ML17244A564

Summary of 790410-11 Meeting W/Util at Site Re Systematic Evaluation Program Topic III-6,seismic Design

ML17244A564
Person / Time
Site:	Ginna
Issue date:	04/30/1979
From:	James Shea Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 7906260087
Download: ML17244A564 (14)

Text

Docket No. 50-244 APR3p )9;g LICENSEE:

Rochester Gas and Electric Corporation (RGGE)

FACILITY:

R.

E. Ginna Nuclear Power Plant

SUBJECT:

Summary of tleeting Held April 10-11, 1979 Representatives of the Nuclear Regulatory Commission (NRC) and RGGE met at the R.

E. Ginna site on April 10-11, 1979, to discuss the Systematic.

Evaluation Program (SEP) Topic III-6, Seismic Design.

A list of attendees is provided as. Attachment 1.

RGGE repi esentatives presented a revision 'to =the Equipment Description Table presented 3n-RGSE letter to NRC dated April 3, 1979, and reviewed briefly the systems and components required for safe reactor shutdown.-

-The RGIIE presentation was based on the information presented in the April 3, 1979 RG8E letter.

The newly installed recently activated Standby'Auxiliary Feedwater System located remotely from all pipes'ontaining high energy fluids was selected for the safe shutdown'eismic analysis because of its simplicity, availability of seismic information, and its,design in accordance with current NRC requirements.

The NRC representatives toured the Service Mater Pump House, Emergency Diesel Generator Annex; Battery-, Relay and Control Rooms, Hain'Transformer Yard, Auxiliary Building and Standby Auxiliary Feedvrater Building, Following the tours, NRC representatives discussed the preliminary assessment of pertinent information required to document sei'smic resistance capability of the R.

E. Ginna facility. It was noted that:

The NRC staff and its consultants have completed a review of the R.

E. Ginna docket for information pertinent to the seismic design bases of the facility and its capability to withstand the effects of potential earthquakes.

Copies of draft report entitled "Seismic Review of Ginna Nuclear Povier Station Unit 1 for SEP" were provided to RGSE.'he information currently in the docket is not sufficiently complete

-to assess seismic capability of the facility.

V 9 0636 0057 orrIcc~

OURNAMCW NRC FORM 518'9 76) NRCM 0240 J

I ~'

U I OOVOANMNNTTNINTINOOtrICNI IOT~

t<$

TI~

0 ~ ~ ~

~ \\ ~

'4

/

II 12 4

~

~

~

~

4 4

4

-. ~

4 4' 49

~ 2 4

S 9

~ Pt*

RP P

44 2'4

~

~

2 92 4 ~

~

P

~ I t

~

I~ et I ~

4 4 4,>(

~

~

4 42~ Vh 4

4 24P 4

2tl r

4 S

4

'll A

~

4 le P ~

4 4 ~ 9

'<'-~ = f 4

e 4

4 94 '."

hl-

~ 14 4

I

~

~

R

'h 4

4 4 ~ ~

PP

~ I'I I

ee ep*

eh

~

'h 2 "22J'l

~ 2 I

~

'I I

4 The following summary of the topics discussed is presented in the format of information required to continue,our seismic review'of the R. E. Ginna.

. facility:

I.=

" Seismic Anal sis and Desi n Criteria For structures required to document the seismic resistance capability:

Building t1odels - Mathematical models for determining seismic response (acceleration profiles, forces,

shears, moments, displacements) to input ground motions. for the following structures:

~

~

Containment Building, including containment internal structures Auxiliary Building Intermediate Building 4

Control Room - Turbine Building - Diesel Generator Room 4

~

1.

Information concerning these models should include:

'a ~

b.

C.

D'evelopment of lumped mass properties, including location of mass centers Developi'ng member stiffness Consideration of torsional effects of buildings d.

Interaction between seismic Category I structures and between seismic Category I and Non-Category' structures If dynamic models of the buildings are not available, the following information should be provided in sufficient detail so that the items tabulated in la - ld can be "

obtained to generate new models.

a.

