ML19318B461
| ML19318B461 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/23/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML100150759 | List: |
| References | |
| NUDOCS 8006260190 | |
| Download: ML19318B461 (10) | |
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, APPENDIX B ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY CO' MISGION M
- WASHINGTON. D.C. 20545 1
SEP 2 31970 fi 1p li%
Honorable C1can T. Seaborg 1
Cheirman i
U. S. Atomic EnerFy Cournission h
Washington, D. C.
20545 Subjects P2 PORT ON INDIAN POINT NUCIEAR GSN5RATENC UNIT MO. 2
Dear Dr. Sesborg:
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'At its 125th eeeting, September 17-19, 1970, the Advisory Committee on Reactor Safeguards. completed its review of the cppitcation'by Consoli-dated Edison Company'of New York, Inc., for authorization to operate the Indian Point Nuclear Generating Unit'Uo. 2.
This project had pre-
{ vlouoly boon concidered at the Co:mnittee's 95th, 98th,122nd, and 124th ecctings, and at Subco:nmittee meetings on August 23, 1909, March 13, 1970, April 25, 1970, May 28, 1970, July 25-29, 1970, and. September 15, 1970. Subcosnittees also met at the site on Deccaber 28, 1967 and
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PHay 11. 1970 The Cocmittee last reported on this project to you on
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(August 16, 1966. During the reviev,the Cer=nittee had the benefit of discucsions with representatives of the Consolidetad Edison Company and their contractors and consultants, and with reprenor.tatives of the ABC l,
Ecgulatory Staff. Tha Comnittee also had the beaafit of.tha docucants I
listed.
The Indian Point sf.te is located in Westchester County, New York, approx.
imataly 24 miles north of the Ucv York City limits. The mininum radius i.
,of the exclucion area for Unit No. 2 is 520 nators and Peckskill, the y
nearcot population center, is appro:<imately one-half nila frda the unit.
Also at.thic site are Indica Point Unit 1, which is licensed for opera-g-
tion et 615 Eit, and Unit 3, rhich is under constructica.
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- p Tha applicant has re-evaluated flooding that could cectir at the cite in II the evout of the prSoabic ner.ioun hurricane and ficod, in the light of more recent information, and has concluded tL conquate protection 1
cnisto for vital couponents and services, j
5 Additional scismic reinforcement being provided for the Indian Point-Unit No.1 cuperhaatar building r.nd reewn1 of t.hc top 80 f t. of the suparh:scter eteck will enabic. the stack to withett.nd vindo in the range.
F' of 300-360 oph corresponding t.o current tornado derian criteria. Since I
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Honorable G1can T. Seaborg SEP ? 31970 L
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.g the reinforcement of the superheater building, which supports the stack, enables the stack to resist wind loads of a magnitude most likely to be y
experienced frcra a tornado, the Cocmittee believes that removal of the top 80 f t. of the stack, to enable it to resist the mexic:ma effects from i
a tornado, may be deferred until a convenient tima during the next few Sj yearo, but prior to the co=soncement of operation of Indian Point Unit f
No. 3.
The applicent has stated that truncation of tho vtack will hava F
no significant adverse effect on the environment.
The Indian Point Unit No. 2 in the first of the large, four-loop Wesi:ing-house pressurized water reactors to go into operation, and the proposed power Icyc1 of 2758 se will be tha largest of any power teactor licensed to date. The nuclear design of ' indian Point Un'it No. 2 is similar to that of n. B. Robinson with the enception that the initici fuel rods to be used in Indian Point Unit No. 2 will not be propressurized. Part-1engt.h control rods will be used to shape the axial pcuer distribution I-and to suppress axici xenon oscillations. The reactor is designed to have a zero or nagative moderator coefficient of reactivity, and the h
applico.nt plans to perfom tests to verify that divergent azi=uthal xenon oscillations cannot occur in this reactor. The Com:sittee recommends that q
the Regulatory Staff follow the measurements and analyses related to these L
tests.
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Unit 2 has a reinforced concrete containaant uith an internal steel liner which is provided with facilitico for continuous prescurization of wold cod penetration areas for icok detection, and a scal-vater system to back up piping icolation valveo. In the unlikely event of an accident' ' cooling g.
of the containment is provided by both a contai.raent spray systen and an cir-recirculation system with fan coolers. Sodiua hydroxide additive is used in the contniinant cpray cyctata to renovo ole:nental iodi.ne from the
' post-c.ccident containment atmosphors. An inprogn:.ted chr.rcoal filter is provided to rer.tove organic iodine.
i Major changes hcve be:n r:ade in the dcaign of the c:accancy cora cooling systen as originclly propoced at the th:a of the construction' permit re-vicu. Four accu:aulators are provided to reco:aplich rcpid reflooding of 1(
the coro in the 2.nlik:1y event of a large pipo break, and redundant pt:aps Q
ore included'to maintain long-torn coro cooling.
