ML20040D424
| ML20040D424 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/28/1982 |
| From: | Lewis S NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Brenner L, Cole R, Morris P Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20040D425 | List: |
| References | |
| NUDOCS 8202010282 | |
| Download: ML20040D424 (8) | |
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N Lawrence Brenner, Esq., Chaiman Dr. Richard F. Cole Administrative Judge Administrative Judge U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Cornission i
Washington, DC 20555 Uashington, DC 20555 Or. Peter A. tiorris Adninistrative Judge U.S. Nuclear Regulatory Comission
!!ashington, DC 20S55 i
In the ! fatter of Philadelphia Electric Company (Linerick Generating Station, Units 1 and 2)
Docket Mos. 50-352, 50-353
Dear fienbers of the Board:
I Pursuant to telephone requests from the Atonic Safety and Licensing Board, the following documents, which were nentioned by the undersigned during the Special Prehearing Conference, are being transnitted to those persons on the service list in this proceeding.
1.
NUREG-0085, Issue 1 "U.S. Muclear Regulatery Coreission Policy and Planning Guidance 1982," Introduction, pp. ?-2 and p.' 10 on Risk Risk Assessment.
(Reference Tr. 233).
I 2.
" Final rule: Licensing Requirements for Pending Constructinn Pemit and Itanufacturing License Applications," 47 Fed. Reg. 2236-i (January 15,1932). Ve have reproduced the initial page and pp. 2301-2302, which contain the rule requiring present construction pemit applicants to subnit PRA's within two years of
,I' issuance of CP's (10 C.F.R. 6 50.34(f)(1)(1).
(Reference Tr.-237).
j At the P,oard's request we are also enclosing:
I 3.
A copy of the construction remits for Lincrick, l' nits 1 and 2, as anended.
Contained in this packet of raterial are:
a.
The CP's and the Federal recister l'otice of issuance, b.
Avendoent No. I to each CP and the Potice of Issuance, c.
" Order Extendino Construction Conpletion Pates" (l'ay 13, 1975)'and the supporting Evaluation, and
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OFFICIAL RECORD COPY uso m asi.- m m Nac ronu sts oo.8%acu eno
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4 An April 24, 1981 transmittal letter and attachments, "
Subject:
Order Extending Construction Completion Date - Lirerick Cenerating Station."
Sincerely, Stephen fl. Lewis Counsel for imC Staff Enclosures fs Stated cc w/ encl:
-l'r. Frank R. Ponano Judith A. Dorsey, Esq.
f*r. Edward G. Rauer, Jr.
Troy B. Conner, Jr., Esq.
Mark J. t!etterbahn, Esq.
ltr. itarvin I. Lewis Janes l'.
fleill, Esq.
Joseph li. White III Environnental Coalition on fluclear Power Thonas Gerusky Pennsylvania Energency fianagement Agency John Shniper Robert L. Anthony Alan J. flogee
- 11. Hilson Goode i
i William A. Lochstet Walter H. Cohen
- Robert 11. Adler Steven P. Pershey, Esq.
Sugarnan and Denworth l
Donald S. Bronstein Esq.
Atonic Safety and Licensing Board Panel Attnic Safety and Licensing Appeal Coard Panel Docketing and Service Section Charles W. Elliott, Esq.
Dist i
NRC Docket File Lewis /Hodgdon/Chan l
PDR ASchwencer LPDR HAbelson l
Cunningham/Engelhardt Chron Christenbury/Scinto FF(2) j.
Rutberg Vogler
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u POLICY AtlD PLAfittli1G GUIDAMCE INTRODUCTI0'l The purpose of this document is to provide guidance to the staff for establishing priorities and for improving the regulatory process --
starting immediately.
It is therefore more than just a docuaent to be used for preparing the FY 84-86 budget request.
It is management guidance intended to focus on specific areas where the Commission believes additional emphasis is required.
Guidance with respect to each and every activity within NRC is not furnished, since it is not intended that the' document be all inclusive.
However, this should not be perceived as a Commission belief that other areas are not equally as important to protecting the public health and safety.
Many of these other areas have effective ongoing programs where major problems do not exist but adequate management attentien and initiative are still important.
Although specific policy and planning guidance is not provided in this document, top management attention is still required for radiation health effects protection, fuel cycle licensing and inspection, materials licensing and inspection, and facets of emergency planning and preparedness not addressed here.
