ML19208A633

Minutes of ACRS 790312 Subcommittee Meeting in Washington,Dc Re Application of TVA for Permit to Operate Facility

ML19208A633
Person / Time
Site:	Sequoyah
Issue date:	04/30/1979
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-1623, NUDOCS 7909170113
Download: ML19208A633 (52)

Text

{{#Wiki_filter:- -g,. m_ Issue Date: 4/30/79 MINUTES OF THE ACRS SUBCCfHITTEE MEETING ON THE SECUOYAH NUCLEAR POWER PLANT, UNITS 1 AND 2 ...- C.'-3 WASHINGTON, DC "'~ pC '. ' : ) MARCH 12,1979 yf /f } } a m. - a d i $ 2 M 269 . I,ug Q; r, r { !! d lul. L { ma u The ACRS Subccmittee on the Sequoyah Nuclear Power plant, Units 1 and 2 held an open meeting on March 12, 1979, in Room 1046,1717 H St., NW, '4ashington, DC. The purpose of this meeting was to review matters related to the application of the Tennesse Valley Authority for a pernit to operate Units 1 and 2 of the Sequoyah Nuclear plant. Notice of this meeting was published in the Federal Register on February 26, 1979. A copy of this notice is included as Attachment A. A list of the attendees for this meeting is included as Attachment C, and a schedule for this meeting is included as Attachment C. Selected portions of the meeting handouts are included as Attachment D. A complete set of handouts has been included in the ACRS Files. No written statements or requests for time to give. oral statements were received frem members of the public. The meeting was attended by Dr. J. C. Mark, Subcommittee Chaf enan and Mr. W. Mathis, Subcommittee member; Dr. R. Savio, ACRS Staff; and the ACRS consuTtants. Dr. f. Catton, Dr. M. Trifunac, Dr. M. White, and Dr. I. Zudans. The meeting was opened at 8:30 a.m. with a short executive session during which Dr. Mark summarized the schedute and the goals for tcday's meeting. The meeting was held entirely in open session and was adjourned at 5:15 p.m. on this day. NRC STAFF INTRCCUCTICN - H. Silver, NRC Staff Mr. Silver gave a brief history of the NRC's review activities for the Sequoyah pl ant. He noted that the construction pernit for the plant was issued on June 27, 1970. Constructien was started on June 5,1969 and is currently about 97 ccmpleted for Unit 1 and 80% complete for Unit 2. The Applicant's projected fuel load dates are for June 1979 for Unit 1 and December 1979 for Unit 2. A draft Safety Evaluation Report had been prepared initially in 1975. This draft SER contained a large number of open items. It was additicnally apparent that the construction schedule for this plant w o uld be semewhat behind schedule. In addition, the seismic issue on this plant was reopened by the NRC Staff. As a result of all this, the issuance of the draft Safety Evaluation Report was delayed until March 1979. The current Safety Evaluation Report contains 5 outstanding issues,17 ccnfirm.atory items, and 7 licensing conditions. It is expected that scre of these matters will be fully resolved by the April Full Comi ttee meeting. ).udin 7909170h3 v---