Structural drawings showing framing details, layout of walls {concrete buildings), foundation details, location and weight of major equipment, etc.

orrIC434 4 OVRNAM4+

OAT4+

"I 4

4'

~

~ ~ ~ ~

~

~

4

~ ~

~ 4 ~

~

~

41 NRC FORM 318 (9-76) NRCM 0240

+ 0 U 4 OOV4IINM4NT~IIINTINOOPPICCI IOT~

TO ~

7 ~ 0

~ It P l P>>

~

tt l

~

E r

.Err lt 4 r>>,

E-E P

r

'l l

I E P

'PI>>)

~f'l h ~ P IPIPP p

~

~ 'I P

a

"* '.-=>>= '

l I

EP E

vtttth f',.'v'PP 'tiling l

>>l 4 ~ E>>l

= P

~

Er

~,

't'E l

F v

~ >

l ~

P h

EE E

E l 8 vrp

~

Ch,t ~

P

~Et't

~

~ ff>>

E -E

~

E Z-l: E P

~

I l

I

y f'

bb

',1

~

b.

Design.l'oads (distributed live load and dead load) c.

Haterial properties d.

Connection details between buildings II.

Seismic In ut to E ui ment Original input used for the analysis of systems and components (floor response spectra or other),

number of input components, combination of response, etc.

III. Hiscellaneous Desi n and Ana, sis To ics 1..

Design of structural masonry walls/reinforcement-details

'nformation, is required to assess the load carrying capacity of these walls and integrity of attached equipment.

2.

Compatibility conditions of containment wall and steel liner under seismic load (treatment of tangential shear) -,-

Original design calculations and/or test data is. required.

3.

Penetration design/capacity of buried piping to withstand relative motion - Information on the foundation of buried service water piping and penetration details is required.

RG&E agreed to provide the above specified information

'a-", <<t Hay 1, 1979.

IV.

Seismic Qqdlification of Hechanical,and Electrical Equipment and Fluid and Electric Distribution S stems II'eismic qualification documentation based-on analysis or testing of actual equipment or similar equipment to that installed at R.

E. Ginna fac~l,~ty,'for the follow'ng equipment related.to safe shutdowniis required.

1.

Generic'n crest - Items identified on th e walk through a.

Ess ntial service water pump - vertical=pump b.

Component cooling surge tank bb c.

Componen t cooling heat exchanger - Horizontal heat exchanger d.

Diesel generator air tanks Ol'4ICCW OIIIINAMCW DATC8t'.

Boric acid storage ank

-. Column upported.tanl b

HRC PORM 518 (976) NRCM 0240

+ U,t, OOVCIINMCNT*tNIN'FINOINbIbICCI It' t ~ ttt ttt

6

$ Stt 4

44 4

I 4

~ )

4

~\\

.4 44 \\>>'I'4

~

4

(

4

~

=

~

4 Nr'4 I

=6 4

2 tt It 6

44 AQ +

\\

~==

i" tl~ 4 I 4 r 4 4 ~

I t I

I 4

I

~

• t 4

~ 4

~

I

~ 4 4

4 t 444 4 ~

I 4

I

~4' pi-4

~ '

~4

~

r II

~ ~ f>>

~

~ 4 4 ~ 4

~ ~

-564 44 II t

I ri g= ~ '

~

I 4 Irtt

~t

~

~

~

4 4

4 4

ti 44 4

~ tt p tl

~i 4

4 44+44. g 4

~ ~

< ~

4 2.

f.

Refueling water storage tank g.

Motor-operated valves on lines

< 4"-diameter (electric or air-operated)

Generic Interest - Inside containment a.

Reactor coolant pump - support integiity/integrity of pressure boundary b.

Pressurizer

- support integrity/integrity of pressure boundary c.

Steam generator - support integrity/integrity of pressure bounday (including tubes and a tube sheet) d.

Control rod drive mechanism - housing integrity and functionability 3.

Potential Interaction of Non-Seismically gualified Equipment with Seismic Category I Equipment a.

Heating Ventilation Air Conditioning directly above electrical panel in Diesel Generator Room b,

Structural steel platform over oil line to feed pumps.

in Diesel Generator Room 4.

Mechanical Distribution Systems a.

RHR system (inside containment) - details of modal dynamic analysis with isometric drawing.

b.

Steam line (inside containment) - details of modal dynamic analysis with isometric drawing c.

Chemical Volume Control System (outside cootainment)-

details of equivalent static analysis using-peak of ground response spectr1~

d.

