ML20209C142

From kanterella
Jump to navigation Jump to search
Discusses 830502 Earthquake Near Coalinga,Ca Which Occurred 25 Kilometers from San Andreas fault.Non-Tech Spec Seismic Recorders Triggered on Low Level Ground Shaking at Diablo Canyon But Not at Rancho Seco
ML20209C142
Person / Time
Site: 05000000, Diablo Canyon
Issue date: 05/04/1983
From: Rolonda Jackson
Office of Nuclear Reactor Regulation
To: Knight J
Office of Nuclear Reactor Regulation
Shared Package
ML20209B094 List: ... further results
References
NUDOCS 8305240289
Download: ML20209C142 (2)
v • d • e


Text

-

b ^ ' ' ['i,, q,,,f.

'o UNITED STATES y

NUCLEAR REGULATORY COMMISSION i

njep,

wash NcTON, D. C. 20555 s.;

.e MAy 0 41983 MEMORANDUM FOR:

James P. Knight, Assistant Director for Components & StW ctures Engineering, DE

{

FROM:

Robert E:. Jackson, Chief-Geosciences Branch, DE

SUBJECT:

EARTHQUAKE NEAR COALINGA, CALIFORNIA A strong earthquake occurred near Coalinga, California at 7:42 p.m. EDT on May 2.

Considerable damage has been reported in the epicentral area.

Preliminary information available from the National Earthquake Information Service (NEIS), U. C. Berkeley and Cal Tech is as follows:

Origin time 23:42:37 GMT(NEIS)~

23:42:38.5(Berkeley)

Magnitude M =6.1(NEIS) m = 6.1 (NEIS)

M = 6.5 (Cal Tech)

Coordinates 36.2*120.2'W(NEIS) 36'14.7'N 120'15.8'W (Berkeley)

L Depth shallow (NEIS) 9 km (Berkeley)

This earthquake occurred on the west side of the San Joaquin Valley, t

l about 25 km from the San Andreas fault. A magnitude 5.1 earthquake occurred in the same area last October.

No faults are shown in this area on the California state geologic map. Geologists from the U. S.

Geological Survey and the California Division of Mines and Geology will explore the epicentral region to determine.if there was any surface faulting associated with this event.

Although the San Andreas fault is heavily instrumented, apparently no more than one strong-motion instrument was located in the near field of l

the earthquake.

Portable accelerographs are being installed to record strong ground motion from aftershocks, and portable seismographs are l

being installed to accurately locate aftershocks and determine aftershock focal mechanisms.

As of this writing, the only available acceleration measurements are frcm Diablo Canyon,110 km southwest of the epicenter.

Non-tech-spec recorders, with a very low trigger threshold, registered.006g on the base mat of Unit 2 containment,.008g at the water reservoir,.00689 at the spring inlet for Unit 1, and.0032g at the met tower. The tech-spec r

f

~Q n,m,

y W

  • 1 MAY 0 41983 recorders have a threshold of.01g and did not trigger, except for one unit which malfunctioned and went off scale. No alarm was sounded as a result of this instrument malfunction.

There is some question as to whether an alarm should have sounded when the non-tech-s'pec recorders triggered. The earthquake was also felt at Rancho Seco, 275 km north of the epicenter, but none of the seismic recorders triggered on the low level of ground shaking.

'Mr. Jeff Kimball, Seismologist, Seismology Section, is en route to the

~

epicentral area to investigate the extent of surface rupture,,1f any, and any damage to well engineered structures.

We are arranging with the U. S. Geological Survey and other investigators to be kept informed of the latest developments, and will update this memorandum as necessary, f

obert E.'

ack' son, Chief Geosci ces/ Branch, DE cc; H. Denton D. Eisenhut R. Vollmer J..McDermott L. Reiter S. Brocoum G. Bagch1 G. Lear P. Kuo P. Justus R. Bosnak V. Noonan B. Buckley H. Polk L. Beratan A. Murphy T. Schmidt J. Harbour GSB Staff W

i c,*

UT;;T E D sT.".T ES

  • UCLE A R R E G U L A TO R Y CC'.* *.". N'.

m.s-n.s:c e.s.c.:: u s

,r.

~

MAY.16 BB3 Docket No. 50-275 MEMORANDUM FOR: George Lear, Chief Structural and Geotechnical Engineering Branch

, Division of Engineering THRU:

ao-Tsin Kuo, Leader Structural Engineering Section 3

~

Structural ano Gectechnical Engineering Branen Divfsion of Engineering FROM:

Harold E. Polk, Structural Engineering Section B Structural and Geotechnical Engineering Branch Division of Engineering SUBJECi:

iRIP REPORT FOR IDVP/PG&E TECHNICAL INTERCHANGE P.EETING-MARCH 29 AND 30, 1983 FOR DIABLO CANYON REVERIFICATION On 's rch 29 and 20 two members of the staff, P. T; Kuo and Harold Folk of

he 23EE and A. J. Philippacopoulos of Erco.Whaven National Laboratory attended a technical interchange meeting between the Independent Design

'ierification Program (IDVP) staff and FG&E Diablo Canyon Project (DCF) staff.

