ML20236C389

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Summary of ACRS 750605 Meeting in Washington,Dc Re Plant. List of Attendees & Proposed Meeting Agenda Encl
ML20236C389
Person / Time
Site: Diablo Canyon, 05000000
Issue date: 07/24/1975
From: Hirons T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20236A877 List: ... further results
References
FOIA-87-214 NUDOCS 8707300040
Download: ML20236C389 (9)


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JUL. 2 41975 l

l DOCK 1:T NOS: 5 ND 50-323 APPLICANT: PACIFIC GAS AND ELECTRIC COMPANY (PG&E)

FACILITY: DIABLO CANYON NUCLEAR POWER STATION, UNITS 1 AND 2 1

SUMMARY

OF ACRS FULL COMMITIEE MEETING HELD ON JUNE 5, 1975 l

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An ACRS Full Comittee Meeting regarding the Diablo Canyon Nuclear Power j Station was held in Washington, D, C. on June 5, 1975. A complete list l of attendees is given in Enclosure No. 1. The agenda for the meeting is l

attached as Enclosure No. 2.  ;

i Introductory Remarks by Applicant i

Mr. Lindblad of PG&E briefly described the site location and gave the status regarding construction, fuel loading and comercial o;eration. l He indicated that fuel loading for Unit 1 would be in late January of 1976, with comercial operation estimated for July of that year.

Project Review Summary and Status Report 1

Mr. Allison of the NkC staff gave the status of the review and schedule for completion. He indicated that geology / seismology is still the limiting item in the review, and that it is planned for the staf f's evaluation of this item to be completed in time for an October ACRS Full Cornittee Meeting. This would 1 cad to a completion of licensing activity around February of 1976. With regard to outstanding unresolved itens, the status was nearly identical to that reported at the Diablo Canyon Subcommittee Meeting on May 23, 1975. The principal exception was the item of insulation used inside containment; this matter was resolved by the staff since the May 23, 1975 meeting.

Tornado Characteristics / Criteria Af ter a brief description sf the site characteristics related to geography, demography, and meteorology, Mr. Ghio of PG&E summarized the tornado capability studies which they had undertaken at the request of the staff (See Transcript, starting page 129). Mr. Grimes of the staff indicated that the tornado protection for the plant had been f :-

reviewed in terms of concrete thicknesses which provide protection, s ,

e7o730004o e70721 PDR FOIA CONNORe7-214 PDR

JUL 2 41975 and in terms of location and redundancy of safety-related equipment.

He stated that three areas had been identified where the protection is weak:

1. The barriers provided for the diesel generstor air intakes; i
2. The component cooling water surge tanks and associated con-necting piping; and
3. The 4 kV switchgear rooms located in the corner of the tur-bine building.

Grimes indicated that discussions will be held with the applicant to I determine what additional protection might be feasible within the I constraints imposed by the as-built facility.

Reactor Design Mr. Little of Westinghouse summarized the status of several WCAP reports related to the 17 x 17 fuel design (See Transcript, starting page 139).

The review of several of these reports has been completed by the staff, and information is still outstanding on several othere.

Dr. Peacock of Westinghouse discussed the status of the ECCS/LOCA evaluation with regard to Diablo Canyon (See Transcript, starting page 141). The revised Westinghouse ECCS model has been approved recently, although the analysis for Diablo Canyon has not been completed based on the revised model. However, it is expected that the Diablo Canyon analysis "ill result in substantia 1'nargins to the Appendix K max =2200*F.

requirement of I ' ,

Mr. Little then discussed in detail the Westinghouse Augmented Startup Program Proposal (See Transcript, starting page 143). This presentation was nearly identical to that nade at the Diablo Canyon Subcommittee Meeting on May 23, 1975 (See Transcript of that Subcommittee Meeting, starting page 231). Little emphasized that this program was developed in an attempt to address the concerns which ACRS and the staff have expressed at various times. He indicated that Westinghouse felt that the program would be most effective if it had between 3 and 5 participants.

Regarding ATVS, Dr. Peccock stated that tus Westinghouse evaluation model and technical position had been submitted in WCAP-8330, and that one round of formal questions from the staff regarding this WCAP had been answered. The staff evaluation of the Westinghouse position on ATWS is expected to be completed later this summer. Resolution of this issue for Diablo Canyon will follow.

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Accident Considerations I The following items were discussed: '

l (1) Reactor Coolant Pump Overspeed i

Mr. Gangloff of Westinghouse stated that WCAP-8163 on this j subject had been filed in September of 1973. The conclusion

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of this report was that there is reasonable assurance that l the reactor coolant pump will remain intact under blowdown j conditions. Westinghouse is continuing with test work in  !

an attempt to substantiate this conclusion (See Transcript, I pas,e 173). The staff indicated that the review of the WCAP should be completed later this summer, and that a meeting

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with Westinghouse would be held to discuss this review. .