Sample field run of 2" diameter piping, ~ 100 feet Orl ICRW 6IIRNAII4~

OAT4~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

HRC PORN 318 (9-T6). NRCbf 0240

• U,S, OOV4NNMRNT RIIINTINOONNICNI ITTl I~ 4 1 ~ 4

~ g

~

U ht C"',K ll I.

1t

\\ ~

'C

~

~

~" 5.

Electrical Equipment

'a.. Battery racks b.

Control room panels c.

Switch gear d.

AC motor control center e.

DC motor control center f.

Criteria for lateral restraint of cable trays g.

Criteria for anchorage of Sa - 6e above

'I RGGE agreed to provide the specified information about May.15l7]979 It is anticipated that some of the information required for documentation may be available but not on the docket; however, other items will require the generation of some new information.

The development of this additional documentation should focus on the integrity of the reactor coolant pressure boundary and the capability of essential systems and components required to safely shutdown the reactor hand maintain it )8 a. safe shutdown condition during and after a postulated sÃsmic distuSance.

I'JNaICQ QLJ Th'omas Cheng Systematic Evaluation Program Branch Division of Operating Reactors

Attachment:

List of Attendees O~~~u James J. Shea, Project Manager Operating Reactors Branch 82 Division of. Operating Reactors cc w/.attachment:

See next page ORRICC~

OURNAMC.&

OATC~

DOR:ORB 2

JJShea:a 4/P(Y/79 DOR:SEPB TCheng gg.~

4/m /79

/9e DOR:ORB P2 DLZiemann 4//79 SEC PORN 318 (976) NRCM 0240

• U N OOVCRNMCNT RRINTINO OI'RICCI It) ~

CC ~

74 ~

~

~

I i 't h ~

4 l

CC Lex K. Larson, Esquire

LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N.

W.

Washington, D. C.

20036 Mr. Michael Slade 1250 Crown Point Drive

Webster, New York 14580 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.

P. 0.

Box 5236 River Campus Station Rochester, New York 14627 J effrey Cohen New York State Energy'ffice Swan Street Building Core 1, Second Floor Empire State Plaza

Albany, New York 12223 Directo'r, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue

'Rochester, New York 14604 "Mr. Leon D. White, Jr.

Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

NRC - SITE VISIT GINNA SEP - SEISMIC REVIEW APRIL 10, 1979 ATTACHHENT 1 RGSE R. Mecredy J.

Covey G.

Wrobel J.

Hung J. Larizza R. Smith NRC J.

Shea K. Jabbour H. Levin T. Cheng Westin house C. Lin F. Loceff R. Kelly Gilbert Associates P.

Shah E. Toll K. Nomose B. Bell

~ C.;

Chen D. Bi ss KMC, Inc.

J.

McEwen

'Woodward.Cl de/NRC Consultant J.

Stevenson Lawrence Livermore Lab/NRC Consultants R. Hurray J.

Weaver C. Liaw Southern California Edison R. Blaschke

RGSE T.

Weis J.

Covey J.

Hutton J.

Hung R. Mecredy G.

Wrobel R. Smith B.

Snow G. Daniels NRC J.

Shea T.

Cheng H. Levin K. Jabbour Westin house F. Loceff R. Kelly C. Lin Gilbert Associates C.

Chen P.

Shah D. Biss B. Bell K. Momose K M C, Inc.

NRC SITE VISIT GINNA SEP -'EISMIC REVIEW APRIL 11, 1979 Southern California Edison R. Blaschke

.J.

McEwen Lawrence Livermore Lab/NRC Consultants R. Murray C. Liaw NRC Consultant W. Hall Woodward Cl de/NRC Consultant J.

Stevenson

~

~

V 0 MEETING

SUMMARY

DISTRIBUTION NRC PDR Local PDR ORB 82 Reading NRR Reading H.

R.

Denton E.

G.

Case V. Stello R. Vollmer W. Russell B. Grimes T. J. Carter D. Eisenhut D. Ziemann A. Schwencer P.

Check G. Lainas D. Davis T. Ippolito R. Reid G. Knighton V. Noonan Project Manager OELD OISE (3)

H. Smith R. Fraley, ACRS NRC Participants J.

R.

Buchanan TERA N. Newmaik W. Hall J.

Stevenson

,R.

Kennedy F. Tokar tz R. Murray J.

Shea (l6)