, l
52.78, and 52.79, comply with the following requirements:
(1)
Incorporate by reference, as part of its application, this appendix; (2)
Include, as part of its application:
(i)
A plant-specific DCD containing the same information and utilizing the same organintion and numbering as the generic DCD for the System 80+ design, as modified and supplemented by the applicant's exemptions and departures; l
l Tl?is change provides additional clarification regarding the use of conceptual design information.
i.
l (ii)
The reports on departures from and updates to the plant-specific DCD requimd by Section 10(b) of this Appendix; (iii)
Technical specifications for the plant that are required by i 50.36 and i 50.36a; (iv)
Information demonstrating compliance with the site parameters and interface requirements; (v)
Information that addmsses the COL action-hems Uisisi
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" This change reflects the provisions in the DCD Introduction. Sec NEI Comments, i VI.
i 2 This change deletes the operational applicable regulations that were originally proposed in the April 1995 NOPR. Scc NEI Comments, i IV.
j l
" This change deletes the applicable regulations. Sec NEI Comments, i IV.
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(3)
Physically include, in the plant-specific DCD, the proprietary information referenced in the System 80+ DCDh-end
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- I 5' This change deletes the applicable regulations. Scc NEI Comments, i IV.
This change deletes the applicable regulations. Scc NEI Comments, 5 IV.
25
This change deletes the applicable regulations. Sec NEI Comments, f IV.
i I
i i
(c)
Facility operation is not within the scope of this appendix, and the Commission reserves the right to impose requirements for facility operation on holders of licenses referencing this appendix by rule, regulation, order, or license condition; p61idiiiissi63MiifsitiilisisiiiftiiifTdsissisiMWiiiiiiUHiiiiiiiiiiiiiiiiiiii c,r52s#formadaa%m.w_tinc jiand[ mud:sa!igns ehenseqq sa%s W9 s
ia
~ ~ ~ - - _s co
~~a.--n-w (d)
The Commission reserves the right to determine whcear, er.d in what manner this appendix may be referenced by an applicant for a construction permit or operating license under 10 CFR Part 50.
5.
Applicable regulations.
(a)
Except as indicated in paragrcphs (b) ;;d (c) of this section, the regulations that apply to the System 80+ design are in 10 CFR Parts 20,50,73, and l
100 codified as of [ insert the date 30 days after the publication date] that are j
applicable and technically relevant, as described in the FSER and any associated supplements.
(b)
The System 80+ design is exempt from portions of the following regulations, as described in the FSER (index provided in Section 1.6 of the FSER):
)
i (1)
Paragraph (0(2)(iv) of 10 CFR 50.34 - Separate Plant Safety Parameter Display Console; (2)
Paragraphs (0(2)(vii), (viii), (xxvi), and (xxviii) of 10 CFR 50.34 -
Accident Source Terms; l
(3)
Paragraph (0(2)(viii) of 10 CFR 50.34 - Post-Accident Sampling for -
l Hydrogen, Boron, Chloride, and Dissolved Gases; i
(4)
Paragraph (0(3)(iv) of 10 CFR 50.34 - Dedicated Containment l
Penetration; j
(5)
Paragraphs III.A.l(a) and III.C.3(b) of Appendix J to 10 CFR 50 -
l Containment Ixakage Testing; and (6)
Paragraph VI(a)(2) of 10 CFR Part 100, Appendix A - Operating Basis Earthquake Design Consideration.
(c)
In r.dd!Sc; to ia r;;;!dex ;paif.cd in pr.r;;.eph (:) of i.i; ;;;ica, e.; fc!!cwing a;w reguiden; are app!!;;bk for purpse;; cf 10 CFR 52.48,52.54, 52.59 ;;d 52.53:
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1 17 This change deletes the applicable regulations. Sec NEI Comments, f IV.
" 1 l
6.
Issue resolution for this design certification.
(a)
The Commission has determined that the structures, systems, components, and design features of the System 80+ design comply with the provisions of the Atomic Energy Act of 1954, as amended, and the applicable regulations identified in Section 5 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, or justifications are not necessary for the System 804-design.
(b)
The Commission considers the following matters resolved within the meaning of 10 CFR 52.63(a)(4) in subsequent proceedings for issuance of a combined i
license, amendment of a combined license, er renewal of a combined license, Mijjj.
j@@M!M[pjjiEEMpis]" proceedings held pursuant to 10 CFR 52.103, and enforcement proceedings -.~.. ~.~ y.
!;g; luj64M(M)l@"
reference this appendix-(1)
All nuclear safety issues associated with the information in the FSER and any associated supplements, the generic DCD (including referenced information which the context indicates is intended as requirements), and i-the rulemaking record for certification of the System 80+ design; l
(2)
All nuclear safety issues associated with the information in proprietary documents referenced and in context is intended as requirements in the generic DCD for the System 80+ design; (3)
Exap :: pre cided in Sc ica S(b)(5)(vi) of di: ;ppadix, a!! t~y.r:;;;
r fic.;. Tic 2 par;;n: :c ;;d in s.T.pliar.c C11; chng: pa-:c;;-:; in i
Ex:ica S(5)(5) cf di appu.di i:: dc ac: aq ::: prix NRC c.rrre cr.!;
i K % # W K S 2 @ N !! M J M M M N Masurkeasigs.ctiongg
\\
1
" His change clarifies that finality is also accorded in design certification renewal i
proceedings. Scc NEI Comments i I.
" His change clarifies that finality applies to plants, not proceedings. kg NEI Comments, 6 I.