Th:- applicant has 4
analyzed the effice.cy of chn ci.urce tcy core cooling synten and concludos that the system uill he:p the cro intact and the pock clad to:gerature J
well belee the paint uhere cir ccioy-uctor reactina saight hcve an adverse 3 _,
offcet on clad ductility and, benew on tha continued structural integrity l
of the fuel cleients. Th: Co=sittee helievec that there la reasonabic assurance that the Indien Point Wit h'o. 2 etargency core cooling systcut i
will perform adequercly at th: propor pcm.r 7evel.
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I Honorabic Glenn T. Seaborg SEP 2 31970 35 The Committee concurn with the applicant that che reactor pit crucibic,'
jj proposed at the thos of the construction parait revicu, is not casen-y tial,as n safety featura for Indinn Point Unit llo. 2 and need not be in-
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cluded.
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To control the concentration of hydrogen which could build up in the
-y containment following a postulated lous-of-coolent accident, the appli-
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. cant has provided redundant flama recombiner units within the contain-ment, built to engineered safety feature standards. Provisions are also included for adequate mixing of tha 'ctnosphere and for sempling purposca.
The cdpability exists also to attach additional equipment so as to permit controlled purging of the containment etnosphero with iodine filtration.
The Committoo believes that such equipment should "oa designed and provided
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in a menner satisfcctory to the Regulatory Staff during the first two years of operation at power.
The cpplicant plans to install a charcoal filter systen in the refueling building to reduce the potential rolcase of radioactivity in the event of damage to an irradiated funi assembly during fuel handling. This in-sta11ation will be completed by the end of the first year of full power s
operation.
The reactor instrumentation includes out-of-core detectors, fuel acccmbly exit thermocouples, and novable in-coro flux nonitcra. Power dirtribution beasurements will also ordinarily be available from fixed in-core detec-tors.
The applicant has proposed that a limited nucher of manual rosets of trip points. mada deliberately in accordance with explicit procedures, by approved personnel, independently nonitored, end uith settings to be cali-brated and tested, should provide an acceptchie basis for the occasional L
operation of Indian Point Unit No. 2. with only three of the four reacto-loops in service. The Committee concure in this position.
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The applicant stated that neutron noiso neasurements vill be made period-
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icelly and enalyzed'to provide developmental infornation concerning the
- 1 possibic usefulness of this technique in >:scertaining changes in core E,'
vibration or other displacements. On a similar Lacis, accelerometers will 9
l be ine.talled on the pressure vessel and stenn geparatorc to ascertain the
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practicality of their use to detect the presence of loose parts.
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The reactor includes a dcInyed neutron raonitor in one hot leg of tha re-I~'
actor coolant cystem to detect fuel clescat failure, e itcbic operability requiro.nents will be maintained on the severci scr.citive nenns of primary system lcnk detectica.
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. Honorable G1can T. Scuborg SEP 2 31970 L
m A conservative method of defining pressure vessel fracturo toughness
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should be employed that is satinfoctory to the Ry,ulatory Staff.
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The applicant stated that cr.isting expericantal resulto and analyses i
provide considerablo assurance that high burnup fuel of the design jj employed vill be abic to u:.dargo anticipated transients and powar per-p turbations without a loss of clad integrity. Ha also described addi-f' tional experiments and analysos to be parformed in the reasonably near l
future which should provide further ascurance in this regard.
The Comcrittee has, in recent reports on other reactorc, discussed the f
need for studies on further means of preventing co::caon failuro snodes from negating scra:c action, and of possible decign features to nahe tolerable the consequences of failure to scrana during anticipated tran-siento. The applicant has provided the results of analyses.which he be-lieves indicate that the consequences of such transients are tolerabia with the existing Indian Point Unit No. 1 design at the proposed power Icycl. Although further study is required of this general question, f
the Cocwlittee believes it ac.ceptable for the Indian Point Unit No. 2 reactor to operate at the proposed power icyc1 while final resolution of this matter is made on a reasonable tins scale in a manner satisfac-f, tory to the Regulatorv Staff. The Co:=aittee wichco to be kept advised.
Other matters relating to larga vater recetors which have been identi-
,fied by the Regulatory Staff and the ACRS and cited in previous ACRS letters should, as in the case of othar reactors recently revicued, La dealt with appropriately by the Staff and tha applicant in the Indian Point Unit No. 2 as suitable approaches are developed.
,The ACRS believes that, if due regard is givan to tha iteta recon:'anded above, and subject to satisfactory completion of construction nnd preop-srational tcoting of Indian Point Unit No. 2, there ic rennonable assur-l ance that this reactor can be operntwd at power Icycic up to 2758 Gt 6
5 without undue risk to the health.and safety of the public.