~ A PPLICANT'S INTROCUCTION - J. Gilleland, T/A Mr. Gilleland briefly summarized T/A's nuclear experience. He noted that T/A currently has 28.5 million kilowatts of generating capacity of which 3.5 million kilowatts are nuclear p' ants. Twelve percent of T/A's last year's generating capacity was from nuclear plants. SITE AND PLANT DESCRIPTION - D. Lambert, T/A Mr. Lambert gave a brief description of the site and the Sequoyah piant. The Sequoyah plant is located on the west bank of the Chickamauga Lake on the Tennessee River. This site is approximately 9.5 miles northeast of Chattanooga, Tennessee and is located in a rural area having no unusual characteristics. The flow in the Tennessee River is regulated by a series of dams up and down the river from the Sequoyah plant. The design base flood was assumed to be at the 727 ft. ele rattor and is equivalent c to a 43 ft. rise in the river. The maximum historic rise is 8 ft. A schematic of the T/A transmission system is given on Figure 1 of Attachment 0, and the layout of the plant is shown on Figure 2 of Attactraent D. Major population areas in the vicinity of the Sequoyah plant are shown on Figure 3 of Attachment D. TVA will act as both the architect-engineer and the construction contractor. The nuclear steam supply system and the initial core loading will be supplied by the Westinghouse Electric Corporation. The reactor contaiment will be of the ice condenser type and the fuel will be the 17 x 17 "R" grid design. Sequoyah will utilize the upper head injection (UHI) in the ECCS. The UHI was added to the plant design after the issuance of the construction permit. The ice condenser contaiment is similar to that used at the McGuire and O. C. Cook plaats. The reactor core is very similar to that used in the Trojan reactor. Figure 4 of Attachnent D Wws a comparison of ther-nal and hydraulic design parameters for the reactor core for the Sequoyah and Trojan reactors. PLANT ORGANIZATICN AND TRAINING PROGRAMS - W. kopp, T/A Mr. Popp stated that, at the present, the construction of Unit I was 96". ccmpleted and that the preoperational testing for Unit I was 57% complete. The orgar.ization charts on pages 5-8 of Attachnent 0 illustrate the essential features of the plant organi:stion. The T/A training program involves simulator training, training lL1DP. s

i._ ~ ~ g at TIA nuclear plants, and training at other nuclear facilities. Reac*ar operatiens personnel have been brought on board at the plant throughout the construction period and are familiar with the construction features of the plant and have had hands-on experience with the various plant equipment. Training of new operators and technicians typically involves six mcnths of classrocm training with an additional year of on-the'- job tra'ining under the supervision of qualified personnel. INDUSTRIAL SECURITY - V. Stephenson, T/A Mr. Stephenson gave a brief description of the industrial security features of the Sequoyah plant. The plan involves the use of physical barriers, detection devices, and amed guards for the deterrence of intruders. The industrial security at the Sequoyah plant meets all of the NRC requirements and T/A is in agreement with the NRC Staff on the industrial security for Sequoyah. OPERATIONAL OA AND CC p90GRA'4S - A. Crevasse, TIA Mr. Crevasse briefly described the operational QA and QC programs at the Sequoyah plant. PrincipaT features of the QA and QC organi e tion and programs are illustrated on Figures 9-11 of Attachment D. EMERGENCY PLANS - J. Lobdell, T/A Mr. Lobdell gave a brief description of the emergency plan for the Sequoyah facility. The emargency plan is patt"bd after the plan which was developed for the Brown's Ferry facility and is in compliance witti the NRC recutrements. The emergency centrol center will be located in Chattanooga. A Ifst of local and state agencies to which T/A has coordinated their emergency plan is given on page 12 of Attachment D. _E_FERGENCY CORE CCOLING SYSTEM (ECCS) DESCRIPTION - S. Jacobs, T/A Mr. Jacobs gave a brief description of the upper head injection system (UHI), the evaluation model, and the results for the Sequoyah plant. The piping schematic and a schematic shewing the flow patterns in the* upper head and in the core are given on Figures 13-15 of Attachment D. The Westinghouse Appendix K :nodel was used and perfect and imperfect mixing were considered. A su: nary of the results of these calculations are shown on pages 16 and 17 of Attachment D. These results were within the requirements of the acceptance criteria presented in 10 CFR 50.56. Ob12[53 r x

