ML19220B328

Forwards Accident Analysis Branch Site Section & Part of SER Input.Remaining LOCA Doses Evaluation Will Be Completed After Evaluation of Spray Sys Is Complete

ML19220B328
Person / Time
Site:	Crane
Issue date:	11/25/1975
From:	Moore V Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 7904250640
Download: ML19220B328 (19)

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Voss A. Mcore, Assistant Director for Light Water Reactors, Group E, RL THFIE MILE ISLMD U*ilT 2, SER INPUT PLMT NAME: Three Mile Island, Unit 2 LICENSING STAGE: OL",

DOCKET NUIEER: 50.-320

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MILESTCNE NU!.3ERT K. y 31 RESP 0hSIBLE BRMCH: LWR 2-2; H. Silver, LPH REQUESTED CCMPLETION DATE: October 1,1975 REVIE'n STATUS: AAB Review Continuing Attached is the Accident Malysis Branch site section and a part of SER input for the TI,ree Mile Island huclear Unit 2 facility.

The recainder of tne Accident Analysis Branch SER input on Sections 6 and 15 will te sent at a later.date. The mmaining evaluation of the LCCA doses will be completed after our evaluation of '.he spray system is complete. We are reeva'uating the spray system effectiveness taking into account the experience on A-kansas 1 and Three Mile Island 1.

We have not provided an aircraft hazard analysis. This ws perfor::ed for Unit I at the OL stam. by the LPH and we presuue that DRL will just reference that analy is.

This input was coordinated by Charles Ferrell, Site Analyst, Accident Analysis Branen.

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"*1nm Harold.o Nnton, Assistant Director for S):e Safety Division of Technical Review Office of Nuclear Reactor Regulation Enclosu't:

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.a THREE MILE ISL.MD SER INPUT 2.0 Site Characteristics The Three Mile Island Nuclear Station Unit 2 is located adjacent to the Unit 1 Station en the 814-acre Three Mile Island in the Susquehanna River.

The reactor site in Lcndenderry Township, in the southern part of Dauphin County, Pennsylvania, is 12 miles southeast of Harrisburg, Pennsylvania.

Figure 2.1 shows the reactor location with respect to tne surrounding centers of popular.icn.

Figure 2.2, taken from a U. S. Geological Survey "ap of the Three Mile Island area, indicates the relatively flat island to be at an elevation of 300 feet.

There are several other islands at this river location. Three Mile Island is approximatly 2 miles long and approximately 1,700 feet wide. The island is about 900 feet from the east cank of the river and approximately 1 mile from the west bank of the river. The normal pool elevation of the Susquenanna River due to the York Haven Dam is shown to be 277 feet. Hills on botn sides of the river rise to elevations of over 500 feet. The nearest residence ie 2,cu0 feet east of the reactor building.

The minimum exclusion distance specified for the Three Mile Island Unit 2 facility is 2,000 feet (510 meters).

Figure 2.3 shows the minimum exclusion radius.

Included within tne 2,000-foot exclusicn radius is a por+ ion of the Three Mile Island, a partion of Shelley Island to the west, and a portion of the Susquehanna River.

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The applicant a_.

specif'id a icw population zone distance of two miles for this site, ie 2 rest population center as defined in 10 CFR Part 100 1s brisburg, Pennsylvania (1970 population of 68,CCO) located 12 miles northwest of the site.

This city experienced a 15% populaticn loss since the 1960 census. The ten-mile population center distance is more tnan 4/3 the distance frcm the cutcr boundary of the icw pcpulation :cne radius and therefore meets the requirements of 10 CFR Part 100.

Figure 2.4 shcws the present and the projacted cumulative population surrounding the Three Mile Island site. The 100 population witnin 50 miles was 1,865,717. The applicant predicts that the population of tnis area will increase to 3,231,126 in the year 2010, an increase of 73%. We have estimated an increase of 32% using the population projections of the Bureau of Econcaic Analysis (SEA) econcmic areas Num::ers 15,16, and 17 (Figure 2.5).

The population of the 2-mile icw pooulation zone in 1970 of 2,320 people is projected to increase to about 4,200 in the year 2010, an increase of 76%. We find tnat the applicant's projections, althougn somewhat nigner than BEA projectinns, are reasonable.