Attendance lists for both days of the meetings are attached..The areas discussed were the DCP progress in the analysis of the Turbine Building and the Containment Annulus Steel Structure and the Auxiliary / Fuel Handling Suilding.

TUR5INE BUILDING The results of the Turbine Building seismic analysis was discussed by the DCP. Although the Turbine Building is a seismic Category II structure it contains seismic Category I equipment and systems, therefore, it must be cemonstrated that the building will not impair the function of these systems during a seismic event. This requirement is satisfied by analyzing the structure and showing it will withstand the postulated earthquake without failure.

The Turbine Building is a combined steel frame and reinforced concrete structure.

The reinforced concrete structure is below elevation 140 feet, the operating floor, and the steel frame structure is above the elevation 140 feet floor. The structure is approximately 400 by 140 feet in plan and is approximately 125 feet tall.

The structure is founded on the underlying bed rock and is independent of the turbine pedestal.

b Q

3 b

O n o5

~

3 :rge Lesr The scope of work-carried out by the DCp was to review the asbuilt drawings, perform onsite inspections, perfom seismic analysis in 3 directions for the Mcsgri earthquake, perfoon seismic analysis in 2 horizontal directions for the

. ~

DE and DDE events, review structural members for loads and stresses and modify the structure where necessary. The provisions of the SEAOC 1974 and ACI 318-73 building codes were used for the review of the reinforced concrete portion of the structure. The AISC 7th edition building code, Part II was 9

used for the structural steel portions of the structure. The review utilized tre actual material properties for the HOSGRI event, while the code design material prc;erties were used for tne CE and DDE events.

. cr the h:rizontal seismic evaluations, earthquake input time histories were

eveloped frca both the Newmark and Blume ground response spectra.

For the vertical seismic evaluations, only one time history based on the Necark vertical ground response spectra was used. The reason for this is that the Ns.emark spectra envelopes the corresponding Blume spectra for the vertical direction. To account for accidental torsion the horizontal ground motion input acceleration values were increased by 10%.

e s.-- a:f cn of the modal responses was based on the double al;ebraic sum e:ncd instead of the double absolute sum or the square root sum of the sc ares (SRSS) metnod.

The DCP was informed by the s:sff that the double al;ebraic sum method is not reccgnized by the staff as an acceptable method to sum the medai responses.

The modifications to the Turbine Building consisted of stiffening a beam at column line 6, between column lines 4 and 5, elevation 119. This modification was.ade to reduce the floor response spectra to match the qualification response s ectra for the 1.6 KV switch gear.

The ccmpression material that was used in the gap between the turbine pedestal and the turbine building at the north and south ends was removed to prevent pedestal to structure interaction. The pedestal to building separations are greater than the absolute sum of calculated maximum pedestal and building displacements. No modifications were required for the Turbine Building Crane.

Eight bolted connections in the lower chord bracing in the Turbine Building roof trusses exceed the allowable stresses in the AISC edition 7 and AISC edition 8 structural steel building code.

The AISC edition 8 code allows higner stresses in bolted connections which are based on test data using finger tight bolts.

If the clamping forces for torqued bolts is considered, the bolted joints are capable of withstanding the imposed loads.

Furthemore, if the model used to predict the member forces is refined the forces would be reduced and thus could meet the AISC edition 8 allowables.

c-:

e Letr.

CO:iTAltiP.ENT AN ULUS The status of the seismic evaluations of the containment annulus structure in' the horizontal, vertical directions as well as mass ratio _ studies were discussed. For the horizontal direction detailed uncoupled models of the three lower floors were being used to obtain mode shapes and frequencies.

The objective of this analysis is to stiffen the floors in the horizontal

~

direction so that structural frequencies higher than 20 Hz can be obtained.

'he vertical evaluations have been completed.

Floor respons'e spectra were ger.erated in this direction using two dimensional frame type acdels.

" ass ratio studies have been undertaken in order to assess the significance of coupling between tne piping systems and the annulus structure.' The appr cach used consists of adding single degree-of-freedom, oscillators which represent the piping sys.tems onto the two dimensional vertical frame models. Floor s:ectra are then generated with the masses in place. This procedure for.

deveicping floor spectra has as yet not been accepted by the staff. The current practice is a decoupled analysis ir.cluding only the mass of the 3.bsystems.

P.7:L:ARY/F'.:EL HA*;2LI ;3 SUILDING.

Results of geotechnical studies were presented with particular emphasis on the upper and lower values of the shear wave velocity. DCP'also presented sensitivity studies on soil springs which they claimed shewed no effect on tne response of the Auxiliary Building.

Several questions raised by the IDVP were brought up and discussed towards the end of the meeting. They dealt specifically with RFI questions pertaining to the Fuel Handling Building's sections given in the Phase I Final Report.