~ h.- 4 CONTA!?ctE'IT/3YPASS LEAR >GE - W. Lau, TVA Mr. Lau discussed the features of the Sequoyah contairment which were intended to reduce bypass leakage. The contalment for each unit of the Sequoyah Nuclear Plant consists of a primary contaircent vessel and a shield building and a common auxiliary buil ding. The primary contatment vessel is the free-standing welded steel structure consisting of a vertical cylinder, a hemispherical deme, and a concrete basemat with a steel membrane. The shield building is a medium leakage concrete structure includ-ing the containment vessel and is designed to provide for the collection, mixing, holdun, and to control release of' containme.nt vessel fission product leakage folicwing an accident. The icwer ccmpartment of the containment houses the reactor and the reactor ecoling system and vents into the ice condenser ccmpartment which houses the ice bed. The upper ccmpartment of the containment accccmodates the air dis-placed from the reactor compartment and tfte ica cendenser compart:nent during postu-lated LOCAs. The annulus between the containment and the shield building is maintained at a pressure below that of the auxfif ary building. The auxilfary building, in turn, is maintained at a pressure belcw that of the envirorment. The analysis of the design base LOCA shows that the pressure in the auxiliary building will be belew that of the envirorment except for a period of about 2 minutes during which the auxiliary building is at a positive pressure of one-fourth inch water. Purge If nes to the auxif f ary bufiding have isolation valves in-board and out-board of the contairment and on the inside of the auxif f ary butiding. Leakage through the isolation valves is bled into the annulus base. ICE CCNCENSER LCACING - W. Popp, TVA Mr. Popp indicated that TVA had profited frcm the experience gained both at the Cook and McGuire plants. Ice basket loading is nearly ccmplete and "ie techniques used have achieved good control over ice distribution. The basket ws ifstribu-tions are shown on Figure 18 of Attachment D. C. DISCUSSICN CF THE SEISMIC CESIGN CRITERIA - NRC PRESENTATICN - L. Raf ter, MRC Staff Mr. Raiter discussed the NRC's findings en the seismic reevaluation submitted by the Tennessee Valley Authority on the Sequoyah plant. The TVA seismic reevaluation treated the Sequoyah Watts Bar, and 3cliefente nuclear power plants and was requested 8dIl'dM. s ~

L ' by the NRC in a menorandum dated December 27, 1977. The three nuclear plants in question are located in the Southern Appalachian tectonic provincu. The largest historic earthquake and the controlling event in this province is the May 31,1897 Giles County Earthquake. The Tennessee Valley Authority contended in their reevalua-tion that: (1) the maximun intensity of the 1897 Giles County Earthquake was a MM VII-VIII rather than a MM VIII as specified in the USGS Catalog of Historic Earthquakes; (2) the intensity rating for the 1872 Giles County Earthquake is soil based and that the same earthquake would result in a lower intensity on rock sites such as the Sequoyah site; (3) the intensity acceleration relationship derived by Murphy and O'Brien (1978) is more appropriate than the Trifunac and Brady (1975) relationship used by the NRC and that the Murphy and O'Brien relation-ship should be used in deternining reference accelerations; and (4) at foundation depth the earthquake induced ground motion is less than at the surface. The NRC uses the intensities for historic earthquakas which are developed by the USGS. NCAA and later the USGS have had the statutory responsibility for assigning intensities to historic earthquakes. The NRC feels that the lack of historic data associated with the 1897 Giles County Earthquake would make it difficult to draw a distinction between soil and rock sites. and the current NRC practic s do not allow the use of deconvolution techniques on shallow soil sites. NRC established as the goals for their review the establishutnt of a realistic yet conservative estimate of the ground motion frcm the contr.;111ng earthquake and the ecmparison of the existing seismic design with this estimate of the controlling earthquake. The NRC reccruended that TVA do the following: (1) deter nine a site-specific safe shutdown earthquake response spectra frcm strong motion records of appropriate magnitude and distance; (2) deter nine the' site-specific safe shutdcwn earthquake respcose spectrum frca strong anotion records of appropriate intensity; (3) evaluata the original seismic structural and core response spectra analysis, taking into account rcre realistM damping ratios and materials properties than were used in the orig.nal design, as well as the site-specific 'sMe shutdcwn earthquake response spectr.m (4) to evaluate the operatin; base earthquak to determine whether it meets the recurrence interal criteria of the 10 CR 100. Appendix A; and (5) to compare tne probability of tha safe shutdown earthquake being exceeded at the Sequoyah Ob.CUU r \\

