ML20198G885

Forwards first-round Questions Re PSAR Concerning Component Descriptions,Design Classification,Process & Effluent Monitoring & Radwaste Processing.Info Requested by 741109

ML20198G885
Person / Time
Site:	Satsop
Issue date:	09/26/1974
From:	Tedesco R US ATOMIC ENERGY COMMISSION (AEC)
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-1338 NUDOCS 8605300001
Download: ML20198G885 (4)

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i Docket Moe. STN 50--508/509 R. DeYoung, Assistant Director for Light Unter Rasetors, Group 1, L EDUND ONE QUESTIONS FOR WASHINCTON NUr1 EAR PE0 JECT UNITS 3 AND 5 PSAR REVIEW Plant Name: Washlagten Nuclear Project No. 3 and 5 Licensing Stage: CP Docket Nushers: STN 5'l-508/509 Responnible Branch: LUR 1-3 Project Leader: P. O'Reilly '

Description of Response: Round One Questionn Requested Completion Date: September 27, 1974 Review Status: Under review Ue have reviewed the radwaste and associated sections of the PSAR for Washington Nuclear Project Units 3 and 5. These units were docketed as a CESSAR reference design; heimer, eacepticos to the CESSAR reference design have been taken in our areas of review.

An a result, we find that insufficient information has been provided in the areas of component descriptions, design classification, process and effluent monitoring, and radwaste processing.

Enclosed are our poottions and the additional enformation we will need to complete our review. We need this information by Nover ' er 9, 1974 to meet our schedule. [

h Robert Tede co, Assistant Director for Containment Safety Directorate of Licensing DISTRIBUTION:

Enclosure:

As stated Docket (STN 50-508/509)

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.. EFFLUENT TREATMENT 011.1 .

(10.4.2) You state that non-condensible gases from the main condenser evacuation system will be continuously discharged through charcoal bed adsorbers and monitored continuously for radioactivity prior to discharge.

This system is not shown on the P&ID's. Figure 10.4-2 contains a notation to the effect that discharge will be through HVAC charcoal adsorber. Identify the RVAC system or effluent discharge point to which this source is discharged. Provide P&ID's which show the charcoal point. bed adsorbers and the effluent discharge

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011.2 (11.1 and In your analysis of the releases of radioactive materials 11.2) in liquid effluents, you did not consider releases from the chemical and volume control system (CVCS) and the steam generator blowdown system (SGBS). You should

. provide justification that:

a.

The plant water inventories can be maintained over the plant lifetime without discharges from these sys tems; b.

The tritium levels in the plant can be controlled to maintain radiation exposures to operating personnel as low as practicable without discharge from these systems; and c.

There is sufficient capacity and flexibility or redundancy in the systems that discharges from these systems to the environment will not be necessary as the result of anticipated operational occurrences and equipment downtime.

011.3 (11.2, 11.5) You propose to design the liquid and solid waste systems to quality Group D classification. We do not consider this 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 e

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011.3 design the systems handling liquid waste including (11.2, 11.5) :omponents in the solid waste system which contain radioactive liquids, to Quality Group D (Augmented) classification as described in the enclosed Branch Technical Position - ETSB No.1, " Design Guidance for Radioactive Wa'ste Management Systems Installed in Light-Water-Cooled Nuclear Power Reactor Plants". ,

011.4 Describe your provisions for controlling overflows (11.2) 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 conden-sate storage tank, indicate the provisions incorporated for each to monitor liquid levels, alarm potential overflow conditions, and collect and sample liquid overflows.

011.5 You state that the radioactive gaseous waste system will (11.3.3.1.3) have H2 and 02 analyzers to indicate changes in hydrogen and oxygen concentrations; however, it is specified that these analyzers will be operated periodically.

Provide a system capable of continuously monitoring oxygen and hydrogen concentrations in your gaseous rad-waste system, with provisions to alarm in the event that oxygen concentrations in the decay tank inlet lines exceed 2%. Include an analysis of your system showing *.he effects of instrument malfunctions.

011.6 Provide a description of the instrumentation to be used (11.4) to monitor radiation levels in process and effluent streams during postulated accidents, in conformance with General Design Criterion 64.

