Text

Control Room Habitability Evaluation,San Onofre Nuclear Generating Station,Unit 1
	ML13330A896
Person / Time
Site:	San Onofre
Issue date:	01/30/1981
From:	Broadhurst R, Karimi R, Toth K; NUS CORP.
To:	;
Shared Package
ML13330A293	List: ML13330A291; ML13330A896;
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM NUS-3704, NUS-3704-R01, NUS-3704-R1, NUDOCS 8104150156
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3 NUS-3704 Rev.

1 CONTROL ROOM HABITABILITY EVALUATION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 (NRC TMI ACTION PLAN ITEM III.D.3.4)

Docket#

so-os Control # StIOa 15)ol523 Date f-13-9 iofDocument

,REGULATORY DOCKET FILE II Prepared for SOUTHERN CALIFORNIA EDISON by K. J. Toth W. C. Arcieri R. Karimi M. C. Check R. H. Broadhurst R. J. Jubach R. W. Speidel January 30, 1981 Approved by E. R. Schmidt, Manager Systems Analysis NUS CORPORATION 4 Research Place Rockville, Maryland 20850 810415o0S REGIJLATORY BUd~{

HLL COP

TABLE OF CONTENTS Section and Title Page No.

LIST OF TABLES 111 LIST OF FIGURES iV

1.0 INTRODUCTION

1-1 2.0

SUMMARY

AND CONCLUSIONS 2-1 3.0 HABITABILITY SYSTEMS 3-1 4.0 RADIOLOGICAL ANALYSIS 4-1 5.0 TOXIC CHEMICAL ANALYSIS 5-1 6.0 ATMOSPHERIC DISPERSION ANALYSIS 6-1 APPENDICES APPENDIX A ADDITIONAL INFORMATION REQUIRED A-1 BY NRC APPENDIX B COMPARISON OF THE SONGS-1 CONTROL B-1 ROOM TO THE CRITERIA OF THE STANDARD REVIEW PLANS 6.4, 9.4.1, AND 6.5.1 APPENDIX C METHODS USED IN RADIOLOGICAL ANALYSIS C-1 APPENDIX D METHOD USED IN TOXIC CHEMICAL ANALYSIS D-1 APPENDIX E ANNUAL JOINT FREQUENCY WIND SPEED E-1 WIND DIRECTION SUMMARIES NUS CORPORATION

3 LIST OF TABLES Table No.

Title Page No.

4-1 Assumptions Used In Radiological Analysis 4-4 At The SONGS 1 Control Room 4-2 Radionuclide Inventory In The Core And 4-6 Containment Sump Water After A LOCA 5-1 List Of Onsite Chemicals In SONGS 1 5-3 5-2 List Of Onsite Chemicals In SONGS 2 & 3 5-4 5-3 Toxic Chemicals Summary Of Results 5-5 6-1 Adjustment Factors For Selected Time 6-7 Internals 6-2 Calculated Z/Q Values For Radiological 6-8 Analysis 6-3 One Hour Z/Q Values For Toxic Chemical 6-9 Analysis C-1 Nuclide Decay Constants And Fission Yields C-14, C-2 Average Beta And Gamma Energies And Iodine C-15 Inhalation Dose Conversion Factors C-3 Isotopic Gamma Energies And Decay Fractions C-16 C-4 Absorption Coefficients For Air C-18 E-1 Annual Joint Frequency Wind Speed-Wind E-2 thru Direction, Pasquill Stability Categories thru E-7 A Thru G E-8 NUS CORPORATION

LIST OF FIGURES S

FIGURE No.

Title Page No.

3-1 Control Room Envelope 3-7 3-2 Control Room Volume And Air Flows, 3-8 Normal & Emergency 4-1 Simplified Control Room HVAC Model 4-7 5-1 Plot Plan SONGS 1,2, & 3 Toxic Chemical 5-6 And Radiation Source Locations C-1 Dose Model Activity Flow Schematic C-19 D-1 Schematic HVAC Diagram And Its Pertinent D-7 Flow Rates Of SONGS 1 Control Room iv NUS CORPORATION

1 I it

1.0 INTRODUCTION

This assessment is written in response to a

Southern California Edison (SCE) request to perform a control room habitability study for San Onofre Nuclear Generating Station Unit 1 (SONGS-1).

This work, in part, is in response to NRC's TMI Action Plan Item III.D.3.4 which directs and issues requirements for licensees of operating reactors to review their control room habitability systems. The guidance (May 7, 1980 letter) essentially requests that all operating plants review their designs against the current requirements in General Design Criteria 19, Regulatory Guides (RG) 1.52, 1.78, and 1.95, and Standard Review Plans (SRP) 2.2.1, 2.2.2, 2.2.3, and 6.4.

The information specified in Revision 2 to Regulatory Guide 1.70 and the above mentioned SRPs considerably expanded the analysis of offsite hazards and the constraints on control room habitability originally required.

Control room habit ability designs have generally become more sophisticated and involved.

SONGS-1 being licensed before these criteria were I

developed, is now requested by the May 7, 1980 letter to comply with these current requirements. The objective of this assessment is to review the SONGS-1 design with regard to these current requirements, utilizing to the maximum extent possible prior work on Units 2 and 3, and flexibility allowed by the requirements to show that the design is adequate where possible.

The configuration change associated with the technical support center titled; Control and Administrative Building -

Area 10 Heating, Ventilation and Air Conditioning Plan and Sections, Third Floor:

Drawing Number 568664 Revision 6, J.O. No. 7764 was assumed to have been implemented.

1-1 I;

NUS coRPORATION

2.0

SUMMARY

AND CONCLUSIONS The SONGS-1 was not designed against the current bases for habitability systems and resultantly falls short of some of the regulatory guidelines.

However, ongoing efforts such as the configuration change (mentioned in Section 1) which will reduce the control room emergency zone, helps to resolve some of these new found anomalous.

Food, water, and medical supplies can be obtained and stored. Eye and skin protection requirements can also be resolved similarly to the respiratory requirements.

The sanitation and kitchen facilities are not available within the control room emergency zone.

Whole body and gamma dose rates with the current HVAC system in the control room do not appear to be a problem. Expected thyroid dose rates on the other hand do exceed the SRP 6.4 criteria.

Even under the most ideal conditions hypothesized for the existing HVAC system, i.e., no in-leakage or infiltra tion, 1,000 ft3/min of filtered air makeup and the latest X/Q factor permissible, the thyroid dose was 48.78 rem as compared to the SRP 6.4 limit of 30 rem.

Radiological doses for realistic conditions and for various hypothetical design changes are addressed further in Section 4.0.

The ideal hypothesized design, i.e.,

reduce in-leakage to 50 ft 3/min, 1,000 ft 3/min filtered air makeup, and filter 3,000 ft3/min of recirculating air produce a thyroid dose of approximately 26 rem.

The effects on the control room of an offsite toxic chemical accidental release is under further study and therefore is not presented in this report.

2-1 NUS cORPORATION

With respect to onsite chemicals, the analysis of those from Units 1,

2 and 3 indicates that special provisions are required for ammonia and hydrazine.

While further analysis of toxic chemicals is required this should be done only after a decision is made on the resolution of various areas where the control room design does meet current standards.

Toxic chemical considerations indicate that normal and emergency air intake rates and infiltration rates should be reduced as much as possible.

Summarily, this analysis and equipment examination reveals that the SONGS-1 control room habitability systems do not comply with many of the NRC's current design criteria when evaluated according to Standard Review Plan 6.4.

Some areas for improvement have been identified and will require further evaluation.

I 2-2 NUS coRPORATION

I 3.0 HABITABILITY SYSTEM 3.1 Definition of Control Room Envelope The control room emergency area which is defined as those areas requiring continued occupancy by operators is the con trol room (#301), the watch engineer's office (#302), and the central alarm station (#324).

See Figure 3-1.

Other areas such as the kitchen and sanitary facilities which require infrequent occupancy by the operators are not located within an emergency control zone.

3.2 General Description The system is low pressure and is designed to heat, ventilate and condition 13,650 ft 3/min of air to maintain a room temper ature of 750 F with an outside temperature of 36 F.(1)

The system is controlled in the watch engineer's office (room #302), where switches for the heat pump air conditioning unit, A-31, and the emergency outside air intake unit, A-33, are located. The cooling and heating cycles of the system are controlled by a preset thermostat located in the control room.

Conditioned air is provided by a supply air duct and adjust able ceiling or wall registers. Return air flows through the wall return type grills located in the control room cabinet area.

The fresh air intake is at the inside air unit (A-31) on the second floor.

The outside air units (A-31c and A-31d),

located in the air conditioning equipment room, start automat ically in sequence (one compressor for a light load and two for a maximum load) and draw outside air from wall louvers through outside air coils and discharge to a common exhaust plenum.

Each of these units runs in tandem with a booster exhaust fan.

3-1 NUS CORPORATION

I Under normal operation, outside air passes through a normally

opened, standard commercial (without resilent seals), control damper, through a prefilter, through heating and water cooling coils to fan A-31. Fan A-31 has a total capacity of 13,650 ft 3/min but will be adjusted down to maintain the current approximate airflow, 10,900 ft3/min airflow into the control room.

Airflow and pressurization is to be regulated by a one way (outflow) damper in a control room door next to the watch engineer's office.(2) From fan A-31, the flow goes directly to the watch engineer's office (302),

the control room (301),

and the central alarm station (324).

Two return air ducts are located in the control room cabinet area with capacities of 4,365 ft3/min and 5,530 ft /min for 9,895 ft 3/min total outflow. The difference in these airflow rates, (10,900 ft3/min in minus 9,895 ft 3/min out) will be balanced with the loss of air from exfiltration due to the positive pressure and the one way damper.

(Figure 3-2)

There are three doors into the area served by A-31. One door next to the watch engineer's office leads to the hall, the other two doors are at either end of the man trap entrance.

If There are four internal doors which are located at the watch engineer's office (302), the central alarm station (324), the north end of the control room cabinet area, and one louvered door on the south end of the control room cabinet area.

(Figure 3-1)

The criteria and instructions for initiation of the emergency mode of operation for the heating, ventilation, and air condi tioning system in the controlled area are outlined in the SONGS Primary Plant Operating and Maintenance Instructions.

1 I

3-2 NUS CORPORATION

I The normal air intake will close and the emergency system lit damper will open automatically on high containment pressure and automatic containment isolation.

"If airborne radioactive gaseous or particulate matter is being delivered to the control room through the ventilation system, the air condition ing unit A-33 should be started from the switch in the watch engineer's office." (3)

I The separate filtering system, A-33, works in series with A-31 during an emergency.

The system consists of a prefilter for normal dust collection, a high efficiency filter for fine radioactive particle collection, and a charcoal filter for radioactive gas absorption.

When the switch in the watch engineer's office is actuated, the unit dampers are positioned automatically to supply filtered outside air.

The dampers may also be positioned manually.

The design capacity of the emergency outside air intake unit, A-33 is 1,000 scfm. (4) The remainder of the system functions the same as in the normal mode. (4)

The volume of the emergency zone served by this system in the emergency mode or the normal mode is 27,521 cubic feet cal culated from available drawings.

(Figure 3-2)

There is no redundancy in either A-31 or A-33, nor is either system seismic qualified. (6)

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3-3 NUS CORPORATION

1 The control room habitability systems can be operated from on site power but requires manual action by the control room watch engineer.

For further detail, see reference 4.

NOTE: This control room assessment is based on the assumption that the control room area configuration change has been com pleted.

Flow rates will remain approximately the same as shown on drawing no. 568664-6 and that the A-31 and A-33 flow rates will be adjusted and tested to maintain habitability. (5)

It is also assumed that this configuration change will enable the emergency unit A-33 to maintain the control room under positive pressure during emergencies to meet NRC require ments. (4) 3.3 Component Description 3.3.1 The emergency air supply unit, A-33, (HEPA, charcoal filter, fan) is not classified seismic cateory I.(6) Data on other components such as instrumentation, the normal unit A-31, and ducting are not available but are also believed to be not seismic qualified.

3.3.2 The control room emergency air treatment system is designed to filter the control room intake air during control room isolation.

The system is placed in operation under administrative control when conditions warrant its use.

The system utilizes a fan, a high efficiency particulate absolute (HEPA)

filter, pre-filters and a charcoal adsorber bed. The pre-filters are installed before the charcoal bed to prevent clogging of the iodine adsorbers.

The two (2) inch bed depth charcoal filter adsorbers(8) reduce the potential intake of radioiodine to the control room.

(Technical Speci fication 3.12) 1 3-4 NUS CORPORATION

U At least once per refueling cycle, the pressure drop across the combined HEPA filters and charcoal adsorbers is demon strated to be less than 6 inches of water for flow conditions equal to or greater than design flow rate. HEPA and charcoal filters are tested for greater than 99% efficiency at least annually or every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of operation and following signi ficant painting, fire, or chemical release in any ventilation zone communicating with the system.

(Technical Specifi cation 4.11)

The isolation damper is tested once per refueling cycle for automatic closure of the fresh air intake to the control room.

(Technical Specification 4.11)

The criteria establishes no requirement to check for leakage while closed or time required for closure.

I 3.3.3 There are three control room access doors, none are sealed or equipped with automatic closing devices.

