ML051300462

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Technical Specifications Change 438- Response to Request for Additional Information Regarding Excess Flow Check Valve Surveillance Test Frequency
ML051300462
Person / Time
Site: Browns Ferry 
Issue date: 04/27/2005
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC4659, TVA-BFN-TS-438
Download: ML051300462 (18)


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabarna 35609-2000 April 27, 2005 TVA-BFN-TS-438 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of

)

Docket No. 50-259 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) -

UNIT 1 -

TECHNICAL SPECIFICATIONS (TS) CHANGE 438 -

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING EXCESS FLOW CHECK VALVE SURVEILLANCE TEST FREQUENCY (TAC NO. MC4659)

This letter provides TVA's responses to the NRC request for additional information (Reference 1) regarding proposed Technical Specification (TS) 438.

On October 12, 2004 (Reference 2), TVA requested a TS change (TS 438) to revise the frequency of Surveillance Requirement 3.6.1.3.8 by testing a representative sample (approximately 20 percent) of Excess Flow Check Valves (EFCVs) every 24 months, so each EFCV is tested once every 120 months.

NRC requested additional information to support the review of the submittal.

The NRC requests and TVA's responses are enclosed.

TVA has determined that the additional information provided does not affect the no significant hazards considerations associated with the proposed amendment and TS changes.

The proposed amendment and TS changes still qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c) (9).

Togo

r U.S. Nuclear Regulatory Commission Page 2 April 27, 2005 If you have any questions about this submittal, please contact me at (256) 729-2636.

S ncerel T. E.

Manage L

icensin and ndustry Affai s Refer

1.

NRC letter, M.H. Chernoff to K.E. Singer, dated April 8, 2005, "Browns Ferry Nuclear Plant, Unit 1 -

Request for Additional Information Regarding Revision to Excess Flow Check Valve Surveillance Testing Frequency (TS-438) (TAC No. MC4659)".

2.

TVA letter, T.E. Abney to NRC, dated October 12, 2004, "Browns Ferry Nuclear Plant (BFN) -

Unit 1 -

Technical Specifications (TS) Change 438 -

Revision to Excess Flow Check Valve (EFCV) Surveillance Testing Frequency".

U.S. Nuclear Regulatory Commission Page 3 April 27, 2005 Enclosure cc (Enclosure):

State Health Officer Alabama Dept. of Public Health RSA Tower -

Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Margaret Chernoff,Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION BROWNS FERRY NUCLEAR PLANT, UNIT 1 TECHNICAL SPECIFICATION CHANGE REQUEST (TS 438)

EXCESS FLOW CHECK VALVE (EFCV)

SURVEILLANCE TEST FREQUENCY NRC REQUEST

1.

"Page E1-7 under Section B, "EFCV Failure rate" states that TVA will address crud build up and valve sticking by flushing lines and inspection 100 percent of the EFCVs.

The application does not address the time period between performance of the testing and startup of the plant.

How will EFCV operability be maintained/assured during the time period between completion of the testing and startup of the plant?"

TVA RESPONSE All Unit 1 excess flow check valves will be inspected, cleaned, and tested prior to Unit 1 restart.

The testing will be accomplished during plant hydrostatic testing, which occurs just prior to restart.

The time period between hydrostatic testing and restart is currently scheduled for approximately four weeks.

This testing is sufficient to demonstrate operability until the next scheduled surveillance test.

NRC REQUEST

2.

"For EFCV refueling testing it is not clear what action the licensee will take if an EFCV failure is identified within the "representative sample" or if a repeat EFCV failure is noted.

For example, will another "representative sample" be tested?"

El-l

TVA RESPONSE At BFN, EFCVs are included within the scope of 10CFR50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.

Technical Instruction 0-TI-346, Maintenance Rule, specifies no more than two EFCV failures are allowed over a 24 month rolling interval.

Investigations and evaluations would be performed in accordance with TVAN Standard Programs and Processes SPP 6.6, Maintenance Rule Performance Indicator Monitoring, Trending and Reporting.

