AUG 2 8 ~7~

Docket Mos. 50-275and 50-323

APPLXCAhT: PACIFIC GAS 6 ELECTRIC COEPAhY (PG6E)

FACILITY: DIABLO CANYON UNITS 1 & 2

SUMMARY OF VISITS TO AZC REGION V OFFICE, PGM OFFICES, A'R DIABLOGQFXON SITE, AUGUST 14-15, 1973

The principal purpose of the trip was to nake an initial visit toDiablo Canyon and become familiar with overall site characteristicsand the plant layout and construction. Additionally, during thecourse of the trip, meetings were held with the Reactor OperationsOffice in Berkeley, and with representatives of PGSZ at their officesin San Francisco.

On August 14, X visited tho ARC Region V Office in )berkeley and metwith J. CrewsF Senior Reactor Inspector on the, Diablo Canyon Project.Eu. Crews summarized the highlights of Diablo Canyon construction andprovided general background information on the project. Among theitems discussed were the percentage of construction completely on Units1 and 2, the projected fuel loading date for Unit 1, and the environmental heaxings on Unit 2 which are scheduled to resume next month.

Later on August 14, I met with xepresentatives of PGSE at their officesin San Francisco The principal contact at PGSE is Sill Lindblad, ProjectEngineer for Diablo Canyon. The main purposes of this meeting wore tomeet representatives of PGGE who are involved with the Diablo Canyonproject, and to discuss in general terms some of the deficiencies inthe FSAR which was tendered by POSE on 7«16-73. The completeness reviewof the Diablo Canyon FSAR was still in 'progress at the time of the,meeting. Other PGM personnel present included John Hoch (LicensingEngineer), Jim Gormly 0fechanical Engineer)» and Erwin Vollak (CivilEngineer).

On August 15, I was given a complete tour of the Diablo Canyon site;included in t'e tour were the intake'uilding, disCharge structure,turbine building, auxiliary building, containment structure, electricalswitchyard, and certain significant locations within the site boundary.

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P66E personnel accompanying um on the tour vere B. Lindblad, J. Hoch,and B. Coley (a start-up engineer assigned to the site). The tourWas thorough and inforE3ative, and all questions concerning safety andconstruction vere answered promptly and politely.

O 'ginai Signed. bX

Thomas J.- Hirons, Pro)ect HanagerP>R Branch Mo. 33ircctorate of T icqnsing

cc: AKC Pj)RLocal PQRR. C. Be7oung,R. M. KleckerRO (3)TR Assistant Qixectora'XR Branch ChiefsRP Assistant MrectorsRP Sranch ChiefsL. ChandlerL. MernerJ. andricR. P. Praley', ACR8 (3)

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Docket Nos. 50-275and 50-323 SEP 7 t@3

APPLICAHT: PACIFIC GAS & ELECTRIC COMPANY (PG&E)

~Pur oee

FACILITY: DIABLO GNYON UNITS 1 AND 2r

SEQfARV OF MEETING HELD ON AUGUST 21 1973 TO DISCUSS DEFICIENCIESIH THE DIABLO CANYON FSAR

A meeting was held between repx'asentatives of PG&E, Westinghouse, andthe Regulatory staff on August 21, 1973, in Bethesda. A liat of participants is attached as Enclosure Ho. 1 The meeting vas requested byPG&E to discuss certain deficiencies in their Diablo Canyon FSAR submittal.As a result of the preliminary review conducted by the staff, the applfca»tion for operating licenses for Diablo Canyon Units 1 and 2 was reJectedon August 13, 1973. The principal reasons'or reJection vere the exten'sivanature of the deficiencies identified in the FSAR, and the fact thatRevision 1 of the Standard Format and Content of Safety Analysis Reportsfor Nuclear Power Plants (October 1972) was not, followed in the prepare~tion of the FSAR. PG&E plans to resubmit their application during thelast veek of September.