700RORBINA. plant with that at other T/A plants that meet the current Standard Review Plan criteria. The parameters for the site-specific spectra were to be an earthquake of the magnitude of 5.3 to 6.3 with an epicentral distance of less than 25 kilcmeters frem the plant. The site conditions were to be rock. In addition, damping values consistent with current NRC practice were to be used. T/A used records frem 13 earthquakes which had occurred in the United States and Italy to develop their site-specific spectra. The response spectra for these earthquakes are shcwn on Figure 19 of Attachment D. Spectra were developed which bound the maximum, minimum,16th, 50th, and 84th percentiles (. based on log normal distributions) of the total 13 response spectra and are shown on Figure 20 of Attachment D. The NRC Staff selected the 84th percentile level (the mean plus one standard deviation) as the level to be used in the Sequoyah a nalysis. This is consistent with the treatment of the data which was used to derive the Regulatory Guide 1.60 spectral shape and is also consistent with the recommendations in the Standard Review Plan for the use of site-specific spectra. The present Sequoyah design spectra for the various structures were compared to these 84th percentile site-specific spectra. The most li.niting case was for reinforced concrete and the greatest departures of the design spectrum frem the 84th percentile spectra were at about 15 hertz. The Sequoyah design spectra respense frequency was at about the 67th percentile. In terms of actual spectral response for this period, the present design is at 0.18g while the 84th. percentile spectrum would be at 0.2Sg. In terms of peak acceleration, the 84th percentile spectra is associated with a peak acceleration of 0.25g. A ccmparison cf the present Sequoyah design spectra for reinforced cencrete with that of the 84th percencile spectra is shown on page 21 of Attachment D. T/A differed with the Staff as to the appropriate methods for developing these site-specific spectra. T/A contends that the site-specific spectrum should-have beegchosen using the same procedure that was used in deriving tne Regulatory Guide 1.60 spectrm and the site-specific spectra in the Standard Review Plan. Folicwing these procedures, all streng motion records would have been nnlized to the same peak acceleration and the appropriate percentile spectral shape calculated. These spectral shapes should have been then anchcred to the 50th percentile peak accleration (0.10g) of the data set. If the site-specific spectra would have been develcped in this ObbM. s

w ~ 300R OR 8 NL. manner the present design spectra for Sequoyah would have exceeded the 84th percentile spectrum at all frequencies. A ccmparison between the Sequoyah design spectna and the 84th percentile spectrum would then have been as shown on page 22 of Attachment O. The NRC Staff did not consider this procedure applicable in these site-specific studies. The Regulatory Guide 1.60 spectrum was calculated from strong motion records of earthquakes of different magnitudes and recorded at different epicentral distances at different site conditions. It was specifically developed for use with differing reference peak acclerations to estimate different earthquake conditions. The Staff believes that the detemination of the site-specif c spectrum from strong :nction records of the appropriata stze earthquake, distance, and site conditions obviates the use of this approach and allows the use of the unnonnalized response spectrum at each period. The NRC Staff has reccmmended that the Applicant assess the significance of the differences between the present design and site-specific response spectra by using probabilistic techniques to compare the relative difference in the seismic hazard associated with the two response spectra. The Applicant has used a widely used and tested earthquake hazard c::mputer code developed by the USGS. The relative recurrence rates ( b values) were assumed to be 0.57 (as suggested by Chinnery,1979). The upper intensity cutoff was conservatively assumed to be a rii IX. The intensity attenuation with distance was determined frcm the 1886 Charleston earthquake (Sollinger,1977) and site intensities were converted to peak acceleration utilizing the relationship of Murphy and O'Brien (1978). Scme of the results of this analysis are shown on page 23 of Attactment D. Uni fom hazards spectra at 7': dampening are shown for annual risks of exceedence of 10~, ~4 10',13 , and 10 The Phipps Bend,, present Sequoyah, and 84th percentile site-specific spectra are shown on this Figure. The S4th percentile site-specific spectrum and the present Sequoyah design specium in the frequency range of interest a -3 ~4 are nearly bounded by the 10 and 10 annual risks of exceedence. Od1EE s v

