ML19317F191

Summarizes 700623 ACRS Subcommittee Site Meeting W/Util to Observe Status of Unit 1 Completion & Discuss site- Related Matters

ML19317F191
Person / Time
Site:	Oconee
Issue date:	07/02/1970
From:	Schwencer A US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001080905
Download: ML19317F191 (7)

Text

_

A i

[ a4 $2/

.b

/

UNITED STATES ATOMIC ENERGY COMMISSION I.

I WASHINGTON. D.C.

20545 JUL 2 1373 I

Richard C. DeYoung, Assistant Director, PWRs Division of Reactor Licensing THRU: Charles G. Long, Chief, PWR Project Branch 2, DRL h ACRS SUBCOMMITTEE SITE MEETING WITH DUKE POWER COMPANY, OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3, DOCKET NOS. 50-269] 50-270 AND 50-287 The' ACRS held a subcommittee meeting with Duke Power Company at the Oconee site on June 23, 1970. ACRS members present were Dr. W. R. Stratton, Subcommittee Chairman, Dr. C. P. Siess and Dr. J. M. Hendrie. The primary purpose of the meeting was to observe the state of completion of Oconee Unit 1 and discuss site related matters.

In addition, the Subcommittee was interested in identification of areas wherein the. applicant had made changes to satisfy staff concerns and areas where the staff still has reservations. An attendance list is attached.

ACRS-Staff Discussion The Subcommittee first met with the staff for preliminary discussion.

~"

Mr. Long stated that we were prepared to orally brief the Subcommittee on site-related matters as well as highlighting balance-of-plant matters.

Site Matters Meteorology - We said that Duke has been told that the staff will allow credit for a X/Q value of 1.16 x 10-4 m/sec for the Oconee site, and that we are awaiting Duke's response on how their Oconee Station design will be improved to accommodate this X/Q.

Since Duke has orally said they would reduce leak rare if necessary to meet a more stringent X/Q value than proposed in ths FSAR (7.4 x 10-5 m/sec), we presented a graph to the Sub-committee showing a 2-hour thyroid dose of 155 Rem for a 0.2% per day leak rate and 190 Rem for a 0.25% per day leak rate. A copy of that graph is attached to these minutes.

In response to a question from Dr. Stratton we said no credit has been assumed by the staff or the applicant for dose reduction due to spray action. We also noted that it is unlikely Duke would resort to chemical l

addition because iti could increase the hydrogen generation problem.

Control of Hydrogen in Containment We said we have made Duke aware of our concerns on the hydrogen control problem. We acknowledged that hydrogen generation is, an issue not reviewed ww 9*

Rooloso g

I.

i.

n e

Richard C. DeYoung 2

at the CP stage. Based on our request, Duke has submitted an evaluation We are which proposes control of hydrogen concentration by purging only.

.[

currently reviewing their submittal. We have made Duke aware of the posi-tion expressed in the Millstone 2 ACRS letter; however, we have not yet taken a position with Duke on this issue.

Fuel Pool Filters We explained that it is our intent to tell Duke that filters will be required for the fuel pool.

In response to a question from Dr. Stratton, we affirmed the fuel pool accident is consistent with models used for other recent cases before the ACRS in that we assume (1) all rods in a single bundle fail, (2) 10 percent of the halogens escape from the rods, and (3) a 10 percent retention in the fuel pool water.

Dr. Stratton put us on notice that he is not convinced that filters are necessary for the fuel pool accident.

Charcoal Filter Efficiencies We said Duke and the staff are not in agreement on allowable ef ficiency values for charcoal filters used. for radioactive gaseous releases.

Duke u~a has been told that to get credit for 90% efficiency we believe the filters should exhibit 99% efficiency when tested. Until Duke agrees to demon-strate such a margin 'for loss of efficiency, we cannot conclude our evalua-tion on this matter.

Environmental Policy Statement We noted that Duke has not responded to our May 6,1970 request.for informa-tion needed to prepare our environmental policy statement.

Minimum Practicable Activity Releases We noted that we are currently discussing Tech Specs with Duke to. assure minimum practicable radioactive releases are achieved.

Seismic Adequacy of Structures We stated that while there are still some data outstanding on seismic design of site structures, we do no,t. expect any problems in this area.

Plant Changes Based on DRL Concerns l

f At the request of the Subcommittee, we identified four areas where Duke modified their design to satisfy our concerns:

(1) increased reactor vessel pm

t 3

Richard C. DeYoung 0

irradiation specimen capsules from 3 to 5, (2) added a strong motion (3) incre accelerometer to detect seismic disturbances, initial operation cre i

in our would consider a reduction af ter licensing if operating exper ence f

judgement so warrants, and (4) agreed to provide vibration monitoring o reactor internals and steam generator during start-up.