This change clarifies that changes to Tier 1, Tier 2*, and Tier 2 are accorded 2
l finality if the changes are made in accordance with the change process. &&
j NEI Comments, i I.
l 13-1
- - - -.... - - -.~ - -.
i i
t (4)
All environmental issues concerning severe accident design alternatives i
associated with the information in the NRC's final environmental assessment for the System 80+ and Revision 2 of the Technical Support Document for the System 80+ design, dated January 1995, for plants referencing this appendix whose site parameters are within those specified in the Technical Support Document. KiifisisijillsiKg gridii"E"gi"p7isWT&4iElini. Sipjiggnacamme Tseygge (c)
Except in accordance with the change processes in Section 8 of this appendix, the Commission may not require an applicant or licensee who references l
this appendix to:
(1) -
Modify structures, systems, components, or design features as described 4
in the generic DCD; (2)
Provide additional or alternative structures, systems, components, or L
design features not discussed in the generic DCD; or (3)
Provide additional or alternative design criteria, testing, analyses, acceptance criteria, or justification for structures, systems, components, l
or design features discussed in the generic DCD.
l (d)
Persons who wish to review proprietary information or other secondary refdrences in the DCD for the System 80+ design, in order to request or participate in the hearing required by 10 CFR 52.85 or the hearing provided under 10 CFR 52.103, or to request or participate in any other hearing relating to the certified design l
in which interested persons have adjudicatory hearing rights, shall first request access l
to such information from ABB-CE. The request must state with particularity:
(i) the nature of the proprietary or other information sought; (ii) the reason why the information currently available to the public in the NRC's public document room is insufficient; l
(iii) the relevance of the requested information to the hearing issue (s) which l
the person proposes to raise; and l
2' This addition clarifies that severe accident design alternatives (SAMDA) retain l
finality when an exemption has been issued for a technical support document j
site parameter absent a showing that the exemption has an adverse impact on the SAMDA. Scc NEI Comments, { I.F.
i
_14
(iv) a showing the requesting person has the capability to understand and utilize the requested information.
(3)
If a person claims that the information is necessary to prepare 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 52.85 or 10 CFR 52.103. If l
ABB-CE declines to provide the information sought, ABB-CE shall send a written response within ten (10) days of receiving the request to the requesting person setting forth with particularity the masons for its refusal. The person may then request the Commission (or presiding officer, if a proceeding has been established) to order disclosure. The person shall include copies of the original request (and any subsequent clarifying information provided by the requesting party to the applicant) and the applicant's response. The Commission and presiding officer shall base their decisions solely on the person's original request (including any clarifying information provided by the requesting person to ABB-CE), and ABB-CE's response. The Commission and presiding officer may order ABB-CE to provide access to some or all of the requested information, subject to an appropriate non-disclosure agreement.
(s)"Ad'agiipH6aist"feir'disigiTifti6cstiini ien' ival'shall'iipdats'ths"a^ p~ptidatio'ai e
f6iF' assign certification. The' update shall consist of an amendment of Tables l.8-2 1,8-3,^and't.84 of Tidr 2 for tbs System 80+ to ii ;ify relevant expedence betetejis, the time of'certificadon 'and the renewal application. For each relevant esperience; the updated applica'tiin shall explain whether the maandadi design adeqisately **anM
^
~
for thefnew esperiensi and, if not? whether the new~ experience indicases s'need for a
' change la she'standedfdesign'in order to'(1) provide' adequate prec*ian of she puhuc beidth and'inisty,'(2) ensose complisaice with NRC segulations in effect'et flieftinfof
'the orighial dereiA^malan, or '(3) provide a substantial, cost justified' increase la safety
'under'10 CFR'52.59. The NRC review of the renewal application wiB be liasited'io the uphised_ data and,information and_any snodificafens proposed _by,_the] enemal[
g is 7.
Duradon of this design certification.
This design certification may be referenced for a period of 15 years from
[ insert the date 30 days after the publication date], except as provided for in 10 CFR 52.55(b) and 52.57(b). This design certification remains valid for an applicant i
22 This addition is made to clarify the scope of the renewal application and the staff's review. See NEI Comments, $I D.
4.-
or licensee who references this appendix until the application is withdrawn or the license expires, including any period of operation under timely renewal or a renewed license.
8.
Processes for changes and departures.
(a)
Tier 1 information.
(1)
Generic changes to Tier 1 information are governed by the requirements in 10 CFR 52.63(a)(1).
(2)
Generic changes to Tier 1_ information are applicable to all plants referencing the design certification as set forth in 10 CFR 52.63(a)(2).
.(3)
Departures from Tier 1 information that are imposed by the Commission through plant-specific orders are governed by the requirements in 10 CFR 52.63(a)(3).
(4)
Exemptions from Tier 1 information are governed by the requirements in 10 CFR 52.63(b)(1) and i 52.97(b).
(b)
Tier 2 information.
(1)
Generic changes to Tier 2 information shall be governed by the same requirements in 10 CFR 52.63(a)(1) that govern generic changes to Tier 1.
(2)
Generic changes to Tier 2 information are applicable to all plants referencing the design certification as set forth in 10 CFR 52.63(a)(2).
(3)
The Commission may not impose new requirements on Tier 2 by plant-specific order while the design certification is in effect under il 52.55 or 52.61, unless:
(i)
A modification is necessary to secure compliance with the Commission's regulations applicable and in effect at the time the certification was issued, a; ad fed in htisa 5 of ei; Agndix,23 or to assure adequate protection of the public health and safety or the common defense and security; and (ii)
Special circumstances as defined in 10 CFR 50.12(a) are present.
(4)
An applicant or licensee who references the design certification may request an exemption from Tier 2 information. The Commission may grant such a request only if it determines that the 23 This change reflects the deletion of the additional applicable regulations..
exemption will comply with the requirements of 10 CFR 50.12(a). %e
.. ;dag of such en ex.apdca.ns;; b; 2;.bbc: :c !!dg:d- ' - - --
4
________.t__r__..___.t_
_ _ o _ _ ; m _ _ _ < _ _ _. _ _
...... ~.
