ML20155F589

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Notification of 740117-18 Subcommittee Meeting in San Jose, CA to Further Discuss Util Application for CP & to Inspect GE Test Facilities Used to Verify Containment Performance
ML20155F589
Person / Time
Site: Grand Gulf, 05000000
Issue date: 01/12/1974
From: Mckinley J
US ATOMIC ENERGY COMMISSION (AEC)
To: Okrent D
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20155E140 List:
References
FOIA-88-91 NUDOCS 8806160437
Download: ML20155F589 (6)
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ADVIS3W. COM.'.ilTTEE ON RE ^.CTOR SAFEGU ARD3 4 uni n:0 STNr?.U ~ mlC ENE.E CO'>iMIS3f GN W A ' h NGTo N. D.C. OGG Jcouary 12, 1974 ,

D. Ohrent, C'.u i r ;:- .

Grand Gulf S i::: .i:tec GRAND GULF Sti r XI! TEE MEETING, JANUARY 17-1S, 1974 The Grand Gulf Su'rcomittee vill meet at the Ryatt House Hotel, . in Scn Jose, Californic on January 17-18, 1974 to further concider the application by the Mississippi Power and Light Compcny for a permit to construe: Units i and 2 and to inspect General Electric test facilities used to verify containment performance. The tentative schedule is: -

Januare 17, 1974

8:30 101 Executive Session (Closed) 9:00 A'.i Meeting with the Mississippi Power and Light Company and the AEC Regulatory Staff (Open)

, 12:30 ?> L'2;CH 1:30 R: Resume meeting with the Mississippi Power and Light Company and the AEC Regulatory Staff (Open) 5:03 7M Visit General Electric test facilitics (Closed) 7:00 FM Recess ,

Januar: ::. li44 8:30 iM Executive Session (Closed) 9:03 ._*. Meeting with the Missiscippi Power and Light Cempany and the AEC Regulatory Stcff (0 pen) 12:30 P.' LL7;CH 1:30 PM Resume meeting wit;h the MLssissippi Powe cnd Light Company and the AEC Regulatory Staff '(Open) 4:30  ?*. Caucus (Closed) .

5:00 E! Su=ation (0 pen) 5:30 ?: Adjourn l 1

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D. Okrent January 12, 1974 s

Topics to be discussed incit.S:

1. Seismic design 3:ses (Thurs::ay morning)
2. Hydroser. generation and con:rol
3. tncer: sic:ies in recouc,: potter and paver distribution
4. Loss of ::a'_:n: accident and ECCS per formance
5. Potential curbine generated missiles
6. Reliabili:, of control rod design
7. Pressure 3 ppression system performcnce
5. Resolution of SUR generic items
9.  !!atters identified in Regulatory Staff Safety Evaluation Report
13. Seiscaic design considerations
11. Environmental considerations Topies may ':e added to or dele:ed from the cbove list at the discretion of :he Sub:0:=1: ee Chairman. Closed sessions may be held when proprietary ir. formation runt be censidered. Attendance by the following ACRS me.:J: r; and consul cn:s is cntic!. pated and hotel reservations have been made et the Hyatt 2.:use 2. c e l , 1740 !! . F ir s t S t r e e t , San Jose, California for the nights indi:::ed.

D. Okren: (J an. 16, 17, & IS) C. U. Solbrir, (Jan. 16, 17 & 13)

S. H. 3csh (J an. 15 & 17) T. G. Theo ferous (Jen. 16, 17 & 13)

L . *.J . F = (J a n . 16, 17 6.16) G. A. Thompson (!:one)

H. D. Cure: (:one) 1:. Trifunac (J e n. 16)

D. P., E'tsns (1one) J. T. Wilson (None)

B. M. Page (None) Z. Zudans (?!one) w

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< John C t;cK1.. ey Senior Staf f Assistri!-

cc: Listed or Scu e3

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Jar.ua ry 12, 1974 D. Okrent cc: ACRS !:enbers H. D. Cure t D. R. Evcns B. M. P0;=

S. S. Th 1 brick R. W. Shr sy C . U. S o '. r i ;

T. G. Tha:fsnaus .

G. A. T'.:: psen M. Trifuns:

J. T. Wilson F. Zalouie'.;

Z. Zudcns V. Moore, L R. DeYoung, L W. Butler, L

% % . Owsley, L J. Hendrie, L P. Morris , RO H. Kouts, L R. Tedesco, L 1

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GRAND GULF SUBCOn!ITTEE MEETINO, JANUARY 17-18, 1974, SAN JOSE,. CALIFORNIA l

Listed below are specific aspects of the topics to be considered at the Grand Gulf Subcommittee mee:ing, January 17 and 18. Other aspects or topics may be brought up by the Subcommittee or its consultants.

