ML20072A818

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Person-Motion Study of Post-Accident Sampling Activities to Demonstrate Compliance W/GDC-19 & NUREG-0737,Item II.B.3
ML20072A818
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/31/1982
From:
TEXAS UTILITIES SERVICES, INC.
To:
Shared Package
ML20072A797 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NUDOCS 8301240140
Download: ML20072A818 (25)
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  • COMANCHE PEAK STEAM ELECTRIC STATION PERSON-MOTION STUDY OF POST ACCIDENT SAMPLING ACTIVITIES TO DEMONSTRATE COMPLIANCE WITH GDC-19 AND <

NUREG 0737 ITEM II.B.3 DECEMBER 1982 TEXAS UTILITIES SEPVICES INC.

NUCLEAR ENGINEERING

.no-8301240140 830118 PDR ADOCK 05000445 PDR E

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TABLE.0F CONTENTS section title page I. Statement of Problem 1 II. Assumptions 2 III. References 3 IV. Results 4 i

LIST OF TABLES table title page 1 Post Accident Sampling-Required Activities (7 sheets) 5 2 Post Accident Sampling-Dose Assessment (4 sheets) 12 2A PASS Dose Assessment-Entry to Sample Room, Without Cart 16 2B PASS Dose Assessment-Exit from Sample Room, Without Cart 17 2C PASS Dose Assessment-Entry to Sample Room, With Cart 18 2D PASS Dose Assessment-Exit from Sample Room, With Cart 19 3 Post Accident Sampling System-Containment Isolation Valves 21 LIST OF FIGURES figure title 1 PASS Access / Egress Paths - Turbine Building 2 PASS Access / Egress Paths - Safeguards Building i

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I. STATEMENT OF PROBLEM This evaluation demonstrates that all the activities necessary to

, acquire, retrieve, and analyze post-accident samples of reactor coolant and containment air can be performed without exceeding the exposure limits of General Design Criterion 19 (GDC-19) in Appendix A to 10CFR Part 50.

It also shows that, by a coordinated effort of several individuals, the required post-accident samples can be acquired, retrieved and l analyzed within the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> time limit established by NUREG-0737, Item II.B.3 (Ref. 1).

This evaluation was performed to satisfy the licensing requirement to provide a summary of person-motion studies which verify compliance with GDC-19. this requirement was imposed in Supplement 2 to the CPSES Safety Evaluation Report (Ref. 2).

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II. ASSUMPTIONS _

The assumptions made in this evaluation are as follows:

1. The source tems used are those listed in Section II.B.2 of  ;

the CPSES FSAR. These source tems exceed Regulatory Guide 1.4 release quantities (Ref.3).  ;

2. Post-accident background dose rates are as shown in Figures II.B.2-1 through II.B.2-24 (Ref. 4). For the purposes of this evaluation, the approximate mid-range value for each ,

Zone Classification in Figure II.B.2-1 (at a time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the accident) is used. The dose rates for each Zone are therefore assumed to be as follows:

Zone I s 0 Rem /hr Zone III s 5.0 Rem /hr Zone II a 5.0 Rem /hr Zone IV E 50' Rem /hr

3. For dose evaluation purposes, two persons perform all the required activities. One person is stationed at the location of the PASS Remote Operating Modules (see Figure 1). This person perfoms all activities which require manipulation or observation of this equipment. The second individual performs all other required activities.

This is a conservative assumption for demonstrating compliance with GDC-19. It is expected that several individuals would be involded in a coordinated post-accident sample acquisition, retrieval, and analytic process.

The evaluation of compliance with the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> criteria of NUREG-0737 takes credit for the coordinated involvement of several individuals.

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4 The walking speed of an individual is 4.0 ft/sec, unless the individual is pulling a transport cart, in which case the rate is set at 2.0 ft/sec.