Eilisiiili6i~l6KCOriiispiniiiifissiiNst$5stWiltljiid6EW gg
>m ygueqggrgy$ eases.asudW~~~~
isPilGEM6MMdexeinstionMufl listeseitairesipantsni MiiIbisiiings@sMnar[sg l.i. cense..mmaamemaan?
(5)
(i)
An applicant or licensee who references the design certification j
may depart from Tier 2 information, without prior NRC approval, l
unless the proposed departure involves a change to or departure from Tier 1 information, Tier 2* information, or the technical l
specifications, or involves an unreviewed safety question as j
defined in paragraphs (b)(5)(ii) and (b)(5)(iii) of this section.
l When evaluating the proposed departure, an applicant or licensee shall consider all matters described in the plant-specific DCD.
i (ii)
A proposed departure from Tier 2, cier 1:n cm.?cc ing @
iiiWTiifiiffeiEf?6iiii*ttiii resolution of a severe accident issue tir 4
OM5hdih@ni identified in Secdon 19.11 Q
[
1% of the plant-specific DCD ix!; ding appcadice; 19.11A ircugh 19.11L, invcive:Vi_lG_lillWdi_ Bis _iB.Wii.is76t.Gi! an unreviewed o
m_m I
safety question if:
iA)
The probability of occurrence or the consequences of an i
accident or malfunction of equipment important to safety i
previously evaluated in the plant-specific DCD may be j
mcreased; j
(B)
A possibility for an accident or malfunction of a different type than any evaluated previously in the plant-specific DCD may be created; or (C)
The margin of safety as defined in the basis for any technical specification is reduced.
(iii)
A proposed departure from Tier 2 affecting resolution of a severe 49:+1-QMg5]dssij6;lisi[iishid6W issue identified in accident Kyj6nd of the plant-specific DCD, ix!uding 24 This addition clarifies the hearing requirements associated with issuance of an j
exemption to Tier 2 information. See NEI Comments, 6 XI.
25 These changes clarify that all of Chapter 19 should be subject to the
" substantial increase" standard in the change process. Sec NEI Comments, i V..
l l
apF.-Z= 19.!! A i=gh 19.llL, involves an unreviewed safety l
i l
question if:
l (A)
There is a substantial increase in the probability of a severe l
accident 6ig6Ed}desijs^) sis'sc6idsiidM$li CIGijiioE19 such that a particular severe accident g!i5j6~sd design _b_uis~aEEid6Ef reviousiy reviewed and determined
_P to be not credible could become credible; or l
(B)
There is a substantial increase in the consequences to the public of a particular severe accident glisjgiid]dnigij
@yc6idejiil previously reviewed.
(iv)
If a departure involves an unreviewed safety question as defined in paragraph (b)(5) of this section, it is governed by 10 CFR 50.90 l
and $ 92.
(v)
A departure from Tier 2 information that is made under paragraph l
,d6-estn_oL, _l_ve_an_w?f5iDii"dsisisiiiiF^"fr6E (b)(5) of this section e
l
- - -~~~ ~
gdoes not
-w a ww m_ _vo unr_e_vew_ed_a;
. __on_
m m -
__m l
require an exemption from this Appendix.
l (vi)
A party to an adjudicatory proceeding for either the issuance, I
amendment, or renewal of a combined license or for operation i'
under 10 CFR 52.103(a), who believes that an applicant or licensee has not complied with paragraph (b)(5) of this Section when departing from Tier 2 information, may petition to admit l
into the proceeding such a contention. In addition to compliance with the general requirements of 10 CFR 2.714(b)(2), the petition l
must demonstrate that the departure does not comply with l
paragraph (b)(5) of this Section. Firths 7diiifiinitisii"Eiiid jggjj;ggjjjgg;jjg g @g g *gjgjjjp,g g h g y wr 3WWME l
@ aii N N 5)i106reoperationil"hesijlig(6r;[Adil%hhand6 ears dir$itifyiij l
- I"*88 g g-- - -- -
g g,
m mEndm.ent?' Any other party may file a response thereto. If, am on the basis of the petiuon 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 p
2' This change provides that an exemption is not required for departures from Tier 2* that do not involve an unreviewed safety question. Sr& NEI Comments, 6 XI.C.
This change clarifies that there must be a nexus between the asserted non-27 compliance and the subject of the proceeding.
l
! L
I a
determination of the admissibility of the contention. The Commission may admit such a contention if it determines the petition raises a genuine issue of Eis_lElisize fact regarding compliance with paragraph (b)(5) of this Section.
i i
(6)
(i)
An applicant for 6E_libid.R5f a combined license may notilii.niEii i-
.~
Ei6iif,flill*ji5iiiis.4.^wiF;2' depart from Tier 2* designation, which is
+xWe' FgA WasetM-designated with italicized text or brackets and an asterisk in the r
Mv.MMw generic DCD, without prior NRC approval. The iy um wi!!
1
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i neerinec wii pr. ;.. ph (b)(6)(ii) of Sh Scch;. Abr ic This change clarifies that the alleged non-compliance must be material. Scc 2:
NEI Comments, i I.G.
29 This change reflects the expiration of Tier 2* information at first full power.
Scc NEI Comments, i VI.
This change reflects the expiration of Tier 2* information at first full power.
Sec NEI Comments, ) VI.