These and other support functions are vital to accomplishment of the overall agency mission and objectives.
The document is organized in terns of seven major themes: Safe Operation of Licensed Plants; t: car-Term Licensing Problems and Responses; Coordinating Regulatory Requirements; Improving the Licensing Process; Supporting New Initiatives in liuclear !!aste i.nd the Cleanup of Three Nile Island; Improving Related Regulatory Tools; and Safeguards..The policy section is intended to establish a general framework for !!RC managers to shape their own particular programs.
Planning guidance is furnished in those areas where the Commirsion believes care detail is warranted to meet specific concerns about schedules and priorities or where major assumptions are needed for program development.
Specific guidance involving programs will be provided by the Executive Director for Operations.
The EDO will also develop and provide a management system for the Commission to keep track of the major 1932 program accomplishments and resource expenditures that support this policy and planning guidance.
It is the Comission's intentien that nuclcar regulation reflect a continuing ccmaitment to ccme to grips with the reality of nuclear technolooy and of its relationship to those who control it, to those who work with it; to those who live near it, and to the general public.
This commitment requires not only an open and of fective approach within the agency, but an apprcach to tne public (including the regulated public) that permits more efficient decisionmaking.
As part of this process, the Comission must state its basic assuaptions and criteria clearly, amend them when the facts so require, and live by them consistently and forthrightly in all activities.
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. To carry out the policy of the Commission will require the dedicated effort of all employees as well as the effective and efficient use of all NRC resources.
Innovative, attentive and responsive management effort will be required to accomplish the Commission's goals.
NRC's greatest resource is its employees.
Retention of our most creative and productive talent and the recruitment of new personnel with fresh insights and perspectives should be a management priority. To maintain a highly qualified and informed staff, the Commission's most creative and productive employees should be recognized and provided further opportunity for development.
Increased effort should be expended, in the face of highly competitive conditions, to hire the best qualified individuals essential to the future ability of the NRC to carry out its regulatory responsibilities.
SAFE OPERATION OF LICENSED PLANTS Policy A.
HRC's fundamental task is to make sure that existing plants and those coming on-line operate safely.
To this end, the highest priority will be given to assuring that operating facilities achieve and maintain adequate levels of protection of public health and sa fety.
Planning Guidance 1.
NRC on-site inspection of operating reactors will focus directly on the activities and operations of licensees, licensee contractors, and vendors.
NRC will improve its own capabilities for independent and confirmatory measurements. The analysis of operational data and systematic assessment of licensee performance will be used to l
help focus inspections and to allocate inspeccion resources.
l 2.
The NRC and the industry must continue to learn the lessons that l
only experience can teach.
Efforts to collect, analyze, disseminate, I
and act upon operational data relevant to the safe operation of major licensed facilities must continue to receive priority attention.
The framing of effective regulations must be based on a close study of operating experience.
3.
HRC will continue to operate and improve, as needed, a Licensee Event Reporting (LER) system.
NRC should continue to work with the Institute of Nuclear Power Operations (INPO) in its operation and l
development of the Nuclear Plant Reliability Data System (HPRDS).
NRC should continue to support 1NP0 in the operation of an industry-wide screening service to identify LERs and other operating experiences of significance to nuclear power plant licensees.
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. 2.
Qualitative safety goals and associated quantitative, numerical guidance, when approved by the Commission, should be used in the evaluation of proposed and existing NRC reactor safety requirements.
Risk Assessment Policy A.
Probabilistic risk assessment is an important tool for weighing risks against one another and for defining achieved safety levels.
Quantitative risk assessment techniques will be used to estimate the relative importance of potential nuclear power plant accident sequences.
Planning Guidance 1.
Special attention should be given to using probabilistic as.sessment techniques where the data warrants such use and in areas especially amenabic to risk assessment, e.g., in licensing reviews as appropriate, dealing with generic safety issues, formulating new regulatory requirements, assessing and revalidating or climiMting existing regulatory requirements, evaluating new designs, and formulating reactor safety research ard inspection priorities.
Siting Polig Policy A.
Siting criteria for nuclear power plants and other major nuclear facilities need improvement.