u _ r The Staff's conclusions are summarized on page 24 of Attachment D. The Staff has concluded that the difference in seismic hazard between the present design at Sequoyah and the design associated with the site-specific response spectrun is not substantial. Because of such factors in the original plant design methods such as the usage of icwer bound material prepertd es, conservative analysis methods, and loading combinations that include low occurrence probability secondary events, the Staff believes that a substantial additional margin exist. However, the NRC Staff, because the design spectra fall below the site-specific spectrum in certain frequency ranges and as a verification of the Staff's judg-ment regarding structural margins, is requiring that the Applicant quantify the additional margin in representative critical section? of the reactor building, the auxiliary building, and in ccaponents required for safe shutdown. The Staff intends to condition the operating license to require that such evhluations be performed prior to the startup following the first regularly scheduled refueling outage. Dr. Trifunac noted that the Trifunac and Brady relation commonly used by the NRC to correlate earthquake intensity to peak acceleration was developed as a means of displaying the results of Trifunac and Brady's analysis of the historic data and was not intended as a " plug in" correlation for seismic design. Trifunac ~ stated that the work which he had published in 1975 correlating probability of exceedence to MM intensity was, hcwever, intended as a design tool. Using this work, Dr. Trifunac had calculated the probability of exceedence for a MM VI, MM VII, and MM VIII of a 0.189 acceleration at respectively 20%, EG% and 75%. The correspcnding probabilities of exceedence for a.25g acceleration are 5%, 355, and 60%. DISCUSSICN OF SEISMIC OESIGN CRITERIA - APPLICANT'S PCESE'ITATION - J. Hunt & F. Hand, T'/: Mr. Hunt and Mr. Hand expanded upon the NRC StaA's sumary of their work. They indicated that TVA balleves that the analysis used was conservative and indicated that the studies perforned by TVA had concluded that: (1) the Giles County Earthquake was in the MM VII-VIII range rather than the designate'd M VIII; (2) the evaluation of the Giles County Earthquake was based on soil-site conditions 3d..DO

A__ __ P00R ORGDIAL ~~ and that the intensity would be lower for rock sites; (3) the Trifunac-Brady curve (1975) was a conservative correlation of MM intensity with acceleration. (A comparison with other correlations is shown on page 24 of Attrihment D); and (4) the region in which the Giles County Earthquake occurred was a separate ' tectonic province and was not part of the tectenic province in which Sequoyah is sited. NRC PRESENTATICNS - H. Silver, NRC Staff Mr. Silver briefly summarized the open issurs, confirmatory issues, and licensing conditions. He indicated that the NRC Staff and the Applicant were at this point in agreement with the resolution to these items &nd it was expected that a nunber of these itens would have been resolved prior to the April ACRS fall Ccamittee meeting. SUCCCMMI s t et CCMMENTS AND DISC'JSSION OF FUTURE SCHEDULE Dr. Mark sumnarized the day's proceedings briefly and indicated that the Applicant could expect to discuss these matters with the full ACRS at their April meeting. The meeting was then adjeurned at 5:15 p.m. on this day. NOTE: For additional details, a ecmplete transcript of the meeting is available in the NRC Public Cccument Recm,1717 H St., N.W., Washington, D.C. 2C555, or from Ace-Federal Reporters, Inc., 444 North Capital Street, N.W., Washingten, D.C. Ca. h22b9