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' Sincerely yours, d
Original binned by Joseph H. Hendrie j
.Icecph h. Hendrie Chair:nn
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References attached.
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- SEP 2 3.1970 i
Honorablo Glenn T. Sicbor;; j n
1 References - Indian Point Mu:1 car Generating Unit Po. 2
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Amendment llo. 9 to Application of Consolidated Edison Company of i,
Now York for Indit:n Foint Nucicar Genarating Unit No. 2, consisting i
of Volumes I - IV, Final Safety Analysis Report, roccived October 16, 1968 i
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Amettdmonts 10 - 20 to the License Application i
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Amendments 22 - 24 to the License Application f
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Deputy Director for Technical Review Directorate of Licensing GS-18
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PURPOSE DF POSITION The Deputy Director for Technical Review, Directorate of Licensing, conducts, for the Director, the review and evaluation,
of power reactor applications in the area of reactor safety, plant safety and site safety.
These functions include the development and administration of the programs and policies governing the licensing and authorization of nuclear reactors
'other than for export.
TECHNICAL KNOWLEDGE:
A broad technical, knowledge of the scientific and professional fields involve'd in reactor design, construction and operation including nuclear physics, mechanical engineering, chemical engineering, as well as extensive experience in thefield of nuclear reactor design, construction, and operation.
Specialized knowledge is also required to implement safety and
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environmental standards, codes and guides for the purpose of assuring, to the maximum extent, that the design, construction
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reactor coolant system d.esign and associated auxiliary systen design; emergency core cooling systems design.
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Review and evaluation of: seismic and pipe whip design criteria; mechanical design of reactor vessels, reactor core supports, reactor fuel, reactor coolant pumps, steam generators, reactor coolant piping, pressurizers and component supports; seismic Category I mechanical components, and ASME Code. Class 2 and 3 components; l
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Materials evaluation of coinponents of the reactor coolant pressure boundary and. ASME Class 2 and 3 components.
Performs technical r'eviews, analyses, and evaluation of the materials and fabrication of nuclear power plant components and systems.
Review and evaluation of the design of instrumentation, control and electric power systems; and the nuclear desi.gn of reactors.
Reviews Conduct of Operatians and Preoperational and Safety 5ections of Safety Analysis Reports, including industrial security; conducts periodic and special reviews and analyses of operational aspects of reactor safety for all licensed power, test and research reactors; prepares guidelines for the evaluation of the administrative aspects of reactor operation; coordinates activities with* regard to emergency and disaster planning; reviews
. reactor safety aspects of proposed berthing of nuclear powered warships.
Reviews re' actor lic'ense applications and related documents to
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evalunte the auxiliary and power conversior, systems.
Reviews.re' actor'.1.icense applications and related documents evaluate-the~coritainmentcsystem and associated subsystems,, t'o,
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' design, construction and operation of nuclear power plant structure Reviews reactor license applications to assure compliance with the Commission's quality assurance criteria during plant design, fications. for reactor fac'iJities. construction and uperation; revie c.
Reviews reactor license applications to evaluate plant systems and.
. equipment foi fission product removal a'nd the treatment of radioactive e
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waste, including the development'of analytical models, assumptions and calculated methods for evaluating the effectiveness of i
proposed systems.
Reviews r'eactor. license applications to evaluate the consequences - '
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for incorporation in environmental statements.
Reviews reactor license applications to evaluate site adequacy, including such factors as geography, demography, meteorology, hy-drology, geology, seismology, and the problems posed by nearby.
industrial, transportation and military facilities; evaluates adequacy of protection for on-site personnel.
Assessment of the radiologicalinpact of licensee facilities on I
the environment, including potential pathways for exposure to man and biota; develops and prepares radiological evaluations for
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i Provides specialized expertise in assessing the benefits of nuclear facilities and balancing these against the costs of environmental J-
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for preparation of. environmental reports by applicants and.
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CONTACTS:
Contacts are with the Director, Directorate of Licensing, the Director of Regulation and his staff, representatives of private industry, other Government agencies and other AEC personnel for the puipose of managing and conducting the above functions.
Daily contact with his Assistant Directors to issue assignments and instructions, to secure information,. and,to follow-up on activities of the various offices.
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Supervision Received:
Director, Directorate of Licensing, GS-18.
Work is reviewed for over-all adequacy.
Independent Action:
Reviews the overall performance of those organizational units reporting to him for accuracy and completeness.
Review incoming correspondence, documents and technical assignments; determines order of priorities, and issues assignments.
4 Prepares important correspondence not requiring a major policy decision 'for the signature of the Director, Directorate of Licensing, or the Director of Regulation, as appropriate.-
Hakes appointments, schedules meetings and conferences.
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