The staff has been working to prepare in the very near term modified regulations concerning the sit!.13 of nuclear power plants. The Commission has decided to better deilne its safety objectives and better characterize the radioactive source term before proceeding with new siting regulations.
Planning Guidance 1.
The radioactive source term should be reassessed by early 1983.
2.
Based on the safety goal and the formulation of a new radioactive source term, a proposed siting rule should be published by late 1983.
Y w
rederal Rep.hte.r / Vol. 47. No.10 / FriLy. January 13. W2 '
223:;
The Commission's c<msid, ration of Action plan. NUREC-0CCO. In the commer.ts racived are reficcted in O'9 e of the Federal Ecgister, pursuant councet.on v.ith a roquest,for public part by resi< <-d tmt in the ;+rtinent to 1 CF R E2 hereby removes from the comments on these new requircrnents, sections of NURLG47r. nnd in part by
(.. :e of rederal Regulations Title C.
the Commission noted that Enal rules the fo!!pwing dl5cuwion. %e comments
~ Ch.pur Vf. Assistant Secretary for might be issued on some or all of the are grouped in fne meas as indicated
,\\,';,Mr Ntion.Depattment of the ~
mattcrs discussed in thtd notirk below and are scie:enced by the use of
- 3. t.or.sisting of Part 602, and The Commission held a %,s.es of-Tsca'a:
Sabihty, consisting of Parts 701 through rnectL as regarding this proposed rule in the abbreviations indicated above.
Chrster Vll. Cmmcil on Wage and Price January, February, and hf arch of 1981.
Comments on Propose'!Rcquirements in j
Tit!c 6. Code of Federal Regulations is At its March 12 rnecting the Commission A MWN L
704 inclusive.
decided that a furthcr brief period of hereby vacated.
p*lic comment was desirable prior to The fo!!owing is a discussion of b
srao coor isch-as mulgation of a final rule to ensure comments received on specific NUREG-p m.____.__
that all interested persons have an 0000 items for which draft NUREG4718
_u
_m opportunity to revie,w the contents of the proposed requirements applicable to the t?JCLEAR REGlATORY proposed rule and, m particular, have pending ap;>11 cations.
Q COMMISSION the opportunity to comment on the applicability of the proposed rule to the Mon gement Long hun Impmmmenu d
10 CFR Parts 2 and 50
- pending manufacturing license (PSO).
Ucensing Bequ!rements for Pending applicat!on.The additional comment.
II.].3.1-Management for Design and Construction Permit and period was discussed and noticed in the Con &udion (PSO).
Manufacturing License Applications -
Federal Register on March 23.1987, at The commentor notes that there is an 4
ACENCY: Nuclear Regulatory The Commission particularly desired industry. wide effort related to these pages 18015-.10019.
activitaes.
Commission.
comment on whether or not the pending ACTION: Final rule.
manufacturing license application, filed by Of f,hore Powe c Systems. Inc., should The Commission is not entirely EUMMAnY:The Nuclear Regulatory be covered by'the proposed rule. At certain to what specific activity the Commission is adding ta its power issue is whether the rule's requirements commen'or is referring. Liaison is reactor safety regulations a set of for the capacity of containmeats to maintained with the lastitute for licenslng requircments applicable only withstand the effects of acchlent-Nuclear Power Operations (INpO) which to construction permit and T
manufacturing license applications genciated hydrogen are sufficient when ~ is in the process of conducting utility,1 -
1 zpplied to floating nuclear power plants, management audits using its own pending at the effective date of this rule. -Analysis of Public Comments guidelines.
The requirements stem from the Commission s ongoing effort to apply ~
The comments that were received and The classification of Action Plan Item the lessons learned from the accident at the Commission's responses are I.B.I.1 has been changed to Category 2
%ree Mile Island to power plant presented below in Iwo parts.ne first (i.e., an item that is to be addressed at licensing. Fach applicant covered by this part addresses the comments received in the operating license review sta rule must meet these requirements in response to the rederal Register Notice than et the construction permit review a
order to obtain a permit or of October 2,1980 regarding the stage) since it dmis with operations manufacturing license.
proposed requirements set forth in draft sannagement. %e discussion that EFFECTIVE DATt: February 20,1982.
NUREC-0710.The second part follows addresses the comments with r0R FURTHER INFORM ATION CONTACTt addresses comments responding to the respect to guidance availability.