The two doors of the man-trap vestibule are not physically inter locked.

However, as a matter of security procedure one must be closed before the other can be opened otherwise an alarm is sounded in the central alarm station.

I 3.3.4 A single beta-gamma G-M Tube Detector is installed in the control room in the southwest corner with a sensitivity range of.01-100 mr/hour.

An alarm is sounded when the set point of 1.0 mr/hour is reached and displayed on the control room area monitor channel R-1231.

(Reference 1, p. 12-1) 1 3-5 NUS CORPORATION

U I 3 3.4 References

1.

Southern California Edison Company and San Diego Gas and Electric Company.

San Onofre Nuclear Generating Station, Unit 1, Station Manual System Descriptions, Volume 1,

p. 27-11.

2.

Santa

Ana, Fabian, Configuration

Change, Control and Administration Building - Area 10 Heating Ventilation and Air Conditioning Plan and Sections, Third Floor,"

SCE, Drawing No. 568664 Revision 6, J.O. No. 7764.

3.

San Onofre Nuclear Generating Station Primary Plant Oper ating and Maintenance Instructions.

Operating Instruc tion S-3-5.29, Revision 7, p. 2. (July 22, 1980).

4.

Memorandum for File, March 11, 1977, 36.20, San Onofre 1, Current Design Status of Emergency Air System Control Room Envelope, SONGS-1, p. 8.

(Drawing 5149957-2, Emer gency Operating Condition, 4 kV and 480 V LOP-SIS SIS/LOP Train No. 1.

5.

Smith, Howard, SCE, Letter (October 16, 1980).

6.

Docket No. 50-206, "Systematic Evaluation Program (Seis mic) San Onofre Nuclear Generating Station Unit 1",

(August 29, 1979).

7.

San Onofre Nuclear Generating Station Engineering Pro cedure S-V-2.8, Revision 2, (May 17, 1978).

8.

Smith, Howard, SCE, Telecon (November 21, 1980).

3-6 NUS CORPORATION

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TECHNICAL SUPPORT CENTER II INC N

CENTRAL

4.

ALARM STATION

_(324)

DNC DNC CONTINUOUS OCCUPANCY WATCH NGINEER CONTROL ROOM

((301)

(302)

W'vi, 0

CONTROL ROOM CABINET AREA FIGURE 3-1 CONTROL ROOM ENVELOPE I

I 3-7 I

3 NUS coRPORATION

mm -WNm "We-

-a-MM 380 CFM duct out leakage 10900 CFM suCM air central 5530CFM

-)

r -1J--2R/A alarm louvered doo( ~

'~"

station 1

-control room control operator room area cabinet pre-filter440u.

re I

Vol 13381 11 280 CEMply.ai 5370CFM heatstation cooling DNG c

l9895 GEM coils_____

eng.

rtr i

refil3er one way damper (302)t pre-areaeI 1005 GEM

_duct in leakage

~

~385 GEM harcoa filter HEPA OUTSIDE AIR

~~ NO RMAL z

-T3 F-1000 GEM C

0) pre-fil 0

FIGURE 3-2 O

1

-a OUTSIDE AIR CONTROL ROOM VOLUME and AIR FLOWS -NORMAL

&EMERGENCY O

ABNORMAL 1000 GEM 0 z

U I

I 4.0 RADIOLOGICAL ANALYSIS The section summarizes the methods and results of the analysis of control room habitability during postulated radiological accidents at SONGS-1.

4.1 Methods I

The methods used to calculate the beta and gamma whole body dose and the thyroid dose to the control room operators are standard calculational techniques for modeling the gener ation, release, transport,

buildup, and removal of radio nuclides.

The equations used to model these phenomena are well known.

The specific equations incorporated into the computer program used in this study to calculate the control room operator doses are presented in Appendix C of this report.

The analysis of direct radiation from sources outside the control room was submitted to the NRC in September, 1979(1) in response to NRC questions.

4.2 Results The radiation dose to individuals within the control room during a postulated design basis accident at the SONGS-1 is computed using the data listed in Tables 4-1 and 4-2.

The simplified HVAC model used in this evaluation is shown in Figure 4-1 and is based on information provided, and the ASHRAE Handbook.

This figure shows only the possible inleakage paths into the ductwork. Radiological doses do not 3

include any possible control room infiltration leakage. Upon completion of the control room configuration change, pressur ization and infiltration/exfiltration leakage rates will be established and doses will be recalculated. (5) 4-1 NUS CORPORATION

As indicated in Amendment 52 to the FSAR(2),

the maximum hypothetical accident is a loss of coolant accident (LOCA).

This is because the magnitude and duration of the radionuclide release during a LOCA is much greater than that for any other accident.

The 30 day integrated dose (rem) to an individual in the control room based on the present HVAC system design as shown in Figure 4-1 is SONGS-1 Integrated Dose Integrated Dose NRC 45 min. Outside 90 min. Outside Criteria Whole Body 7.6 8.7 5.0 Thyroid 382 430 30 Skin 10.6 10.6 30 I

These calculations make provisions for the operators to depart the control room emergency zone and go to the kitchen and/or bathroom which are not in the emergency zone. (6) Times out side the emergency zone are computed for 45 and 90 minutes out of successive eight hour periods.

The thyroid dose includes a contribution of two (2) rem from recirculation system leakage outside containment.

The whole body dose includes a dose of 6.2 rem from direct radiation and skyshine from the containment. This result is based on infor mation presented in references 1 and 4. Further review of the analyses supporting these references is required to determine if the dose value is overly conservative and what if anything can be done to reduce it.

I 4-2 NUS CORPORATION

It is concluded that the calculated thyroid and whole body dose does not meet present NRC criteria.(3)

There are various HVAC system designs that can be utilized to reduce the thyroid dose.

All of them involve reducing the amount of inleakage, and installing a recirculation system.

The best hypothesized design would be to reduce the inleakage to 50 scfm, intake 1000 scfm from the outside and recirculate 3000 scfm through a charcoal filter.

The thyroid dose then computed to be about 25 rem.

4.3 References

1.

Baskin, K. P. Docket No. 50-206, Control Room Operator

Doses, San Onofre Nuclear Generating Station, Unit 1, letter to USNRC-Office of Nuclear Reactor Regulation, September 22, 1977

£

2.

SONGS-1 FSAR, Amendment 52, Docket 50-206, December 1975

3.

U.S.

Nuclear Regulatory Commission, Standard Review Plan 6.4 NUREG 751087, Rev 1.

4.

Bechtel Corp.,

Control Room Dose Evaluation, letter to Southern California Edison dated October 1, 1977

5.

Smith, Howard, SCE, Telecon (December 18, 1980)

6.

Moody, W. C., SCE, Letter (January 8, 1981)

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4-3 NUS CORPORATION

U TABLE 4-1 ASSUMPTIONS USED IN RADIOLOGICAL ANALYSIS I

AT THE SONGS-1 CONTROL ROOM Power Level

= 1347 MWth I

Operating Time = 1000 days I

Containment Volume = 1.21 x 106 ft3 o

sprayed volume

=

1.04 x 106 ft3 (86%)

o unsprayed volume

=

1.69 x 10 ft3 (14%)

o mixing flow rate

=

1000 cfm between sprayed and unsprayed region Spray Removal Rate o

elemental iodine

=

17.5 hr 1

o particulate iodine

=

0.353 hr 1 o

organic iodine

=

0 hr 1

Leak Rate from Primary Containment 30 0.12 % volume/day for 0-24 hrs.

1 0.06 % volume/day for 24 hrs.

Leak Rate for Sources Outside Containment o

valve stem leakage 360 cc/hr o

pump leakage 265 cc/hr o

total 625 cc/hr max. tech spec limit Iodine Partition Factor

=

0.01 Sump Water Volume

=

8.53 x 10 8cc U

II 4-4 NUS CORPORATION

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TABLE 4-1 continued Charcoal Filter Efficiency o

elemental

=

0.95 o

organic

=

0.95 o

particulate

=

0.99 I3 X/Q Values (sec/m ) at the Control Room Intake 0-8 hrs 1.5 x 10 3

8-24 hrs 1.0 x 10 1-4 days 3.8 x 10-4 4-30 days 1.1 x 104 I

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I 4-5 NUS CORPORATION

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TABLE 4-2 RADIONUCLIDE INVENTORY IN THE CORE AND CONTAINMENT SUMP WATER AFTER A LOCA (FROM REFERENCE 2)

NUCLIDE RADIONUCLIDE INVENTORY (ci)

Core Containment Sump 1-131 3.95 x 107 1.97 x 107 1-132 5.33 x 107 2.53 x 107 1-133 7.35 x 107 3.65 x 107 1-134 8.26 x 107 3.61 x 107 1-135 7.12 x 107 3.50 x 107 Kr-83m 5.80 x 106 Kr-85m 1.38 x 107 Kr-85 4.92 x 105 Kr-87 2.93 x 107 Kr-88 3.69 x 107 Xe-131m 2.86 x 105 Xe-133m 1.77 x 106 Xe-133 9.21 x 107 Xe-135m 2.20 x 10 Xe-135 2.98 x 107 Xe-138 6.84 x 107 I

I I

4-6 3

NUS CORPORATION

1005 C.(r 3Comrc Rcomr,Watch 5 -7 0 C 4t bS c~e 15 0.CCn 3S 3 l3i ;-is 03,90 c4mn C>S cf10 0CnFIUEI FIU4-7 NUS CORPORATION

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5.0 TOXIC CHEMICAL EVALUATION This section presents the evaluation of the effect of onsite toxic chemicals on the control room habitability.

The buildup concentrations of toxic chemicals at the control room air intake and within the control room volume are evaluated. The results are compared to Regulatory Guide 1.78 requirements to identify the acceptability or unacceptability of the habit ability of the control room under current design with respect to accidental toxic chemical releases.

5.1 Method of Analysis The potential hazardous chemicals in Unit 1, 2 and 3 were located (see Figure 5-1).

Those chemicals that are non volatile (i.e., solid chemicals, lube oil) and in small quant ities (i.e., standard bottle of CO2 ' 2, H2, He, and Argon) were eliminated. The chemicals of concern were assumed to be accidentally released. For the liquified gases the adiabatic flash fraction for the instantaneous puff release and the boiling (evaporation) rate for the continuous release of the remainder of the spill were evaluated based on the set of equations developed in Reference 1. For high boiling point chemicals the evaporation rates were evaluated based on the theory of the binary diffusion.(1,2)

For the additional assumptions and methodology see Appendix D.

5.2 Summary of Results Tables 5-1 and 5-2 show the list of the onsite toxic chemicals and their distances from the Unit 1 control room air intake.

Chemicals like sodium hydroxide, sodium hypochloride and lube oil were not analyzed because they were either not hazardous I

I 5-1 NUS CORPORATION

I I

or non-volatile.

Among the chemicals analyzed only aqueous ammonia and hydrazine posed a potential hazard to the control room habitant under present control room HVAC design.

Table 5-3 summarizes the resultant maximum concentration of the spilled chemicals at the control room air intake and within the control room.

The control room concentration for halon is based on the postulated release of all the 4,500 lbs. directly in the control room.

I It is worth mentioning that the above concentration is based on relative atmospheric dispersion only. No credit is taken for the building wake dilution and/or meandering effect. The toxic limit concentrations shown in Table 5-3 are taken from Section 6.4 of SONGS 2 and 3 FSAR, and Regulatory Guide 1.78.

I 5.3 References

1.

Nathan, S.

J.,

and

Nieto, J.

M.,

"Determination of Acceptable Site Specific Frequancy of Hazardous Chemical Shipments Passing San Onofre Units 2,

3" NUS-1942, September 1977.

2.

Bird, R. B.,

Stewart, W. E.,

and Lightfoot, E. N.,

Transport Phenomena, John Wiley & Sons, New York (1942)

3.

Smith, H., SCE, Telecon (December 15, 1980)

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5-2 NUS CORPORATION

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TABLE 5-1 LIST OF ONSITE CHEMICALS* IN SONGS #1 I

CHEMICAL DISTANCE FROM NAME CAPACITY CONTROL ROOM Liquified N2' 532350 SCFG 260 ft Stored in a satur ated liquid condi tion at 45 psia**

Halon 10 bottles 20 ft of 450 lbs Diesel Oil 4-55 Gal 300 ft Sulfuric Acid 2000 Gal 200 ft Hyadrazine 2-35 Gal 100 ft 35%

Ammonia, Aqueous 2-55 Gal 100 ft 29.4 %

I Only those chemicals that are volatile are considered.

I From Reference 3.

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I N c5-3 NUS CORPORATION

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TABLE 5-2 LIST OF ONSITE CHEMICALS IN SONGS 2&3*

I CHEMICAL DISTANCE FROM NAME CAPACITY CONTROL ROOM Liquid N 2 91,800 lbs 700 ft Ammonia Aqueous 3,000 Gal 1000 ft 29.4%

Hydrazine 55 Gal 1200 ft I

35%

Sulfuric Acid 10,000 Gal 1200 ft I

Diesel Oil **

350 Gal 490 ft Carbon Dioxide 13 Ton 1100 ft List of onsite chemicals was taken from SONGS 2 & 3 FSAR and only those chemicals that are volatile were considered.

The Diesel Oil stored underground was not considered.