Additional surveillances or corrective actions would be determined based on the evaluation of the specific failures.

NRC REQUEST

3.

"The Radiological Dose Assessment of your submittal states that the leak flow rates and fluid pressure are taken from General Electric NEDO-21143-1, Radiological Accident Evaluation -

The CONAC03 Code, dated December 1981.

Please submit a copy of this report, or provide a reference to a prior submittal of this report."

TVA RESPONSE A copy of General Electric NEDO-21143-1, Radiological Accident Evaluation -

The CONAC03 Code, dated December 1981, and Addendum 1, dated December 1976 are attached to this letter.

E1-2

C--.

NEDO-21 14301 76NED7S CLASS I DECEMBER 1978 f

t 11 cl - " 0V3Rw-%P,,N--

, 314or-5.7v 3 W 1 T7 T17

.1

. -.. C-,o t -

'f nqv.-d f:

t I

CONAC01 MODIFICATIONS (ADDENDUM 1) l D. G. ABBOr I

I GENERALO ELECTRIC

NEDO-21 143-01 76NED78 Class I December 1976 CONAC01 MODIFICATIONS (ADDENDUM 1)

D. Abbott s

BOILING WATER REACTOR SYSTEMS DEPARTMENT

DISCLAIMER OF RESPONSIBILITY This report was prepared as an account of researci and development work performed by General Electric Company. It is being made ailable by General Electric Company widtout consideration in te interest of promoting the spread of technical knowledge. Neither General Elecmric Company nor the individual author:

A. Makes any warranty or representation, expressed or implied, with respect to the accacy, completeness, or usefulness of the Information contained In this report, or that the use of any Information disclosed In this report may not infringe privately owned righ ts, or B. Assumes any responsibility for liability or damage which may result from the use of any Information disclosed in this report.

LN-2 ii

NEDO-21143-01 CONACOl MODIFICATIONS

1. INTRODUCTION The purpose of the CONAC code Is to evaluate the dose consequences of the four design basis accidents In accordance with NRC Regulatory Guides.. As originally written and described," the method of analysis required that containment and buliding parameters(i.e., leakrates, recircrates, purge rates, and filter efficiencies) remain constant during the entire accident tme. Unfortunately, as system modermg requirements became more demanding and buiding ventilation and purge system designs became more complex, It was necessary to evaluate the accident with variations In these parameters during the accident period. To make this analysis easier, the CONAC code was modified to allow modeling with such parameter changes.

.2.

DESCRIPTION The CONAC user models the plant as a system of compartments connected In serles.2 In the original version. the variables used to describe these compartments consisted of six arrays Indexed by compartment. These arrays have now been converted to two-dimensional arrays, indexed by compartment and time. An additional array and a new variable have been created to Identify the time periods. The new variable list for describing compartment behavior is as follows:

UTCHAN number of time Intervals TCHAN(IT) time at beginning of time interval IT; the first interval must always begin at time zero (hr)

RLEAK(ICMP,rr) leak rate from compartment ICMP to next compartmnent during time Interval IT (0%

per day)

FLEAK(ICMP,iT) leakage filter efficiency from compartment ICMP during Interval IT (%)

RECIRC(ICMP,1r) recirculatlon rate In compartment ICMP during Interval IT (V. per day)

FRECIR(ICMPrfl) recirculation filter efficiency for compartment ICMP during Interval IT (%)

RPURGE(ICMP,IT) -

purge rate to environment fromn compartment ICMP during Interval IT (% per day)

FPURGE(ICMP,IT) -

purge filter efficiency from compartment ICMP during Interval IT (0/%)

In addition to the above changes in Inputvalues, the outputtables were modified so the compartment variations with time can be printed In the output.

3. METHODS The only portion of the code which was changed was the section that calculates the Inventories and releases as a

,function of time. The sections which generate source terms, atmospheric diffusion factors (X/0) and doses were not modified.

In the originalversion.the compartment activityand release values were determined by calling the subroutine RELES, once for each Isotope. One call of RELES generated the values at all the times of Interest (typically 1 minute, 30 minutes, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, etc;).

