ML20198F985

From kanterella
Jump to navigation Jump to search
Forwards Round 2 Questions & Positions Re Effluent Treatment,Per Review of Amended PSAR as Result of Site Change & Addition on WPPSS 4.Info Required by 741021
ML20198F985
Person / Time
Site: Washington Public Power Supply System
Issue date: 08/23/1974
From: Tedesco R
US ATOMIC ENERGY COMMISSION (AEC)
To: Moore V
US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-0993, CON-WNP-993 NUDOCS 8605290167
Download: ML20198F985 (4)


Text

4

~~

ke.k d Ries i

AUG 2 31974 Docket Nos. 50-460 and 50-513 i

Vogg Moore, Assistant Director for Light Water Reactors, Group 2 L I

ROUND TWO QUESTIONS AND POSITIONS POR WASHINGTW NUCTFAR PROJECT UNITS 1

& 4 PSAR REVIEW Plant Name: Washington ::uclear Project No. 1 & 4 Licensing Stage: CP Docket Numbers: 50-460/513 Responsible Branch: LUR 2-3 Project Leader:

T. Cox Description of Response: Roend Two Questions and Positions for PSAR Review Requested Completion Date: August 26, 1974 Review Status: Under Review We have reviewed the anended PSAR for the Washington Nuclear Project Unita 1 and 4.

We will need some additional infonnation as the result of a site change, extensive revisions in the areas we reviewed, and the addition of Unit No. 4.

The addition of Unit No. 4 to the site has not been evaluated by RAB.

Based on the results of that evaluation, E73B may have additional comments.

Enclosed are our positions and the additional information we will need to complete our review. We need this information by October 21, 1974 to meet our schedule.

M Robert L. Tedesco, Assistant Director for Contaimnent Safety Directorate of Licensing

Enclosure:

As stated cc: w/o enclosure A. Giambusso

(

W. Mcdonald

-7/

l t

8605290167 740023 PDR ADOCK 0500 O

A i

o

\\

\\

\\

2 AUG 2 31974 Vos. Moore cc: w/ enclosure S. Hanauer F. Schroeder W. Regan j

R. Imose A. Schwencer T. Com S. Varga J. Kastner W. Kroger J. Glynn i

V. Benaroya P. Stoddart Dis tribution:

Docket L Reading CS Reading ETSB Reading ETSB Staff ETS.B _ hl.

S B..._...

ETSB

. _. /

o"'***

PS.todda_r t :ks jJTCollins..

VBenaroya...

eh co..

8/23/74.._

8/2b /74

. 8/1}. / 74.

8/.h/74.-

F.we AIC.)l9 (Rev. 9 Sn AFCM 0244 e*o Ca*

  • * * * *. s. e e s..a e.

f s

o 01 EFFLUENT TREATMENT 01.1 You propose to design the liquid and solid waste systems to (11.2 &111.5) quality Group D classification. We.do not consider this e

classification adequate because the design guidance should provide reasonable assurance that equipment and components used in the radioactive waste management systems are designed, constructed, installed, and tested on a level commensurate with other plant systems and structures to protect the health and safety of the public and plant operating personnel. You should design the systems handling liquid waste including components in the solid waste system which contain radioactive liquids, to Quality Group D (Augmented) classification as described in the attached Branch Technical Position - ETSB No. 1,

" Design Guidance for Radioactive Waste Management Systems Inst:11cd in Light-U:ter-Cected Mucicar,Peuer Reacter Plant:".

'01.2 In Amendment 8, you state that Turbine Building leakage is (11.2.2) collected in 3 sumps and sampled prior to discharge.

Provida the design capacity of the sumps and sump pumps.

Duscribe your provisions for obtaining a representative sample of sump contents prior to discharge in conformance with Regulatory Guide 1.21.

01.3 Your reply to 11.8a in Amendment 8 does 211.5.3.2) not specify a method for the detection of free water in packaged solid waste.

Provide the methods that will be used to verify the obsence of frec liquid in solid waste containers and the procedure to be followed if free liquids are detected.

\\

01.4-You have not described your provisions for controlling over-(11.2 & Q11.7) flows from tanks containing potentially radioactive materials.

Provide curbings or dikes around all tanks having the potential to overflow to the floor (inside the plant) or to the ground (outside the plant). For all tanks containing potentially radioactive materials both inside and outside the plant including the condensace storage tank, indicate the provisions incorporated for each to monitor liquid levels, alarm potential overflow conditions, and collect and sample liquid overflows.

01.5 You state that the radioactive gaseous waste system will (11.3) have h2 and 02 analyzers to indicate changes in hydrogen and oxygen concentrations; however, it is not specified that these analyzers will be operated continuously.

Provide a system l

capable of continuously monitoring oxygen and hydrogen concen-trations in your gaseous radwaste system, with provisions to alarm and automatically isolate the system in the event that oxygen conecatrations in the decay tank inlet lines exceed 27..

Include an analysis of your system showing the effects of instrument malfunctions.

6

r s

/

r a

m.

o g_

L i

~ 01.6.

Provide _a description of the instrumentation to be used to (11.4) monitor tadiation levels in process and effluent streams s

'du' ring postulated accidents, in confomance with General Design Criterion 64.

-'m.-

7

/,

. &S

}

?

/

I

. w s'

n

,L w

.e4m

.s.-

14*

e. '

e e

4 k

,1/

.1 5

~

b

'k

  1. R,s y

a v-4.& T p"

i

.=

l

,,p s

o s

i P

f

_,.e f' s,

./

s y

i' h,~ y 8

O e

b g

v

[

.e e

s'

,.r F

'~

l' Er

/~