5. The time required to obtain clearance past a security door is 10 seconds. All other doors require 2 seconds for passage.
6. Anti-contamination clothing and/or equipment is "put-on" and "taken-off" in a Zone II post accident radiation area. The l time allotted for each of these activities is 5 minutes.
7. Samples of depressurized reactor coolant, reactor coolant off-gas, and containment air are captured3 retrieved, and analyzed. _

l 8. The dose contribution from shielded micro-volume samples in l

transit is insignificant and set at 0.0 mrem /hr.

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r III. REFERENCES

1. NUREG-0737, Clarification of TMI Action Plan Requirements, U. S. Nuclear Regulatory Commission, November,1980.
2. NUREG-0797, Safety Evaluation Report Related to the Operation of Comanche Peak Steam Electric Station, Units 1 and 2, Supple-ment 2. U. S. Nuclear Regulatory Commission, January, 1982, page 22-3.
3. Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Waters, Revision 2, U. S. Nuclear l Regulatory Commission, June 1974.
4. Final Safety Analysis Report, Comanche Peak SES, Texas Utilities Generating Company, Sections II.B.2 and ll.B.3.
5. Reactor Coolant PASS Technical Manual, Appendix B, Radiological Assessment-Retrieval of Samples, General Dynamics-Reactor Plant Services, September, 1982 (Preliminary copy).
6. Containment Air PASS Technical Manual, Appendix A, Radiological Assessment-Retrieval of Samples, General Dynamics-Reactor Plant Services, September, 1982 (Preliminary copy).

IV. RESULTS The activities necessary to obtain post accident samples of depressurized reactor coolant, reactor coolant off-gas, and containment air are listed in Table 1. The estimated doses received by the two individuals assumed to perform these activities are itemized in Table 2. Table 2 also presents conservative estimates of the time required to perform each activity. The continuity of each activity in the overall sampling process is considered in Table 2 and is noted by the activities which are shown to occur concurrently with others.

Based on the information presented in Tables 1 & 2, the two individuals involved in the sampling process receive a total whole body dose of 4.34 person-rem. The individual who is stationed at the PASS Remote Operating fiodule location receives an estimated 1,387 mran from the room background. The other individual, who is assumed to perform all retreival and analy-tical activities receives an estimated 2,957 mrem. This second individuals in estimated to receive an extremity dose of 3.35 Rem. Each of these doses is well within the limits of GDC-19, as is the person-rem total for all activities.

As shown in Table 2, all required sample acquisition, retreival, and analysis are conservatively estimated to take approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 47 minutes to perform. This is within the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> requirement of NUREG-0737.

As demonstrated herein personnel at the Comanche Peak Steam Electric Station have the capability to obtain and analyze all required post-accident samples within the time restraints of NUREG-0737 while maintaining compliance with General Design Criterion 19.

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Page 1 of 7 TABLE 1 Post Accident Sampling - Required Activities ACTIVITY # DESCRIPTION OF ACTIVITY l Decision to take RCS and Containment air samples. Energize PASS equipment.

2 Enter Sample Room via path A (see Figures 1 and 2) to perform activities 2(a) - 2(c). i 2(a) Position the following valves as indicated:

CLOSE valves 1PS-054 and 1PS-055 OPEN valves 1CC-1014 and 1CC-1015 These operations align safeguards Component Cooling Water (CCW) to RC PASS Sample Cooler and " valves out" the non-safeguards CCW flow path.

2(b) Verify the position of these valves:

1PS-038 and 1PS-039 must be CLOSED 1PS-040 must be OPEN These valve positions will permit the flow of reactor coolant, or Containment sump water to the RC PASS Sample Module (and blocks the normal sampling path) when the sample acquisition process is begun. (see Activity 7(a) ).

2(c) Verify the position of these valves:

1PS-056 and 1PS-059 must be OPEN These positions will assure the operational i

capability of the RC PASS Sample Module spray system and drain system, respectively.

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TABLEI Post Accident Sampling - Required Activities Page 2 of 7 ACTIVITY # DESCRIPTION OF ACTIVITY 3 Exit the Sample Room via path B (see Figures 1 and 2).

4 Verify the flow of safeguards CCW to the RC PASS Sample Cooler by observing the indications provided by the temperature, pressure, and flow instrumentation on the CCW inlet and outlet piping. These indica-tions are displayed on the RC PASS Auxiliary Module.