P. P. SWavage. E. J. Morgan. Conservative R

  • oiticAccidednt Evauaton - The CONACO0 Code, March 1976 (NEDO-21 149).

See Reference 1, page 25 for an luatratkon.

NEDO-21 143-01 The modification consisted of reprogramming so that, for each time interval IT, RELES Is called once per isotope. The Inventories at the end of one interval became the Initial Inventories for the beginning of the nexd Interval. The program sorts through the times of interest and arranges them in the appropriate time intervals. For each interval, the values calculated at the times of Interest are then stored as the program moves on to the next Interval. Alter all the time Intervals have been processed, the tables of Inventories and releases at the t11es of interest are frnmed In the same format as the previous version of the code. Those tables are then used by the code to calculate the dose.

3.1 SAMPLE CASES Two sample cases are shown. The first (able 1) shows the Input only for running a case when parameters do not

  • change with time. Note that NTCiiAN and TCHAN (1) default to the values of 1 and 0, respectively. Thus, they need not be Input for this case.

The second sample (Table 2) with output shows the method for a system that does vary with time.

  • 4.

DESIGN VERIFICATION To assure that the code accurately calculates the desired values, several design verification runs were made.

1.

Run 2981 S -

This run compares the resuft of proviilng Identical Input to the old and new versions of CONAC or all four ccidents. The results were identical

2.

Run'2520S -

This run models the Black Fox LOCA. The Stack Fox containment has parameters that vary three imes. An analysis had previouslybeen performo and design verified for the Black Fox PSAR The previous analysis used the older version of CONAC. Each Uime Interval was run separately with output from the previous cases used to provide inputtothe next step. The results were summedby hand. The new version of CONAC dupicated the previous results.

3.

Run 2886S This run modeled the Phipps Send site. The parameters here changed five times. Results were compared with similar results obtained using the ORDOS code (unverilied code). These results agreed to two significant figures.

.2-

NEDO-2i1 43-01 Table 1 SAMPLE 1 1 O 9tS,R(

IS) 1010$: IDENT:NUMB,DGR-TTTO PEXPRESS 1020$ :SELECT :COIACO1 1030$:DATA: I 2000)CRDA 2010 TITLE=42H FSRR HANLYSIS 2020 IRCT=1 2030 P=3458 (AT 105% OF RATED STEAM FLOWJ) 2040 PObIER=3458 (BWR 5 -

MARK II) 2050 BDUD=764 2060 IICOMP=1 (CONiDENSER) 2070 RPURGE=1.0 (CONDENSER LEAK RATE; i

. PER DAY) 2080 DIST=509P 915, 6400 (ER, REC ARER, :& LPZ9 M) 2090 BCS=1500 2100 HITE=O 2110 3000)LOCA 3010 IACT=2 3020 NCOMP=2 3030 RPURGE=0.0 100.

(PC

& RD PURGE RATE, '

PEP DRY) 3035 PLEAK=0.635 (PC LERK PRTE) 3040 FPURGE(2,1)=90.

(SGTS EFF) 3050 HITE=113 3060 BCS=Q 3070 S$

4000)FUHR 4010 IACT=3 (8X8 FUEL) 4015 DOMP=1 4020 RPUPRGE=7200 0.0 (RELEASE IN Z HRS) 4025 FDR=lc5 (125 RODS FOR MK II CONT) 4030 FPURGE=90 0.0 4035 RLEfKO..0 4040 5000)SLBA 5010 IACT=4 5020 SVI=6907 (FT3 -