Robert A. Purple Deputy Director, h1 arch 23,1031 notice containing the Although the NRC is developing '
Division of Licensing. Office of Nuclear proposed requirementa, as modified guidelines for utility organization and 6.
Reactor Regulation, U.S. Nuclear of ter consideration of comments,in the.
management for operations (I.B.1.1), and
- Regulatory Commission, Washington, form of a proposed rule.
design and construction (!!43.1), the D C. 20555. Telephone: (301) 492-7930.
p Comments to FR N&.ce of Octob" NRC is still required to make a finding SUPPLEMENTARY INFORMATION:
2,1980. Comments were received from:
on management and organizational C.W.Rowley Sand Springs, Oklahoma capability prior to issuance of a llackgroundof theRulcmaking construction permit or operating license, (Rowley)
%e events leading up to the Department of theInten.or (USDI) cven if approved guidelines are not
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promulgation of this rule were discussed Marvin I. Lewis, Philadelphia, available.Therefore, as has always in detailin the Notice of Proposed Pennsylvania (Lewis) been the case, applicants are required to Rulemaking. which appeared in the
. Dcchtcl Power Corporat. ion San describe their organizational structure ond managcment for design and Federal Register on October 2,1980. at cnsteIn I e an, Reis c! rad &
constru,ction, regardicss of whether or pages 65247 -GS248. In that notice, the g,o Commission reviewed some of the Toll (Lowenstein) n t an mdustry approachis available or
+
actions it had ab rady taken in response Offshore Power Systems (OPS) is bemg developed. Por example, in the to the accident at Three Mile Island andPublic Service Company of Oklahoma NRC reviews of utility management and
. outlined the options it was considerina (PSO) organization for recently issued with regard to the review of Doston Edison Company (UEC) operating licenses, cach one has been construction permit and manufacturin3 General Electric Company (GE) cvaluated on a case-byJcase basis. In license applications.The Commission Westinghouse Electric Corporation (10 conducting these reviews.the draft proposed to resume licensing using pre-Portland General Electric Company document " Guidelines for Utilities (pGE)
Management Structure and Technical TMI requirements augmented as Duke Power Company (Dake)
Resources," NUREG-0731, which has necessary by new requirements Combustion Engineering (CE) identified in the Commission's TMI t
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Fetieral Register / Vol. 47. No.10 / Friday January 15. 1982 / Rules and Regulations 2301 r
I accommodated completely in both
' needed to be considered for tf:e iradvertut Reorganization Act of 1974. as amended.
situations.
incrting conditions during normai oprations-and Sections $52 and 553 of Title 5 of the The Commissinn has already
-* *
- Ge staff was asked whether or not United States Code. the following "8
amendments to Parts 2 and 50 of Title Instructed the staff to use specific
'j,*"['t bu ! ci 1e
- 10. Chapter I. Code of 1 :dcral provisions in this rule as the basis for its considered.or to rephrase it whether or not Regulations are published as a position in contested construction the containme*J 4 ell of both ice condenser permit cases. What it is now providing amd Mark III pir.ats would buck!c tmder the document subject to codification.
is that intervonors who wish to.-
inadvertent inerting cnd test conditions, challenge the adequacy of some of the
-' *
- The general consensus was that PART 50-DOMESTIC LICENSING OF -
provisions proposed here will not be,
the contaimrent would ne twAle for the PRODUCTION AND DTILtZATION e
fortowing reawns * * *
. FACILITIES able to do so. In effect, the Eoards are~
- the rode has a k rtoe of safety of 3 -
c being required to rule against them without hearing the,r evidence.
_.. p he Code limits are established for reads as follows:
i t
r This authoritarian obsession with the external pressure and uniaxial Authority: Secs.103. t ot.101.182.183.189 Evoidmg of pub lic chaffenge has been a compression * *
- ea stato,0.sa7.ma csa.sst.oss.oso.as source of continumg troub!c for nuclear
' *
- the case ofdiscuss. ion (here]is for amended (42 U.S.C 2133,2134. 2201. 2232.
power o'ver the fast decade. That it intemalpressurfi.ation that Induces tension 2233. 2239); secs. 201. 202. 200. ca Stat.1243.
should now be applied to limit the in most parts of the shet! * *
- 1244.1240 (42 U.S.C. satt, satz, ss4c) unless lesscas to be learned from the accident
~* *
- there was an agreement (by NRC otherwise noted. Section 50 73 also issued ataff mannsement and techmcal personnely under sec.122. ca Stat. 939 (42 U.S C 21521. -
Ihat a helped to cause provides an
. thauhe queshon,ucaUy not a tecimical Sections 50.c0-.50.81 also issued under Sec.
s unsuttling Indicatien that the NRC may
"'d be returning to its former bad habits.