I I

I 5-4 NUS CORPORATION

TABLE 5-3 TOXIC CHEMICAL

SUMMARY

OF RESULTS Chemical Spilled Size, Toxicity Release Max. Concentration mg/m3 Does It Evaporation Mode Name location Limi Duration Air Intake Control Meet or Boiling mg/r Sec Room RG 1.78 Rate mg/sec Liq N2 8.14xl04 (lbs) #2&3 1.66x10 5 19 l.1xl06 2.3xl04 Yes 1.9xl01 0 C

1.04xl04 (lbs) #2&3 1.66xl0 5 7.4xl05 6.1xl03 Yes P

34819 (lbs) #1 1.66xl0 5 19 l.1x10 6 2.3xl04 Yes 8.1x10 8 C

4181 (lbs) #1 1.66xl05 1.0xl06 5.3xl03 Yes

-P Lig OO2 1.19xl04 (lbs) #2&3 9.14xl04 118 1.2x105 1.1x104 Yes 3.0xl07 C

1.41xl04 (lbs) #2&3 9.14xl04 7.2xl05 6.9xl0 3 Yes P

Aq NH3 7.50xl03 (lbs) #2&3 70 3923 4.2x10 3 4.2x10 3 No 8.7xl05 C

vi 137.5 (lbs) #1 70 6338 4.2x10 3 4.2xl0 3 No 9.8xl0 3 C

Hn dydrazine 55 (gal) #2&3 6.5 6.60xl04 11.3 11.3 No 3.2x103 C

35 (gal) #1 6.5 8.12x104 704 704 No 1.6xl03 C

Sulfuric Acid 10000 (gal) #2&3 2.0 less than 1 less than 1 Yes 0.5 C

2000 (gal) #1 2.0 1.7 1.7 Yes 19.7 C

Diesel Oil 350 (gal) #2&3 4xl03+

30.7 30.7 Yes 1.8xl03 C

55 (gal) #1 4xl03 280 280 Yes 6.6xl03 C

Halon 1301 4500 (lbs) #1 5.9xl0 5 2.62xl05 Yes Control room concentration is calculated at the end of the evaporation rate.

Refers to a very long time for evapration.

+

Taken from Reference 1.

c

=Continuous release P

=Puff

O4SITE UNIT 1 10 L=19U Distance In Feet

~

NO.

Chemical Location From Air Intake EZJ E=~~

1.

Liquid Nitrogen Wlest Of reactor bldg.

285 WNW

2.

Halon Outs ide 4 KV room -

main bldg.

20 W (bottozm of ELJ Ci C___

4.:

u dA North of condensate tank 200

-SW tis C

C Hydrazine ~~ water deck EC

)C i C

)

C iC i

C iC

6.

Cimoi M-.

fee are unde fee 100 -i viC i

Ci C waeIec Z

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/

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/3 SI?2 UNIS 2 £ 3 TAI UATCRL'W USGST CT 0A Z5 L

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I I

6.0 ATMOSPHERIC DISPERSION ANALYSES 6.1 Introduction Atmospheric dispersion estimates were calculated for both the radiological release and toxic chemical release analyses for the control room habitability assessment.

Calculations were made of relative concentrations

( '/@

values) at the plant control room air intake based on appropriate conservative models and methodology selected for the particular release point characteristics and dose assessment methodology. Values of X/Q were computed considering the following Nuclear Regula tory Commission (NRC) guidance:

o Regulatory Guides Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assess ments at Nuclear Power Plants" (4)

Regulatory Guide 1.78, "Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a

Postulated Hazardous Chemical Release"(5) o Standard Review Plans S.R.P. 6.4, "Habitability Systems"(3)

I 0

NRC Reports NUREG/CR-1152, "Recommended Methods for Estimating Atmospheric Concentrations of Hazardous Vapors After Accidental Release Near Nuclear Reactor Sites"(6) 6-1 NUS CORPORATION

NUREG-0570, "Toxic Vapor Concentrations in the Control Room Following a Postulated Accidental Release" (7)

NUREG/CR-1394, "Diffusion Near Buildings as Determined From Atmospheric Tracer Experiments" (2) o Miscellaneous "Nuclear Power Plant Control Room Ventilation

System Design

for Meeting General Criterion 19",

Murphy and

Campe, 13th AEC Air Cleaning Confer ence.(1 )

Radiological releases from the containment were analyzed based on considerations of building geometries and onsite wind flows.

Figure 5-1 shows the relative locations of the potential release points and the intake.

The dispersion analyses for the toxic chemical assessment are based on releases transported toward the intake.

%/Q values were calculated at various distances for use in the disperion analysis in Section 5.0.

The methodology and meteorological data utilized to calculate the %/Q values are discussed in the following sections.

1 6.2 Calculations -

Radiological Releases 3/Q values for radiological releases from the containment were calculated based on procedures outlined in References 1, 2 and

3.

These releases were assumed to be from a diffuse source (i.e., activity leaking from many points on the surface of the containment) with a point receptor (a single intake).

6-2 NUS CORPORATION

I Y/Q values were calculated for time periods of 0-8 hours, 8-24 hours, 1-4 days, and 4-30 days as recommended in Reference 3.

For the 0-8 hour calculation, results of recent analyses of diffusion tests near buildings were utilized (2) The results of these tests have shown that for most meteorological combi nations of atmospheric stability and wind speed, the model and methodology provided in Reference 1 overestimates even the maximum measured concentration, usually by one to two orders of magnitude.

In addition to the dispersion test results utilized in Reference 2, data from dispersion tests at the San Onofre site were also evaluated.(8) Although these tests were not specifically applicable to this type of evaluation (the tests were conducted under specific atmospheric conditions only and at distances greater than those analyzed in this report), the results substantiate the test data provided in Reference 2. The San Onofre onsite tests show the same order of magnitude overestimation of calculated concentrations to measured values as NUREG/CR-1394.

Because of this large overestimation of the NRC model, the 0-8 hour %/Q was calculated based on the recommendations of Reference 2. The studies provided in the reference were con ducted at two dissimilar sites with containment areas dif fering by nearly a factor of two. Consistency between the two sets of measured concentrations was obtained by scaling the plume path length by the square root of the minimum cross sectional area of the containment.

Utilizing this approach and Figure 9 of Reference 2, a one hour

/Q for San Onofre Unit 1 was calculated.

This one hour value was conservatively assumed to apply for 0-8 hours and also reflects an upper bound envelope of measured concentrations.

The assumptions for this determination are outlined below.

Containment Cross-Sectional Area

=

1440 m2 Minimum Distance to Intake

=

45 m 6-3 NUS CORPORATION

I Scaled Distance 0.95 Y/Q from Figure 9 of Reference 2

=

1.5 x 10 sec/m3

/Q values for the remaining time periods were calculated utilizing the methodology in Reference 1.

Analysis of the plant building configuration indicates that 6 wind sectors could affect the intake for releases from the containment.

Winds from the south-southwest through northwest were utilized in the analysis. Data from these wind sectors were then used to obtain the wind speed and direction factors needed to calculate the Y,/Q values for the 8-24 hours, 1-4 days, and 4-30 days time periods.

Diameter of Containment

=

44 m s/d Ratio

=

0.80 Wind Sectors

=

SSW, SW, WSW, W, WNW, NW Wind Speeds (10 m) 5%

=

1.1 m/s 10%

1.4 m/s 20%

=

1.9 m/s 40%

=

2.7 m/s Wind Direction Frequency

=

43.28%

Factors used to adjust the X_/Q values for the various accident periods (obtained utilizing the methodology from Reference 1) are provided in Table 6-1.

Z/Q values are provided in Table 6-2. Meteorological data used in the calculations are discussed in Section 6.4.

6.3 Calculations - Toxic Chemical Releases The relative atmospheric disperion values were calculated to support the toxic chemical analysis. These calculations pro duced from continuous release (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), direction independent f'/Q values at a series of distances out to 500 m from the 1

6-4 NUS CORPORATION

I plant.

These X'Q values are given in Table 6-3.

These calculations utilized Equation 1 of Regulatory Guide 1.145 (Ref.

4),

without the building wake credit or plume meander.

From these calculated values of 41Q, the corresponding average wind speed was calculated (based on an extremely stable GI atmospheric stability class which is representative of 5% con ditions) for use in the toxic chemical analysis discussed in Section 5.0.

6.4 Meteorological Data Meteorological data utilized in the atmospheric dispersion analyses were collected onsite during the three year period January 25, 1973 through January 24, 1976.

The data used for each analysis are listed below.

Atmospheric Wind Speed/

Combined Analysis Stability Wind Direction Data Recovery I

Radiological N/A 10 m Level 96%

Releases-Con tainment Toxic Chemical AT 3 6m-6m 10 m Level 88%

Releases and A T4 0 m-10m The joint frequency distributions of wind speed and wind direction, by atmospheric stability class are provided in Appendix E.

A description of the onsite meteorological system is provided in the SONGS 2 and 3 FSAR Section 2.3.

I 6-5 NUS CORPORATION

I 6.5 References

1.

Murphy, K.

G.

and Campe, K.

M.,

"Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19," 13th AEC Air Cleaning Conference, August 1974.

2.

Sagendorf, J. F.,

Ricks, N. R.,

Start G. E.,

and Dickson C. R.,

Diffusion Near Buildings as Determined From Atmospheric Tracer Experiments, NOAA Technical Memorandum ERL ARL-84 (NUREG/CR-1394), April 1980.

3.

U.S.

Nuclear Regulatory Commission, Standard Review Plan, NUREG-75/087 Section 6.4, "Habitability Systems."

4.

U.S.

Nuclear Regulatory Commission, Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants", August 1979.

5.

U.S.

Nuclear Regulatory Commission, Regulatory Guide 1.78, "Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release", June 1974.

6.

Connell, J.

R.

and Church, H.

W.,

"Recommended Methods for Estimating Atmospheric Concentrations of Hazardous Vapors After Accidental Release Near Nuclear Reactor Sites", Sandia Laboratories, NUREG/CR-1152, April 1980.

7.

U.S. Nuclear Regulatory Commission, "Toxic Vapor Concen trations in the Control Room Following a Posutlated Acci dental Release", NUREG-0570, June 1979.

8.

Septoff, M.

and L.

Teuscher, "Report of Tracer Tests Conducted at the San Onofre Nuclear Generating Station,"

NUS-1702, April 1976, NUS Corporation.

6-6 NUS CORPORATION

m A

M M

m O

o M

UM TABLE 6-1 ADUS'IMENT FACTORS USED 'TO CAlTjLATE EFFCTIVE RELATIVE CONCENTRATIONS FOR SELECTED TIME INTERVALS (RELEASES FROM THE CONTAINMENT)

SAN ONOFRE UNIT 1 Adjustment Time Interval Factors 0-8 irs.

8-24 Hrs.

1-4 Days 4-30 Days Wind Speed 1.0 0.79 0.58 0.41 Wind Direction 1.0 0.86 0.72 0.43 Occupancy 1.0 1.0 0.60 0.40 Overall Reduction*

1.0 0.68 0.25 0.07 The overall reduction factor is defined as the products of the wind speed factor times the wind direction factor times the occupancy factor.

z C

O 31 O

0 0 z

-m mmrme-m-mma-ame TABLE 6-2 CALCULATED X/Q VALUES AT THE CONTROL ROOM INTAKE FOR RADIOLOGICAL RELEASES FROM THE SAN ONOFRE UNIT 1 CONrAINEr (INCLUDES OCCUPANCY FACIOR)

Time Period X/Q (sec/m3 0-8 Hours 1.5 x 10-3 8-24 Hours 1.0 x 10-3 1-4 Days 3.8 x 10-4 4-30 Days 1.1 x 10-4 00 z

c cco 0

0 0

II 0

z

I TABLE 6-3 I

ONE HOUR /Q VALUES FOR THE TOXIC CHEMICAL ANALYSIS AT SAN ONOFRE UNIT 1 No Meander, No Building Wake, No Initial Plume Volume, 5% Direction Independent I

Distance ()/Q (sec/m3 (mn)

(ft) 100 330 3.3 x 10-2 150 490 1.7 x 10-2 200 655 1.0 x 1o-2 250 820 7.0 x 10-3 300 985 5.1 x 10-3 350 1150 3.9 x 10-3 1

400 1310 3.1 x 10-3 450 1475 2.6 x 10-3 500 1640 2.2 x 10-3 I

I I

I 6-9 NUS CORPORATION

I I

APPENDIX A I

I I

I A-i U

NUS CORPORATION

U 1

1.

Control Room Mode of Operation in the event of a radio logical accident isolation or chlorine release:

Response

The control room emergency HVAC is manually selected in the watch engineer's office and is designed to filter the control room air intake during a radiological accident.

Chlorine is not utilized in the plant operation in suffi cient quantities to cause concern for control room habitability.

I

2.

Control Room Characteristics:

3

a.

air volume:

Response

27,521 cubic feet calculated from available drawings.

b.

control room emergency zone:

Response

The emergency zone includes the control

room, watch engineer's office, and the I

central alarm station.

c.

control room ventilation system schematic with normal and emergency flow rates:

Response

See Figure 3-2

d.

infiltration leakage rate:

Response

The infiltration leakage rate will be calculated after completion of the control room configuration change.