These changes reflect the expiration of Tier 2* information at first full power and clarify that departures from Tier 2* only require prior NRC approval; an j
exemption is not required for Tier 2* changes that do not involve an unreviewed safety question. Sec NEI Comments, i VI. -
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~ sus sa u s 32 This change reflects the expiration of Tier 2* information at first full power.
Scc NEI Comments, i VI.
" This change clarifies that departures from Tier 2* only require prior NRC approval; an exemption is not required. See NEI Comments, i VI.
" These deletions are necessary to reflect the prior deletion of the applicable regulations..
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9.
Inspections, tests, analyses, and acceptance criteria (ITAAC).
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l (a)(1) An applicant or licensee who references the design certification shall
(
perform and demonstrate conformance with the ITAAC before fuel load.
With respect to activities subject to an ITAAC, an applicant for a COL may proceed at its 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 yet have found that any particular ITAAC has been satisfied.
l (2)
The licensee shall notify the NRC that the required inspections, tests, and analyses in the ITAAC have been successfully completed and that the corresponding acceptance criteria have been met.
l (3)
In the event that an activity is subject to an ITAAC, and ic applican; or lic== he act demc=:ra;;d i;; i: ITAAC hn han :::i;f.cd,1:
l
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_d _m,_,ih4iiiitW,nilTA,ACythe an ianinoncon a
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_n_@. _.fo,sy_@_~. __,wyQL M e.r---e ~~.-me ap gant PAC ither take corrective actions to successfully complete that ITAAC, reque;; an gi6i[UsiiMMpJR l
iigiii.ss..ia.IW's"slWGijif.fii.'6if exemption from the ITAAC in accordance
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ec ITAAC==: mcc: i: rcquiremer.:: cf ".,= tic: S(:)(1) of di; appendix l_ish"d._ssij_i ~ds.m._ifida_ti_6s_i"i_hls.i_f6_FRS_fia_6H_i180_E_S_unidiGFd Ft P_lisi.
.-~
This addition specifies how changes can be made to the DCD Introduction. Sec 35 j
NEI Comments, i VI.
36 This addition specifies how changes can be made to the DCD Introduction. Scc NEI Comments, i VI.
37 This change clarifies that a COL applicant or holder may either request an l
exemption from an ITAAC requirement or obtain NRC approval to change the j
ITAAC in accordance with the change process specified in the rule.
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s (b)(1) The NRC shall ensure that the required inspections, tests, and analyses in the ITAAC are performed. The NRC shall verify that the inspections, tests, and analyses referenced by the licensee have been successfully j
completed and, based solely thereon, find the prescribed acceptance l
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 Commission shall find that the acceptance criteria in the ITAAC for the combined license are met before fuel load.
(3)
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10.
Records and Reporting.
(a)
Records.
(1)
The applicant for this design cenification rule shall maintain a copy of i
the generic DCD that includes all generic changes to Tier 1 and Tier 2.
The applicant shall maintain the proprietary information referenced in the l
1 L
Rulemaking is not required.
i j
These changes are needed to conform with the provisions in the DCD Introduction. &c NEI Comments, QVI.
1 l
)
generic DCD for the period that this appendix may be referenced, as l
specified in Section 7 of this appendix.
j (2)
An applicant or licensee who references this design certification shall maimain the plant-specific DCD to accurately reflect both generic j
I changes to the generic DCD and plant-specific departures made pursuant to Section 8 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 mferences this design certification shall l
prepare and maintain written safety evaluations which provide the bases for the determinations required by Section 8(b) of this appendix. These l
evaluations must be retained throughout the period of application and for the term of the license (including any period of renewal).
i l
(b)
Reponing.
l l
(1)
An applicant or licensee who references this design certification rule shall submit a repon to the NRC containing a brief description of any depadures from the plant-specific DCD, including a summary of the l
i safety evaluation of each. This repon must be filed in accordance with l
the filing requirements applicable to reports in 10 CFR 50.4.
l (2)
An applicant or licensee shall submit updates to its plant-specific DCD, which reflect the generic changes to the generic DCD and the plant-specific departures made pursuant to Section 8 of this appendix. These updates shall be filed in accordance with the filing requirements applicable to final safety analysis report updates in 10 CFR 50.4 and 50.71(c).
(3)
The reports and updates required by Section 10(b)(1) and (2) above must i
be submitted as follows:
(i)
On the date that an application for a combined license referencing this design certification rule is submitted, the application shall i
include the report and any updates to the plant-specific DCD.
(ii)
During the interval from the date of application to the date of issuance of a combined license, the report and any updates to the plant-specific DCD must be submitted annually and may be submitted r.long with amendments to the application.
(iii)
During the interval from the date of issuance of a combined license to the date the Commission makes its findings under 10 CFR 52.103(g), the repon must be submitted g.
dy [o@
t r
3 1
k i
issii[allj." Updates to the plant-specific DCD must be submitted annually.
i (iv)
After the Commission has made its finding under 10 CFR i
52.103(g), reports and updates to the plant-specific DCD may be l
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 combined license.
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This change reduces the reporting burden by requiring reports only twice a year instead of four times a yer.r.
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ATTACHMENT B ABB-CE's PROPOSED DESIGN CERTIFICATION RULE FOR THE SYSTEM 80+ STANDARD PLAhT DESIGN 4
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Appendix B To Pad 52 Design Certification Rule f
L for the System 80+ Design i
i 1.
Introduction.
Appendix B constitutes design cenification for the System 80+* standard plant design, in accordance with 10 CFR Part 52, Subpart B. The applicant for cenification of the System 80+ design was Combustion Engineering, Inc. (ABB-CE).
2.
Definitions.
{
As used in this part:
i' (a)
Generic design control document (generic DCD) means the document that contains the generic Tier 1 and Tier 2 information that is incorporated by i
reference into this appendix.