"[le u "len 184. 63 Stat. 954. as amendedg [42 U.S.C bu er d
in st 223 M " *"*SM " 2"*"'d"*I*r Additional views of Commissioner cond; tion,.
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,Abearne, f. cst si!cnce be taken as As I wrote in my December Uth rpo es f 3.
S a t. 9 a. s asscut. I note that I strongly disagree memorandum to my fellow '.
amend d:(42 U.S.C 2273). I so.st(i) issued.
with Commissioner Dradford's opinions Commissioners ("CP/ML Rule under se.1011. oa stat. H9;(41U.S.C of the reasons for declining to make Containment Structural Requirements"):
22o1(i)). IJ 50.70. so.n and so.7a issued under
" ** * # S " "*" " "d* M i# E S C -
SECY-at-241into a ru!c. the reasons for I do not see the analytte case for requirfne 220t( }) and the Laws referred to in making SECY-al-20D into a rule the a buckling criterion * * *. I do not believe Appendices.
lessons !carned from the lire protection the Code buckling criterion is needed for rule, and of the NRC's approach to inadvertent inorting.On the other hand.(t)his
- 2. A new paragraph (f)is added to criterion also does not come close to meeting 6 50.34 to read as follows:
publ c hearings.
~
TurtherAd////dnal Views of the detonation pressure Of there were a Commissioner Ahearne. %e NRC srafr hydrogen explosion). If the Commission's 9 50.34 Contents of applications;technicat
" suggests that the Commission consider position is that a'J containments shou!d ha se information.
an estunated pressure capability of X.we the desitabil;ty of further modifying shou!d address that Issue directly.
Md<litional 7MI-related section (3)(v](!!)(1) on page 81 to require I believe we must develop regulatory requirements. In addition to the, that instability be considered in designing the containment to withstand requirements based on reason. lf we are requirements of paragraph (a) of this inadvertent inerting." (P. 3. Sccy--81-031 substantially uncertnin about an issue.
. section. cach applicant for a light-water.
Nos ember 4.1981) we should leave it open to be debated in reactor construction permit or
%e basis for this recommendation is individual cases.
mamdacturing license whose a November 2.1931 NRR memor'andum Ilegulatory flexibility Statement in application was pending as of (insert.
" Containment lastability." (Enclosure 2 accordanco with the Regulatory effective date of amendment) shall meet to Secy-81.G31)In this memorandum.
Flexibility Act of 1980. 5 U.S.C. 605(b),
the requirements in paragraphs (b) (1) the reasons are given to be the the Commissica hereby certifies that through (3) of this section.This rule this rule will not have a significant applies only to the pending applications following:
impact on a substantial number of small by Duke Power Company (Perkins entities.This rule affects five applicants Nuclear Statio,n Units 1. 2 and 3).
o7u d r the a er ent (nerting cosir 1r construction permits and one llouston Ughtmg & Power Ccmpany condition may limit the usefulneas of the rule by presenting the opportunity for techrJcal applicant for a raanufacturing license.
(Allens Creek Nuclear Generating cha!!ceges to fature operatioa of plants These opplications are for permits or a Station. Unit 1). Portl.md Cencral chco:,ing post accident inerting systems.
license for plants that do not fall within Electric Company (Pebb'c Springs
-ASSIE Code Service Umit A strest the scope of the definition of"small Nuclear Plant. Units 1 and 2). Public critoria are therefore required in the rule to entitics" set forth in the Regulatory Service Company of OL!ahomi (Biack anure with hh:h confidence that inadvertent Flexibi!Itv Act in the Small Basiness Fox Station. Units 1 and 21. Puget Sound merung occurring at any time in the hre of a Size Staddards set out in regulations Power & I ight Company (Sk.qit/
pi at er seserol times for that matter wodd issued by the Small Business Ilanford Nuclear Power Project. Units 1 e uh in degradation of the containment Administration at 13 CFR Part 121.