The Three Mile Island site is currently surrounded by farm lands within a 10 mile radius. These are used for dairy cattle, tobacco, poultry, vegetables, fruit, corn, wheat, a1d otner products. The Susquenanna River is used for scort fishing and boating. The dam located below the reactor site does not have locks, therefore only locally used boats will pass the site. The river is not used for commercial fisning.

O

'ib 038

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- 3 There are no schools or major industries and only one recreaticnal area (Falmouth Fish Commission) wichin the two-mile L?Z. There is some seasonal shift in population within a 5-mile radi"s of Three Mile Island since there are over IC0 summer cabins cn the islands within this area. Additional tiansients participate in boating activities in the vicinity of the plant site.

The applicant has indicated plans to develop the southern portion of the island for recreational uses. Access to this area is provided frca tnr.

east bank of tne river by a wooden bridge.

On the basis of the applicant's specified population center distances, icw population :ene, and minimum exclusion area, our analysis of the on-site meteorological data from which atmospneric dilution factors were calculated (Secticn 2.3 of this report), and the calculated consequences of design basis accidents (discussed in Section 15.0 of tnis report), we have concluded tnat the exclusion area radius and the icw population zone and the pcpulaticn center distances meet the guidelines of 10 CFR Part 100 and are acceptable.

2.2 Nearby Industrial, Transcortaticn, and Military Facilities There are no military firing ranges or missile facilities witnin a 10 c' radius of the plant. We nave evaluated the industries, including fuel oil storage facilities, located between three and five miles from the site and detemined that they will not adversely affect the safety of the nuclear

^

facility. The 23 industrial firms located within a 5-mile radius of the

'ib 041

_4 Three Mile Island site employ approximately 2,400 persons. There are gas and oil transmission lines located at a minimum distance of approximately two miles, which assures that flammable cencentraticns frcq postulated failure of their lines would not reacn the plant.

State Highway 441, a %o' lane highway, is located on the east bank of the ri ve r.

The Penn Central Railroad lines are located on both sides of the Susquehanna Rvier, the closest being the east bank, approximately 2,0C0 feet frcm:ne Three Mile Island Unit 2 containment. At our request, the ap:licant has provided an analysis of the postulatad accidental release of LP gas from a railway accident.

Routine traffic in a liquified petroleum gas was identified on the railroad line which passes along tne east shore of the river. The applicant has analyzed the effect ucen the plant of missiles created by railroad accidents involving this traffic, and tne worst case dispersal of the flammable gas released frca the largest single railroad car engaged in this traffic. We ccncur Nitn the applicant's conclusions that any missiles generated by this traffic wculd be less damaging than :ne aircraft strikes, and that flammable gases would dissipate before reaching the plant.

The Harriscurg International Airport, fomerly Olmstead Air Force Base, is located on the nortn bank of the river ap;:roximately 2-1/2 miles northwest.

The air;: ort proximity led to :ne design of the plant for aircraft impact

^

including protection of the engineered safety features and safe shutccwn

'Q - n y equipment.

-M

- 5 Industries in the region consist of manufacturing of clotning, wood products, shces, electrical wiring devices, and steel products, meat packing and the processing of various foods. These activities, within a 10-mile radius of the site, are confinad chiefly to the cities of Harrisburg, Now Cumberland, Steelten, and Middletown. Fuel oil storage facilities exist at Harrisburg International Airport.

The closest military installation to the site is the Air National Guard facility at Harrisburg International Airport. Other military facilities are Army and Navy depots located respectively at New Cumoerland and Mechanicsburg, Pennsylvania.

3.5.1 Turbine Missiles The Unit 2 turbine generator is arranged such that the Unit 2 reactor building and a portion of the centrol recm building are exposed to potential low trajectory turbine missiles. Penetration of tne control recm building walls is not foreseeable even in the event of a destructive overspeed turbine failure. The minimum control room wall thickness is a feet of concrete, and the minimum angle of incidence for a turbine missile is 55 degrees, so that the effective thickness of the exposed control room building wall is over 20 feet of concrete. The minimum effective concrete thickness for the exposed reactor building wall with respect to Icw trajectory turbine missiles is about 5 feet.

Protection against high trajectory turcine missiles is adecuate since all safety related plant structures are covered by high strength concrete (5CCO psi compressive strengtn) roofs

..,a 043 c

L_

J 6

of 3 feet or more. This is sufficient to prevent penetration by the postu-lated design overspeed high trajectory turbine missiles.