(b)
Plant-specige DCD means the document, maintained by an applicant or licensee who references this design certification rule, consisting of the information in -
l the generic DCD, as modified and supplemented by the plant-specific depanures and exemptions made under Section 8 of this appendix.
j (c) 77er 1 means the portion of the design-related information contained in the generic DCD that is approved and certified by this design cenification rule (hereinafter Tier 1 information). Tier 1 information includes:
(1)
Definitions and general provisions; (2)
Cenified design descriptions; (3)
Inspections, tests, analyses, and acceptance criteria (ITAAC);
(4)
Significant site parameters; and (5)
Significant interface requirements.
The certified design descriptions, significant site parameters, and significant interface requirements are derived from Tier 2 information, but may be more general l
than the provisions in Tier 2. Compliance with the more detailed Tier 2 material provides a sufficient, but not the only acceptable, method for complying with the more general provisions in Tier 1 (including the ITAAC). Compliance methods differing...
. _ --__ m __
_ _ _. _. _ _.. -. ~.. _ _. _ _ _ _ _
from Tier 2 material must satisfy the change process provisions specified in Section 8(b), and such differences shall not negate a COL applicant's or holder's general requirement to reference Tier 2 when referencing Tier 1.
l The Design Descriptions in Tier 1 penain only to the design of structures, l
systems, and components of the System 80+ standard plant and not to their operation, l
maintenance, and administration. In the event of an inconsistency between Tier 1 and Tier 2, Tier I shall govern. Design activities for structures, systems, and components outside the scope of the System 80+ standard design may be performed using site-specific design parameters.
Tier 2 mea ~ s the ponion of the design-related information contained in f
(d) n the generic DCD that is approved but not certified by this design certification rule i
l (hereinafter Tier 2 information). Tier 2 information includes:
)
(1)
Information required by 10 CFR 52.47; (2)
Information required for a final safety analysis report under 10 CFR l
50.34; (3)
Supporting information on the inspections, tests, and analyses that will j
i be performed to demonstrate that the acceptance criteria in the ITAAC
]
have been met. Compliance with Tier 2 is a sufficient, but not necessarily the only, method for complying with the ITAAC. The j
provisions and methods specified in Tier 2 shall be followed unless a J
l change is made in the plant specific DCD in accordance with the change j
processes specified in the design certification rule for the System 80+
standard design; (4)
Combined License (COL) Information Items, which identify certain f
j matters that. need to be addressed by an applicant or licensee referencing the design cenification rule for the System 80+ standard design. The i
purpose of then COL License Information Items is to identify the type
]
l of information that must be addressed in plant-specific DCDs that -
reference the design certification rule for the System 80+ standard design. These COL License Information Items do not establish l
requirements; rather, they identify an acceptable set ofinformation, but j
not the only acceptable set of information, for inclusion in a plant-l specific DCD. An applicant may deviate from or omit these COL License Information Items, provided that the deviation or omission is identified and justified in the plant-specific DCD. After issuance of a l
construction permit or license, the COL License Information Items have no funher effect to that license; instead the corresponding provisions in the plant-specific DCD are applicable; and l -.
_ ~ - _ _
l L
(5)
Proposed technical specifications for the portion of the plant within the scope of the standard design. These proposed technical specifications are J
applicable to an applicant for a combined license or operating license.
)
referencing this design certification rule, and shall be incorporated in the 1
technical specifications in the license, except as changed pursuant to the provisions in Section 8 of this design certification rule that apply to changes to Tier 2 information. Changes in the proposed technical specifications by a license applicant are subject to NRC review and approval and a hearing as part of the license proceeding. After issuance of the combined license or operating license, the pmpc,r.,d technical specifications in Tier 2 have no furthei effect as to that licensee, and the technical specifications in the license become effective.
(6)
References to the System 80+ Standard Safety Analysis Report, which shall not be construed as incorporating these sections, or the information therein, in Tier 2.
j (e)
Tier 2* means the portion of the Tier 2 information which cannot be-changed without prior NRC approval by letter or other written document. This information is identified in the DCD. The restrictions on changes to Tier 2*
information expire at first full power for a plant that references this design certification rule. Thereafter, changes to the Tier 2* information shall be controlled in the same manner as changes to other Tier 2 information.
(f)
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.
3.
Scope and contents of this design certification.
(a) System 80+ Design Control Document, ABB-CE, dated is incorporated by reference. This incorporation by reference was approved by the Director of the Office of the Federal Register on [ Insert date of approval] in accordance with 5 U.S.C. 552(a) and 1 CFR Part 51. Copies of the generic System 80+ DCD may be purchased from National TechnicalInformation Service, Springfield, VA 22161. Copies are also available for examination and copying at the NRC Public Document Room, 2120 L Street NW. (Lower Level), Washington, DC 20555, and for examination at the NRC Library,11545 Rockville Pike, Rockville, i
J j
Maryland 20582-2738.
i l
-_c
l l
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(b)
An applicant or licensee referencing this appendix, in accordance with l
Section 4 of this appendix, shall comply with the requirements of this appendix, including Tier 1 and Tier 2, except as otherwise provided in this appendix.
l (c)-
If there is a conflict between Tier 1 and Tier 2 of the DCD, then Tier 1 i
controls.
i (d)
If there is a conflict between the generic DCD and either the application for design cenification for the System 80+ design or NUREG-1462, " Final Safety Evaluation Report related to the Certification of the System 80+ Design," dated August 1994 (FSER) and any supplements thereto, then the generic DCD controls.
(e)
As provided in 10 CFR 52.47(a)(1)(ix), conceptual designs provided i
for those portions of the plant outside the scope of the System 80+ standard design l
l are not part of the design certification rule for the System 80+ standard design, and j
do not impose requirements applicable to a license, nor to an application for a license, that xferences the design certification rule; j
l 4.