I 3

NA-2 NUS coRPORATioN

I I

e.

HEPA filter and charcoal adsorber efficiencies:

I

Response

HEPA efficiency tested at 99%.

3 charcoal adsorption efficiency tested at 99%.

f. closest distance between containment and air intake:

Response: Approximately 45 meters.

g.

layout of control

room, air intakes, containment

building, and chlorine or other chemical storage I

facility with dimensions:

Response

See figure 3-1, 3-2, and 5-1 of this report.

h.

control room shielding including radiation stream ing from penetrations, doors, ducts, stairways, etc.:

Response

See SCE response dated September 22, 1977 to NRC question regarding control room operator doses.

(Reference 1 of Section 4 of this report).

i.

automatic isolation capability--damper closing time, damper leakage and area:

Response: Isolation must be manually selected in the watch engineer's office.

Damper closing time and leakage tests have not been conducted.

The A-31 normal fresh air inlet damper area is two (2) square feet.

I A-3 NUS CORPORATION

I I

j.

chlorine detectors or toxic gas (local or remote):

Response

None provided.

k.

self-contained breathing apparatus availability I

(number):

Response

Nine SCBA are kept in the control room and TSC.

1.

bottled air supply (hours):

Response: Nine SCBA bottles at 24.88 SCF (224 SCF),

32 cylinders at 43 SCF (1376 SCF),

2 cylinders at 200 SCF (400 SCF) equals 2000 SCF for a total of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

M.

emergency food and potable water supply (how many days and how many people):

Response

None stored in control room.

n.

control room personnel capacity (normal and emergency):

Response

The shift complement for normal oper ations is five people.

During emergencies, the number of people in the control room will be increased by one or II two at the descretion of the watch engineer.

I I

A-4 NUS CORPORATION

U I

0.

potassium iodide drug supply:

Response

There are 900 potassium iodide tablets stored in the control room emergency kit.

U3.

On-Site Storage of Chlorine and Other Hazardous Chemicals:

a.

total amount and size of container:

I

Response

Chlorine is only used in the liquid (hyprclorite) form for water treatment.

I Other hazardous chemicals stored onsite are evaluated in Section 5 of this I

r epor t.

b.

closest distance from control room air intake:

Response

See figure 5-1 of this report for hazardous chemical locations.

4. Off-Site Manufacturing, Storage or Transportation Facilities of Hazardous Chemicals:

Ia.

identify facilities within a five-mile radius.

b.

distance from control room.

C.

quantity of hazardous chemicals in one container, and

d.

frequency of hazardous chemical transportation traffic (truck, rail, and barge)

Response

Under evaluation -

to be determined later.

A-5 3

NUS CORPORATION

I I

5.

Technical Specifications:

a.

chlorine detection system:

I

Response

There is no chlorine detection system in the control room.

b.

control room emergency filtration system including I

the capability to maintain the control room pressur ization at 1/8-inch water

gage, verification of isolation by test signals and damper closure time and filter testing requirements:

Response: Chapter 4.11 of the San Onofre Unit 1 technical specifications provides the surveillance requirements of the fans and associated charcoal and absolute falters for the control room.

Damper closure time is not recorded.

I I

A-6 NUS CORPORATION

I I

APPENDIX B COMPARISON OF THE SONGS-1 CONTROL ROOM TO THE CRITERIA OF NRC STANDARD REVIEW PLANS 6.4, 9.4.1, AND 6.5.1 I

I I

B-1 NUS CORPORATION

I I

B.1 COMPARISON WITH SRP 6.4 B.1.1 Control Room Emergency Zone The control room emergency zone includes the control panels and consoles for the control of unit #1.

a.

The control room safe shutdown controls are within the control room emergency zone.

b.

Unit 1 does not have a computer room and therefore, it is not part of the emergency response plan.

C.

There is a separate watch engineer's office (room 302).

The shift supervisor and the watch engineer is a dual role position.

d.

The washroom and kitchen are not included within the emergency zone.

e.

The cabinet room and relays are accessible from the control room.

B.1.2 Control Room Personnel Capacity I

The occupancy of the control room is five men during normal 3

operation and will be increased by one or two at the discre tion of the watch engineer for emergencies.

There were no specific storage facilities for food, blankets and cots for the normal occupancy of five days.

I I

I B-2 NUS CORPORATION

I I

B.1.3 Ventilation System Layout and Functional Design A

more detailed system description is provided in Section B.3.2 of this report. Isolation is effected manually on high radiation alarm in the control room. In isolation the fresh air intake is closed. The system is designed to press urize the emergency zone to prevent infiltration.

Ia.

The isolation dampers are of standard commercial quality without resilient seals.

I

b.

The isolation dampers, emergency filter and filter fan A-33, and the air conditioning unit are not redundant components.

IC.

The system is designed to pressurize the control room.

(The leakage rates will be calculated for dampers, doors and penetrations upon completion of the configuration change.) (1)

B.1.4 Toxic Gas Protection I

Self-contained breathing apparatuses are available in the control room.

No special protection against toxic gas intrusion and no toxic gas detectors are provided in the design of the control room.

B.1.5 Emergency Standby Filters See paragraph B.3.2 and B.3.3 below.

I I

B-3 NUS CORPORATION

I I

B.1.6 Relative Location of Source and Control Room I

a.

The control room ventilation air inlet is on the west wall of the control and administration building approximately 45 meters from the containment.

I

b.

Toxic gases -

Unit 1 onsite toxic gases and offsite sources of hazardous chemicals are addressed in section 5.0 of this report.

c.

Confined area releases -

The potential for contam ination of the control room air from releases inside adjacent areas of the building will be discussed after completion of the configuration change.(1)

However, the potential for contamination appears to be negligible.

d.

Failure of the recirculation fan A-31 will cause loss of control room pressurization and could result in an increase in the radioactivity or gas concen tration during a postulated accident.

I

e.

The system can be electrically loaded to the emergency diesel generator bus.

f.

Loss of ventilation to the HVAC equipment room will have little effect on the control room system per formance.

I I

I B-4 NUS CORPORATION

I B.2.2 Separation Analysis None of the control room ventilation equipment is redundant.

I The refrigerant condensers located on the east wall are exposed to the same outside hazards such as tornado or other flying debris.

B.2.3 Analysis of Failure of Nonseismic Equipment Except for ducting, the HVAC system is located on the second floor of the control and administration building and is fairly well protected from damage by other equipment or building seismic failures.

However, seismic failure of one or more of the HVAC system components within the HVAC room could disable the entire system. Ducting routed through the cable spreading room, adjacent to the TSC, and through the control room is not seismic qualified nor is it protected from seismic debris.

B.2.4 Adequacy to Maintain Suitable Environment Years (14) of operating experience indicate that the system design is adequate to maintain a suitable environment for men and machines.

B.2.5 Ability to Detect, Filter and Discharge Airborne Contaminants in the Control Room There are no radiation monitors or gas detectors on the air intake to the control room.

There is a radiation monitor located in the control room on the control panel (southwest corner near the #1 diesel generator panel).

It will alarm the system so that the watch engineer can manually switch to the emergency (air intake A-33) mode if the radioactivity exceeds the setpoint of 1.0 millirem per hour.

I B-5 NUS CORPORATION

I I

The normal ventilation rate will be determined when the con figuration change is complete.

It should be adequate to clear the control room of smoke and fumes within approximately 30 minutes.

B.2.6 Provisions to Detect and Isolate Portions of System in Fires, Failures and Malfunctions Because the system serves no other area, it is not necessary to isolate a portion of the system.

I B.3 REVIEW AGAINST ACCEPTANCE CRITERIA OF SRP 6.5.1 B.3.1 The System Was Designed to Operate After a DBA by I

Manual Control from the Control Room B.3.2 Comparison with Paragraph 11.2 of SRP 6.5.1

a.

A high efficiency filter (HEPA) is not provided after the charcoal filter.

A prefilter and HEPA filter are provided.

A moisture separator is not required in this application.

b.

No redundancy of the filter system was provided.

c.

All components are not seismic category I by current standards.

d.

The filter system design flow is less than the 30,000 CFM maximum defined in SRP 6.5.1.

I

e.

The single filter system does not record pressure drop or flow rate.

I B-6 NUS CORPORATION

I I

f.

The emergency filter system is not activated auto matically by a DBA, it must be switched manually.

There could be a significant delay between the time intake of contaminated air begins until the sensing of radioactivity, interpreting the visual reading, and the manual switchover to the isolation (emergency) mode is completed.

B.3.3 Comparison with Paragraph 11.4 of SRP 6.5.1

a.

The filter design predated AINSI N509-1976 and is not I

constructed for and does not have provisions for the testing described in Section 5.4 of ANSI N509-1976.

b.

Since high relative humidity is not expected, mois ture removal equipment is not required to assure a relative humidity less than 70%.

IC.

There are no provisions for testing prefilters separately from the HEPA filters.

d.

The HEPA filters cannot be accurately tested in place because there is no access between the HEPA and charcoal banks.

Ne.

Filter and adsorber

-mounting frames are not in accordance with current practice and ANSI N509 I

1976.

f.

Filter housings including floors and doors are not in accordance with ANSI N509-1976.

Lights and viewing ports are missing, as well as fire pro tection for the charcoal filter.

I B-7 NUS CORPORATION

I I

g.

Water drains were not provided because no sprinkler system was provided.

h.

The adsorbent is acceptable for adsorbing gaseous iodides.

i.

The adsorption unit maximum loading of total iodine is unspecified but is expected to be compatible with current standards of quality.

j.

No provisions (fire detectors) were included to pro vide warning of higher than design temperatures in the adsorber section. There is a steady flow of air leaking through the dampers that cools the filter but also could load the filter with hydrocarbon fumes to eventually reduce the adsorber capacity.

k.

The recirculation system fan ductwork has holes in the connections downstream of the adsorber section which could permit unfiltered air to enter the emergency zone ventilation system.

1.

The ductwork was designed to Sheet Metal and Air Conditioning Contractors National Association (SMACNA) low pressure duct construction standards.

This type of construction allows excessive leakage both inward and outward of ductwork and is not in accordance with ANSI N509-1976.

I

m.

The dampers are not low leakage dampers.

I N

cB-8 NUS CORPORATION

I I

B.3.4 Comparison with Paragraph 11.5 and 11.6 of SRP 6.51 The Space between mounting frames and the provisions for testing each filter stage do not meet the criteria of these paragraphs.

I B.3.5 Equipment Environment The control room HVAC equipment is located in the HVAC Equip ment Room and is designed to meet the conditioned environment of that room.

The filters are not shielded and could become a radiation source after.a postulated design basis accident.

B.3.6 Component Design and Qualification Testing

a.

The design standards of the filter system are not in accordance with current practice and do not incor porate the recommendations of ANSI N509-1976.

b.

No protection was provided against charcoal fires.

3 B.3.7 In-Place Testing Both HEPA and charcoal filter systems have been tested. From the test results, (2) the filter performance is acceptably above minimum efficiencies.

B.4 References I

1.

Santa

Ana, Fabian, "Configuration Change, Control and Administration Building - Area 10 Heating Ventilation and Air Conditioning Plan and Sections, Third Floor",

SCE, Drawing No. 568664 Revision 6, J.O. No. 7764.

B-9 NUS CORPORATION

I I

2.

San Onofre Nuclear Generating Station Engineering Procedure S-V-2.8, Revision 2, (May 17, 1978).

I I

U I

I I

B-10 3

Nus coRPORATION

I APPENDIX C METHODS USED IN RADIOLOGICAL ANALYSIS The control room dose calculation model consists of a release pathway model and a dose evaluation model. The release model computes activity inventories and releases in the containment and control room based on TID-14844(l) releases and prespec ified flow rates, filter efficiencies, halogen non-removal

factors, and meteorological data.

The dose model computes individual doses within the control room.

S I

3 I

I IC-1 NUS CORPORATION

I C.1 RELEASE MODEL The activity release pathway model is shown in Figure C-1.

Four activity nodes are represented:

two primary containment volumes (sprayed and unsprayed), the secondary containment volume and the control room. The equations for nodal activities, contain ment release and integrated control room activity are derived from first order activity balances in the following paragraphs.

These equations form the basis for the NUS developed com puter code AXIDENT(.

The definition of all variables used is presented in section C.3.

C.1.1 Primary Activity The primary containment activity is the sum of the activity in the sprayed and unsprayed regions.

A A +A 2 (1) dA dt Ap lAl r Al p

1 1

2 (2)

I dA2 A

A + a A (3)

A2 X rA2 p A 2 V 2 2

V 1 1

I I

'I C-2 NUS CORPORATION

The simultaneous solution of (2) and (3) when combined with (1) gives the primary containment activity as A

= C2-e-m2t - C e-mlt (4)

A 10 (X 1 ml) +A 20 2 - ml I

C =

1(5) 2 m

-im 2

1 C

A10 1

2

+

20 2

m2 (6) m-m)A 0

i 2

2 1

mlm

=

+

+1(7) 1~1 2

2

-+ 1 V

V L

1 2

-4 (

+

gV

+ V 2

v2 1

11 X

= )+X+,~+X(8) 1 1

r p

sp I~~

=

)+

+X (9) 2 I

r p

A 1

-4 em2t- 03 e-mlt (10) 1143 C-3 NUS CORPORATION

A (1-M +

) -

A 10 1

1 V I V 20 C

=

(11) 21 10n1-2n V2 20 2 1 2

C 2 (C2-CMe 1(12)

A2

=

2 -

4) e-m2 (CI - C3 )e -m1t (13)

Note that the above solution for Ap degenerates to a one-volume problem if X

= 0.