l (2) _ Steam Generator Integrity-Slug Flow l

l Dr. Peacock referenced the presentation on this item at the i May 23, 1975 Subcommittee Meeting (See Transcript of that meeting, starting page 62). He stated that they had investigated the fluid-hydraulic regimes that would exist for both large and small breaks, and had compared them to a number of literature correlations to assure that conditions would not be appropriate for the onset of slug flow. Dr. Okrent asked that the staff and the applicant be prepared to discuss (at a future meeting) some of the slug flow issues raised previously by the Subcommittee. Mr. Allison indicated that the staff's position on tube rupture is that adequate assurance be provided that tube ruptures will not occur following a - '

LOCA, dnd that chemistry control and inservice inspection are used to help provide this assurance. In connection i with this, the steam generator tube inspections at Point Beach were discussed in some detail. l (3) Subcompartment Pressure Calculations Dr. Stratton asked about the sensitivity of the containment liner plate or typical heat sinks to the total containment 1 pressure. Mr. Gallaghere 6f.. Westinghouse:Indicatedt thatt the  !

liner effect was in the neighborhood of 3-6 psi.

On a related problem, the staff inforced the Committee of i a recent generic problem involving consideration of forces i on the reactor vessel supports from the blowdown following a LOCA. The problem first arose on the North Anna docket, but is,beine investigated on a cenerie basis.

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JUL. 2 41975 l

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I' (4) Water Hammer 1 The staff indicated that they had not yet completed their review of this item. In the meantime, PG&E is proceeding  ;

with the fix of shortening the feedwater lines. j

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, (5) _ Lockout of Power Operated ES7 Valves i Mr. Lindblad of PG&E stated that they had already agreed

! to lock out power to certain motor-operated valves specified i l by the staff. Some discussion followed involving the time i available to take certain corrective actions. j l

Protection Against Propagation of Damage From Fires l i

Mr. Nielsen of PG&E made a presentation which included some comparisons j

of fire protection practices at Diablo Canyon and Browns Ferry (See j Transcript, starting page 193). This item was also covered in detail  !

at the May 23, 1975 Subcommittee Meeting (See Transcript of that meeting,

, starting page 211). j l

Electric Power Systems <

l Mr. Eoch of PG&E made a presentation regarding shutdown capability vith prolonged loss of all a-c power (See Transcript, starting page 199).

This item was also covered in detail at the May 23, 1975 Subcommittee )

Meeting (See Transcript of that meeting, starting page 176). Hoch l emphasized that they considered in this analysis circumstances which l are outside the plant design envelope. The conclusion of the analysis ' ,

was that the reactor could be brought to hot standby for about six j hours if all a-c power was lost. -

l Dnergency Plan Dr. Moeller inquired about the status of the State of California Energency  !

Response Plan. Mr. Hirons of the staff indicated that this plan was j

, being formulated during the course of the Diablo Canyon review, but that J it had not been reviewed completely by th'e staff at the time. Mr. Shiffer l of PG&E indicated that this state plan is in final form, with an April j 1975 draf t being the latest version. The plan is expected to go to  ;

the California Legislature for approval within a short time. Within l NRC, the Office of International and State Programs will also review 1 this plan. Dr. Moeller asked several other questions related to the j Diablo Canyon Dnergency Plan and the authorit/ which is delegated to l l the Local Sheriff's Department. 1 I  !

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JUL. 2 41975 6

i Dr. Okrent then asked the applicant what progress they had made with regard to instrumentation tc follow a serious accident. Mr. Shiffer j of PG6E made a detailed presentation on this subject (See Transcript, starting page 214). He indicated that they are developing some detailed procedures for this using available instrumentation, but that also he l had been pushing EPRI to fund a generic study on this subject, with '

particular emphasis on implementation of the proposed Regulatory Guide.

As a result, EPRI has given a contract to Nuclear Services Corporation to study the instrumentation of a large PWR on a generic basis. Their first report should be published in the near future. i Summarv After a brief caucus, Dr. Kerr indicated that the Committee would write a letter which will constitute a partial review of the operating license application for the Diablo Canyon Units.

Original signed By Dennis P. Allison 4 Thomas J. Hirons Light Water Reactors l

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) Project Branch 1-3 l

Division of Reactor Licensing j Enclosure No. 1: "

I Attendance List I 1

b Enclosure No. 2:

Meeting Agenda ' ~'

cc w/ enc 1:

Mr. John C. Morrissey Philip A. Cranc, Jr., Esq. l Andrew J. Skaff, Esq.

Mr. Frederick Eissler, Ms. Raye Fleming Ms. Sandra A. Silver ,

fir. John Forster Mr. William P. Cornwell i Mr. W. J. Lindblad Mr. Gordon Silver i

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omes > N'* f -

eURNAME> ,8,,* .,8 pare >

Form AEC.518 (Rev. 9 5 5) AECM 0240 W u. s. GOYERNM ENT PR6MTING OmCEI 19N.926166  !