Discussion

The following technical ax'eas in the FSAR vere discussed at the meeting;any decisions regarding action items are indicated below.

l. Tornado Desi n Criteria

Tornado design criteria vera not discussed in the tendered FSAR.PG&E indicated that they had been wox'king on this item, using theBechtal document (BC-TOP-3) as a guide The staff noted that anaw regulatory guide on this subJact ~ould be issued.soon, probablyin November. This guide divides the country into three regions forpux'poses of design basis tornado charactexistics (Saa Enclosure Ho.2 for a draft summary of these characteristics for each region).Diablo Canyon falls in Region II. PG&E intenda to supply a summaryof the tornado capability of all Category I structures and systemswhich could affect safe shutdown. This analysis will include thediasels and the condensate vatar storage tank. However, the detailed

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analysis af tarnado generated missiles vill nat be provided «Amp WaapplisaHon ia resubmitted, but would ba, availhbla within 60-90 daysafter docketing. This procedure vas agreed ta by the Regulatarjr staff.

Protection @inst amia Effects Associated with the PostulatedRu turn of Pi in

>lith regard ta pi.pe break autsi«la containmentj PGM initially,indicatedthat they vould like to reply by correspondence, using, the letter A'cm

A Giambussa dated 12/18/72 as a reference. PGK had retained Huc|eOrServices Corporation to doaan analysis an thia sub)ectj and a draft

a& tof their'eport is nearly'ready for submittali The staff said thatthey would need mare dost'j'ice information in the pSAR an pipebreak both insido nnd outside containment. Xt was finally agreedthat, PCS would provide t:ore infoxmation 'on pipe brisk in the PSARj

'andthat the report fram Nuclear Services would ba incorporated asan Appendix ta the PSAR.

3. Desi n af Cate o X Structures

The staff agreed that Document (8) an structural design criteria(see Enclosure No. 3 of lettex'=-af re)ection to PC&8 dated 8/13/V3)is riewj but the infoxmntion outlined.,in this document is not. Xfthis document did not exist, the applicant would have to establishsome appx'opriate criteria of his awn for pipe break 'outside contain-ment. These comments were made in'eference to Item 3.8.1-5 ofEnclosure 1 of the letter of re)ection to PC68 (referred to hax'eafterns Enclosure 1). Also, it was agreed that Item 3.8.2-b of Enclosure1 (position vith regard to ACI-359 qn concrete containments) shouldcamo under the catogaxy of additional information to be suppliedji.e., an asterisk item nat required for docketing.

Auzilia S stems

Qith regaxd to item 10.1 on yaga 22 of Enclosure 1, the staff clarifiedthat the statement vns poaxly'orded; and that tva separate requestsfar information vera being stated: 1) Plant hoat balance, and 2) safetyrelated design features'f the steam nnd pawex'onvexsion system.

Containment Punctianal Desi n and Heat Removal S stems

On page 14 of Enclosure 1 there ax'e five deficiencies undor the headingaf Containment &nctional Resign and Heat Removal Systems. Aftersame discussion it vas agreod that Items 1 (Containmont prassuxeresponse dialysis for a spectrum of hot l,eg breaks) and 4 (Containmentand subcompartment pressure response analysis far a spectrum of mainsteam line ruptures within containment) would.not be required for

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On page 25 of Enciosura I.,- the staff questioned the description, ofalarm set-points 4n,tormen of ci/cc. |3Q&E indicated that thirs wasan erroj in the FBARi and that the Tables containing- these unitswould be corrected.

Alao- on page 255 PG&E questioned the need for Continuous particulateand gas monitors in thy spent fuel, handling compartment 'and,in theradwaste area. lhe staff indicated'that this @as the recommendedprocedure to insure against the manual. error of forgetting to''turn

'n.the monitor wheT|,entering those areas.11

7. Diesel Genex'atox's

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On page 18 oi EncioSure l (Sect%'on .8.3.2)>.PG&E asked for clarificationon the question concerning Iterating and .loading ef the Shared dieselgenex'atox.- 'Lhe staff explained that information was required on theswitching capability of the fifth diesel, and that PG&Z should demonstratethat the provision of the'ifth diesel docs not impair the ability

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the Emexgency Power System to perform its safety function.