C.1.2 Secondary Activity The rate of change of secondary containment activity is the fraction of the primary activity which goes to the secondary containment less the removal by decay, clean-up, and leakage (or exhaust) to the environment.

dA s

=

f kA 3A rA A

(14)

I

~dt s 1p 3 s r s s s

=

f A -).A (15) s 1p 4 s 4

=

+

r +

(16)

I4 3 r s flC f)lC A

f s 1 2 e-m2t f S I 1 e-m1t + C e-4t (17) s 4 -

2 4-m 5

I C

A 2

S+ ).

1 (18) so 14 -m 2 4 - ml C-4 NUS CORPORATION

I I

C.1.3 Containment Activity Release Rate 1

The containment activity release rate has two components; the secondary containment release,after filtration, and the frac W

tion of the primary containment leakage which bypasses the secondary containment.

R F3A + (1 - f )

A (19) 3 r

3 s si1p R

=

F fX [e M

2 t em1 (20) r 3S 1 L 4 -in 2 4

1 S+FX C e 4 +

3 5 (1I fs 1

)

C2 e-mIn2t -

Cl1 e-m1 t R =

6 2 - Ce 1 + Ce 4 (21) r 6

7 8

FX 3 s C

=I-

+ i - f 1(22)

I 4

4-M2 lC C 7 3 s

+ I -f S C

(23)

C 8 3 C)

I C-5 NUS CORPORATION

1 I i C.1.4 Integrated Release from Containment The integrated release from the containment is obtained by inte grating the release rate, equation 21, over the time period of interest.

R

=fRrdt (25)

R 6

-m2 t 7

-m t 8

-4(26)

( 1-e

)

(1 -e

) +

-8 (1-e

)t(6 M2 eM1

(-

x4 C.1.5 Control Room Activity The rate of change of activity in the control room is the differ ence between the rate at which activity is drawn in from the outside air and the rate at which it is removed by decay, clean up, and leakage (or exhaust).

dAc

= F q (X/Q)

R - xA -

cc A -

A 2cc c r r c V

c cc (27) dt cc dAc

=

C Rr X7A (28) dt

=

r +

cc

+

(29) cc C

= F 2 q VQ)

(30) 9 2 cc c

MA

= C C e-m2t - C C e -mit+ CC e -\\4t dt 96 97 9

I d-7 A

(31)

A

=

C C6

-m2t C C7 e

lt C C8 e

4t c

-m2 7-mA7 A4

+C e7t (32)

I C-6 NUS CORPORATION

I I

CC6 CC C C83

=A 6

+

97 98 (33) 10 co 7 - m 2 1 - m 7

x4 C.1.6 Integrated Activity in Control Room The integrated activity in the control room is obtained by integrating equation 32 over the time period of interest.

SRc

=fAcdt (34)

C 9C 6

-m C9C7

-Mt R

(1-e m2 t) -

(-e it) c (17 -2

)M2 mlI (X7 -

mi)

+

9 C8 (1-e ) 4t)

( 1 - e-17t)

(35) 4 7

4 7

Implicit in the above derivations is the assumption of con stant coefficients.

In the actual transient simulation, solutions are broken into a sequence of discrete time inter vals over which the input parameters which make up the coefficients are prespecified constants. The input parameters consist of flow rates, X/Q's, decay and iodine removal con stants, provided as stepwise constant functions of time.

Initial secondary containment and control room activity inven tories are assumed to be zero. Initial primary activity may be based on the analysis of TID-14844(1 ) using the fractional iodine release assumptions of Regulatory Guide 1.3(2) or 1.4(8).

The source term equation is:

-_xT U

~3 rto A

= 8.6S x 10 P 0 ff( 1 - e

) (curies)

(36)

I

~

C-7 NUS CORPORATION

1 I

C.2 DOSE MODEL At the end of each time interval,control room individual thy roid and whole body doses are determined using the containment release rate, integrated control room activity and input values of 7/Q at the control room intake.

Thyroid inhalation dose in the control room is given by the following equation:

D T DT (rem)

U 1i1 BR Rc.DCFI (37) cc where BR = breathing rate

-4 3 (3)

= 3.47 x 10 m /sec Beta dose in the control room is given by:

D

=

D (rem)

(38)

I I

0.23 R C cwhere c

(39) 3T

= average beta energy (MeV/dis)

(See Table C-2)

I I

ucC-8 3

NUS CORPORATION

3 I

Gamma dose in the control room is given by DI=

D I (rem)

(40)

I 0.25 R'

L f~

e/uir

+

A r

(41)

Gamma energies and fractions are presented in Table C-1.

Ab sorption coefficients divided by the density of air are listed in Table C-2.

I I

I C-9 NUS CORPORATION

U I

C.3 NOMENCLATURE A = Primary Containment Activity Ap = Activity in sprayed Volume A2 = Activity in unsprayed volume 1 = Primary containment leak rate r = Radiological decay constant (See 1 ) (See Table C-1)

X = Cleanup rate in primary containment p

f

= Fraction of activity released to sprayed volume f= Fraction of activity released to unsprayed volume V1 = Sprayed volume V2 = Unsprayed volume X3 = Secondary leak rate Xsp = Spray removal rate fs = Fraction of primary leakage which enters secondary F = Filter non-removal factor for secondary building exhaust system F2 = Filter non-removal factor for control room (center) intake system (X/Q)c = Atmospheric dispersion to control center qcc = Control center intake flow Vcc = Control center volume Yi = Average gamma energy (MeV/dis) (See Table C-2)

= Average beta energy (MeV/dis) (See Table C-2)

R. = Integrated release from containment (Ci) 1 V cr = Control room free volume (m 3 )

Ey

= Energy of jth gamma of ith isotope (MeV/X) (See 3

i,j Table C-3 C-10 NUS CORPORATION

I I

f.

= Fraction of jth gamma of ith isotope (y/dis) a

= Energy absorption coefficient for air (m-)

(See aj Table C-4)

= Total absorption coefficient for air (m )

(See Table C-4) r = Radius of hemisphere with same volume as control room (m) s = Cleanup rate in secondary containment I

xc =

Cleanup rate in control room V

= Control center free volume (m3 Rc. = Integrated control room activity (Ci-sec) 1 DCT. = Dose conversion factor (rem/curie)

(See Table C-2)

Po = Base loaded core power (Mwt)

y.

= Fission yield (percent) (See Table C-1)

T0 = 1000 days (assumed) f = Fraction of core inventory available for release

= 0.25 (for iodines)( 2 )

= 1.0 (for noble gases)

f. = 0.91 (for elemental iodine)(2 )

1

= 0.05 (for particulate iodine)

= 0.04 (for organic iodine)

=1.0 (for noble gases)

Q = Mixing flow rate between sprayed and unsprayed volumes I

I C-ll NUS coRPORAnION

I C.4 REFERENCES

1.

DiNunno, J. J., Anderson, F. D.,et al., "Calculation of Distance Factors for Power and Test Reactor Sites,"

3 TID-14844, March 1962.

2.

Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Cool ant Accident for Boiling Water Reactors," Directorate of Regulatory Standards, U.S.A.E.C., Rev. 1, June 1973.

3.

"Report of Committee II on Permissible Dose for Internal Radiation," International Commission on Radiological Pro tection, Pergamon Press, 1959.

1

4.

Meek, M. E. and Rider, B. F., "Summary of Fission Product 235 239 241 Yields for U

, Pu

, and Pu at Thermal, Fission Spectrum and 14 MeV Neutron Energies," APED-5398, March 1968.

I

5.

Lederer, C. M., et al., Table of Isotopes, 6th Edition, John Wiley and Sons, New York (1968).

6.

"Final Environmental Statement Concerning Proposed Rule Making Action:

Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Crite rion 'As Low as Practicable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents,"

WASH-1258, Volume 2, Directorate of Regulatory Standards, U.S.A.E.C., July 1973.

7.

Hubbell, J. H., "Photon Cross Sections, Attenuation Coeffi cients, and Energy Absorption Coefficients from 10 KeV to 100 GeV," NSRDS-NBS 29, August 1969.

I II C-12 NUS CORPORATION

I I

8.

Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors," Directorate of Regulatory Standards, U.8.A.E.C., Rev. 2, June 1974.

9.

Nathan, S. J., "Axident -

A Digital Computer Dose Calcula tion Model," NUS-1945, August 1979.

I I

I C-13 NUS CORPORATION

I I

TABLE C-1 NUCLIDE DECAY CONSTANTS AND FISSION YIELDS(4 )

Decay Constant Fission Yield

'-1 Nuclide (sec

)

(percent) 11 3 1 9.97 (-7)*

2.91 Il32 8.37 (-5) 4.33 Il33 9.17 (-6) 6.69 1134 2.22 (-4) 7.8 1135 2.87 (-5) 6.2 Kr83m 1.03 (-4) 0.52 Kr85m 4.38 (-5) 1.3 Kr85 2.04 (-9) 0.27 87 Kr 1.52 (-4) 2.5 Kr88 6.88 (-5) 3.56 Xel31m 6.79 (-7) 0.022 Xel 33m 3.55 (-6) 0.17 Xe 1 3 3 1.52 (-6) 6.69 Xel 3 5m 7.40 (-4) 1.8 Xel 35 2.11 (-5) 6.3 Xe1 3 8 6.60 (-4) 5.9 I

I

Read as 9.97 x 10 I

C-14 NUS CORPORATION

I I

TABLE C-2 AVERAGE BETA AND GAMMA ENERGIES AND IODINE INHALATION DOSE CONVERSION FACTORS Nuclide y(MeV/dis)(5) 8(MeV/dis)(5)

DCF (Rem/Curie)(6) 113 1 0.371 0.197 1.48 (+6) 1132 2.40 0.448 5.35 (+4) 1133 0.477 0.423 4.00 (+5) 1134 1.939 0.455 2.50 (+4) 1135 1.779 0.308

.1.24 (+5)

Kr8 3m 0.005 0.034 Kr 0.156 0.233 Kr 85 0.0021 0.223 Kr 8 7 1.375 1.050 88 Kr 1.743 0.341 Xe 0.022 0.135 Xe1 3 3m 0.033 0.155 Xe 1 3 3 0.030 0.146 Xel 35m 0.422 0.097 Xe1 35 0.246 0.322 Xe 2.870 0.800 I

I I

I C-15 NUS CORPORATION

TABLE C-3 ISOTOPIC GAMMA ENERGIES AND DECAY FRACTIONS(4 )

t*131 1*132 1-133 1134 1*135 XE*131H xE*Il33N XE*133

,9308 5.640c*.itWZ 2.IOE-03

.5300 9.*0E-01

.1360 5.00E-02

.2204 1.0E002 O0S06.00E-0Z

.0297 leite**

.0308 3.8e*O*I 93RG2 2.509-64.2630 2.00E-02

.7500 2.00E0.2

.1800 7.00E-02

,2864 3.40E-02

.0300 59CE001

.0338 3.261-02

,o353 8,601-0?

1172 2.0L-01

.Ri5o 5.00E-01

.0609 7.01-02

.3900 7.001-02

.4175 3,20L-02

.1640 2.30C02

.2320 6.001*02

.0796 6,00(-03

.26&) 5.90E*02

.500 I.00E-02 1.0330 1.00E-02 04100 6,001-03 44J40 6.20E-05

.080 3,70!-01

12%8 2

.0-0l s5010 2.00t-02 1.200 2,00e-02

.4300 3.00E-02

,5?69 1.49L-01

.1607 6.601-44

,1645 7,97E1-t.523 0

.b01-01 1,3i0 2,00E-02

.5100 9.00f-01 1%465 6.20k-02

.2234 2.40(-06

.50l0 306@-41

6?06 4.00*02

.5400 8,00-02

.7071 5.90E-01 0301t 5.10E*O5 6370 6.8*L-0

.6330

.90-01

.b00 i.49E-01 369 5.00L-02

.3841 2.30$*04 729 1o0cw0e0

.450?

4,00f-0?