LCS I) 5V030 COaNC=.013o

.12,

.0899

.24iF.13 (CI.B.. CODLRNT COMC) 5040 RELIOQ=86000 5050 RESTM=14000 5055 HITE=30 5060 50D70)LRST 5080$ :ENDJOB Table 2 SAMPLE 2 DTA CALL NO.....N1 IPUT EDITS CRD NO....1 TITLE-50H COMPARISON CASE CR0 NO.... 2 IACTx2 P:3758 NCOMPa2 DIST*500 CRD NO....3 CHIo=2.6-4 34 1.7-4 x2 2.6-5 '2 1.4-5 5.8-6 CRD NO.... 4 NTCHANs5 CRD NO....5 TCHAN(1)z0.O RLEAK(1,1)*.46 RPURGE(1,1)u0.04 0.0 FPURGE(1,11'o 99 CRD NO.... 6 TCHAN(2)=0.0167 RLEAK(1,2)a.46 RPUROE(1,2)=.04 0.0 FPUROEC1,2)=99 99 CR0 NO.c...7 TCHAN(3)8.111 RLEAK(1,3)e.428 RPUROE(1,3)=.072 212 FPUROE(1,0)u99 99 CRD NO.... t TCHANC4)-2 RLEAK(1,4)F.449 RPURGE(1,4)=.051 73 FPURGE(1,4)u99 99 CRD NO....9 TCHAN(5)28 RLEAK(1,5)=.453 RPURGE(1,5)n.047 47 FPURGE(1,5)*99 99 CRD NO... 10 S2 a

(4 I

Table 2 SAMPLE 2 (Contnued)

NRC LOCA COMPARISON CASE FRACTION HALOGEN RELEASE 0.250 FRACTION NOBLE GAS RELEASE 1.000 REACTOR THERMAL POWER (MWT) 3758.0 ISOTOPE LAMBDA BETA-EN.

GAMMA EN. SPECIFIC ACT. AIRBORNE ACT BETA DCF GAMMA DCF HAL. DCF t/SEC MEV/DIS MEV/DIS CI/MWT CI REM/Cl-SEC/M**3 REM/Cl 1131 9.98E-07 2.09E-01 3.75E-01.

2.51E 04 2.36E 07 4.81E-02 9.38E-02 1.49E 0o 1132 8.43S-05 4.2lE-01 2.29E 00 3.81E 04 3.58E 07 9.68E-02 5.72E-01 5.67E 04 1133 9.26E-06 4.03E-01 6.36E-01 5.B2E 04 5.28E 07 9.27E-02 1.59E-01 3.70E 05.

1134 2.20E-04 5.58E-ol 2.51E 00 6.58E 04 6.18E 07 1.28E-01 6.27E-01 2.86E 04 1135 2.92E-05 4.75E-01 1.46E 00 5.10E 04 4.79E 07 1.09E-01 3.64E-O1 1.35E 05 ISOTOPE LAMBDA BETA EN.

GAMMA EN. SPECIFIC ACT. AIRBORNE ACT BETA DCF GAMMA DCF 1/SEC.

MEV/DIS MEV/D0S CI/MWT CI REM/Ct-SEC/M**3 m

KR83M

.1.04E-04 3.71E-02 2.48E-03 4.15E 03 1.56E 07 8.53E-03 6.20E-04 0

KR85M 4.30E-05 2.53E-01 1.59E-01 1.30E 04 4.87E 07 5.82E-02 3.98E-02 7

KR85 2.05E-09 2.50E-01 2.20E-03 4,10E 02 1.54E 06 5.75E-02 5.50E-04 KR87 1.52E-04 1.32E 00 7.93E-01 2,34E 04 8.77E 07 3.04E-01 1.98E-01

KR8B 6.88E-OS 3.77E-Ot 1.95E.00 3.20E 04 1.20E 08 8.67E-02 4.88E-Ol o

KR89 3.66E-03 1.37E 00 2.00E 00 3.98E 04 1.50E 08 3.15E-01 5.00E-Ol XE131M 6.69E-07 1.42E-01 2.01K-02 2.60E 02 9.75E 05 3.27E-02 5.03E-03 XE133M 3.60E-06 1,91E-01 4.20E-02 1.38E 03 5.20E 06 4.39E-02 1.05E-02 XE133 1.52E-06 1.35E-01 4.54E-02 5.02E 04 2.11E 08 3.11E-02 i.14E-02 XE135M 7.55E-04 9.50E-02 4.32E-01 1.56E 04 5.85E 07 2.1KE-02 l.OE-Ol XE135 2.10E-OS 3.17E-01 2.47E-01 5.36E 04 2.02E 08 7.29£-02 6.17E-02 XE137 3.01E-03 1.64E 00 1.94E-01 5.10E-04 1.92E 08 3.77E-01 4.55E-02 XE138 8.14E-04 6.11E-0l 1.18E 00 4.78E 04*

1.79E 08 1.41E-Ol 2.95E-Ol

NUMBER OF.