and 2). and Off.,here Pew er Sptems OMO llegulatoryliequimments (Ucense to Manufacture Floating His staff suggestion was discussed at clearance. The npplication inquirements Nuclear Plants). The number of units a meeting with the NRC staff described conta!ned in this final & Mfrct fewer that will be Srccified in '! 2 i
In a Decen.ber 17.1941 memorandam by than 10 persons (npplicanS) and, manufacturing licens.., if issued, will be l}r. n. D. Uaw *NTCP/htL Ruld therefore, are not subi-ct ta Office of that number whose start of manufar.tute.
ntamm :nt Structural Requirement s."
Mana;;en ent and Eudot c!carance as as defined in the lic:mm ap;,lic.ni+m. can
- t. Uaw makes the following p'i.ts:
required by Pab. L nG-3tt.
pnctically begin within a tenqmt
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- th; 7 anon cent,. red amund Pursuant to the Atomic l#rgy Act of period commencing on th..d.ne of
- Scr er n3t da Cat. t.dby cnteria.
1934. as awnded. the Ene cy inaance of th.i manufactuin,; bcense.
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4 f ederal licpister / Vol. O, No.10 / fMday. Tar.unty 15,1M2 / Rules and He;:ula T02 normal ( Arected air (or nitrorcn) probabihty of an cutomatic PORV Icalage through vah es. (A; phcable to L t in no eu r.t win that number be in itolation spiem that wcalJ op. ute 1;WR's only). (!! 1:.ur!
}
ess of is n. The n.mncfactuing licuse when the reactor celant system (si) Provide en evaluation of
- 3i.1 egane the pLnt der e n to be pru.sme I dh adM the PORV h.
d"per tsurizaban methods, other than by u
updated no hitor than fivc years af ter its o;wr.ed. ( Applicabic to PWR's en!s ).
full attaation of the automatic
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approvat Pmpaphs (b);1)bii). (2)(is),
and (3)b) of tl.is section, pertaining to (v) Pc: form an es atuation of the r afety deptr surization svstem, tha (llL32) reduce th. pwibiiity of exceedmg b>drogen r unteel mensm es, taust be snet effectivenus of providing for sr p:
vea el integnty hmits during rapid ation by all upplicants covned by this rule.
of high pressure coolant injecth.n itIPCI) coo!down. (Appbcable to InVR's only)
Ilowever, the Commission may decide and reactor core isolution coolin :
to impose additional regirernents and (RCIC) system initiation levc!s so that (1113a3)
(>.ii) Per fmn an evaluation of the issue of uhether iompliance with the RCIC system initiates at n LLher 3.!!arnative hydrogen control systems l
ther.e provisions. together with 10 CFR warr letcl than the IIPCI s3 stem. and that weald salirfy the requirements of M.41 and Criterion I,0 of Apperidix A to of providing that both rystems restart on gj 10 CFR Part 50. is sufficient for issuancelow water level. (For pLnts v.ith high parginph (b)12)lix) of this s'ection. As a minimum include consideration of a of the manufacturing license may be pressure core spray systems in hcu of hydrogen ignition nnd post accident 1
considered in the manufacturing license high pressure coolant injection tystems, i
proceedmg.
substitute the words. "high prr pure inerting system. The evaluation shall (1)To satisfy the fo!!owing core spray" for "hirh pressure coolant include:
(A) A comparison of costs and requirements, the apphcation shall injettion" and "IIPCS" for "ilPCl"}
benefits of the n!iernative systems provide suf ficient i:Jormation to (Appbcubic ta BWR s only). (!!K3.13) describe the nature of the rtudies, how (vi) Perform a study to identify wnddr' red.