W Y

Harold E. Polk, Structural Engineer Structural Engineering Section B Structural and Geotechnical Engineering Branch Division of Engineering

Attachment:

As noted cc:

R. Vollmer A. Philippacopoulos, BNL

0. Eisenhut

. Miller, BNL J. Knight

. Schierling P. Kuo B. Buckley M. Reich, B?il H. Polk

s

- s g.

-=

r.

l :

\\

.]

g e

d 2

Y

(

a

_ g u.J -

J (.. ::

ydq

% r y *

'N,g %kM ;-:

L W

2 p.3 -

?.'yr*

n.t

. r

'l Q

W

'
s.

m a

1

~

\\ J V

y w

.:2s$h

?.

QQ2e

~.

e 7 7 Q, c d

  • a;; y i

L E

.Y,.,.D

$ <C I

..g M (- 'h N I

' =

w

, M n.

3. u a

C.5--3 N 's._:, Q O

s

,N

'8.*

s

'c tL. q yM L

-=.

s

>=

l i.s

  • =

l

~

s

$'d k

w- + ii? !(D N l (a dr S%' k ( f ;q

% n.i g

q G

um Vvc.

4 w

g4 w

w i

s h N $ 0 k k 9,O s SO I

k

  • 4 k

a s ss x

1 D4

. s g

sk r.

h l TI'. I n.i. -

~

Uk -}

(,

S m

j

,,.6

.- j 4

Uz 4 4 y.

% -s A.s 7,2 ~

Q, 2 d

5l k

b T'%

wk

,a

  • 3Y.-

bN I

i 0

N a

u

'>% c w

$, V m %

~7 k,- 3 "o %:

W S

1 4-).

  • v

.q %

Os s

s v

T - N,y b.

.s 4

O h s

s v r

s Ik vl

.k h O s a) t n.1 4

t

.s., e 1 :>, %. 1, 6,d N. '

- i

~~.

s, 2

..a-e z

~

s 0; c1 g

<h hn, s

-s a v c.v a - -

c>

d

'N

\\C

=,-.

2 1

c'.2 -; y t

y u:

    • <e Q g VQ:>

Q N % * $, i' 67

=

d

r f.

..t.:..

n

=

E-a

~W

~, I.

-~

9,;

..J g.

.j' @ w.c G

.J ~

L\\*

. g *c *,$

2

  • T } hr-

-S /s/

-ea w

e g

9 9

r d.

,/.:

s:

EI e

I b A

"E

.M --

e,,

a

.T i il i V'

d

. g'g i

c y

o 1

. e u,.,.

d

.q'

'i

'J* '

""4l*

i

+

i i

l i

i l

l.

I.

- i g

i.

{ [. j t

i h]ID l

j.,*,)

si l

l

  • ' t

~~

k

- r. w. w.

s.

i w

I s

N l

i c.$ r),. v.!' :.

6

't c.

re.

O N,,,

I NI

'4:

\\ IO. Q,

i i

\\

j.

4 4,,l t.,

1 N

.[*

J

r T.

4 g

g

-: 2 c..

M t

~

' %p.

s x

.A s

3 1

I-D

. Nl g v...~

,3 d

@ - }

3. --

. (.

. b.

'.4. ' -=

/)

. L.0-

/g

.d } 9 =te

- (Q.- !

.:.w= x-

- 2.

p 1:

~; y y G M4%% &us q q d<.dl eg.

4 i

rhh h Y 5 h E'.E' N.$ k $W-?Y hW k.

.a 4

g

~

~a u..

W.

-Q

.=

6 w

E-v r.

.a...

1~,

p.-

Q l

l l

,i s

3

.p.

y y_.

9 z.

s Q,q.

y

..i.

q-

4 y.
a.:

~

1 ey..

k I

D

.a-

~

  • 2 N

T[

b}.. i (,
d d 19 3 S-e J

'E i

ec 3

$....'n,. b J j

,.d y'

Qi s

tt

'i y.J

\\

g-T y- -

4 s ' M-..i.

3 g-6 N

[ t;7 'i 9! :' i, d%.E. *3 iHI w T'{W.:

3 I

I.as "1 9l

-4

)N 1 N; %.=.ee 2 "I ?;J,i.@.:i 4 '

56 r

t
W:

i i

e- :

V.,.

=x

m. ::.

,-; s :::%M. '. ', 3 g C

.f. ':'.g % ; -::Tc. M p.J

, "!.S:

b_

C ;-

- l.s t

.:t

,i f*# "*N UMTED STATES r'

4 NUC, LEAR REGULATORY COMMISSION waswswovow, p. c.nossa MAY 181983 Docket No.: 50-275 MEMORANDUM FOR: Chairman Palladino Comissioner Gilinsky Comissioner Ahearne Comissioner Roberts Comissioner Asselstine FROM:

Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation

SUBJECT:

INFORMATION ITEMS REGARDING THE-DESIGN VERIFICATION PROGRAM FOR DIABLO CANYON, UNIT 1 (Board Notification No. 83-69)

In accordance with the present NRC procedures for Board Notifications, the following items are enclosed for information of the Commission:

1.

Stone & Webster Engineering Corporation, ITR 25 Rev.1, " Verification of the Auxiliary Feedwater System Electrical Design," dated May 2,1983.