Applications and licenses referencing this design cenification: additional requirements and restrictions.
l (a)
An applicant for a combined license that wishes to reference this Appendix shall, in addition to complying with the requirements of 10 CFR 52.77, i
52.78, and 52.79, comply with the following requirements:
l (1)
Incorporate by reference, as part of its application, this appendix; l
(2)
Include, as part of its application:
(i)
A plant-specific DCD containing the same information and utilizing the same organization and numbering as the generic DCD for the System 80+ design, as modified and supplemented by the l
applicant's exemptions and departures; (ii)
The reports on departures from and updates to the plant-specific DCD required by Section 10(b) of this Appendix; i
(iii)
Technical specifications for the plant that are required by 5 50.36 and i 50.36a; (iv)
Information demonstrating compliance with the site parameters and interface requirements;-
(v)
Information that addresses the COL License Information Items, including justifications for any deviations from or omission of the l
COL License Information Items; and E r l
I
' (vi)
The information required by 10 CFR 52.47(a) that is not within the scope of this rule; (3)
Physically include, in the plant-specific DCD, the proprietary l
L information referenced in the System 80+ DCD.
i (b)
(Not used.)
i (c)
Facility operation is not'within the scope of this appendix, and the l
Commission reserves the right to impose requirements for facility operation on holders l
oflicenses referencing this appendix by rule, regulation, order, or license condition; l
provided, however, that to the extent the Commission imposes new requirements affecting information in the design certification, it must satisfy the requirements of 10 l
CFR 52.63 and Section 8 of this Appendix.
(d)
The Commission reserves the right to determine in what manner this appendix may be referenced by an applicant for a construction permit or operating l
license under 10 CFR Part 50.
5.
Applicable regulations.
I l
(a)
Except as indicated in paragraph (b) of this section, the regulations that apply to the System 80+ design are in 10 CFR Parts 20,50,73, and 100 codified as of [inort the date 30 days after the publication date] that are applicable and technically relevant, as described in the FSER and any associated supplements.
(b)
The System 80+ design is exempt from portions of the following l
regulations, as described in the FSER (index provided in Section 1.6 of the FSER):
(1)
Paragraph (0(2)(iv) of 10 CFR 50.34 - Separate Plant Safety Parameter i
i Display Console; l
(2)
Paragraphs (0(2)(vii), (viii), (xxvi), and (xxviii) of 10 CFR 50.34 -
Accident Source Terms; (3)
Paragraph (0(2)(viii) of 10 CFR 50.34 - Post-Accident Sampling for Hydrogen, Boron, Chloride, and Dissolved Gases; (4)
Paragraph (0(3)(iv) of 10 CFR 50.34 - Dedicated Containment Penetration;
j l
(5)
Paragraphs III.A.l(a) and III.C.3(b) of Appendix J to 10 CFR 50 -
l Containment Leakage Testing; and (6)
Paragraph VI(a)(2) of 10 CFR Part 100, Appendix A - Operating Basis l
Earthquake Design Consideration.
}
i 6.
Issue resolution for this design certification.
(a)
The Commission has determined that the structures, systems, components, and design features of the System 80+ design comply with the provisions of the Atomic Energy Act of 1954, as amended, and the applicable l
regulations identified in Section 5 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, or justifications are not necessary for the System 80+ design.
(b)
The Commission considers the following matters resolved within the meaning of 10 CFR 52.63(a)(4) in subsequent proceedings for issuance of a combined license, amendment of a combined license, renewal of a combined license, design certification renewal proceedings, proceedings held pursuant to 10 CFR 52.103, and enforcement proceedings involving plants that reference this appendix:
(1)
All nuclear safety issues associated with the information in the FSER and any associated supplements, the generic DCD (including referenced information which the context indicates is intended as requirements), and the rulemaking record for certification of the System 80+ design; (2)
All nuclear safety _ issues associated with the information in proprietary documents referenced and in context is intended as requirements in the generic DCD for the System 80+ design; (3)
All changes to Tier 1, Tier 2*, and Tier 2 made in accordance with the change process in Section 8, and; (4)
All environmental issues concerning severe accident design alternatives l
associated with the information in the NRC's final environmental assessment for the System 80+ and Revision 2 of the Technical Support Document for the System 80+ design, dated January 1995, for plants referencing this appendix whose site parameters are within those specified in the Technical Support Document. If an exemption is sought from a site parameter in the Technical Support Document, a severe accident design alternative will continue to have finality in all subsequent 4
proceedings absent a showing that the exemption has an adverse impact on the specific severe accident design alternative evaluation.
l
-(c)
Except in accordance with the change processes in Section 8 of this -
appendix, the Commission may not require an applicant or licensee who references this appendix to:
(1)
Modify structures, systems, components, or design features as described in the generic DCD; (2)
Provide additional or alternative structures, systems, components, or i
L design features not discussed in the generic DCD; or (3)
Provide additional or alternative design criteria, testing, analyses, acceptance criteria, or justification for structures, systems, components, l
or design features discussed in the generic DCD.