JUL. 2 41975 4

ENCLOSURE NO. 1 ATTENDANCE LIST DIABLO CANYON ACRS FULL' COMMITTEE MEETING JUNE S. 1975 I

I ACRS Dr. W. Kerr

, D. D. W. Hoeller Mr. J. H.' Arnold Mr. M. Bender Dr. S. H. Bush Dr. M. W. Carbon Mr. L. W. Fox l Dr. S. Lawroski i Dr. D. Okrent Dr. C. P. Siess Dr. W. R. Stratton ACRS STAFF J. Conran PACIFIC GAS AND ELECTRIC COMPANY _(PG&E)

W. J. Lindblad J. B. Hoch H. J. Gormly '

E. P. Wollak R. M. Laverty_

V. J. Ghio D. Nielsen R. A. Young J. R. Herrera J. C. Carroll R. A. Ramsay J. D. Shiffer WESTINGHOUSE D. W. Peacock W. Gangloff

! A. J. Abels i J. Little

'P. Blau J. Gallahher i

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SURNAME 5 ,,,,, ,,,%

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l Porm AEC.318 (Rev. 9 53) AECM 0240 W u. s. cove RNMENT PRINTING OFFICat 1974e 516165

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I JUL. 2 41975 )

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, Enclosure No. 1 l NRC - STAFF D. P. Allison T. J. Ilirons

0. D. Parr '

B. K. Grimes D. G. Mcdonald M. S. Dunnenfeld P. S. Check F. M. Almeter P. Hearn D. Fisbher P. Seiffert F. Litton l t i

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i SURNAMEP DATS W e-1 Form AIC.)l8 (Rev 9 55) AICM 0240 W u. s. oovsRNuaNT PRINTING OFrtCEI 1974 826166 I

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v% g ENCLOSURE NO. 2_

PROPOSED ActNDA P0h SE ACKS PARTIAL OL REVIEW OP DIABLO CANYON j

June 5,1975 - Washington, D. C.

PRINCIPAL SP0XESHEN:

Vm. Lindblad, PC&E (ProJ. Eng. . Diablo Canyon)

Dennis Allison, DRL (Prpj. Hgr. - Diablo Canyon) f I

. (P0&E)

(5 min.) 1. INTRODUCMRY REHARKS BY APPLICANT '

A. trief Description of Site and Facility B. Construction Status / Fuel Load Schedule /$chedule for Operation C. Organization / Assignment of, Responsibilities for Project (MRC)

(30 min,) II. PROJECT REVIEW $ UNWARY &.STAWS REPORT A. Status of NRC Review - Sc.hedula for Coe$1etion B. Update and summary of Unresolved / Incomplete Items (15 min.) III. $RIEP SUNK 4RY OF SITE CHARACTERISTIC 8 (IXCEPT OEcth3Y/8 W)

A. Geography, Demography, Noteorology .

(P0&E)

(P0&O

.  % Tornado Characteristics / Criteria

1. Brief Sucasry by P0&E
2. Degree of Conformance to current criteria
3. Systems for Safe Shutdown Weekly Protected from tornado-(DRL/NR(

C. Basis for Acceptability of Tornado Design IV. REACICR DESIGN ,. (MAIM (5 min.) A. Remaining Questions on 17 x 17 Core (10 min) B. Power Distr. Control - ECCS/thCA Evaluation (10 min.) C. Augmented Startup Program Proposal (5 min.) D.AWS ,

V. ACCIDENT CONSIDERATION,NS (5 min.) A. Containment Insulation

8. RCP Overspeed (5 min.) ,

(5 min.) C. Steam Centrator Integrity .

(5 min.) . D. Pipe Breaka outside Containment

($ a10.) 3. Subcompartment Pressure Analyses (10 min.) P. Water Haxoner (5 min.) 0. Lockout of Power-operated ESP Valves (PG&E65 (15 min.) VI. hROTSCTION ACAINST PROPAGATION OF DAMACE FROM PIRBS (PC6E)

VII. ELECTRIC POWER SYSTEMS (5 min.) A. Reliability considerations (10 min.) . 8. Shutdown capability with Los's of AC Power (PG&ES (10 min.) VIII.,EMBRO M CY PLAN

- A. Interaction / Coordination with , State .end 14 cal covts.

B. Instrumentation / Procedures to Pollow the Course of an Accident IX. CWER,ITW8 (aa appyopriat )

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Distribution:

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Docket File (2 R. W. Klecker LWR 1-3 File (2) M. Williams NRC PDR (2) F. Schroeder Local PDR R. Ucineman NRR Reading (M. Groff) R. Tedesco R. C. DeYoung . Stello V. A. Moore R. Maccary '

D. Skovholt H. Denton D. Muller V. Benaroya i

R. Denise J. Collins K. Goller G. Lainas W. Butler D. Ross J. Stolz T. Ippolito R. Clark J. Knight T. Speis S. Pavlicki D. Vassallo L. Shao K. Kniel B. Grimes

0. D. Parr W. Gammill A. Schwencer R. Ballard j R. Purple P. Fine 1 D. Ziemann T. Novak P. Collins M. Spangler l G. Knighton J. Kastner G. Dicker EP Project Manager - W. Ross l

B. Youngblood Project Manager - D. Allison/T. Hirons W. Regan J. Tourtelotte R. Vollmer L. Davis W. liouston P. Seiffert G. Lear IE (3)

V. H. Wilson ACRS (14) -

J. Wetmore D. G. Mcdonald M. Dunnenfeld P. Check F. Almeter P. Hearn F. Litton D. Fischer i

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