PONENTS - 2 LEAK RATE,

% PER DAY PURGE RATE,

% PER DAY RECIRC RATE, X PER DAY

.LEAK FILTERS EFFICIENCY, %

PURGE FILTERS EFFICIENCY, %

RECIRC FILTERS EFFICIENCY, %

TIME, HRS 0.

0.017 0.111 2.000 8.000 0.

0.017 0.111 2.000

e. 0oo 0.

0.017 0.111 2.000 8.000 0.

0.017

0. 111 2.000 8,000 0.

0,017 0.111 2.000 8.000 0.

0.017 O. 111 2:000 8.000 0.460 0.460 0.425 0.449 0.453 0.040 0.040 0.072 0.051 0,047 0.

0.

0.

0.

0.

0.,

0.

0.

0.

0.

0.

89.000

99. 000 99.000 99.000 0.

0.

0.

0.

0.

Table 2 SAMPLE 2 {Conlinued)

.IPONEtT NUMBER 2

3 4

5 0.

0.

0.

0.

0.

0.

0.

212. 000 73,000 47.000 0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

99.000 99.000 99.000 99.000 99.000 0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

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O.

0.

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0.

0.

0.

0.

0.

0.

O.-

0.

0.

a) zm 0

N) w DISTANCEIM 500.0 TIME BREATHING RATE,rt43/SEC 1 MIN 30 MIN 1 HR 2 HR 4 HR 3.5E-04 3.5E-04 3.5E-04 3.5E-04 3.5E-04 INPUT CHIO, SEC/M**3 30 MWN t HR 2 HR 4 HR a HR 2.60E-04 2.60E-04 2.GOE-04 1.70E-04 1.70E-04 8 HR 12 HR 1 DAY 4 DAY 30 DAY 0.5E-04 1.7E-04 1.7E-04 2.*E-04 2.3E-04 DISTANCE 500.

1 MIN 2.60E-04 12 HR

2. SOE-05 I DAY
2. 60E-05 4 DAY I.40E-05 30 DAY S. 8OE-06 BUILDING CROSS SECTION,Mxx2 HEIGHT
  • 0.

0.

Table 2 SAMPLE 2 (Contnued)

. COMPARISON CASE TABLE 15.1.39 CONTAINMENT ACTIVITY,CURIES NRC LOCA 130TOPE I MIIN 30 MIN 1 HR 2 HR 4 HR 8 HR 121-HR I DAY 4 DAY 30 DAY 1131 1132 1133 1134 1135 TOTAL I 44 KRSSM KR85M KR85 KR87 KRS8 KR89 XE131M XEI33M XEI 33 XEI 3511 XE1¶35 XE137 XE 138 2.4E 07 3;6E 07 5.$E 07 6.1E 07 4.8E 07 2.2E 08 1.6E 07 4.9E 07 1.SE 06 8.7E 07

1. 2E 08 1.2E 08 9.8E 05 5.2E 06 2.1E 08
5. 6E.07 2.OE 08 1.6E 08 1.7E 08 2.4E 3.1E
5. 2E
4.
  • E 4.5E 07 07 07 07 07 2.3E 07 2.6E 07 5.1E 07 2.8E 07 4.3E 07 2.3E 1.9E
4. 9E
1. 3E
3. 9E 07 07 07 07.