5 Verify the availability of nitrogen gas to the RC PASS and CA PASS Remote Operating Modules from the local supply.

6 Position the valves in the RC PASS Flush and Diversion Manifold in the sampling mode (i.e.-

FDP-1 and FDP-2 should be open; FDP-3 and l

FDP-4 should be closed). These valves are actuated by controls on the RC PASS Auxiliary Module.

7(a) Request that the Control Room operator (s) transfer control of the sampling Containment isolation valves to the PASS Isolation Valve Control Panel (PIVCP). Inform the Control l

Room that Containment Isolation (if present) will be overridden.

Initiate the reactor coolant sampling pro-I cess by opening the proper RC PASS Contain-l ment Isolation valves (listed in Table 3).

' These activities are performed at the PASS Isolation Valve Control Panel (PIVCP), see l

l Figure 1).

7(b) Initiate the containment air sampling process by opening the proper CA PASS Containment Isolation valves (see Table 3) at the PIVCP.

TABLE 1 Post Accident Sampling - Required Activities Page 3 of 7 ACTIVITY # DESCRIPTION OF ACTIVITY 8(a) Purge the RC PASS Sample Module until a representative sample can be acquired.

8(b) Purge the CA PASS Sample Module until a representative sample can be acquired.

9(a) Verify flow of reactor coolant thru the RC PASS Sample Module by observing the indica-tions provided by the temperature, pressure, flow and radiation monitoring instrumenta-tion located in the RC PASS Sample Module.

These indications are displayed on the RC PASS Remote Operating Module.

9(b) Verify flow of containment air thru the CA PASS Sample Module by observing the indica-tions provided by the temperature, pressure, flow, and radiation monitoring instrumenta-tion located in the CA PASS Sample Module.

l These indications are displayed on the CA l PASS Remote Operating Module.

10(a) Capture undiluted samples of depressurized coolant and reactor coolant off-gas in the RC PASS Sample Module via operations at the RC PASS Remote Operating Module.

l 10(b) Capture undiluted samples of Containment air as well as Containment air iodine and

! particulate samples in the CA PASS Sample Module, via operations at the CA PASS Re-mote Operating Module.

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. . l TABLE 1 Post Accident Sampling - Required Activities Page 4 of 7 ACTIVITY # DESCRIPTION OF ACTIVITY 11 Calculate the amount of total dissolved gas l in the reactor coolant by comparing initial and final temperature and pressure readings in the gas loop of the RC PASS Sample Module. l These indications are displayed on the RC PASS Remote Operating Module.

i 12(a) CLOSE the RC PASS INFLUENT Containment Isolation valves at the PIVCP. (See Table 3).

The RC PASS EFFLUENT Containment valves (downstream of the RC PASS Sample Module) remain open.

12(b) CLOSE the CA PASS INFLUENT Containtment Isolation Valves (see Table 3). The CA '

PASS EFFLUENT Containment Isolation valves remain open.

13(a) Position the valves in the RC PASS Flush and Diversion Manifold in the flush mode (i.e.,

FDP-1, FDP-2, FDP-3, and FDP-4 should be open). These valves are operated at the RC '

PASS Auxiliary Module.

13(b) Position valve CAP-10 (in the CA PASS Sample Diversion Valve Module) to the flush position.

This valve is operated from the CA PASS Remote Operating Module.

14 Verify that the RC PASS Flush Module is filled with demineralized water and that a supply of make-up water is available. See Figure 1 for the location of the RC PASS Flush Module.

TABLE 1 Post Accident Sampling - Required Activities Page 5 of 7 ACTIVITY # DESCRIPTION OF ACTIVITY

, 15(a) Initiate the RC PASS flushing process by switching on the positive displacement pump which is part of the RC PASS Flush Module. This pump is activated by a switch f located on the RC PASS Auxiliary Module.

l 15(b) Initiate the CA PASS flushing process by opening)the (CAP-11 . This nitrogen valve ispurge supply operated fromvalve the CA PASS Remote Operating Module.