Ph sical Se ration Criteria of Electrical E ui mentr

Again on yaga 18 of Encldsure. 1 (Section 8.3.3), PG&E requestedclarification on the que'stion con'cerning physical separation, criteria'a'»used for all redundant Clead IE electrical powex'quipment, devices~circuits and x'aceways. %e staff indicated that actual physicaldimensions should be 'provided for distances between equipment, devices„ »

redundant cables trays, etc.1

S stems Re uircd fox'afe Shutdown

On page 17 of Enclosure 1 (Section 7.4.1)$ the staH agreed thatmodifications required for instr'umentatoton and controlo should

refex'o

the cold shut down condition rather than hot shut .down as statedin the Enclosure't was fux'thor'greed that theso modificationscould be dhihyed until the Technical Specifications stage;

Reactor coolaT|t s stdm and connected s stems

Pith regard to the questions oa Chapter 5 of the TSAR (page 13 ofEnclosuxe 1), the folloigng items werc discussed:.

a. 5.1 a: it vas agrebd that appropx'iate Piping and. XnatrumentationDiagxams 'ward available in Chapter 3 of the /SAR. PG&E will inserta cx'oss reference to this effecti

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b. 5.2-b.'he statement with regaxd to ovcrpresaure protectionshould be deleted;

c. 5.3-c: the Thermal and Hydx'aulic Characteristics Summaxy Tableis contained in Section 5.'1 of thc PSAR. PCS will„cross refarencethis'

Basic Geolo ic nnd Seismic"Xnformation

With regard to Section 2.5.1 on pago 4 of Enclosure 1» PCS indicaLedthat'they'ad provided the rcfercnc document by Ri H. Jahns in

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submittal. Thc staff agreed that they did not have to provideit again.

Uses of Ad scent Land and Materd

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Under Section 2.1,4 of Enclosure 1, PGGE asked fox a clarificationof nearby" in the statement» "". uses of neaxby suxface and groundwater." The staff indicated that a distance of 2 3 mileg would baappropriate.

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Stabilit of Subsurface Materials

On page 6 of Enclosure 1, the applicant: is asked to provide assuxancethat oil and/or water will not be extracted from beneath or ad3acentto the plant such that it may pose a hazard to plant operation andsafety. 'The staff is paxticularly concerned with adjacent offshoreproperties. PG&E indicated that, there is currently no specific interestin offshoro propexties, and asked if they could defer a detailedanalysis of this item until such interest is expressed. Iho staffagreed that a statement in the PSAR to this effect would ba

satisfactoryj'ut.

that any availabla data on these properties should be providedat this time.

Slo e Stabilit

Pages 6«7 of Enclosure 1 contain sje'cific comments on the slopestability analysis presented 6y the applicant in the FSAR. PG68asked for clarification ao to what information was required fordocketing and what could bc provided later. The staff indicatedthat the following information must be provided for docketing:1) Details of 'the static stability analysis, including soil androck properties and assumptions> 2) A description of the boringprograms including the proposed schodule for this program. 'lhodescription of this boring program should include an acceptablemethod of Sampling which px'oduces undisturbed coro boxings and samples

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Original Signed by

Thjanad J. HironaPAR Branch No. 3Directorato of. Licensing,

Enclosures:l. Attendance Liat21 Design Basin Tornado Characteristics

cc Tr/encl.olAEQ PDRLocal PDRR» 0» DeYoungIC. R. GollarR. N'. l(leckarRO (3)TR Assistant DirectorsTR Branch ChiefsE»,CusbIIIanV. H. wilsonRP Assistant DirectoxsRP Branch ChiefaL» Chandler, OGG

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ENCLOSURE NO. l

ATTENDANCE LIST

PACIFIC GAS 6 ELECTRIC COMPANY

V. J. GhioJ. B. HochW. J. LindbladE. P. Wollak

WESTINGHOUSE

'A. J. AbelsP. BlauJ- W. Dorrycott

AEC

J. S. BoegliS. BlockA. T. CardoneJ. E. FairobentK. R. GollerT. J. HironsR. E. LipinskiE. H- MarkeeW. C. MilsteadJ. E. RichardsonG. W. RivenbarkM. SrinivasanC. W. SullivanA. R. Ungaro

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With the exception of J. S. Boegli and T. J. Hirons, all AEC attendancewas on a part time basis.

ENCLOSURE NO. 2

TABLE 1

DESIGN BASIS TORNADO CHARACTERISTICS

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m h

TranslationalSpeed (mph) Radius

Maximum Minimums/ ~feet

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Rate ofPressure Drop~/

300 60 20 275 3.0 1.0

250 50 15 275 2.25 0.6

III 200 40 10 275 1.5 0.3

—The minimum translational speed, which allows maximum transit time of2/the tornado across exposed plant features, is to be used whenever lowtravel speeds (maximum transit time) is a limiting factor in design of theultimate heat sink'.

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