07 2.3E 07 1.1E 07 4.6E 07 2.6E 06 3.1E 07 2.3E

3. 1E
4. 0E l.lE
2. 1E 07 06 07 05 07 2.3E 07 9.3E 05 3.5E 07 4.6E 03 1.4E 07 2.2E 07 2.4E 04 2.4E 07 3.4E-01 3.SE 06 1.9E 0B 1.7E 05 1.4E 08 1.1E 08 B.7E 07 7.2E 07 4.9E 07 1.8E 07 1.5E 0S 1.6E 07 7.5E-06 2.1E 06 0.

1.8E 03 1.5S 06 0.

1.7E-03 0.

0.

I.3E 4.5E 1.5E 6.7E I.1E 2.1E

9. 7E 5.2E 2.1E
1. SE 1.9E 8.5E
4. IE U

a 0*

07 07 06 07 08 05 05 06 08 07 08 05 07 t I E 4.2E 1 SE

5. 1 E 9.4E 2.8E
9. 7E
5. IE
2. 1E 3.9E 1,9E

$. 8E 9.6E 07 07 06 07 07 02 05 06 08 06 08 03 06 7.4E 06 3.6E 07 1.SE 06 2.9E 07 7.3E 07 5.4E-04 9.7E 05 5.1E 0O 2.1E 08 2.5E 05 1.7E 08 7.4E-02 5.1E 05 3.5 06 2.6E 07 1.5E 06 9.8E 06 4.5E 07 1.9E-15 9.7E 05 4.9E 06 2.1E 08 1.1 03 1.5E 08' 2.9E-11 1.5E 03 7.8E 05 1.4E 07 1.5E 06

.1.1E 06 1.7E 07 0.

9. 5E 05 4.7E 06
2. OE 08
2. 1 E-02 1.lE 08 0.

I. 2E-02 1.7E 05 7.6E 06 1.5E 06 1.2E 05 6.IE 06 0.

9.6E 05 4.4E 06 2.OE 08

4. 0E-07 8.1E 07 0.
9. 6E-08 1.9E
1. 2E
1. SE
1. 7E
3. 1E 0.

9.2E 3.8E 1.8E 0.

3.3E 0.

0.

03 06 06 02 05 05 06 08 07 3.6E-09 1.7E 01 1.5E 06 O;

5.4E-03 0.

7.6E 05 1.5E 06 1.2E 08 1.4E 05 0.

0.

0.

0.

1.3E 06

0.

0.

0.

1.5E 05

4. OE 02 3.5E 06 0.

0.

0.

0.

TOTAL NO 1.2E 09 7.OE 08 6.2E 08 5.4E 08 4.56E 08 3.5E 08 3,0E 08 2.2E 08 1.3E 08 5.OE 06

Table 2 SAMPLE 2 (Continued)

COMPARISON CASE TABLE 15.1.39 SHIELD BUILDING ACTIVITY,CURIES NRC LOCA ISOTOPE I MIN 30 MIN 1 HR 2 HR 4 HR 8 HR

.12HR I DAY 4 DAY O0DDAY 1131 1132 1133 1134 1135 TOTAL I KR83M KR8BM KRG5 KR87 KR88 KRB9 XE1311M XE133M XE133 XE1 35M XE1 35 XE137 XE138 TOTAL NO 7.5E 1.11E

1. 7E 2.0E 1.SE 01 02 02 02 02 2.1E 2.7E 4.GE 3,7E 4.0E 03 03 03 03 03 4.0OE

.4.

5K S.* BE 4.8KE 7,4E 03 03 03 03 03 7.7E 6,4E 1,6E 4.2E 1, 3E 03 03 04 03 04 1.GE 7.1E 3.1E 1.7E 2.1 04 03 04 03 04 3.OE 4.1 E 5.3E 1, 4E 2.7E 04 03 04 02 04 4.3E 1,8E

6. SE
8. 9E 2.6E 04 03 04 00 04 7.6E 04 8.7E 01 8.4E 04 1,2E-03 1.4E 04 1.3E 05 6.2KE-0 1.7E 04 0.

1.6E 01 1.5E 04 0.