1. Seismic design bases
a. Descripti:n of the safe shutdown earthquakes ~

b .' Extent of :he New Madrid earthquake zone

2. Hydrogen genera: ton and control
a. Bases for hydrogen evolution rate (Regulatory Staf f)
b. Possible mechanisms which could lead to hydrogen generation beyond that calculated by the applicant for a double-ended pipe break ,

(Regulatory Staff and applicant)

c. Rel.iability of the system proposed for coping with hydrogen (Regu-latory Staf f)
d. Automatic or manual activation of hydrogen control system (Regula-tory Staff and applicant)
e. Capability cf drywell, etc., to withstand various hydrogen burning

. events (Regulatory Staff)

3. Uncertainties in power and power distribution (nuclear uncertainty factor) ,

4 Loss of coolant accident and ECCS performance

a. Evalua: ion of LPCI capability (without any consideration for core spray) (Regulatory Staff)
b. Means to ascertain potential blockage .of core spray nozzles over the reac:or's lifetime (Regulatory Staff and applicant)
c. Degree to which blockage of core spray nozzles is tolerable (applicant and Regulatory Staff)
d. Blowd:vn forces resulting from a LOCA -- any unknowns (Regulatory S ta f f)
e. Independent confirmation of the analyses by the Regulatory Staf f
f. Possible future improvements in ECCS (include flow rate comparisons of the several systems for BWR/4, 5 & 6, and reliability considera-tions (Regulatory Staf f and applicant)
5. Turbinc =issiles (turbine orientation end possible missile trajectories)
6. Reliability of new control rod design g.--- e- +- r --.- - e ,q-, = *v .cw,.-e .m.y-.v ------e.*v+y - - - - * --e m -- ---

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7. Pressure Suppression System
a. Forces on s true tures above the pool (Regulatory S taf f)
b. Extent to which e::perinental corroboration. is required' (1) ?rior to issuance of a construe:Lon permit (Regulatory Staf f)

(2) 7:10: to some later milestone (Regulatory Staf f)

c. Possible dyne =ic ef fects in the suppression pool resulting from relief cs'.ee discharge (Regulatory Staf f and applicant)
d. Role cf nrn-condensables and other phenomena in relief valve discharge to the suppression pool (Regulatory Staf f and applicant)
e. Possible dynamic leads on containment or drywell wall, .etc., from relief ;cl re operation (Regulatory S taf f and applicant)
f. Detailed description of the dynamic phenomenona important to the action of the suppression system in a 14CA (Regulatory Staff and applicant)
g. Role of non-condensables in item f above (Regulatory Staff and applicant)
h. Effec'ts of solid walls on the results of tests perforced in the seg=ent of a full-scale experimental facility (Regulat.ory Staf f and applicant)
i. Possibility of pool oscillations permitting an intermittent bypass path for steam from the drywell escaping into the containment. Are the experi.=ents adequate to study this phenomena or circumferential wave effects? (Regulatory Staff and applicant)
j. Role of non-condensables in the Moss Landing and Quad Cities test results
k. Drywell bypassing considerations. *
8. Resolution of generic ite=s (refer to the December 18, 1972 ACRS report -

and subsecuect ACRS reports)

9. Matters iden:if ed in the Regulatory Staff Safety Evaluation Report
a. Seis=ic classification of various syste=s and structures
b. Quality group classifications
c. Stress li=its and design loading combination
d. HPCS diesel generator reliability
e. Radionuclide concentrations in the refueling water storage tank f.- Freon deconposition potential ,
g. Main s tea =line isolation
h. Ma1 positioning of control rod (s)
1. Reactieity reduction follouing a reactor trip t i

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10. Seismic design considerations
a. How is a representa:L >e set of stresses obtained for a' given direction .ehen core thcn one code chape is considered?
b. How is reic:ive motion treated for "rigid" members -(base slao and walls)?
c. Is the use of "beam type" mode treat =ent completely acceptable?
11. Environmen:21 considerations:
a. Poten:ial doses to water drinkers downstream frora Grand Gulf f rom all cuclear plants upstream of the user (applicant)
b. Effects of f ailure in the radwaste storage system (Regulatory S ta f f)
c. Considera: ion of the ef fects of mining, preparation, and process-ing of fuel and radioactive waste storage (Regulatory Staff)

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