(D) For the selected system, analyses they are to be conducted, cr.timated practicable system modifications that submittal dates, and a program to would redere rhenres emt f"ilum of und test data to u rJy mmpliance with
)
ensure that the resuhs of such studies rtbeivalves, mthout compromiting the the regmremer.ts of (b)(2)(ix) of this are fadored into the fmal design of the performance cf the valves or other section.
facility. AU studies shall be completed systems. (Apphcabic to DWR's only).
prehminary desinn desciiptions of (C) for the erlected system, l
no later th m two years following
(!!K3.10) issuarice of the construction permit or
[vii) Perfonn a feas.bility and n. k equipmment fun'ction. and layout.
s g
manufacturing bcense.*
assessment study to nefernane the g.yo wry the fcMowing (i) Perform a plant / site specific optimum automat,ic depres sunzation requiremcnts, the application r. hall-probabHistic riss assessment, th:* ru,m of sy: tem (ADS) des,1;;n rnodificatmna that iu runicient information to which is to seek such improvements m would chminate tne need for rnar.ual demonstrate that the required actions M16.W only cwnpleted by the the reliabihty of core and contain, ment cctwation to ensure adequate core i
heat removal systems as pre tagn ficant cooling. (Apph, cable to ItWR s only).
peratmg licem stage. 'I.h.. formation is in is of the tyre customanly required to and practical cnd do not impact
(!!K3.10) form a study of the effect en sausfy 10 CFR. 0.35(a)(2) or to address excessively on the pbmt. (it.lu) 5 (viii) Per (ii) Perform an evaluation of the cll core. cooling modes under accident
"*8 h".d generic safr ty issues.,
proposed ausihary feedwater system conditions of designing the core spmy (Q Pmde sunu!stor capability that
( AFWS), to include (applicable to and low pressure coolant injection wrectly models the control room and I
PWR's only)lli E.1.1):
systems to ensure that the systems will includes the capability to simulate (A) A simplified ArWS reliability automatically rt.statt on loss of nater Emalbbreak LOCA's. (Apphcable to analysis using event. tree and fault-free level, atter having licen manually construction permit apphcants only).
logic techniques, stopped,if an initiation signal is still (LA.4.2.}
(D) A design review of AFWS.
present. [ Applicable to flWR's only).
(ii) r.stablish a program, to beg,m i
(C) An evaluation of APWS flow
(!!K3.21) during runstruction end follow into design bases and criteria.
(ix) Perform a study to determine ibe operation, for integratin;; and expanding (iii) Perform an evaluation of the -need for additional rpace cooling t;;
current efforts to improve plant potential for and impact of reactor ensure reHable long-term operation of procedures.The rcepe of the program coolant pump seal damage following the reactor core isolation cooling (RCIC) shallinclude eme gency procedures, small break 1.OCA with loss of offsite and high.precsure coolant initction reliabihty analyses, human factore power.lf damage cannot be precluded, (I!PCI) systems, foHowing a comph:ta engineering. crisis management.
~
provide an anal sis of the1: mitier small-loss of offsite power to the pbmt for at operator training. and cocrdination with 3
break loss-of-coolant accident with least two (2) haars. (For plants with high INPO and other mdustry efforts.
subsequent reactor toolant pump seal pressure core spray systems in Ucu of (Applicab!: to construction permit damage. (IIK2.16 and ilk 3.25) high pressure coolant injection systems.
applicants only) (i.C.9)
(iv) Perform an unalysis of the substitute the words. "high pressure (iii) Preyide, for Comm: scion review.a probabihty of a small-break losc-of-core sprcy" for "high pressure coo! ant control room design that reflects state.
coolant accident (LOCA) caused by a
. injection" and "lii CS" for "1iPCP')
of.the. art boman factor principles prior stuck.open power. operated relief valve (Applicable to DWR's only). (ILK.3.24) to committieg to fabrication or revision (PORV) If thin probability is a
[x) Perform a study to ensere that the of fabricated control room pancis and significant contributor to the probability Autmnatic Dc;;tessurization System.
layouts. (i.D.1) of smalbbreak LOCA's from all causes, valves, accumulators, and associated (iv) provide a plant safety paramcter provide a description and evaination of equipment und it.suumentation will be display console that will display to the effect on smalbbreak LOCA capahic of pesforming their intended operators a minimum ret of paramelen functions during and fol!owing an defining the safe tv status of the plant.
' At,%n nc aw.imm wnrw.Nhe accident situation. taking no credit for capable of disp!ahing a full range LI retet ubon gh oe n.
in Nt'KI G 0718 eM nonufety tel&d equipment or Important plant parameters and datJ f
.I d instrumentation, and acCountiOS or 1 12A t
t heron tot intermaho only, q
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