1.7E-05 0.

0.

7.1E 02 1.7E 04 3.0E 04 4.7E 04 7.7E 04 1.1E 05 1.4E 05 1.7E 05 1.5E 05 1.5E 04 5.OE 1.6E 4.9E 2,8E 3.8E

3. SE 3.1 E 1.7E S.8E 1.8E f.fE 5.1E S.5E 3,8 E 01 02 00 02 02 02 00 01 02 02 02 02 02 03 1.1E 4.0KE 1, 4E
5. GE S.,4E 1.8E 1.9E 1.3E 1, 7E 7,5SE 3.7E 6.2E 03 1.8E 03 03 7.2E 03 02 2.7E 02 03 a 7E 03 03 1,6E 04 01 4.9E-02 01 1.7E 02 02 0.,E 02 04 3.6£ 04 03 6.6E 02 04 3.2E 04 0.1 6.5E-0l 03 1.6E 03 04 I.1E 05 2.4E 03 1.2E 04 5.1E 02 9,6E 03 2.4E 04 1.8E-07 3.2E 02 1.7E 03 6.9E 04 8.4E 'O1 5.7E 04 2.4E-05 1.7E 02 2.3E 03 1.8E 04 1.OE 03 6.6E 03 3.0E 04 1.3E-18 6.5E 02 3.3E 03 1.4E 05 7.5E-Ol 1.0E 05 1.9E-14
9. 8E-01 1.OE 03 1.8E 04
2. OE 03 1.4E 03 2.2E 04 0.

1.2E 03 6.1E 03 2.6E 05 2.7E-05 1.4E 05 0.

1. 5E-os 3.4E 02 1.5E 04
3. OE 03 2.4E 02 1.2E 04 0.

1.8E 03 8,6E 03 3.8E 05 7.7E-1O 1.6E 05 0.

1.8E-10 S.9E 00 4.2E 03 5.4E 03

6. lE-Ol l.1E 03 0.

3.3E 03 1.3E 04 S.5E 05 0.

1.2E 05 0.

0.

3. OE-Il 1.4E-a1 1.2E 04 0.

4.4E-05 0.

6.2E 03 1.2E 04 1.OE 06 0.

1.1E 03 0.

0.

0.

0.

1.3E 04 0.

0.

0.

1.4E 03 3.9E 00

3. 5E 04 0.

0.

0.

0.1 zm a9 1.8E 05 3.OE 05 4.6E 05

!B.8E 05 B.OE 05 1.OE 06 4.9E 04 s.

Table 2 SAMPLE 2 (Continued)

COMPARISON CASE TABLE 15.1.39 RELEASED TO ENVIRON ACTIVITY,CURIES NRC LOCA ISOTOPE 1 MIN 30 MIN 1 HR 2 HR 4 HR 8 HR 12 HR I DAY 4 DAY 30 DAY 1101 1132 1133 1134 1135 6.5E 00

9. 9E 00 1.5E 01 1.7E 01 1.3E 01 1,0E 1.5E 2.3E 2,5E 2.0E 01 01 01 01 01 1.52 2.1E 3,3E 3.2E 3.0E 01 01 01 01 01 2.7E 3.3E 6.0E 4, 2E 5.1E 01 01 01 01 01 4.4E 4.3E 9.4E 4.SE 7.6E 01 01 01 01 01 9.2E 5.5E 1*SE 4.8E 1.3E 01 01 02 01 02 1.4E 5.9E 2.6E 4.8E 1,

.E 02 01 02 01 02 3.3SE 6.1E

5. 1E 4.82E 2.3E 02 01.