.6900 7&300-D0

.91P0 1.80E-02

.6LI Q.00E-o2

.7500 1.ooE-b2 I.0387 9.00V-02

bold 9,z4E-01

.7100 6,00-002 1.1011 1.10-020 st.h97 6.001-02

.0500 9.50L-91 1.1213 3.iE-02

$67t0 60001-02 08600 4.00c-02 141316 1,75L-01

.7210 3J20E-02 60900 7.00c-u0 1.1691 7.90E-03

.7290 3.20E-02

',9600 2.000-02 1,2604 2,50L-01 C, 71?9 8101O-01 1 0000 5.00-02 1,11575 7.00-02 I

.9547 194t-o1

.1.0700 1511E-0II

.51029

.201..02 5.l3)0 2.001-02 1.1500 1.201-01 1.5659 1.40-02 1,600 a4.CGL-02 1,2000 1.00E-02 1,6185 9.03-02 1.?200 7.cM-04 1,3400 2,o0E-02 1.7010 3.60f-02 1.2400 6,000102 1,4600 4.00E.02 1.7919 7,60E*02 5.1630 2.COL-02 1,4900 1900E-02 1.6314 6.40E5O 1.380 8.00l-02 1,6200 5.000-o2 2.0467 8,301-03 14,1400 3.00L00z 1.7900 5.00E-02 a.2567 6.30E*03 1.1200 300E-03 2.4079 9.00E-03 I 1100 S.1)0-03 1.9100 1.30E-02 1.v 1 0 Itstro02 2.C4#0 3.00E03 2.1600 2,00(-03 as?200 2.00-03 2.3900 2,00E*Cl 2.5500 5.OOt-04 z

2g6690 2.601.04 C) 0 O

O O

0 z

TABLE C-3 (Continued)

ISOTOPES@ GAMMA (RCIES AND FRACTION3 Ifa135M U1-133 XE-136 KR*53't KR-8SN KA..85 K61-87 KR-18

,0043 4*001oII s0110 4,501-02

.0300 3.0OE-02

.0016 8001F 02.0016 6.501-0 0.5104 0.35E-03 4030 5090-03

$1660 6.93E.02

93,1.jsI53ol.01.50S 2.10[-0I

.1560 7*OE-0a

UovJ 8.00.402

.0126 5,20L"02 6 741 2.50E"0?

.1961 3.611-01 9$276 Osl@C-01

1999 20OOE-0I

?4J30 3.6O&"02

.0128 1.60fw01

.1495 7*10E-01

8360 8.001-03 o3L66 0~2 92498 9.16E-01

?Sq0 3.70E-01

.3050 i#35E*01

f005q 6,10k-02

39~l 6.v~f-sl

&31$b 2.20L-01

.3970 7.OOE.0a 017,35 1.U40L'02 40.23

.i3

.3131 1.301-00 0020 2,80E-02 I,3V0-7950L-01

."J-17 1.31!-0I

.4382 3,30E-01

4340 2.10E-01 193UU0 5.50E-01 vtb2a; 15,ofE-03 g5113 as.sL-5 1,7700 20000-01 1.7100 2,00t-02,9V7 1 h:102

.6066 2,401-62 2.0000 1460E-01 2,0120 2,60L-02 1 *14i7 1.'3E-CG2

.6546 3.20E-04 2.5560 9,50L-02 1.10.15 9.0(L-03 s719 4.40E".04

?.5590 5,10E-02 1.25n). 3.3'E-)2

.8126 SOOCE-04 2.AII2 4001-03 1.5I.32 1.5it[*Z2 1.0630 3.M~wO5 3.3C98 6.00E-03 1.52,13 3~E 2*19*59 1.s*-01 2l2316 3.60E-02 2.393 3.82-01 z c 0

0 0 z

I TABLE C-4 ABSORPTION COEFFICIENTS FOR AIR(7)

E u/p a/p 2 MeV cm /qM

.01 4.99 4.61

.015 1.55 1.27

.02

.752

.511

.03

.349

.148

.04

.248

.0669

.05

.208

.0406

.06

.188.

.0305

.08

.167

.0243

.1

.154

.0234

.15

.136

.0250

.2

.123

.0268

.3

.107

.0288

.4

.0954

.0295

.5

.0870

.0297

.6

.0805

.029C

.8

.0707

.0289 1.0

.0636

.0280 1.5

.0518

.0257 2

.0445

.0238 3

.0358

.0212 4

.0308

.0194 I

(1)

Table 3.-27, NSRDS-NBS 29 (2) Table 1.-7, NSRDS-NBS 29 I

C-18 NUS CORPORATION

El-Is) At REMOLINRESSIRES FILTERDOSE DIERSION A3 INTA E SPRAYED FL REMOVAL 1

F2 RATE 0r f CONTROL Room

'IDECAY)

ApA A

A.

-~ -

1 20 3

UNSPRAYED Al Is n i l REMOVAL MIXING RFMOVAL rAF FLOW RATE FILE A,

DOSES 1A 1

PRIMARYCONTAINEATEL1 FITE AC FIGUREC-i. DSE MODL ACTIITY EFOV~AL I

BOUNDARY Z

c co 0

0 0

z

I a)

Puff release 22 2

(X/Q I) =

X puff EXP

+ 2 Y

+

a2 Z ax +a 0o 2

2 2

2 -1 x

I

"+aI az+aI X

f 7.87

(

)

(a + a )

Puff 2'

2 2

)

where:

a =

initial standard deviation of the puff I Q 1/3 7.87p I where Q

is the puff release quantity, and p is the density of the gas at standard condition.

a xa a

=

standard deviation of the gas concentration in the horizontal along wind, horizontal crosswind and vertical crosswind direction respectively (assume ax = a )

XYZ

=

distance from puff center in the horizontal alongwind, horizontal crosswind, and vertical crosswind directions respectively.

For the analysis we assume Y and Z to be zero and replace X by X = D - Ut, (to be able to determine the variation of unit concentration at specific stationary receptor loca tion), where D is the spillage area - air intake distance and U is the wind speed.

I CD-3 NUS coRPORATION

I I

b)

Continuous release I

F 2

2 21 (X/Q)

Xc EXP -

(D-Ut) /

(ax +

when t<D/U

=

Xc when t >D/U 11 Xc =

2

-n U (a a +

G I where:

a initial standard deviation of material in the plume.

I Q

=

evaporation rate of the spilled chemical.

All other symbols were defined earlier in part (a) above.

The significance of a is to force the maximum concentra tion of the vapor cloud at the spilled location to not be greater than the density (my) of the chemical spilled.

Im3 D.2 Control Room Model and Input Data Figure D-1 shows a simplified schematic control room heat, ventilation and air conditioning (HVAC) diagram and its pertinent flow rates in normal operation. The duct in and out I

II D-4 NUS CORPORATION

I I

leakage flow rates, q8 and 02

, were estimated using leakage criteria for low pressure design ASHRAE 79, equipment, Chapter 1, PP 1-5.

Based on the Figure D-1, the following set of equations was used to evaluate the concentration of toxic chemical in the control room.

C

=

+X

+vC B R

CB

=

aX+ CR -YCB where CR

=

concentration of toxic chemical in the control room CB

=

concentration of toxic chemical in control room cabinet C.

=

rate of change of concentration in room i (i

= R control room, i

=

B control room cabinet)

I a

=

3 -2 x

1F +q 8

F2 VB q 3+

2 B 33 2

1 I

I 8=

3 VB I

D-5 NUS CORPORATION

I I

Y q 3 -q 5

~

q 3 q 2 F2 B

L q 3 02 I

q

=

1+F 1 q8 q2 F2 I

3q + O 2 F q 3 +02 R

I II q

2/VR I

F1F2 are non-removal efficiency of the two filters shown on Figure D-1.

I For those evaluations when the HVAC will be isolated after the detection of the toxic chemical, q1 will be replaced by isolated or emergency make up air flow rate, q6,

in the above equations.

However, in the analysis it was assumed that no toxic chemicals detectors are available to automatically isolate the HVAC system.

I U

D-6 NUS CORRORATION

3b~u raorr%, WAck

-~

j.t

.1005 CF' qS7OF 3

4365 CFM l

co~lrol room ca6t,4&f50 F

533 0 2 380 c.E I

____395 U9 3

FIGURE D-1 SCHMMTIC HVAC DIAGRAM AND ITS PERTINENT FLOWRATES OF SONGS 1 CONTROL ROODM 3

D-7 NUS CORPORATION.J

I I

APPENDIX E I

ANNUAL JOINT FREQUENCY WIND SPEED-WIND DIRECTION SUMMARIES FOR PASQUILL STABILITY CATEGORIES AT THE 10-METER LEVEL AND THE 36.6-AND 40-METER LEVELS COMBINED FOR THE PLANT SITE (PERIOD OF RECORD 1/25/73 -

1/24/76)

(TABLES E-1 THROUGH E-7)

I I

E-1 3

NUS CORPORATION

MMMMMM----m--m=

em TABLE E-1 DATA FRO4 3/2573t 10 1/24/76 LEVEL - 10 mn

SUMMARY

MIND ROSE STABILITY CATEGORY A DISTRIBUTION BY SPEED AND DIRECII0N (NUMOEM)

SPEED(MPS)

N NNE NE ENE I

ESE SE SSE S

SSw Sw "SA o

AN NA NNW TOTAL CALMS 0.26 TO 0.50 0

0 3

I 0

0 0

0 0.SI 10 3.00 0

2 2

I 1

0 5

2 5

4 9

4 6

3 1

42 1.01 TO 1.50 4

6 1

1 0

0 2

a 16 27 35 29 is 19 t0 6

179

.S 10 2.00 3

6 2

2 I

I 4

a 36 62 65 101 61 40 II 5

416 2.01 TO 3,00 8

9 0

3 7

2 44 109 17b 213 345 338 297 6*

12 1641 3.01 10 4.00 0

6 2

0 0

0 2

S 109 199 207 309 511 559 67 4

do?2 4.01 TO 5.00 0

5 1

0 0

1 IS 46 as 104 81 95 260 390 46 3

1178 5.01 TO 6.00 2

a 0

1 0

1 2

20 40 40 19 12 53 154 10 1

m17 6.01 TO 7.00 I

2 0

0 0

0 a

it Is to 0

2 i5 59 3I 3

353 7*0l TO 6.00 0

1 1

1 0

0 1

2 9

I 2

1 5

37 I

0 56 CO e.01 TO 9.09 0

2 0

0 0

1 1

1 5

2 2

13 0

31 I

9.01 TO 10.00 0

0 0

0 2

0 0

0 1

7 3

0 12 MORE THAN 1o 0

1 3

0 0

0 I

3 0

0 0

a 0

0 I5 TOTALS 14 40 2t 7

6 12 66 196 420 626 634 905 1267 1569 396 36 6213 FREQUENCY OF OCCURRENCE (IN PERCENT OF TOTAL 3S)

SPEED(MPS)

N NNE NE ENE E

ESE SE SSE S

33w S

WS A

NNW N

NNW TOTAL CAL1M5 0.00 0.26 TO 0,50 0.00 0.00

.00 0.00

.00

.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.03 0.51 TO 1.00 0.00

.01 00

.01

.00

.00 0.00

.00

.01

.02

.04

.02 e03

.01

.00

.18 1.05 0 O.50.02

.03

.00

.00 0.00 0.00

.01

.03

.07

.12

.15

.12

.06

.08

.04

.03

.77 3.51 TO 2.00

.01

.03

.01

01

.00

.02

.03

.16

.27

.28

.43

.29

.17

.06

.02 1.79 2.01 TO 3.00

.02

.03

.04 0.00

.01

.03

.05 139

.47

.76

.92 1.49 1.46 1.2

.28

.05 7.07 3.01 TO 4.00 0.00

.03

.01 0.00 0.00 0.00

.11

.23

.47

.86

.89 1.31 2.20 2.41

.37

.02 6.92 4.01 TO 5.00 0.00

.02

.00 0.00 0.00

.00

.05

.20

.36

.45

.36

.43 1.32 1.66

.41

.01 5.07 5.01 TO 6.00

.01

.00 0.00

.00

.01

.09

.17

.08

.05

.23

.66

.0

.01 1.0 6.01 TO 7.00

.00

.03 0.00 0.00 0.00 0.00

.02

.05

.06

.04 0.00

.01

.06

.25

.i3

.01

.66 7.03 TO 8,00 0.00

.00

.00 0.00 0.00

.00

.01

.04

.00

.01

.00

.07

.07 0.00

.21 8.01 TO 9.00 0.00

.01 0.00 0.00 0.00 0.00 0.00

.00

.02

.01

.06

.02 0.00 Is 9.01 TO 30.00 0.00 0.00 0.00 0.00 0.00 0.00

.01 0.00 0.00 0.00

.00 0.00

.00

.03

.00 0.00

.0s Z

MORE THAN S0 0.00

.00

.01 0.00 0.00 0.00

.00

.00 0.00

.00 0.00 0.00 0.00

.03 0.00 0.00

.06 c

TOTALS

.06

.7

.09

.03

.05

.26

.84 1.51 2.70 2.73 3.90 5.46 6.76 1.71

.16 26.75 o)

AVE MIND SPEED 2.8 3.4 3.9 2.8 1.7 2.6 3.8 3.8 3.6 3.3 3.1 3.0 3.4 3.9 4.3 2.9 3.5 0

D 0

z

TABLE E-2 DATA FROM I/25/73 to 1/24/76 LEVEL - 10 m

SUMMARY

WIND NOSE StABILITY CATEGORY 8 DISTRIBUTION BY SPEED AND DIRECTION INUM8ER)

SPEEO(MPS)

N NNE NE ENE E

ESE SE SSE S

SSM So WMS WNH NN NNW TOTAL CALM$

0 0.26 TO 0.50 0

1 0

0 0

0 2

0 0

0 2

0 3

0.51 TO 1,00 0

3 1

1 0

0 0

1 4

4 0

2 2

I 2

22 1.01 TO 1.50 3

0 2

1 1

0 0

2 4

5 9

6 8

1 S

6 so 1.51 TO 2.00 2

3 5

1 0

0 4

16 10 7

13 15 6

13 1

6 10 2.01 TO 3.00 3

5 4

I 2

3 4

18 18 17 29 2%

36 30 10 9

222 3.01 To 4.00 0

6 3

0 0

2 9

22 15 16 14 11 20 23 a

5 157 4.01 TO 5.00 0

0 0

1 3

to 15 6

7 2

20 7

9 3

77 5.02 TO 6,00 1

1 1

0 0

0 2

2 7

?