Outstanding Problems (Staff Reservationsl blem We then mentioned and briefly discussed several of the outstanding pro s that have areas where we either are in disagreement with Duke, have concern i

from Duke.

not yet been completely evaluated or are awaiting informat on I

among those highlighted were:

Significant n..

1.

The current ECCS concerns 2.

Single-loop operation (failure to scram) 3.

Anticipated transients 4.

Core flux tilt monitoring Operation at stretch power 5.

Qualification of protection instrumentation 6.

Pressure level instrumentation 7.

8, Diverse ECCS reactor trip Steam line accident (site verification) 9.

Separation of instrunent and power cables 10.

Start-up proceduras and extra personnel 11.

Industrial security details 12.

Fuel pool protection (filters) 13.

Containment leak rate Reactor coolant leakage (incipient f ailures) 14.

15.

Combined loading of core internals 16.

Hydrogen generation and control 17.

Restriction on start-ups with no hydros 18.

Reactor coolant pump substitutions 19.

Reliability of emergency power to ESF loads.

20.

Discussions with Duke h

The Subcommittee members were then given a site orientation by Duke w the site. This briefing included a briefing on the status of progress at l t included a discussion of the wear problems with the Bingham reactor coo an b

pumps which have led Duke to line up a set of Westinghouse pumps as able replacements for Unit 1 only.

We were inf ormed that two of the horizontal tendon sheath be omitted.

tion opening were lef t out thereby causing two tendons to t

W{#27,mti--.

Y

1 o

R. E. Heineman SEP 1 S 1875 1

Technical Review is requested to review the a w = ant request and related Safety Analysis Report and determine whether the proposed modifications are acceptable.

You are requested to provide a written evaluation suitable for input to an SER related to the requested change.

TARGET DATE FOR COMPLATION:

October 17, 1975 Original signed by:

Bobert A. Purple Robert A. Purple, Chief Operating Reactors Branch #1 Division of Reactor Licensing

Enclosure:

Duke 1tr. dtd 9/12/75 cc w/ enclosure:

D. Ross V. Benaroya L. Shao S. PawlicM B. Grimes J. Kastner DISTRIBUTION JDocket File (50-287)

ORB #1" Reading"-

l KRGoller TJCarter RAPurple GZech RSMSheppard SVarga DEisenhut l

VStello l

RTedesco l

RMaccary HDenton

{

RL:0RB#1 RL:D21Lt-b ecr >

GGZech:1 e

suanAut >

DATI >

...k..k.!. _5

.,Q/8./75 Foran ABC-3:e (Rev.9 53) ABCM 0240

.es-tMiesa-a uw s

f W

Richard CC. DeYoung 4

Most B&W':ltems of supply were said to be installed, at the site, or ready for shipment within 30 days.

The Keowenn Lake is 2 f t above maximum drawdown level.

Completicm of installation of the GE turbine generators is expected by mid-Janummy 1971, based on double shif ting of personnel.

Site Tour The Subcommittee then toured the site--first by helicopter in the morning and then by close inspection of all three units in the afternoon.

General Observations on Tour With approximately 1700 workers on the site there was substantial activity.

By comparison with other sites I have visited this site was considered to have poor overall industrial safety provisions. Although not directly a reactor safety matter, it may be indicative of management attitude as schedule deadlines are approached.

An attempt to find the liquid waste discharge line to the Keowee tailrace proved futile. Although no one could locate it on construction drawings at the site, Duke stated they will run this line to a waterpool in the tailrace immediately below the discharge from the hydro units.

This is more favorable than we had assumed from the FSAR description, since it will promote mixing in this pool of considerable volume before entering the river.

Future Plans Although there was no formal concluding session with us or Duke, the Sub-committee indicated that there will be another Subcommittee meeting, with Dr. Isbin present, probably in mid-July to discuss the ECCS problem and other matters. Duke was told that they would be informed of the date and particulars for this meeting through the staff.

W L

Albert Schwencer, Senior Project Leader PWR Project Branch 2, DRL

Enclosures:

1. Thyroid Dose Graph

2. Attendance List Distribution:

See page 5 6cs b

, 2, 2_.g. 3 ().4 I

.[

..:..-...,_..../

t

.. e..:.

g.

s I

...__.i

......, ( p,. 3 _. pf,,,, f.)

p l

y 1.--....

,. e I-

,P

/,4 w.

s.

_.pm -

.4j.

..,.... -..l

.p.:.

l l

7...

- - a

.._ l. :.....

I.

a t,, -

sca

-.....n.

.t e

p

.. =. - -

b g

1.

I.16 x I g

J-

.r.

_ (p s _1..m,l0.

pi f

./3ee...

with 2. 2 C.F) v' w _.

. -. -.. =

.........n.__..

n

., 4 s

......i_...:.

e

,. 3 _ x. 3 0_,.. -..