011.7 Provide a complete description of your solid waste (11.5 ) system, including:

(1) The description of the proposed system operation, indicating your provisions for controlling process flows, chemical and waste additions, and how a solid matrix in the waste container will be obtained. Explain your method for assuring that all liquids have been combined into the solid matrix af ter the process is completed i.e.,

free liquids are not present. Indicate the steps to be taken if solidification is not complete.

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h-011-3 011.7 (2) The provisions for capping and decontaminating (11.5) waste containers and for handling waste spillage in the process areas.

(3) The description of the Volume Reduction Package (page 11.5-1).

011.8 Provide the results of an analysis showing the radio-(15.24) nuclide concentrations which could occur in both (1) the nearest potabic water supply and (2) the nearest surface water in an unrestricted area as a result of leakage based on single failures of components located outside reactor containment containing radioactive liquids. Assume 1% of the operating fission product  ;

inventory is released to the primary coolant, failed tanks release 807. of their design capacity, and all liquids from failed components enter the groundwater, i.e., do not assume liquids are retained by building foundations. Credit for radionuclide removal by the plant process systems, consistent with the decontamina-tion factors in WASH-1258 should be assumed. List all parameters and provide justification for the values assumed in your calculations, including liquid dis-persion and transit time based on distance, the hydraulic gradient, permeability and effective porosity of the soil, and the assumed decontamination due to ion exchange by the soil.

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SEP 2 4 B74 DOCKET NOS: STN 50-508 6 50-509 FACILITY: WPPSS Nuclear Projects No. 3 and No. 5 APPLICANT: Washington Public Power Supply System

SUMMARY

OF VISIT BY STAFF GEOLOGIST TO WPPSS NUCLEAR PROJECTS NO. 3 AND NO. 5 SITE AND SUBSEQUENT MEETING WITil WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS) SEPTEMBER 3-5, 1974 On September 3-5, 1974, D. Budge, Regulatory staff geologist, accompanied by a geologist from the Washington State Department of Natural Resources, Earth Sciences Division (WSBNR), visited the WPPSS Nuclear Projects No. 3 and No. 5 site near Satsop, Washington in order to examine the site and to discuss questions regarding geology. On September 3, 1974, at the WPPSS off. ice in Montesano, Washington, the applicant conducted an orientation session utilizing models of the proposed site and facilities.

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! Following the orientation session, the applicant conducted a 1

general tour of the site area. During this tour, the trenches along the Workman Creek, the Delezene, and the Weikswood Faults were examined.

! On September 4, 1974, the staff geologist and a WPPSS representa- ,

l tive participated in an serial tour of the site area by heli-copter. During the flight, the Weikswood fault, the region near Minot Peak, and the site of several landslides were observed from the air. Upon completion of the flight, the staff geologist, the WSDNR geologist, the applicant, and the applicant's consultant met at Satsop, Washington to examine core borings. The boring l B-17 obtained from the proposed location of the WPPSS Nuclear Project No. 3 containment was examined and discussed. Fossils l were observed in boring A-47. The participants then. traveled by automobile to the Crescent basalt qua m near the site.

Fossils were observed and collected from the Astoria formation while enreute to the quarry. After lunch, the participants met at the Woodward-Lundgren office at Satsop to examine photographs i of the trenches located along the Scammon Creek fault and along

! the tuff bed. A model of the tuff bed constructed with pegs was also examined. The site visit concluded with examination of the trenches along the Gibson Creek fault and the continuous trenches along the tuff bed.

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SEP 0 4 1974 2-On September 5, 1974, the staff geologist, the WSDNR geologist, the applicant, and the a Olympic Inn in Aberdeen,pplicant's Washingtonconsultants to discuss met at the the following questions that were formulated during the site visit. An agenda and a list of attendees are attached.

Status of Site Stratigraphy In view of the crude site stratigraphy, the staff recommended that the applicant employ a consultant to examine the core borings in order to obtain a more accurate indication of the local geologic structures and correlations. The landslidost observed in the area and their relationship to regional geologic formations were also discussed.

Potent-lal Oil and Gas Exploration

, In response to a staff inquiry about future plans for oil and gas exploration in the region, the applicant stated that WPPSS will have title for land and all mineral rights on about 1000 acres in the site area. The applicant indicated that a number of exploratory wells have already been drilled in the site region without any major petroleum discovery. Because of this, the applicant does not anticipate the development of a subsidence problem at the site.