2.

Stone & Webster Engineering Corporation, ITR 26 Rev.1, " Verification of the Control Room Ventilation and Pressurization System Electrical-Design," dated April 29, 1983.

3.

Transcript of Meeting between NRC and PG&E on May.4,.1983 in San Francisco on schedule and allegations regarding Diablo Canyon design verification program.

The enclosures provide information on the status of activities performed '

under the design verification program for Diablo Canyon Uni.t 1 by the participating organizations.

The information is relevant to the safety issue on the design adequacy of Diablo Canypn Unit 1.

This is the subject of Commission Order CLI-81-30.

~

M

(.

Darrell G. Eisen

, Director Division of Licensing Office of Nuclear Reactor Regulation

Enclosures:

As stated cc:

See next page

Contact:

H. Schierling, NRR xt. 27100

~

h 3fF

s 2-i cc:

J. F. Wolf, ASLB G. O. Bright, ASLB J. Kline, ASLB T. S. Moore ASLAB W. R. Johnson, ASLAB J. H. Buck, ASLA8' SECY QGC OPE E%

Parties to the Pmceeding e

I 4

es t

M s

e 9

-.---v

,-.7

,.-.-m----

,y-y w-

-r------ - - - - -. - - -

-n----

-.--.----n--

ve ;V'

    • s-3-

n,

\\

'r DISTRIBUTION LIST FOR BOARD NOTIFICATION

. 2 2

Diablo Canyon Units 1&2 TL, -

1 Docket Nos. 50-275/323 OL ACRS Members 3

Ms. Elizabeth Apfelberg Dr. Robert C. Axtmann :g Mr. Richard E. Blankenbu'rg Mr. Myer Bender Mr. Glenn 0. Bright Dr. Max W. Carbon

~

Mr. Herbert H. Brown Mr. Jesse C. Ebersole,

'?

Dr. John H. Buck Mr. Harold Etherington

? ts Philip A. Crane, Jr., Esq.

Dr. William Kerr

(

Mr. Frederick Eissler Dr. Harold W. Lewis ~~,J:

't David S. Fleischaker, Esq.

Dr. J. Carson Mark Mrs. Raye Fleming Mr. William M. Mathis,_

e Arthur C. Gehr, Esq.

Dr. Dade W. Moeller Mr. Mark Gottlieb D'r. David Okrent. -

Mr. Thomas H. Harris Dr. Milton S. Plessst '

Mr. Richard B. Hubbard Mr. Jeremiah J. Ray o,

Dr. W. Reed Johnson Dr. Paul C. Shewmon

/

Janice E. Kerr, Esq.

Dr. Chester P. Siess Dr. Jerry Kline Mr. David A. Ward Mr. John Marrs Thorus S. Moore, Esq.

Bruce Norton, Esq.

Joel R. Reynolds, Esq.

Mr. James 0. Schuyler

~.

Mr. Gordon Silver'

^ l.

Michael J. Strumwasser, Esq.

' ~

..c Paul C. Valentine, Esq.

s Harry M. Willis s'

i John F. Wolf, Esq Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel i

Docketing and Service Section e

Document Management Branch

}

es

~

1 5'

4

.g I

'M

^

~.

n 1

1

.s i

' y

y"i l

p mee

+

UNITED STATES

%j,'

,9 NUCLEAR REGULATORY COMMISSION a

D E

WASHINGTON. D. C. 20555

/j 4

o,

%e PAY 311M3 Docket No.: 50-275 o'

l

%[

MEMORANDUM FOR: George W' Knighton, Chief, Licensing Branch No. 3, DL 1 :: <

FROM:

Hans Schierling, Project Manager, Licensing Branch No. 3, DL i

3

SUBJECT:

NRC MEETING WITH WESTINGHOUSE AND PG&E ON MAY 20, 1983 0';

SEISMIC QUALIFICATION OF A MAIN CONTROL BOARD FOR DIA3LO

( }7 CANYON UNIT 1 e

. Z-e A meeting was held on May 20, 1983 regarding the seismic qualification of the Diablo Canyon Unit 1 main control board (MCB). Participants at the meeting were the NRC staff and representatives of Pacific Gas & Electric Company (PG8E) and Westinghouse (W). The Governor of the State of California (party to the g

Diablo Canyon licensing proceedings) was represented by a technical consultant.

A list of attendees is attached.

A summary of the issues discussed is cresented

'~

below.

(/ -

The MCB for Diablo Canyon Unit 1 was procurred by W for PG8E in accordance with equipment specifications (E-Specs) prepared by W in 1971 (Note: the same process was follcwed for Unit 2, however the discussions at the meeting were specifically

~ directed to Unit 1). The E-Specs required that the MCS be qualified to an l'

acceleration of 1 g in the horizontal and 0.5 g in the vertical direction with stresses within allowable limits, and for 2 g horizontal and 1 g vertical with stresses not exceeding the yield point. The MCB was designed and constructed by Reliance and an analysis of the MCB was performed by a consultant to Reliance.