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v -;~T.. vn, : c... : :." NOTICIS [7590-01-M1 T7A. and their consultants, pertinent HUCLIAA t! Cut.A;olf to this review. The Subcommittee mar then caucus to determine whether the CCMMISSICN matters ident1Hed in the !nitial sesden AcvtsetY COMMITits oM 11ACTC4 have been adequately covered and SMECUAaDS SUSCCauMTTit CN THE whether the project !s ready for tsCUCTAM NUC.1A1 Pown STATICN review by the full Committee. In addit!ca. It may be necessary for' the Subcommittee to hold one or more The ACRS Subcommittee on the Se-closed sessions for the purpose of ex-quoyah Nuclear Power Stacon will ploring matters involvt2g proprietary hold a meeting on March 12.1979. In Information. I have determined. In ac. Room 1046.1717 E Street N'#, Wash-cordance with Subsec' fen 10(d) of tagten. DC 20555 to revtew the appl 1-Pub. I. 92-443. that, should such ses. cacon of the Tennessee Vaney Au-Mons k reth it b weessary to thority (TVA) for a per=it to operate close these sessions to prated propri. Umts 1 and 2 of this s,w,m etary infor..ation ($ U.S.C. In acecrdance with the..ihad $32WeX4E outuned in the Forza. Rzcts;zz on Cctober C 19*3. (41 FR 459:51, oral or Further hformadon regarding: written statementa =sy be presented topics to be discussed, whether the, by members of the public. recordings meeting hs.s been canceHed or resched-wdl be peruutted only dur.ng those uled, the Chairman's ru!!ng on re-portiens of the meeting when a tras-ques *J for the opportunity to present scrtet is being kept, and questMns P'ay oral statements and the time aHotted be aated only by members of the Sub therefor can be obtained by a pre;sid commit'.ee ita consultants, and M telephone caII to the Cesignated Fed-Persons desittng to mate oral state-eral Employee for this meeting. Dr. ments should notify the Designated Richard P. Sarto. (telephone 207/634-Federal Imployee as far in advance na 3*ST) between 8d5.a.m. and 5.00 p.m practicable so that appropr*me ar*

gg7, rangements can be made to aHM h Background infermat!cn concer.*.ing necessary time during the meeting for items to be considered at this meeting can be found in documents on Ce and e ag.

for subject meeting available f r public inspectica at the shad be as fonows NRC PubHe Document Room.1717 E Mornar. Var's 12.19"3 Street N'F, Washington. DC *0555 and at the ttacocga.HmP.cn g;3e 1.31. t M'a rII cCNCMatoN or County Bicentennial IJbrary. 1001 suru.a t Broad St.eet. Chattacocca. TN 37402. The Sabcommitte, may meet in Ex-l cam Febr2ary 979. ecuuve Session. Eth any of its consul + Joss C. Horut. tants who say be present, to explore and eenate their prew sry optn-Admory Commcee ions regsrcng matters w!nch should yesageme-Lt C/f'cer. be cor.T.dered dur=g the meeting and (FR h Ts-sacsyw 223.y,m w to formuiste a repor*. and recommen-dations to the fu2 Com=it'.ee. At the eenclusion of the IIecutive Session. the Subcommittee vGI hear presentacons by and hold Ciscussions eth representadves of the NRC StMt. D 7n0 II I p:.. w .,I a 2m m 44. MC. M-'-MCNEAI' NI# AT"'AC-MDT A Q 4 ~.4 O4 $ SJ b 1

SUBCCMMITTEE MEETING CN SEQUOYAH NUCLEAR PCWER PLANT, UNITS 112 WASHINGTON, CC f! ARCH 12, 1979 l ATTENDEES LIST l ACRS NRC C. Mark, Chairman H. Silver W. Mathis, Meder S. Varga I. Catton, Censultant R. Priebe M. Trifunac, Consultant B. Milstead M. White, Consultant S. Israel I. Zudans, Censultant G. Kelly R. Savio Staff