Tuff Bed Slickensides The tuff bed slickensides seen at trench TBC-1, which do not exhibit offset, were discussed. The applicant informed the staff that these features were not observed in the core horings (and therefore may be associated with weathering of the trenches).

The applicant indicated that a petrologist will be employed to determine whether the slickensides are of nontectonic origin.

l Significa.'ce of Terraces Located North of Site l The importance of the terraces located north of the site in establishing the age of the faulting observed in the ragion

, was discussed. The staff stated that additiemal work on dating these terraces was necessary. Several methods of dating such as more detailed mapping and the use cf amino acid and pollen techniques were discussed.

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-3 SEP yg n Saprolite Dating of Gibson Creek Fault The applicant stated that an attempt will be made to obtain -

data on erosion and weathering rates for the site area. These data would ther. be used to determine a rate for saprolite ,

development and thus provide a date for the last faulting movements.

Original Signed by Patrick D. O'Reilly Patrick D. O'Reilly Light Water Reactors Project Branch 1-3 Directorate of Licensing

Enclosures:

1. Agenda for September 5. 1974 Heeting

, 2. Attendance List cc: Washington Public Power Supply System Joseph B. Knotts, Jr.

Richard Q. Quigley l

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3 ENCLOSURE NO. 1

-AGENDA FOR SEPTEMBER 5, 1974 MEETING WITl! WPPSS

1. . Status'of Site Stratigraphy

a. . Relationship of landslides to geologic formations in

. site area

2. Potential for future Oil and Gas Exploration in Region Near Site

3. Tuff. Bed Slickensides Observed in Trench TBC-1

a. No observable offset b.. Significance of origin 4.. Significance of Terraces Located North of Site

n. Need for additional work on dating

5. Saprolite. Dating of Gibson Creek Fault I'

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ENCLOSURE NO. 2 ATTENDANCE LIST SEPTEMBER 3-5, 1974 SITE VISIT AND MEETING WITH WASHINGTON PUBLIC F0WER SUPPLY SYSTEM SEPTEMBER 3, 1974 SITE VISIT Washington Public Power EEASCO Supply System A. Wern G..Sorensen D. Tillson D. Whitford

-W. McClain Washington State Department of Natural Resources, Earth Sciences Division Regulatory Staff W. Rau D. Budge SEPTEMBER 4, 1974 SITE VISIT AND SEPTEMBER 5, 1974 MELTING AT ABERDEEN, WASHINGTON j Washington Public Power EBASCO Supply System A. Wern G. Sorensen D. Tillson D. Whitford W. McClain Washington State Department of Natural Resources , Earth Sciences Division Woodward-Lundgren W. Rau A. Patwardhan M. Perkins Regulatory Staff D. Budge

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.Distribdtion: .

. Docket Fil ..

F. Schroeder J AEC PDR H. Denton Local POR R. Meccary

.L Readir.g .V. Stello R. C.'DeYoung R. Tedesco R. Denise V. Benaroya

K. Goller C. Long D. Muller J. . Kastner D. Skovholt G. Lainas V. Moore- D. Ross

% Butler T. Ippolito D. Vassello S. Pawlicki

0. Parr J. Knight K. Kniel L. Shao A. Schwencer B. Grimet J. Stolz W. Gamill R..A. Clark R. Ballard R. freland P. Fine R. Purple T. Novak D. Ziemann M. Spangler P.-Collins EP Project Manager - J. Norris

'R. Vollmer 0GC

< W. Houston R0(3)

G.'knighton V. Wilsen

-G. Dicker R. F. Fraley, ACRS (16)

8. J. Youngblood LWR l-3 Reading W. H. Regan, Jr. LWR 1-3 File S.'.Varga G.-Lear

'R. W. Klecker P. O'Reilly F. Kantor D. Budge E. llawkins C. Liang T. Johnson- P. Stoddart C.-Stepp J. Costello D. Bernreuter F. Cherney T. Murphy P. Chen R. Eornasiewic: E. Brooks R. Satterfield C. Sullivan F. Ashe M. Bolotsky

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