According to this original analysis the lowest calculated natural frequency of the MCB was above 70 Hz, based on a simple analytical model. Stresses were calculated to be well within the specified limits. The axial load in one of the bracing members slightly exceeded the allowable load, and the consultant's report recommended addition of two bracing members to each end frame.

In 1977 the MCB was evaluated with respect to the Hosgri earthquake. The revised seismic input at the base of the MCB produced a 1.55 g horizontal and 0.81 vertical acceleration, both of which are lower than the original E-Spec

. values. Thus the MCB was found acceptable for the Hosgri earthquake without

_' need for modifications.

CAs part of the current seismic design verification effort, PG&E is evaluating

'the seismic design for all safety-related structures, systems, and components, and W is evaluating those safety-related systems and components within the W e

. scooe of supply for which the seismic input has changed as a result of the PG&E effort. New floor resoonse spectra for the auxiliary building (referred to as current Hosgri spectra) were fowarded by PG&E to W.

These spectra indicate higher

-values of the zero period acceleration (IPA) for the vertical direction, namely

,T

  • 1.45_g as compared to the original qualification IPA of 1.0 g.

.a Ew

\\

l fp l*

j,

v i

j i

k.(

2-w

f W modeled the MCB using recent field measurements and results of in-situ tests. The tests pointed out the existence of natural frequencies between 15 Hz to 25 Hz, i.e., much below the lowest natural frequency of 70 Hz
  • l' originally calculated. W has proposed modifications to the MCB (addition j

of plates and channels to"the top of the MCB) in order to strengthen the beam q

property of the MCB and thus yielding higher natural frequencies. The staff i

requested that W verify that the compressive loads in bracing members of the modified MCB are below the buckling loads with adequate margin.

W also evaluated the seismic quaifications of devices mounted on the MCB using as input the current Hosgri spectra at the base of the board in the 15 Hz to 33 Hz range. The floor response spectra, enveloping the DDE and Hosgri spectra, j

were used to generate device input spectra by transient analysis. The devices were tested on a shake table at the maximum expected level. Some modifications such as strengthening of device mounts and restraints are expected. Except for the auto / manual station the major effort on testing has been completed. The staff requested to be advised of the schedule for any further testing. Some non-Class i devices are also being analyzed for structural integrity and modifications to some mountings are anticipated.

Mr. R. Hubbard, consultant to the Governor of the State of California provided' the following comments at the conclusion of the meeting: (1) cooies of the documents that were reviewed by the staff during the meeting will be requested; (2) the IDVP provides specific criteria for acceptability of, for example, stresses changing by more that 15 percent; (3) the current W evaluation should not be limited to those cases where.the input spectra have changed; (4) the root cause of all deficiencies should be identified and (5) there is a need to look not only at the product of the evaluation but also at the process of the evaluation (see transcript pages 116 and 117).

r During the course of the meeting the staff briefly reviewed some of the original specifications and reports (5 documents as identified on page 120 of the trans-cript) some of which contained W proprietary infonnation. The staff commented at the conclusion of the meeting that the ongoing W evaluation effort had not been reported in sufficient detail by PG&E during the course of the design verification and requested that more information be included in future PG&E l

semi-monthly reports and that the entire W effort, including an evaluation and assessment of any root causes, be addressed in the PG&E Phase I Final Report.

l

[i h)

Hans Schierling, Proje t Manager Licensing Branch No. 3 Division of Licensing

Enclosures:

As stated M

d cc w/encls.:

See next page

.]

n l

w mm2 yw--w w

--- - - -w

  • y y+yy

-yvw yy--y-yw

--w-,,-

yww w

w g'

w--

--wa-.--.

e

o 4

L Diablo Canyon

'l Philip 4. Crane, Jr.,-Esq.

Facific Gas & Electrics Comcany Post Office Cox 7442 San Francisco, California 94120 cc: Mr. Malcolm H. Furbush Vice President - General Counsel Resident Inspector /Diablo Canyon NPS Pacific Gas & Electric Company c/

U. S. Nuclear Regulatory Commissio2 ia eac California 93424 SnFac co Ca ornia 94120 danice E..Kerr, Esq.

Ms. Raye Fleming California Public Utilities Commission 1920 Mattie Road 350 McAllister Street Shell Seach, California 93440 San Francisco, California 94102 Joel Reynolds. Esq.

Mr. Frederick Eissler, President John R. Dhillips, Esq.

Secnic Shoreline Preservation Center for Law in the Public Interest Conference, Inc.

10951 West Pico Boulevaro 4623 More Mesa Drive Third Floor Santa Barbara, California 93105 Los Angeles, California 90C54 Ms. Elizabsth Apfelberg Paul C. Valentine, Esq.

1415 Cazadero 321 Lytton Avenue San Luis Obispo, CA 93401 Palo Alto, California 94302 "r. Gc-den A. Silver Mr. William E. Cooper

s. Sandra A. Silver Project Manager - 5511 1750 Alisal Street.

Teledyne Engineering Services San Luis Obispo, CA 93401 130 Second Avenue Waltham, Massachusetts 02254 Harry M. Willis, Esq.