l Persons who wish to review propnetary information or other secondary (d) 1 l
references in the DCD for the System 80+ design, in order to request or participate l
in the hearing required by 10 CFR 52.85 or the hearing provided under 10 CFR l
l 52.103, or to request or participate in any other hearing relating to the certified design j
in which interested persons have adjudicatory hearing rights, shall first request access to such information from ABB-CE. The request must state with panicularity:
l (i) the nature of the proprietary or other information sought; (ii) the reason why the information currently available to the public in the l
NRC's public document room is insufficient; i
(iii) the relevance of the requested information to the hearing issue (s) which j
the person proposes to raise; and (iv) a showing the requesting person has the capability to understand and l
utilize the requested information, j
If a person claims that the information is necessary to prepare a request for j
hearing, the request must be filed no later than 15 days after publication in the Federal l
Register of the notice required either by 10 CFR 52.85 or 10 CFR 52.103. If ABB-CE declines to provide the information sought, ABB-CE shall send a written response t
within ten (10) days of receiving the request to the requesting person setting forth with particularity the reasons for its refusal. The person may then request the Commission (or presiding officer, if a proceeding has been established) to order disclosure. The person shall include copies of the original request (and any subsequent clarifying i
l information provided by the requesting party to the applicant) and the applicant's l
response. The Commission and presiding officer shall base their decisions solely on
~
i the person's original request (including any clarifying information provided by the 8-4 l
requesting person to ABB-CE), and ABB-CE's response. The Commission and presiding officer may order ABB-CE to provide access to some or all of the requested i
information, subject to an appropriate non-disclosure agreement.
(e)
An applicant for design certification renewal shall update the application for design certification. The update shall consist of an amendment of Tables 1.8-2, 1.8-3, and 1.8-8 of Tier 2 for the System 80+ to identify relevant experience between the time of certification and the renewal application. For each relevant experience, the updated application shall explain whether the standard design adequately accounts for the new experience and, if not, whether the new experience indicates a need for a i
change in the standard design in order to (1) provide adequate protection of the public l
health and safety, (2) ensure compliance with NRC regulations in effect at the time of the original certification, or (3) provide a substantial, cost justified increase in safety under 10 CFR 52.59. The NRC review of the renewal application will be limited to the updated data and information and any raodifications proposed by the renewal
(
applicant.
i 7.
Duration of this design certification.
l This design certification may be referenced for a period of 15 years from l
[ insert the date 30 days after the publication date), except as provided for in 10 CFR 52.55(b) and 52.57(b). This design certification remains valid for an applicant or licensee who references this appendix until the application is withdrawn or the i
license expires, including any period of operation under timely renewal or a renewed l
license.
8.
Processes for changes and departures.
(a)
Tier 1 information.
(1)
Generic changes to Tier 1 information are governed by the requirements in 10 CFR 52.63(a)(1).
(2)
Generic changes to Tier 1 information are applicable to all plants referencing the design certification as set forth in 10 CFR 52.63(a)(2).
(3)
Departures from Tier 1 information that are imposed by the Commission through plant-specific orders are governed by the requirements in 10 CFR 52.63(a)(3).
(4)
Exemptions from Tier 1 information are governed by the requirements in 10 CFR 52.63(b)(1) and 6 52.97(b).
3,
i l
1 (b)
Tier 2 information.
(1) _
Generic changes to Tier 2 information shall be governed by the same l
requirements in 10 CFR 52.63(a)(1) that govern generic changes to Tier 1.
(2)
Generic changes to Tier 2 information are applicable to all plants j
referencing the design certification as set forth in 10 CFR 52.63(a)(2).
(3)
The Commission may not impose new requirements on Tier 2 by plant--
specific order while the design certification is in effect under il 52.55 or i
52.61, unless:
l (i)
A modification is necessary to secure compliance with the l
Commission's regulations aoplicable and in effect at the time the certification was issued or to assure adequate protection of the public health and safety or the common defense and security; and (ii)
Special circumstances as defined in 10 CFR 50.12(a) are present.
(4)
An applicant or licensee who references the design j
certification may request an exemption from Tier 2 information. The i
Commission may grant such a request only if it determines that the exemption will comply with the requirements of 10 CFR 50.12(a).
l Issuance of the exemption to a COL applicant must be subject to litigation during the combined license proceeding in the same manner as l
i other issues material to that proceeding. Issuance of the exemption to a licensee must be subject to an opportunity for a hearing in the same j
manner as other license amendments.
(5)
.(i)
An applicant or licensee who references the design certification l
may depart from Tier 2 information, without prior NRC approval,.
L unless the proposed departure involves a change to or departure j
from Tier 1 information, Tier 2* information, or the technical j
specifications, or involves an unreviewed safety question as defined in paragraphs (b)(5)(ii) and (b)(5)(iii) of this section.
When evaluating the proposed departure, an applicant or licensee i
l shall consider all matters described in the plant-specific DCD.'
(ii)
A proposed departure from Tier 2, except as to its affect on the i
resolution of a severe accident issue or beyond design basis accident identified in Chapter 19 of the plant-specific DCD, shall be deemed to involve an unreviewed safety question if:
(A)
The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the plant-specific DCD may be mcreased; i' !
4 (B)
A possibility for an accident or malfunction of a different type than any evaluated previously in the plant-specific-DCD may be created; or (C)-
The margin of safety as defined in tis basis for any technical specification is reduced.
(iii)
A' proposed departure from Tier 2 affecting resolution of a severe accident or beyond design basis accident issue identified in Chapter 19 of the plant-specific DCD involves an unreviewed safety question if:
(A)
There is a substantial increase in the probability of a severe accident or beyond design basis accident identified in i'
Chapter 19 such that a particular severe accident or beyond design basis accident previously reviewed and determined to be not credible could become credible; or -
(B)
There is a substantial increase in the consequences to the '
l public of a particular severe accident or beyond design j
basis accident previously reviewed.
(iv)
If a departure involves an unreviewed safety question as defined in paragraph (b)(5) of this section, it is governed by 10 CFR 50.90 and 50.92.
(v)
A departure from Tier 2 information that is made under paragraph j
(b)(5) of this section, or a departure from Tier 2* information that does not involve an unreviewed safety question, does not require j
an exemption from this Appendix.