._.1...

,.j.

.(Val. ley Podel)E l

4 s

-._...l........._.. EfA p

/

1.co j

b.

!/j i

l5..$.' /

.l d,

K F

y RE%

e,.

t 4

+

DJ a

F o

... u..

........L.L '_ -.... t E 100

.. =

..,s s

I

e..

c:

.. t.

1...

-,t._

.... a. g. - -. - _.

.j..

em-g

-. t

-i g.

l 4:

..4-.

..... ; ;. f..: :...

._.__ _ -. = - -

i.

~..

..z.....

l r,.

F*

a 2

-- J..L..

~

5

.=

a _ _ _-

. "... ! i.

.__U f b..% d@fk~_".TMMD.@,4fQ-7.:

. :.~...[.. _~_

l f E 'M

._.u..

, c

..j. __.. _... _. _...-.. -........... _ -

c r:

-w u

c.-. ;...

t O

=

._ r.. :._;'._ ;.jij;2 2:9.i:.

t, g

-. g: :h.,2.. : L.:_ i.

2-

,f c_4. + p- _ _ _ _

2.: ;.._

,c SO...a

. :

...Q

, +...

-:- ::q.f: ;.

v.:--i -.:..:;;; ::. :-:.

. t:?

.=

. t.-

.. pr r.

.. :c

.1..,.

i e.

2

.g b..._..ictgjg "jWiM 2

- Edg-con jj i-f.

m F '.

.t..._.._,......Ti._...- 4 '----. :

.i.

4 2-i -i - -

,I-

.-t r

.... p.

. L.

.. ;...r..=,.

'.". p..t. ;.,-...

.j.....

r-i-

.. c.,..p.

7.

.p... p....

...t..

L.

1, _,,.. f. _.

.4,. 4. ;... _

}.a

_i,_3 4

_ ;.. ~

... g.,.. g t.

...,..t,.

.. !.g.

.;.;. p

... i i.., i o

_ p.a _.;.. :.

.g*-........

a J p s.,.

a l } g

1. -t -

- 'L r d L-

-I' 8 r l-i F'

.i,

..,...g.,

-i - -

r i-L i.n-

.p

,,-....; r,1 F ?.--.

'r-5 i

e.

q a, j j..;..

j..;. 1 2. i

... i

....L.

...._f.

. g.....,.

3._,_....

3

, p..1 g g -. ;.

..s

..,-.,.. :.. 7. _

i

. t a..

3

,i i

i i

e.

m.m.r.'. _a. _.

m_...=. =_

i...o.., 4 u

o. 7._.

. 4 3 i

e,c.

. i..

i.

4 od,,

d./.. tot,..L_b,.4 ' 9. _.. ~. _'..E.

l

^,' MTt. ear, nTE -

t l

.L..-

}3 i

..t i

..I i

.1. :*..

o i.+

. *tI jg.

i

1. v t t ww4 j.

w.

9

..e.% -

,I a j 'h

-.t ech i

~".,

. e-3' e'

^

e e

. ??,~ #

5,i a

J.'f&

1 i

s.

.e-f s

4..

e.

• +m een.

s

....e

.1 -

. g. '

(.-

- (

l

-Richard C. DeYoun's 5

Distribution:

Docket DRL Reading 7

PWR-2 Reading P. A. Morris F. Schroeder T. R. Wilson R. S. Boyd D. Skovholt E. G. Case, DRS R.

R.~ Maccary Compliance (2)

DRL and DRS Branch Chiefs t

A. Schwencer y s.,

F. W. Karas R. W. Klecker N. Thomasson

~= n s 9

4

\\

i i

1 t

1 a

-w

(.

i a).

(,

ATTENDANCE LIST FOR ACRS SITE VISIT TO t

OCONEE NUCLEAR STATION, JUNE 23, 1970 4

+.

1-AEC/DRL.

.-- 4 C. G. Long -

~ ^j A. Schwencer N. Thomasson ACRS Dr. Stratton Dr. Siess Dr. Hendrie M. C. Gaske

@*M Duke Power Company A. C. Thies, Vice President, Production and Operation P. H. Barton,. Manager, -Technical and Nuclear Services W. 0. Parker, Assistant Manager, Steam Production Department J. E. Smith, Superintendent,.0conee Nuclear Station E. D. Powell R. L. Dick, Manager of Construction John Rodgers, Project Engineer, Oconee W. H. Owen, Principal Mechanical Engineer i

L. C. Dail, Principal Civil Engineer C. A. Dewey, Jr., Principal Environmental Engineer Bill Lee, Vice President, Engineering Steve Apple, Environmental Engineer Bechtel M. Malcom, Project Engineer B&W ER. Smith, Manager, Licensing G. E. Kulynch, Project Engineer i

e l

t t

e I

..n..

-e....