Seym ur & Willis Herbert H. Brown, Esq.

fC' Califc-nia Street, Suite 2100 Hill, Christe;her & Phillies, P.C.

San Francisco, CA 94108 1900 M Street, N.W.

Washington, D. C.

20036 Mr. Richard Hubbard MH5 Technical Associates Mr. Dick Blankenburg Suite K Editor & Co-Publisher 1725 Hamilton Avenue South County Publishing Comp,any San Jose, CA 96125 P. O. Box 460 Arroyo Grande, California 93420 Mr. Jonn Marrs, Managing Editor San Luis Obispo County Telegram Tribune Mr. James 0. Schuyler 1321 Johnson Avenue Vice President - Nuclear Generation F. 0. Box 112 Capartment San uis 0:ispo, CA 93405 Pacific Gas' & Electric Company 77 Beale, Rocm 1451 San Francisco, California 94105 N

T..:

i

?

i4 41

~

y 3

j ENCLOSURE 1 t

LIST OF ATTENDEES g'?

MAY 20,1983 MEETING, MONROEVILLE, PA.

,)

" SEISMIC QUALIFICATION OF MAIN CONTROL BOARD -

-n 1-DIABLO CANYON UNIT 1" NRC:

J. P. Kntght if. E. Schterling G. Bagchi H. Polk

-W:

T. Esselman I. Yanus J. Hoebel C. W. Liu W. T..Bogard W. C. Gangloff T. K. Basu PG&E:

J. Hoch W. H. White R. A. Bitting Others:

R. Hubbard (State of California)

O e-

{

l A:

7 ik 7

.y*

l

..8 N

l w

=l

.o.,

MAY 311983 IE10RANDUM FOR: Chainnan Palladino Comissioner Gilinsky Comissioner Ahearne s

Comissioner Roberts Comissioner Asselstine FROM:

William J. Dircks Executive Director for Operations

SUBJECT:

STATUS OF DIABLO CANYON DESIGN VERIFICATION EFFORT Per your request, enclosed is a sumary of the status of the Diablo Canyon design verification efforts by PG&E, the IDVP and the staff.

In early May, PG&E infonned us that engineering effort and construction of modifications required'to be completed prior to fuel load authorization have fallen behind schedule (four weeks in some areas).

(Signse Elflam J.Bircks i

William J. Dircks Executive Director for Operations 1

Enclosure:

x as stated SECY cc:

s OPE OGC

'l

\\

1 i

s

'i

Contact:

H. Schierling, liRR 492-7100

'$ cya!d$

  • See previous concurrence:

m.'s% f

[m},, /

..NRl ED0.......

LB#,3 L

/

AD/L*

DL:D*

o,,,c,,

H c${,,,,,,,,,,,,,,,yt[,,,h,j,,p,,ht,o,n

,M,,g,y,a k_,,,,,,,,

,DGE,1,s,,e,n,I ut.

.#.9 j.#A.

..HRE ton.... WJDir:cks sua-.s[]5g!/s3 ing:

l

. 5pJ.L8.3........ 5.l....Ra........51...1n....

5 4 1.a3

.. 5/..)

3...

... 5L...Ls,3,,,,q m.

OFFICIAL RECORD COPY usam mi Nac ronu sta no-m uncu ano

ENCLOSURE s

DIABLO CANYON DESIGN VERIFICATION PROGRAM STATUS REPORT - MAY 6, 1983 I.

Schedule This status report is based primarily on information contained in the Teledyne semi-monthly IDVP report dated April 22, 1983 and the PG4E semi-monthly report dated April 22, 1983 and on information provided at an NRC - PG&E - IDVP status meeting on May 4,1983. The PG8E projected schedule for commencement of fuel loading (i.e. Step 1 in Commission approved licensing process) remains as June 30, 1983. However, PGAE stated at the May 4 meeting that some activities, both engineering and construction of modifications, that are required to be completed for Step 1 are on a critical path and are as much as four weeks behind schedule. Thus far the impact has not been reflected in a revision'of the Step 1 date. Similar critical path elements have not been identified for the dates for initial criticality (Step 2,7/15/83) and issuance of a full power license (Step 3,8/15/83). The dates remain unchanged.

It appears at this time that essentially all engineering activities and construction of most modifications for Steps 1, 2 and 3 will be completed at about the same time.

II. PG&E Effort PG&E updated its Phase I Final Report on April 22, 1983. Two additional updates are scheduled for mid May and mid June. The report covers the PG&E seisnic design verification efforts for all safety related structures, systems and components and the IDVP review and evaluation of these activities.

The report also covers the IDVP quality assurance audit of seismic service related contractors.

PG&E has completed the seismic verification analysis, horizontal and vertical, j

of the containment annulus steel structure and the necessary modifications j

are in progress. The modifications are approximately 70 percent complete.