• P. R. Matthews R. A. Aennann
• Cesignated Fewral E:nployee

0. R. Lasher L. Reiter TENN VALLEY AUTHORITY WESTINGHOUSE D. Ladert J. F. G111 eland M. R. Harding M. R. W1senburg V. J. Esposito M. J. Bur:ynski M. A. Sia:nc C. R. Morgan W. J. Johnsen R. D. Guthric P. J. Docherty V. S. Stephenson S. E. Jacobs A. W. Crevasse T. A. Meyer W. Lau F. R. Hand D. R. Cen*4n R. J. Hunt W. M. Seay C. S. Walker C. Mills H. E. McConnell H. E. Crisler D. W. Wilsen J. A. Coffey E. K. S1iger J. S. Olsen G.

J. L:bdell ATTACHMENT 3 301261

~ PRCPCSED SwM FCR %'CH 12, 1979 MEETDG CF ME SEQUCYAH SUBC7MI'ITEE 1 8:30-8:45 a.m. 1.0 Executive Session (CPEN) - ACRS (15 minutes) 2.0 Discussiens with the NRC Staff and the Applicant 8:45-9:00 a.m. 2.1 NRC Introdtetion (15 minutes) (a) Scope and Status of the Review 9:00-10:45 a.m.

2. 2 Applicant's Introduction (a) Introduction and Organi::stien (TVA)

(10 minutes) (b) Site and Plant Cescriction (40 minutes) (c) Plant Crganiration and Status (10 minutes) (d) Training Program - Cperators arx! Technicians (10 minutes) (e) Cperational CA & CC Program (10 minutes) (f) E=ergency Plans (15 minutes) (g) Industrial Security (closed) (10 minutes) 10:45-11:45 a.m. 2.3 Applicant's Technical Presentations (a) ECCS - UHI (35 minutes) (b) Containment and Bypass Leakage (15 minutes) (c) Ice Condenser Leading (10 minutes) 11:45-12:45 p.m.

• ****** * * * * * *** ** LUNCH *** *** * ** * ** * **

12:45-2:45 p.m.

2. 4 Discussion of Seismic Cesign Criteria (a) NRC Presentation (80 minutes)

(b) Applicant's Fresentation (40 =inutes) 2:45-3:45 p.m. 3.0 NRC SER Presentatien (60 minutes) (a) Discussion of Action en MRS Generic Items (b) Discussion of Cpen Issues, Confirmatory Issues, and Licensing Cenditiens (c) Staff Cenclusiens 3:45-4:15 p.m. 40 Applicant's ResPense to Item 3.0 (30 minutes) 4:1 M :45 p.m. 5.0 Sube rmittee Cements and Discussien of Future Schedule (30 minutes) O. Revised 3/7/73 A D ChME C : OdlidU2

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Rockwocc (5,259) Spring City (1,756) McMinnville O (10,662) e Pikeville (1,454) Dayton ,,et) E e Athens (11,790) unlap 7 i 1,672) SEQUCYM NUCLEAR ?LMT Cleve and g (20 51) Jasper ( 1,8 41 )

1. C m a SL 20 Miles Ressville e Ringgold (1,281)

\\ g(Calton18,872) 40 Miles e Lafayette (5,044) O. l i Figure 1.2-8 MJCR v.. __,. :CN ARDS ~ SEQUCYAH.1CCLDR PLANT 351.C1,i,

SLIDE 8 THER. VAL AND hTDRAULIC DESIGN PARAMETERS Sequovah Trojan Reactor Core Heat Output, segawatts ther=al .3411 3411 System Pressure, Nominal, pounds per square inch 2250 2250 Mini =um Departure from Nucleate Boiling Ratio at Nominal Conditions Typical Flow Channel 2.22 2.04 Thimble (Cold 'Jall) Flow Channel 1.31