16(a) Complete the flushing of piping in the RC PASS Sample Module such that the only sources of radiation in the Sample Module are from the shielded vessels which contain small volumes (5 ml) of depressurized reactor coolant and reactor coolant off-gas.

Indications of the ten.perature, pressure, radiation monitoring, pH, and conductivity ,

instrumentation allow a determination that

, the flushing process has been completed.

l These indications are displayed on the RC PASS Remote Operating Module.

I 16(b) Complete the flushing of CA PASS Sample 1 Module piping such that the only sources I

of radiation in the sample module are from the shielded vessel containing about 10ml of containment air and the filter cartridges for iodines and particulates.

I Indications of the temperature, pressure, and radiation monitoring instrumentation allow a determination that the flushing process has l been completed. These indications are dis-

! played on the CA PASS Remote Operating Module.

1 TABLE 1 Post Accident Sampling - Required Activities Page 6 of 7 1

ACTIVITY # DESCRIPTION OF ACTIVITY l 17(a) CLOSE the RC PASS EFFLUENT Containment Isolation Valves downstream of the RC PASS Sample Module (see Table 3) by operation at the PIVCP. All RC PASS Con-tainment Isolation Valves are now closed.

l 17(b) CLOSE the CA PASS EFFi.UENT Containment Isolation valves (see Table 3) by operation at the PIVCP. All CA PASS Containment Isolation Valves are now closed.

18 Prepare hot laboratory, hot cell, and count-ing room for delivery of samples; assure all instrumentation and equipment is in proper working order.

19 Prepare to enter sample room. Obtain the necessary sample micro-syringes, septum-equipped vials, shielded containers, and transport cart.

20 Enter the sample room via Path A, (see Figures 1 and 2) and prepare to obtain the samples.

21(a) Obtain a 50p1 depressurized reactor coolant sample and a 10pl sample of reactor coolant off-gas. Inject each into shielded vails.

21(b) Obtain 100p1 sample of containment air, a 10p sample of :ontainment air (which is in-jected into a shielded vial) and remove the iodine / particulate filter cartridges.

TABLE 1 Post Accident Sampling - Required Activities Page 7 of 7 ACTIVITY # DESCRIPTION OF ACTIVITY 22 Leave the Sample Room via Path C, and trans-port the samples to the hot cell.

[ 23 Prepare samples for the various analyses described in FSAR'Section II.B.3.4.

24 Remove the sample (s) which require radio-logical analyses from the Hot Cell and trans-pcrt these to the counting room, via the shielded pass-thru window.

25 Perform the required chemical analyses by the methods described in Section II.B.3.4.

26 Perform the required radiological analyses by the methods described in Section II.B.3.4.

27 Transmit results.

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Page 1 of 4 TABLE 2

~ POST ACCIDENT SAMPLING-DOSE ASSESSMENT TIME TOTAL ' DOSE DUE ACTIVITY # REQUIRED ' ELAPSED TIME 'TO ACTIVITY ' REMARKS

'(see Table 1) '(min:sec) '(min:sec) (mrem) 1 0:00 0:00 N/A 2 7:17 7:17 245 See Table 2A 2(a) 1:00 8:17 83.3 Zone II 2(b) 1:00 9:17 83.3 Zone II 2(c) 1:00 10:17 83.3 Zone II 3 7:17 17:34 232 See Table 2B 4 (<5.00) -

  • Zone II; Concurrent with2(a)-3.
  • Zone II; Concurrent 5 (<1.00) -

with 2-3.

  • Zone II; Concurrent 6 (<2:00) -

with 2-3.

5:00 17:34 0 Zone I; Activity 7 7(a) started befor comple-tion of 3. See Table 2B, footnote (b).

5:00 22:34 0 Zone I 7(b) 30:00 52:34

  • Zone II 8(a) 8(b) 30:00 -

N/A Concurrentwith8(a)&

10(a) 9(a) (<5:00) - N/A Concurrentwith8(a)

(<5.00) - N/A Concurrentwith8(b) 9(b) 10:00 62:34

  • Zone II 10(a) 7:30 70:04
  • Zone II 10(b)

N/A Performed independent 11 (<10:00) -

of later activities.