The. seismic qualification of Class I systems and components is currently being verified using the revised horizontal spectra. At a meeting on April 27-28, 1983, PG&E discussed with the IDVP the status of other containment i

structure verification efforts (containment shell, base slab and connections to shell, equipment and personnel hatches, reactor cavity wall, crane wall, i

concrete floor at elevation 140 feet and polar crane). Most of the engineering efforts have been completed. Additional modes for potential uplift will be considered for the polar crane evaluation.

III.

IDVP Effort Teledyne issued on May 2,1983 the first part of the "Diablo Canyon Nuclear Power Plant Unit 1 - Final Report - Independent Design Verification Program."

Teledyne will not issue separate final reports for Phase I and Phase II of the IDVP activities. Four additional installments to the single IDVP report are scheduled with the last one due at the end of June.

- I.

. ine following E0I information for. Phase I and Phase II is based on the I;VP semi-monthly report of April 22, 1983. The information from our previous report is also listed for comparison in parentheses (Note:

previous infomation has been corrected).

. Phase I Phase II Construction QA Total 202(201) 72(72) 29(29)

Errors 15( 15) 8( 8) 1( 1)

Non Errors 187(186) 64(64) 28(28)

F.esol ution Resolved oy : dip 166(181) 61(53) 29(29)

Evaluatien Cngoing 16( 20) 11(19) 0( 0)

Tne Phase I efforts of the IDVP have essentially been completed. The main effort continues to be the review and evaluation of the PG8E design verifi-cation of safety-related structures and equipment on the basis of PG&E responses for e:uest for information by the IDVP. The Phase II efforts cf the IDVP are ongoing.

The design verification of redundant equipment in safety syste s is nearing completion. The evaluation of the other f:,- areas selectec for acaitional verification and sampling requires 3.-:ber revie...

e IDVP issues t,:0:TR's on the audit of the quality assurance program r; its inM e entation during the construction of Diablo Canyon. The tas i

u te 1::':'enal infornation on both recorts.

lis:':; ;' i.. :T:'s taat have oeen issuec.

5 aff Effort T*e staff is c:ntinuing its review of ITR's issued by the IDVP, the PG&E Pnase I Final Report supplements and revisions, the PG&E Phase II Status Report and the recently issued IDVP Final Report. The Safety Evaluation Report (SER) will be based on our evaluation of these documents and on information obtained at technical PG&E/IDVP meetings. At this time there 4

is sufficient information available to initiate our preparation of the SER although it cannot be completed until all the necessary information is been su ?' :e:. As stated earlier the PG8E effort with respect to 5 sp 1 reqct re.e-ts, both engineering and construction of modifications, is expectec to slip by about four weeks.

w 7

,na eg

-r--,,,--,-ww,

-y.

m

. On March 28, 1983 we were informed of eight anonymous allegations regarding the adequacy of the Diablo Canyon design verification effort (Board

{

~

Notification 83-48). We have not succeeded in obtaining additional details l

on these allegations"(Board Notification 83-61). PG8E informed us at

)

the May 4 meeting that, based on the limited information provided in the allegations, they have concluded that some of the concerns are being addressed in the ongoing design verification program, but for most of the allegations there is no basis. The staff will continue its evaluation by also.considering the information provided by PG&E.

l

'In late March, Region V interviewed an individual who had made statements regarding inadequate quality control of welding procedures and the qualification of welds. A similar interview was conducted by the Office of the Attorney General of the State of California.- Transcripts of both interviews were issued as a Board Notification. Region V is evaluating the technical aspects of the allegation.

The parties to the D'iablo Canyon licensing proceeding presented on April 14,1983 oral arguments before the ASLAB. On April 21, 1983 the ASLAB ordered the record reopened on the issue of design quality assurance.

The admission of the issue of construction quality assurance has not been decided.

O I

s INTERIM TECHNICAL REPORTS (ITR)

ITR - 1 Additional Verification and Additional Sampling, RLCA Rev. O, June 6,1982 I

Rev. 1, October 22, 1982 ITR - 2 Evaluation of Quality Assurance Program and Implementation Review, TES Rev. O, June 23, 1982 9

ITR - 3 Tanks, RLCA Rev. O, July 16, 1982

TR Shake Table Testing, RLCA

~~

Rev. O, July 23, 1982 ITF - E Design Chain, RLCA Rev. O, August 19, 1982 179. - 6 Auxiliary Building, RLCA Rev. O, September 10, 1982

. ITP.

Electrical Raceway Supports, RLCA

.Rev. O, September 17, 1982

TR - E Verificaticn Progran for PG&E Corrective Action, RLCA Rev. O, October 5, 1982
TE - :-

Develcpment of the Service Related Contractor

.ist of Non-Seisric Design Work Performed for DCNPP-1 Pric" to June 1978 - Phase II, RFR'

ev. O, OctcSe* 15, 1982
TR - 1.