We are currently performing a generic study and formulating a Regulatory Guide on the matter of turbine missiles. When the res0lts of our study are available, we will review the significance of potential turbine missiles on this facility and determine if additional protection is required beyond that already offered by the presently proposed plant design. Any changes resulting frcm the review would be directed at reducing the probability of a destructive overspeet turbine failure in terms of turbine overspeed pro-tection system improvements, turbine startup procedures, and inservice inspection procedures.

3.5.2 Tornado Missiles Protecticn to all safety related equipment is provided by stru:tures with 36-inch concrete walls and roofs. This is considered adequate protection against possible tornado generated missiles.

15.i General We and tne applicant have evaluated the off-site radiological consequences for postulated design basis accidents. These accidents are the same as those analyzed for previcusly licensed PWR plants and include a steam line break accident, a steam generator tuce rupture accident, a loss-of-coolant accident, a fuel-handling accicent, and a rupture of a radioactive gas storage tank in tne gaseous radioactive waste treatment system.

• iif -044

.m-

_a TABLE 15.1 FOTENTIAL CFF-SITE COSES CUE TO CESIGN SASIS ACCICENTS Two Hour Course of Accidents Exclusien Scundary Low Population Zcne Accident (610 t'eters)

(3218 Meters)

Thyroic rioie cocy Thyroic W.1oie 5ccy a

(Rem)

(Rem)

(Rem)

(Rem; Loss-of-Coolant Post-LCCA Hydrogen Purge Dose

< 1 Fuel Handling 58 4

7

<l Tube Rupture 10 1

Tube RLpture with Iodine Spike 150 1

Steam Line Break 4

< 1 Loss of Off-Site Powe r 1

< 1 Loss of Off-Site Power with Coincident Icdine Spike 2

< 1 Gas Decay Tank Rupture Negligible 8

Negligible

<l Rod Ejection

• Case I 190 3

35 2

Case II 250 5

28

<1 Actual rod ejection doses will not exceed the doses for Case I (releases througn the containment) or Case II (releases througn tne secondary system).

'ib- 045

G

& The aoplicant has evaluated the loss-of-coolant accident, the fuel handling accident, the rod ejection accident, and the radioactive gas decay tank rup tu re. Tne off-site doses we calculated for these accidents are presented in Table 15.1 of this report, and the assumptions we used are listed in Section 15.2.1.

All potential doses calculated by tne applicants and by us for the postulated accidents are within the 10 CFR Part 100 guideline values.

On the basis of cur experience with the evaluation of the steam line break and the steam generator tube rupture accidents for PWR plants of similar design, we have concluded that the consequences of these accidents can be controlled by limiting the permissible reactor coolant and secondary coolant radioactivity concentrations so that potential off-site doses are small. The Standard Technical Specifications limit the equilibrium primary coolant activity to 1. uCi/ gram of I-131 Eq and 100/E uCi/ gram of noble gases.

The secondary coolant activity is limited to.1 uCi/ gram of I-131 Eq and the primary to secondary leak rate of 1. gpm.

Hydrogen Purce Case Analysis Using Regulatory Guide 1.7 assumotions, we have calculated a hydrogen purge dose of less than one rem (thyroid) at the Lcw Populaticn Zone.

15.2 Design Basis Accident Assumotions 15.2.1 Loss-of-Coolant Accicent (LCCA) 1.

Power level of 2772 MWt.

2.

Regulatory Guide No.1.4, " Assumptions Used for Evaluating the Potential Radiological Ccnsequences of a Loss-of-Coolant Accident for Pressuriced Water Reactors," Revision 1, June 1973.

7' 0F

O e

8 -

3.

Design containment leak rate of 0.2% for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and l/0 0.1/ day thereafter.

4.

Icdine removal by the containment quene.h spray system was based on:

6 3

Reactor Building Volume x 10 ft Spray Fall Height feet Spray Flow Rate gpm Elemental Mass Transfe-Velocity cm/sec Organic Mass Transfer Velocity cm/sec Spray Drop Diameter micron Spray Terminal Velocity cm/sec Factor of Conservatism Spray Reduction Limits Elemental Organic Particulate Spray Removal Rates

-I Elemental hrs

-I Organic hr Particulate h r-I 5.