0 I

7 6

0 35 6.01 TO 7.00 1

1 2

0 0

0 1

4 5

4 1

1 1

1 2

0 23 b'1 7.01 TO o

.00.

0 0

1 0

0 2

1 0

0 0

1 2

0 8

8.01 TO 9,00 0

0 0

I 0

0 0

0 1

to 9.01 TO 10,00 0

0 0

0 1

0 0

2 0

0 1

MORE THAN 10 0

0 0

TOTALS 10 20 16 4

4 6

Z4 so 79 61 74 64 92 94 56 33

?19 FREQUENCY OF OCCURRENCE (IN PERCENT OF TOTAL 088)

SPEED(MPS)

N NNE NE ENE E

ESE 3E SSE U

SSM S

H3 0

6N NW NNA TOTAL CALM3 0.00 6.26 TO 0.50 0.00

.00 0.00 0.00 0,00 0.00

.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.00 0.00

01 0.52 TO 1.00 0.00

.01

.00

.00 0.00 0.00 0.00

.00

.02

.02 0.00

.01

.00

.ut

.09 1.01 TO 1.50

.01 0.00

.01

.00

.00 0.00 0.00

.01

.02

.04

.03

.01

.03

.25 2.51 TO 2.00

.01

.02

.00 0.00 0.00

.02

.07

.0e

.01

.06

.0b

.03

.06

.01

.03

.47 2.01 TO 3,00

.01

.02

.00

.01

.02

.00

.08

.07

.12

.11

.16

.13

.08

.04

.96 3.01 TO 4.00 0.00

.03

.01 0.00 0.00

.01

.0o

.09

.06

.07

.06

.05

.10

.03

.02

.68 4.01 To 5.00 0.00 0.00 0.00 0.00 0.00

.00

.01

.06

.u3

.0s

.01

.04

.03

.0o

.01

.33 S.01 10 6.00

.00

.01 0.00 0.00 0.00

.01

.03

.01 0.00

.00

.02

.03

.01 0.00

.15 6.01 TO 7.00

.00

,00

.00 0.00 0.00 0.00

.00

.02

.00

.01 0.00

.10 1.01 10 8,00 0.00 0.00 0.00 0.00

.00 0.00 0.00

.01

.00 0.00 0.00 0.00

.00

.01

.00 0.00

.01 8.01 10 900 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.00 0.00 0.00 0.00 0.00

.00 Z

9.01 To 10.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.Ou

.00 0.00 0.00

.01 0.00 0.00

.01 c

1MU4E THAN 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTALS

.04

.09

.08

.02

.03

.10

.34

.14

.26

.32

.28

.040

..e4

.14 3.10

)

AVE WIND SPEED 2.1 2.7 a.?

1.4 3.6 1.2 3.3 3.3 3.3 3.0 2.7 2.6 3.0 3.1 1.3 2.3 3.0 0

O 0

z

m~~~~o

=

m

-m m---

TABLE E-3 DATA FRO 1/25/1 S 1 Ia/lb LEVEL

10 m SUMMARV IND k35k SIABILITY CATEUY C DISTRIBUIOIN HY SPEED AND DIRECTIJN (NUMBER)

SPLED(MPS)

N NNE NE ENE E

ESE SE SSE S

SSw S

030 W

ian 94 PNNW TOTAL CALMS I

0.26 TO 0.50

1) 0 0

0 0

1 0

0 0

0 1

0.51 10 1.00 3

1 A

0 0

0 1

1 I

3 A

3 5

2 0

I 25 1.01 10 1.50 1

1 0

2 I

I 2

6 6

I 6

S to to 9

11 1oa t.51 0 2.00 4

6 4

2 2

0 6

5 9

19 lb to d

I 12 1

147 2.01 TO 3.00 9

9 It 0

1 5

1 So 19 2?

25 2t 30 42 29 Is 287 3.01 TO -4.00 1

6 0

1 4

20 Sb 1?

Is 15 12 IS

?b 14 S

186 4.01 To 5.00 0

1 1

0 1

1 1

13 19 II S

2 5

7 S

3 83 S.01 TO 6.00 0

0 I

I 0

1 2

5 9

5 2

I 2

6 4-2 et 6.01 TO 7.00 1

1 1

1 0

2 1

2 3

3 a

I I

2 I

2 2b

7.

10 0.00 0

0 0

1 2

0 0

0 3

8.01 tU 9,00 0

1 a

0 0

0 1

0 0

0 1

2 0

0 1

4.010 3

0 0

1 0

5 MOE IMAN 10 0

0 3

0 0

2 I

0 6

TOTALS 25 sa 25 6

8 14 46 103 86 99 76 66 07 11?

81 46 920 FREQUENCY OF OCCUNRENCE (IN PERCEI aF TOTAL 08)

SPkLD(MPS)

N HN NE ENE E

ESE SE 55E 5

33N 84 as" W

NN" 0

NNW A0tL CALMS

.00 0.2b TO 0.50 0.00 0.00 0.00 0.00 0.00 0.00

.0.00 0.00 0.00

.00 0.00 0.00 0.00 0.00 0.00 0.00

.00 0.51 TO 1.00

.01

.00

.00 0.00 0.00 0.00

.00

.01

.00

.01

.01 0.00

.00

.11 1.01 TU 2.50

'01

.03 0.00

.01

.00

.01

.05

.03

.01

.03

.02

.0

.04

.0s

.4 2.51 to a.00

.o

.03

.02

.01

.01 0.00

.01 02

.04

.08

.01

.09

.08

.0s

.03

.63 2.01 10 3.00

,ve

.0e

.05 0.00

.01

.02

.03

.13

.08

.12

.11

.13

.18

.12

.06 1.24 3.01 TO 4.00

.00

.03

.01 0.00

.00

.02

.09

.16

.07

.06 0b

.0s

.06

.11

.ob

.02

.00 4.01 TO 5.00 0.00

.00

.00 0.00

.00

.03 Ob

.08

.05

.02

.01

.02

.03

.01

.36 5.01 TO 6,00 0.00 0.00

.00

.00 0.00

.00

.01

.02

.0e

.02

.01

.00

.01

.03

.0#

.01

.10 6.01 TO 1.00

.00

.00 0.00

.01

.00

.01

.00

.0

.01

.11 Z

7.02 to 0.00 0.00 0.00 0.00 0

o o

.oo0 0.00 0.00

.00

.01 0.00 0.00 0.00 0.00 0.00 0.00 0,00

.01 c

8.01 To 9.00 0.00

.00

.01 0.00 0.00 0.00 0.00 0.00

.00 0.00 0.00 0.00

.00

.01 0.00 0.00

.03 9.01 TO 10.00 0.00 0.00 0,.

.00 0.00 0.00

.01 0.00 0.00 0.00 0.00 0.00

.00 0.00

.02 MOE thAN 10 0.00 0.00

.00 0.00 0.00 0.00 0.00

.01 0.00 0.00 0.00 0.00 0.00

.01

.00 0.00

.03 (OTALS

.11

.14

.11

.03

.06

.21 044

.37

.43

.33

.28

.37

.50

.35

.20 3.96

])

AVE MIND SPEED 2.0 2.6 3.1 3.0 2.6 3.6 3.6 3.4 3.6 2.7 2.b 2.4 2.6 3.0 3.1 2.b 3.0 0

0 z

TABLE E-4 DATA FROM 1/25/13 T0 I/24/76 LEVEL - 10 m

SUMMARY

WIND 403E STABILITY CATISORY 0 DISTRIBUTION BY SPEED AND DIRECTION (NUM"ER)

SPEED(MPS)

N NNE Ne ENE E

ESE SE SSE S

3S SN MW n

MN No NNs TOTAL CALM8 3

0.26 TO 0.50 0

1 0

0 0

2 1

J 5

3 3

3 1

2 1

26 0.51 TO 1.00 21 17 Is 5

9 5

3 9

23 22 to 27 20 t6 3o 23 25 1.01 TO 1.50 61 34 32 22 a

12 24 42 41 50 50 51 48 42 45 35 603 1.51 TO 2,00 57 57 66 20 17 12 39 13 54 64 44 50 61 55 46 44 737 2.01 TO 3.00 67 97 6t 18 26 56 124 184 121 94 82 66 106 114 100 60 1370 3.01 TO 4.00 9

40 2?

3 6

37 116 158 104 83 40 44 45 a8 83 42 913 4.01 10 5.00 9

jo 1

2 2

6 70 112 I5 29 24 to It 30 55 i5 495 5.01 TO 6.00 1

z 6

a 1

7 34 44 43 2t 13 12 9

16 23 to 241 6.01 10 7.00 1

5 6

6 1

I a5 21 24 10 1

It 0

3o 17 6

IS4 7.9 to 6,00 1

1 3

5 0

1 19 II II s

5 6

1 1

12 3

93 8

8.01 tO 9.00 0

5 0

0 3

a 4

9 4

5 3

6 6

1 1

63 9.01 TO 10.00 0

1 0

1 2

3 7

I 5

3 4

1 6

5 I

43 OMOE THAN 10 0

0 0

1 1

0 0

4 2

4 13 to 8

I 54 TOTALS 227 2b9 202 84 73 146 4F3 664 519 390 301 297 355 30e 413 242 5046 FREQUENCY OF OCCUMENCE (IN PERCENT Of TOTAL 03)

SPLED(MPS)

N NNE NE ENE k

ESE SE SSE S

33H S

0SN w

WNW NW NNW TOTAL CALMS

.01 0.26 10 0.50 0.00

.00 0.00 0.00 0,00

01

.00

.01

.02

.01

.00

.01

.00

.01

.00

,tt 0.51 TO 1.00

.09

.07

.06

.02

.04

.02

.01

.04

.10

.09

.00

.12

.09

.07

.06

.10 1,06 1.01 TO 1.50

.20

,15

.6

.09

.03

.05

.30

.18

.2?

.22

.25

.21

.18

.19

.35 2.60 1.51 TO 2.00

.25

.19

.09

.01

.05

.17

.11

.23

.28

.19

.22

.26

.24

.20

.39 3.17 2.01 TO 3.00

.29

.42

.26

.08

.11

.24

.53

.19

.55

.40

.35

.28

.45

.49

.43

.26 5.93 3.01 TO 4.00

04

.11

.12

.01

.03

.16

.50

.68

.45

.36

.21

.19

.29 036

.10 3,93 4.01 TO 5.00

.04

.06

.03

.01

.03

.30

.48

.32

.12

.10

.06

.13

.11

.26

.06 2.13 5.01 TU 6.00

.00

.01

.03

.01

.03

.16

.19

.38

.09

.06

.05

.04

.07

.09

.04 I.04 6.01 TO 7.00

.00

.02

.03

.00

.11

.09

.10

.04

.01

.05

.03

.04

.07

.03

.66 7.01 TO e.00

.00

.01

.02 0.00

.00

.08

.0

.02

.03

.00

.03

.05

.01

.*0 8.01 TO 9.00 0.00 0.00

.02 0.00 0.00

.01

.03

.02

.04

.02

.0e

.01

.03

.00

.26 Z

9.0 TO 0.00 0.00

.00 0.00

.00

.0

.us

.00

.02

.0

.02

.00

.03

.02

.01

.00

.9 c

MURE THAN 30 0.00 0.00 0.00 0.00 0.00

.00

.01 0.00 0.00

.02

.01

.02

.06

.08

.01

,00

.23 TOTALS

.98 1.16

.87

.36

.31

.63 2.04 2.06 2.23 1.68 1.30 1.20 t.53 1.67 1.18 3.04 21.73 AVE WIND SPEED 1.9 2.4 2.6 2.7 2.4 3.1 3.8 3.3 3.4 1.0 2.9 2.0 3.1 3.4 3.5 2.7 3.1 D

0 0

z

TABLE E-5 DATA FROM 3/25/S5 30 1/11176 LEVEL = 10 n

SUMMARY

WlND R4SE STABILITY CATEGORY E DISTRIBUTION BY SPEED AND DIRECTION (NUMBER)

PCEoIMP8)

N NNE NE ENE E

ESE SE S3E 3

Sw So mWn W

)N" No NNW TOTAL CAL4S 6

0.26 TO 0.50 4

I 4

4 2

0 1

I 0

0 2

2 1

I 1 3

27 0.51 TO 1.00 So 37 21 20 1t lb 4

6 25 25 I?

20 19 is 10 19 296 1.01 TO 1.50 2

85 4t 26 22 23 40 41 46 31 36 12 35 36 29 27 603 3.51 TO 2.00 f8 312 i5 20 28 35 38 61 38 28 19 23 3

36 21 30 647 2.01 TO 3.00 70 167 120 19 27 45 101 116 67 44 22 24 41 5?

69 39 1028 3.01 TO e.00 38 90 71 2

7 29 85 l

50 la 10 8

I3 28 63 5i 636 4.01 10 5.00 15 37

,32 4

4 16 t

40 28 11 7

6 11 16 33 3

322 5.01 TO 6.00 2

20 7

6 3

33 31 la l4 1

4 7

to 16 1?