.erificaticn of Design Analysis Hosgri Spectra, RLCA Rev. O, Octcber 29, 1982

TR - 11 Pacific Gas & Electric / Westinghouse Seismic, TES Interface Review Rev. O, November 2, 1982 l

ITR - 12 Piping, RLCA Rev. O, November 5, 1982 ITR - 13 Soils - Intake Structure, RLCA Rev. O, t,'ove-ber 5,1982

ITR - 14 Verification of the Temperature, Pressure, Humidity and Subemergency Environnents Used for Safety-Related Equipment Specif" ation Outside Containment for Auxiliary Feedwa-System and Control Room Ventilatiop and 4rization System, SWEC Rev. O, December iS2 ITR - 15 HVAC Duct ad Supports Report, RLCA Rev. 0,-December 10, 1982 ITR - 15 Soils - Outdoor Water Storage Tanks, RLCA Rev. O, December 8, 1982 IT. - 17 Piping - Adcitional Samples, RLCA Rev. O, December 14, 1982 ITR - :3 Verification of the Fire Protection Provided for_ Auxiliary Feedwater System, Control Room Ventilation and Pressurization System, Safety-Related Portion of the 4160 V Electric System, SWEC Rev. O, December 13, 1982

TR - 19 Verification of the Post-LOCA Portion of the Radiation Environments Used for Safety Related Ecuipnent Soecification Outside Containment for Auxiliary Feedwater System and Control Room Ventilation ar.d Pressurization System, SUEC Rev. 0, Decender 16, 1982
TR -

Verification of the Mechanical / Nuclear Design of s Co.t -i Ror-Vertilation and Pressuri eticr. Systen, S'JEC 7 5c..,

e:1 cr if, 15E2 Rev.1, April 25,1933

TR - 21 Verification of the Effects of High Energy Line Cracks and Modera e Energy Line Breaks for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System, SWEC Rev. O, December 15, 1982 ITR - 22 Verification of Mechanical / Nuclear Portion of the Auxiliary Feedwater System, SHEC Rev. O, Decenber 17, 1982 Rev. 1, April 25, 1983

~

ITR - 23 Verification of High Energy Line Break and Internally Generated Missile Review - Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System, SWEC Rev. 0, December 20, 1982 ITR - 24 Verification of the 4160 V Safety Related Electrical Distribution System, SWEC Rev. O, December 21, 1982 ITR - 25 Verification of the Au.xiliary Feedwater System Electrical Design, SWEC Rev. O, December 21, 1982 Rev. 1, May 4, 1983 ITR - 26 Verification of the Control Room Ventilation and Pressurization System Electrical Design, SWEC Rev. O, December 21, 1982 Rev. 1, May 4, 1983 ITR - 27 Verification of the Instrument and Control Design of the Auxiliary Feedwater System, SWEC P.ev. O, Decenber 23, 1982

TE - il Verification of the Instrument and Control Design of the Control Room Ventilation and Pressurization System, SWEC Rev. O, December 23, 1982
al Semrie, SLE:

- 3:';- :-zi-Re..

, J anua ry 17, 1983 ITR - 3C Snail Bore Piping Report, RLCA Rev. O, January 12, 1983 ITR - 31 HVAC Components, RLCA Rev. O, January 14, 1983 v-- - -

,r y

-r

ITR - 32 Pumps. RLCA Rev. O, February 17, 1983 Rev.1, April 1,1983 ITR - 33 Electrical Equipment Analysis, RLCA Rev. O, Febrary 18, 1983 Rev.1, April 29,1983 ITR - 34 Verification of Diablo Canyon Project Efforts By Stone & Webster Engineering Corporation, SWEC Rev. O, February 4,1983

-: R - 35 ' ICYP Verification Plan for Diablo Canyon Project Activities, RLCA Rev. O, April 1,1983 ITR - 36 Final Report on Construction Quality Assurance Evaluation of Guy F. Atkinson Company, SWEC Rev. O, February 25, 1983 ITR - 37 Valves, RLCA Rev. O, February 23, 1983

TR - 38 Status Report on Construction'0uality Assurance Evaluation of Wisner & Becker, SWEC Rev. O, March 1,1983 Final Report on Construction

, Cuality Assurance Evaluation c'. isrer & 5ecter, S'.:EC Rev.1, :iarcn le,1953 ITR - 39 Scils - Intake Structure Bearing Capacity and Lateral Earth Pressure, RLCA Rev. O, February 25, 1983 ITR - 40 Soils Report - Intake Structure Sliding Resistance, RLCA Rev. O, March 9, 1983

'ITR - 41 Corrective Action Program and Design Office Verification, RFR Rev. O, April 19, 1983

i.

5-

  • ITR 42 RFR IDVP Phase II Review and Audit of PG&E Company and Design Consultants for Diablo Canyon Unit 1, RFR Rev. O, April 13, 1983
  • ITR - 43 Heat Exchangers, RLCA Rev. 0, April 14,1983
  • ITR - 44 Shake Table Test Mounting Class 1E Electric Equipment, RLCA Rev. O, April 15, 1983
  • ete:

0.LCA - R. L. Cloud Associates RFR - R. F. Reedy, Incorporated' SWEC - Stone & Webster Engineering Corporation

- New ITR issued O

f e

e n

-r----

7

,--..,.-..,----nn,.,__

...--.-p.

,,ec--

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20209C142&oldid=4029391"