X/Q Values 610 Meters (0-2 hours) 1.4 x 10- sec/m 3218 Meters (0-3 ' ours) 8.3 x 10-0 sec/m r

-5 3

(8-24 hours) 5.7 x 10 sec/m 3

(1-4 days) 2.2 x 10~:" sed /m

-6 3

(4-30 days) 5.6 x 10 sec/m 7b 047

.- w

- 9 Our evaluation of the iodine removal effectiveness of the containment sprays is discussed further in Secticn 6.2 of this report.

15.2.5 Hydrogen Purge Case The assumptions used ts calculate the low population :cne doses due to pnst-loss-of-coolant accident hydrogen ourging are:

Power Level: 2772 D!t 6

3 Centainment Volume: 2.1 x 10 ft Purge Time: 30 days Holdup Time Prior to Purging: 25 days Purge Rate: 35 cfm Sodium Thicsulfate Soray Reduction Factor for Iodine:

1000 for Elemental and 20 for Organic Iodides.

Charcoal Filter Efficiency of 30", and 70% for Elemental and Organic Icdine, respectively X/Q Value: 4-30 days (5.6 x 10-6 sec/a )

3 15.2.2 Fuel Handling Accident The assumptions used to calculate off-site doses frca a fuel handling accident (Regulatory Gu:de 1.25) are:

1.

Rupture of all fuel rods in one assembly.

2.

All gap activity in the rods, assumed to be 10". of the ncble gases and 10% of the iodine (with a peaking factor of 1.65), is released.

3.

The accident accurs 72 hcurs after shutdown.

W O48

'N

u__ j 10 4.

99% of the iodine is retained in the pool water.

s 5.

Icdine above the pool is 75% inorganic and 25% organic species.

6.

X/Q values (610 meters) 0-2 hours:

1.4 x 10-3 sec/m (3218 meters) 0-2 hours: 8.8 x 10-5 sec/m 3

7.

Iodine removal factor of 90% and 70% for tne charcoal filter for elemental and organic iodines respectively.

15.2.3 Gas Decay Tank Ruoture The assumpticns used to calculate the off-site doses frcm u gas decay tank rupture were:

1.

Gas decay tank contains one complete reactor coolant lecp inventory of noble gases resulting frcm operation with 1". failed fuel (97,000 curies of ncble gases).

-3 7

2.

X/Q values (510 mters) 0-2 hours:

1.4 x 10 sec/m' (3218 meters) 0-2 hcurs: 8.8 x 10-5 sec/m 3

15.2.4 Ccn Red Ejec*icn Accident s

The assumot ' : s!c to calculate off-site doses frcm a control rod ejecticn accident art.

Case I 1.

Power ie..i of 2772 'Gt.

2.

26% fuel f.:le. in transient.

3.

10% of iciine and ncbie gas inventory in gap of failed fuel.

4.

Release of ni gap activity in failed fuel to containment building.

'jh 049

.w.

L_3 g

g.

- 11 5.

50% plate-out of radioactive iodines.

6.

Containment building sprays are not initiated.

7.

Containment building leak rate of 0.2"./ day for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

X/Q values (610 meters) 0-2 nours 1 A x 10-3 sec/m 3

-5 3

(3218 meters) 0-8 hours:

8.8 x 10 sec/m

-5 3

8-24 hours: 5.7 x 10 sec/m 15.5 Tube Failure, Steam Line Failure, and Case II Rod Ejecticn Accident Assum:ticns ASSUMPTICNS:

- Power = 2772 M'.ith 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> X/Q = 1.4 x 10' sec/m at exclusion boundary

- Iodine decentamination factor of 10 between water and steam

- Primary and secondary coolant equilibrium concentrations as limited by by Standard Technical 5:ecifications (1. uCi/ gram I-131 Eq ar.d 100/E LCi/ gram Noble Gases for primary coolant and.1 ' Ci/ gram I-131 Eq for secondary coolant)

- Primary to secondary leak rate as limited by Standard Technical Specifications (1 gpm)

- For accidents assumed to accur in coincidence with an icdine spike, the primary ccolant concentra::icn is as limitec by the Standard Tecnnical Specificatiens for 48-hour periods (50 aci/ gram I-131 Eq at 100% power)

- Source soike factor of 5CO after accidents

- 10% of iodine and ncble gases fuel activity in gaps

- All releases througn tne secondary system ib-050

12

- 25% fuel with clad failure after red ejection accident

- 0% fuel reacning initiation of melting after rod ejection accident

'ib-~051

.-