1. 71 To tal 6

6 Thermal Flow Race, pounds per hour 133.3 x 10 13;,7 x 73 6 F.ff ective Flow Race for Heat Transfer, pounds per hour 127.8 x 10 126.7 x 10 Effective Core Flow Area, square feat 51.1 51.1 Average Coolant !=cperature Nominal Inlet, degrees Fahrenhei:. 345.7 552.5 Average Rise in Core, degrees Fahret.h-it 67.8 66.9 Active Heat Transfer Surface Area, square feet 59,700 59,700 Active Heat Flux, Stu per hour-square foot 189,800 139,300 Maximum Heat Flux, for normal operation, Stu per hour-square feet 474,500 474,500 Average *her=al Cutput, kilowatts per f:oc 5.44 5.44 her=al Cutput, for normal operation, Mae ' kilowatts per foot 12.20 12.60 Heat Flux Hot Channel Factor, F 2.25 2.32 q Peak Fuel Castral Temperature at 100 percent Fower, degrees Fahrenheit 3400 3400 6., D <m,~._ e.d t)i.G U g

to e CDw NH in CQ SUPT SERVICE ORGN'S

f. ADMIN g

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2. PLAN T SERVICES

3. SECURITY

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...r-. .3 r. ~ .m. m-- T/A'S CCffiBTICNS- (FFASE I) (1) TE PAXI?Ui INTEGITY CF TE 1897 GILES CCCNTY EMTHCISE WAS REU.Y VII-VIII RATFER TF#1 VIII. (2) TE INTENSITY RATING FCR TE 1897 GILES CCCNTf EETHCCAE IS SDIL SIASED #0 TFAT TIE S#E EETHCl3E WCLLD RESLLT IN A LG8 INTENSITY AT RCC< SITES SLCH AS AT SECLCYAH. (3) T'-E INiBSITY-X.CE!SATICN RELATICNSHIF EERI'ED BY EWhY AND O' ERIE'1 (1978) IS BIEE AFFRCFRIATE TFAN TFAT FCU0 IN TRIFLtK #0 BADY (1975) #0 SH01D E USED IN ETEYlNING ft-d?CE ACCELSATICNS, (4) AT FCttiEATICU EECTH, EARTHCUAE-IECCED GCU0 MOTICN IS LESS TFAN IFAT AT TE S$FAE. Ii ij C. 3 351281.

ATMS rF RPH Ps (D PA(ING A RER.ISTIC 'tET CCEVATI'<E ESTIPAE CF GCUT MOTICN FRCM TrE CCNTRCLLING EARTRNE. (2) CCfFARIK TMS ESTIPATE WITH TE E(ISTING SEISMIC ISIGN. (D EMINING TE SIGNIFIC#G CF NiY DIrr -SE EiiEN TE AEGE. P00RORIBiNAL v e. .0bb.55b5.b

~ ~~ ~3.t.~. -;'.:; 7 '... aT~;.. -... ~ ~ ~~- ?00R3 RENAL ECOREDED AFFCACHES: i / 1. DETERMIE SITE-SPECIFIC SSE ESP 0CSE SPECTRA FRCH STRONG MOTION RECD,"as T APPCPRIATE PMNITUDE AND DISTMCE 2. DETERMIE SITE-SPECIFIC SSE ESPONSE SPECTRA FRCM STRONG MOTION RECOCS OF APPETRIATE IFtMSITY 3. REEVALUATE OPI61XAL SEISMIC STRUCTURAL AND FLOOR I RESPONSE $PECTRA ANALYSIS, TAXING INTO ACCOUNT MORE REALISTIC ETHODS AND MATERIAL PRCitxilES, AS ELL AS SITE-SPECIFIC SSE RESPCKSE SPECTRA i 4. EEVALUATE THE OBE TO SEE )EETER IT EETS THE RECURPSiCE IWtRVAL CRITERIA CF APPEEli A TO PART 100 5. CCP.PAPE THE PROEASILITY OF SSE E!XG EXCEEED AT THE SUBJECT PLMT VITH THAT AT OTHER 1YA PLANTS THAT MEET THE SR? CIITERIA C., 3512S;

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