02 01 02 2.3E 6.1E 1.3E 42 BE 2.*7E 03 01 03 01 02 1.OE 6.1E 1.5E 4.8E 2.7E 04 01 03 01 02 TOTAL I 6.1E 01 9.3E 01 1.3E 02 2.1E 02 3.0E 02 5.1E 02 6.7E 02 1.2E 03 4.OE 03 1.2E 04 KR83M 4.3E 00 KR85M 1.4E 01 KR85 4.3E-01 KR87 2.4E 01 KR88 3.3E 01 KR89 3.7E 01 XE131IM 2.7E-01 XE133M 1.4E 00 XE133 592E 01 XEt35M 1.6E 01 XE135 5.6E 01 XE137 4.9E 01 X9138 4.9E 01 TOTAL No 3.4E 02 2.2E 02 7.2E 02 2.4E 01 1.2E 03 1.7E 03 2.3E 02

.1.5E 01 8.oE 01 3.3E 03 4.5E 02 3.OE 03 3.8E.02 1.3E 03 4.6E 1.56 5.6E 2.4E

3. sE 2.3E 3.5E I.92 7.6E

.7.02E 3.8SE 1.82 02 03 01 03 03 02 01

,02 03 02 03 02' 03 S.2E 02

3. 6E 03 1.4E 02 4.4E 03 8.1E 03.

2.32E 0 8.6E 01 4.5E 02 1.9E 04 6.8E 02 1,6E 04

3. 8E 02 1.9E 03 1.3E 03 5.9E 03 2.5E 02 5.7E 03 1.2E 04 2.3E 02 1-.6E 02 S.2E 02 3.4E 04
6. SE 02 2.8E.04 3.8E 02 1.9E 03 1.7E 03 S9.SE 03 5.7E 02 6.4E 03 1.8E 04 2.3E 02 3.5E 02 1.8E 03 7.62E 04 6.9E 02 5.4E 04 3.8E 02 1.9E 03
1. 7E 1.2E 8.8E 6.5E
2. OE 2.3E 5.5E 2.7E 1.2E
  • 6.9E 7.4E 3.8E
  • 1.9E 03 04 02 03 04 02 02 03 05 02 04 02 03 1.8E 1.5E 2.2E 6.5E 2.2E 2; 3E 1.4E 6.4E
2. 9E
6. 9E 1.2E 3, SE

.1.9E 03

.1.

BE 04 1.6E 03 1.BE 03 S.5E 04 2.2E 02 2.3.E 03 1.0E 03 3.1E 05 1.8E 02 G.9E 05 1.7E 02 3.8E

03. 1.9E 03 04 04 03 04 02 04 04 06 02 05 02 03 1.8E 03
1. 6E 04
2. 0E 05 6.5E 03 2.2E 04 2.3E 02 S. 8E 04 5.3E 04 S.1E 06 8.9E 02 1.7E 05 3.8E 02 1.9E 03 zm 0

Pt 1.3E 04 2.6E 04 5.6E 04 9.1E 04 1.7E 05 2.4E 05 4.6E 05 2.1E 06 S.6E 06

Table 2 SAMPLE 2 (Condnued)

NRC LOCA COMPARISON CASE DISTANCE 500, M, TIME X/Q (SEC/M3)

THYROID WHOLE BODY BETA SKIN (DOSESM REM) 1 MIN.

2.60E-04 1.63E 00 2.26E-02 l.Z8E-02 3,84E-02 30 HIN 2.60E-04 2.50E 00 5.03E-01 3.37E-01 8.40E-O1 1 HR 2.60E-04 3.68E 00 9.56E-Ot 8.24E-01 1,58E 00 2 HR 2.60E-04 8,54E 00 1.63E 00 1.19E 00 3,02E 00 4 HR 1.70E-04 9.04E 00 2,39E 00 1.57E 00 3.96£ 00 8 HR 1.70E-04 1.56E 01 3.28E 00 2.29E 00 5.57E 00 12 HR 2.0KE-05 1,8tE 01 3.35E 00 2.37E 00 0,73E 00 1 OAY 2.60E-05 1,79E 01 3.50E 00 2.61E 00 6.11E 00 4 DAY.

1.40E-05 2.82E 01 3.80E 00 3.37E 00 7,17EO00 30 DAY..

5.80E-OS 4,43E 01 4.09E 00 4.22E 00 8.30E 00 3m

.0 o.

8 7