179 6.01 To 7.00 a

6 I3 4

3 5

7 19 39 2

0 10 7

8 6

6 189 0

7.01 10 8.00 e

4 5

8 6

1 10 a

1 2

6 5

It 3

13 4

as 6.01 TO 9.9U 0

2 3

3 6

3 7

6 7

0 1

1 7

12 16 2

76 01 9.01 TO 30.00 0

1 3

2 1

1 3

t 1

0 3

9 6

3 43 MORE THAN 10 0

1 0

0 2

15 14 4

0 1

5 0

10 1

54 TOTALS 253 563 396 389 121 176 38 426 324 184 13 ISO 184 234 299 233 4124 FREQUENCY OF OCCURRENCE (IN PENCENT OF TOTAL 043)

SPEED(MPS)

N NNE NE ENE E

ESE SE SSE S

SSf 34 SW 4

WNN NW hNW TOTAL CAL43

.03 0.26 10 0.50

.02

.00

.02

.01 0.00

.00

.00 0.00 0.00

.01

.00

.01

.12 0.51 To 1.00

.13

.16

.09

.05

.07

.02

.03

.11

.10

.07

.09

.06

.08

.04

.08 1.27 1.01 TO I.50

.18

.37

.19

.3t

.09

.0

.17

.18

.21

.16

.*b

.14

.15

.16

.Il

.12 2.60 3.53 TO 2,00

,dI

.48

.32

.09

.12

.15

.16

.26

.16

.12

.08

.09

.13

.16

.12

.13 2.79 2.01 TO 3.00

.30

.72

.52

.08

.12

.19

.43

.50

.29

.19

.09

.10

.18

.25

.30

.17 4.43 3.01 TO 4.00

.16

.39

.31

.01

.03

.12

.36

.32

.22

.08

.04

.03

.06

.12

.21

.22 2.74 4.01 TO 5.00

.06

.16

.14

.02

.07

.13

.11

.12

.01

.03

.05

.07

.14

.13 3.39 5.01 TO 6.00

.01

.09

.03

.02

.01

.06

.13

.08

.06

.03

.02

.03

.04

.07

.77 6.01 TO 7.00

.01

,03

.05

.02

.01

.02

.03

.08

.00

.01

.02

.04

.0

.03

.01

.03

.51 7.01 10 8.00

.01

.02

.03

.00

.04

.01

.03

.01

.03

.02

.03

.06

.0e

.36 6.03 to 9.00 0.00 03

.0

.03

.0

.03

.01

.03 0.00

.00

.03

.05

.01

.0

.33 Z

9.01 TO 10.00 0.00

.00

.01

.00

.01

.00

.0

.01

.00

.00 0.00

.01

.04

.01

.19 c

MORE THAN 10 0.00

.00 0.00

.00 0.00 0.00

.01

.06

.02 0.00

.00

.02 0.00

.04

.00

.23 co TOTALS 1.09 2.42 1.13

.51

.52

.77 1.446 1.83 1.40

.19

.57

.58

.19 1.01 1.29 1.00 17.76 O

AVE MINo SPEED 2.2 2.5 2.8 2.8 2.8 2.7 3.2 3.6 1.6 2.7 2.b 2.6 3.3 3.2 5.9 3.1 3.0 1

0 0 z

TABLE E-6 DATA FROM 1/25/73 TO 1-/2476 LEVEL a 10 m

SUMMARY

aIND ROSE STABILITY CATEGORY F DISTRIBUTION SY SPEED AND DIRECTION (NUMMER)

PEEDO(NP3)

N NNE NE ENE E

ESE SE SSE 3

asW Sm 030 N

44 NO NNN TOTAL CALMS 3

0.26 TO 0.50 0

2 a

2 1

0 1

1 0

0 0

1 0

1 ta 0.51 10 1,00 10 22 24 14 16 13 to II a

7 8

a 4

2 S

9 171 1.01 10 1.50 23 es 5o 26 21 It 12 11 to ta e

1 e

9 a

are 1.51 TO 2,00 31 51 91 25 6

11 19 t8 10 4

2 1

to 10 12 5

320 2.01 TO 3.00 21 162 101 19 9

to 26 13 9

1 3

5 21 Is 7

So 3.01 TO 4.00 is A19 96 8

5 9

II 9

7 I

4 0

3 6

I5 I3 326 4.01 TO 5,00 6

74 47 6

4 4

6

£2 3

1 0

0 0

a 7

IQ 162 5.01 TO 6.00 1

23 22 3

0 A

I 4

2 0

0 0

0 1

0 6

66 6.01 TO 7.00 4

2 to a

I I

I 3

1 0

0 0

It 7.01 TO 8,00 0

5 7

3 I

0 0

0 1

0 0

2 20 6.01 TO 9.00 0

1 a

1 0

0 1

0 0

0 5

9.01 TO £0,00 0

0 0

1 0

0 1

2 0

0 0

0 4

MORE THAN 10 0

0 1

0 0

0 1

1 1

I 0

0 0

0 5

TOTALS 11 507 S49

£14 b4 4e 90 9£ 52 33 24 19 30 64 62 be 195e FREQUENCY OF OCCURRENCE (IN PERCENT OF TUTAL 088)

SPEED(MPS)

N NNE NE ENE E

ESE SE 55E 8

S3 w 34 0

go N

No NNw TUTAL CALMS

01 0.26 to 0.s0 0,00

.01

.00 0.00

.00

.00 0.00

.00 0.00 0.00 0.00

.00 0.00

.00

.01 0.5£ TO 1.00

.04

.09

.10

.06

.07

.06

.0

.05

.03

.01

.03

.02

.01

.02

.00

.74 1.01 To 1.50

.10

.20

.23

.12

.09

.05

.01

.04

.05

.03

.0

.0.

.01

.02 1.20 1.5£ TO 2.00

.13

.22

.42

.11

.03

.05

.08

.06

.04

02

.01

.00

.08

.05

.02 1.38 2.A1 TO 3.00

.09

.70

.79

.08

.0

.08

.1t

.06

.04

.03

.00

.01

.02

.10

.06

.07 2.20 3.01 TO 4.00

.98

.51

.41

.03

.02

.04

.05

.04

.03

.00

.02 0.00

.01

.03

.06

.0b 1.40 4.01 TO 5.00

.03

.32

.20

03

.02

.03

.05

.01

.00 0.00 0.00 0.00

.0S

.01

,04

.78 5.01 TO 6.00

.01

.10

.09

.01 0.00

.00

.02

.01 0.00 0.00 0.00 0.00

.00 0.00

.03

.28 6.01 TO 7.00

.02

.01

.06

.02

.00

.01

.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.11 1.01 TO 8,00 0.00

.02

.03

.01

.00 0.00 0.00 0.00

.00 0.00

.00 0.00 0.00 0.00 0.00

.01

.09 z

8.01 TO 9,00 0.00

.00

.01

.00 0.00 0.00

.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.02 9.01 TO £0.00 0,00 0.00 0.00

.,00 0.00 0.00

.00

.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.02 MONE THAN 10 0,00 0.00

.00 0.00 0.00 0.00

.00

.00 0.00 0.00 0.00 0.00 0.00 0.00

.02 TOTALS

.50 2.16 2.34

.49

.28

.29

.39

.19

.22

.14

.10

.08

.13

.28

.27

.29 6.41 0

O AVE NINO SPEED

?.1 2.9 2.8 2.4 1.9 2.2 2.5 2.7 2.1 2.1 1.5 1.3 1.6 2.2 2.5 3.0 2.4

-a 0

0

TABLE E-7 DATA FROM 1125/73 TO 1/24/16 LEVEL

10 m

SUMMARY

mIND RUSE STABILITY CAILGORY G DISTRIBUTIlN BY SPEED AND DINECTION (NUMBER) 8PEED(MPS)

N NNE NE ENE E

ESE S E3E 3

SSw S"

0S n

No NN%

TOTAL CALMS 3

0.26 10 0.50 1

I 1

1 2

0 1

a 0

0 0

0 a

I 2

I 13

St0 0

to t0 18 25 12 12 It 7

14 4

6 8

10 8

6 191 1.0 TO a.50 26 42 65 60 at 35 32 If 12 6

7 12 as 8

9 12 393 1.51 TO 2.00 21 72 aas 46 24 23 23 15 13 9

a a

as 405 2.01 To 3.00 36 21S 329 61 is 14 27 15 5

2 1

5 5

26 21 13 791 1.01 10 4.00 s0 277 419 42 I

6 9

6 I

a 0

1 1

a at a

83S 4.01 TO 5.00 10 257 423 35 a

3 1

0 0

2 2

12 6

161 5.01 TO 6.00 5

I54 305 32 1

2 t

0 0

1 3

2 506 6.01 TO 7.00 4

78 156 Is 0

0 0

a 0

1 0

0 1

a 0

2 259 7.01 TO 0.00 0

25 43 6

0 0

2 0

0 0

76 8.01 10 4,00 0

3 7

1 1

0 0

1 0

0 13 00 9.01 TO 10,00 0

0 0

MORE THAN t0 0

0 0

TOTALS 153 142 1899 317 98 95 106 67 40 33 20 23 35 63 84 66 4246 FMEQUENCY OF UCCuNRENCE (IN PENCENT OF TOTAL 085)

SPEED(MPS)

N NNE NE EN I

ESE SE 33E 3

SS Sm "so of NNW 141 NNN TOTAL CALMS

'01 0.26 TO 0.50

.00

.01 0.00

.00

.00 0.00 0.00 0.00 0.00

.00

.01

.00

.06 0.51 TO 1,00

.05

.08

.09

'08

.11

,05

.05

.0

.03

.06

.02

.03

.04

.03

.82 1.01 TO 3.50

.11

.10

.35

.26

.09

.15

.14

.07

.05

.03

.05

,06

.03

.04

.05 1.69 los TO 2.00

.09

.31

.50

.20

.10

.06

.04

.03

.00

.02

.0

.08 1.74 2.01 TO 3.00

.16

.93 1.42

.26

.08

.06

.12

.06

.02

.01

.00

.01

.02

.11

.09

.06 3.1 3.01 TO 4.00

.13 1.19 1.80

.18

.02

.03

.04

.93

.00

.00 0.00

.00

.03

.09

.03 3.60 4.01 10 5.00

.08 loll 1,82

.aS

.00

.01

.00

'00 0.00 0.00 0.00 0.00

.01

.05

.03 3.26 5.01 TO 6.00

.02

.66 1.31

.14

.00

.01

.00 0.00 0.00 0.00 0.00 0.00 0.00

.00

.01

.01 2.16 6.01 TO 7.00

.02

.34

.67

.06 0.00 0.00 0.00

'00 0.00

.00 0.00 0.00

.00

.00 0.00

.01 1.12 7.01 10 8,00 0.00 ill

.19

.03 0.00 0.00 0.00 0.00

.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.33 8.01 10 9.00 0.00

.01

.03

.00

.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

.00 0.00 0.00

.06 Z

9.01 10 10.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

0.

0.00 0.00 0.00 0.00 0.00 0.00 MORE THAN 10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTALS

.66 4.92 8.18 1.31

.42

.41

.46

.29

.17

.14

.09

.10

.1

.27

.36

.29 16.28 AVE IN10 SPEED 2.6 3.9 4.0 3.0 1.?

3.8 1.8 1.9 1.8 1.5 1.4 1.4 1.7 2.3 2.?

2.3 3.5 0

'0 TI 0

0 Z

I I

D.0 ASSUMPTIONS AND THE EQUATIONS USED IN THE CONTROL ROOM TOXIC CHEMICALS CONCENTRATION EVALUATION D.1 Analysis Assumptions To evaluate the effect of a toxic chemical release on the control room habitant, it was assumed that the chemical will be accidentally spilled totally.

The instantaneous fractional release of the liquified gases will be estimated by using adiabatic flash calculation.

The direction independent 5 per centile one hour relative concentration (X/Q) which were cal culated from onsite meteorological data given in Appendix 2.3B of SONGS 2 and 3 FSAR, at a series of downwind distance (see Section

6), will be used to find the average wind speed.

Examination of meteorological data shows that G stability is a good representative of 5% atmospheric stability condition.

Using G stability and the 5 percentile (X/Q) 's an average wind speed of 2.32 meters/second was calculated.

Evaporation and/or boiling rates for all the spilled chemicals analyzed were evaluatd based on the following:

1) wind speed of 2.32 m/sec,

2) spill spread over an area such that the average depth is one centimeter unless there is a

berm around the storage tank,

3) ambient temperature of 100 0 F, and

4) concrete temperature of 100 F.

In accordance with Regulatory Guide 1.78, it was assumed that the wind blows directly toward the control room air intake without the dilution in the building wake.

The following atmospheric dispersion equations were used to evaluate the concentration at the air intake of the control room for puff and continuous release:

I D-2 NUS CORPORATION

1 I

APPENDIX D I

METHODS USED IN TOXIC CHEMICAL ANALYSIS I

I I

I IU NUs CORPORATION

ML13330A896

Contents

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1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

System Design

Response

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Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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ML13330A896

Text

1.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

System Design

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

Response

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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