(vi)
A party to an adjudicatory proceeding for either the issuance, amendment, or renewal of a combined license or for operation under 10 CFR 52.103(a), who believes that an applicant or licensee has not complied with paragraph (b)(5) of this Section when departing from Tier 2 information, may petition to admit imo the proceeding such a contention. In addition to compliance with the general requirements of 10 CFR 2.714(b)(2), the petition must demonstrate that the departure does not comply with paragraph (b)(5) of this Section. Further, the petition must demonstrate that the change bears on an asserted noncompliance l
with an ITAAC acceptance criterion in the case of a Section l
52.103 preoperational hearing, or that the change bears directly on the amendment request in the case of hearings on a license amendment. Any other party mayTde a response thereto. If, on the basis of the petition and any response, the presiding officer determines that a sufficient showing has been made, the presiding i
officer shall certify the' matter directly to the Commission for l I
4 determination of the admissibility of the contention. The Commission may admit such a contention if it determines the petition raises a genuine issue of material fact regarding compliance with paragraph (b)(5) of this Section.
(6)
(i)
An applicant or holder of a combined license may not, before first full power, depart from Tier 2* designation, which is designated with italicized text or brackets and an asterisk in the generic DCD, without prior NRC approval. 'After the plant first achieves full power, Tier 2* information expires and has no further effect as to that licensee.
(ii)
A departure from Tier 2* information that does not involve an unreviewed safety question as defined in paragraph (b)(5) of this section does not require an exemption from this Appendix.
j (c)
Other requirements of this design certification rule.
j (1)
Generic (rulemaking) changes to the provisions in this Appendix or to the DCD Introduction are governed by the requirements of Subpart H of i
j l
(2)
An applicant or licensee may request an exemption from the provisions in this Appendix or the DCD Introduction in accordance with 10 CFR 50.12(a).
9.
Inspections, tests, analyses, and acceptance criteria (ITAAC).
(a)(1) An applicant or licensee who references the design certification shall perform and demonstrate conformance with the ITAAC before fuel load.
With respect to activities subject to an ITAAC, an applicant for a COL may proceed at its 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 yet have found that any particular ITAAC has been satisfied.
I (2)
The licensee shall notify the NRC that the required inspections, tests, and analyses in the ITAAC have been successfully completed and that the corresponding acceptance criteria have been met.
.(3)
In the event that an activity is subject to and in noncompliance with an L
ITAAC, the applicant for or holder or a COL shall either take corrective actions to successfully complete that ITAAC or request and obtain NRC I
approval of a change in or exempion from the ITAAC in accordance with the design certification rule for the System 80+ Standard Pla....
1 I.
T l
}
-(b)(1) The NRC shall ensure that the required inspections, tests, and analyses in the ITAAC are performed. The NRC shall verify that the inspections, tests, and analyses referenced by the licensee have been successfully completed and, based' solely thereon, find the prescribed acceptance criteria have been met. At ap'propriate intervals during construction, the NRC shall publish notices of the successful completion ofITAAC in the Federal Register.
(2)
In accordance with 10 CFR 52.99 and 52.103(g), the Commission shall find that the acceptance criteria in the ITAAC for the combined license are met before fuel load.
(3)
- After the Commission has made the finding required by 10 CFR 52.103(g), ITAAC no longer constitute regulatory requirements; provided, that as regards to specific ITAAC which are the subject of a Section 103(a) hearing, their expiration shall occur upon final Commission action in such proceeding. However, subsequent modifications must comply with the Tier I and Tier 2 design descriptions in the plant-specific DCD unless the licensee has complied with the applicable requirements of Section 8 of this appendix.
10.
Records and Reporting.
(a)
Records.
1 (1)
The applicant for this design certification rule shall maintain a copy _of i
the generic DCD that includes all generic changes to Tier 1 and Tier 2.
The applicant shall maintain the proprietary information referenced in the generic DCD for the period that this appendix may be referenced, as specified in Section 7 of this appendix.
(2)
An applicant or licensee who references this design certification shall maintain the plant-specific DCD to accurately reflect both generic -
changes to the generic DCD and plant-specific departures made pursuant -
to Section 8 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 design certification shall prepare and maintain written safety evaluations which provide the bases l
for the determinations required by Section 8(b) of this appendix. These
- evaluations must be retained throughout the period of application and for the term of the license (including any period of renewal).
f (b)
Reporting.
(1)
An applicant or licensee who references this design certification rule shall submit a report to the NRC containing a brief 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 shall submit updates to its plant-specific DCD, which reflect the generic changes to the generic DCD and the plant-specific depanures made pursuant to Section 8 of this appendix. These updates shall be filed in 'accordance with the filing requirements applicable to final safety analysis repon updates in 10 CFR 50.4 and 50.71(c).
l (3)
The reports and updates required by Section 10(b)(1) and (2) above must be submitted as follows:
(i)
On the date that an application for a combined license referencing this design certification rule is submitted, the application shall include the repon and any updates to the plant-specific DCD.
l (ii)
During the interval from the date of application to the date of issuance of a combined 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.
(iii)
During the interval from the date of issuance of a combined license to the date the Commission makes its findings under 10 CFR 52.103(g), the report must be submitted. semi-annually.
Updates to the plant-specific DCD must be submitted annually, j
(iv)
After the Commission has made its finding under 10 CFR 52.103(g), reports and updates to the plant-specific DCD may be submitted annually or along with updates to the site-specific l
ponion of the final safety analysis report for the facility at the l
intervals required by 10 CFR 50.71(c), or at shoner intervals as specified in the combined license.
l l
This change reduces the reporting burden by requiring reports only twice a year l
i instead of four times a year.
l.-.