  • See Note 6

TABLE 2 POST ACCIDENT SAMPLING-DOSE ASSESSMENT Page 2 of 4 TIME TOTAL DOSE DUE

  • ACTIVITY # REQUIRED ELAPSED TIME TO ACTIVITY REMARKS L (See Table 1) (min:sec) (min:sec) (mrem) d 12(a) l<4:00) -

0 Zone I; Concurrent I

with 10(b) 4

! 12(b) 4:00 74:04 0 Zone I 13(a) (<2:00) -

N/A Concurrent with fp 12(b) b 13(b) (<2:00) -

N/A Concurrent with I 12(b) 14 (<5:00) -

N/A Concurrent with 8(a) 15 1:00 75:04

  • Zone II K

1:00 76:04

  • Zone II 15(b) 16(a) 15:00 91:04
  • Zone II r
  • H. 16(b) 15:00 96:04 Zone II. Activity b 16(b) is started
  • S minutes after V 16(a) is begun.

< 17(a) (<4:00) -

N/A Concurrent with 16(b) 17(b) 3:00 99:04 0 Zone I 18 (<60:00) -

250 Concurrent with 2-17(b).

Assumes 30 min. in Hot p Laboratory (Zone II) 19 (<10:00) 83.3 Zone II; Concurrent

> with 16(a) and 16(b) r-F 20 9:12 102:22 453 Preparation for 7 entry partially

/ completed during activity 16(b).

See Table 2C.

  • See Note 6 .

TABLE 2 POSTACCIDENTSAMPLING-DOSEASSESSMENT Page 3 of 4 i

TIME TOTAL DOSE DUE ACTIVITY #

REQUIRED ELAPSED TIME TO ACTIVITY (see Table 1) (min:sec) (min:sec) (mrem) REMARKS 21(a) 2:20 104:42 267 See Note 1 21(b) 2:45 107:27 234 See Note 2 22 12:12 119.39 440 See Table 2D and Note 3 23 25:00 138:27 241 Activity 23 started prior to completion of 22. See Table 2D, footnote (c) and Note 4.

24 2:00 140:27 16.7 Zone II 25 25:00 165:27 236 Zone II; See Note 5 26 20:00 -

0 Zone I; Concurrent with activity 25 27 1:00 166:27 Zone II TOTALS: 166:27 2957

  • See Note 6

Pagn 4 of 4 NOTES TO TABLE 2:

, 1. Dose due to background in the Sample Room (Zone III) is 194 mrem.

Dose due to the presence of the RC PASS sample and the acquisition thereof is 73 mrem whole body. The extremity cose due to sample acquisition is 936 mrem. (Ref. 5)

[ 2. Dose due to background in the Sample Room h 229 mrem.

Dose due to the presence of the CA PASS sample and the acquisition i thereof is 5 mrem whole body and 58 mrem to the extremities.

(Ref. 6) k

' 4. For the 25 minutes allotted for sample preparation, all of the samples o are assumed to be inside the hot cell for 20 minutes. The samples re-quiring radiological analysis are assumed to be removed for counting

' insnediately upon dilution. Doses from these samples are n:gligible.

[ The samples requiring chemical analyses are assumed to be outside y' the hot cell for 5 minutes. Contact with these samples which will result in extremity doses are estimated to occur for 1 minute per i sample source. The extremity dose due to these activities is estimated

. to be 731 mrem.

[ 5. During the 25 minutes allotted for sample analysis, the samples required for chemical analysis are assumed to be outside the hot cell, resulting in an estimated whole body dose of 22.9 mrem. The extremity dose assumes contact with these sources for 2 minutes each. The extremity dose due to these activities is estimated to be 1463 mrem.

. 6. The dose due to the activities denoted by

  • are attributed to the indi-P vidual stationed at the PASS Remote Operating Module location (see Assumption 3). This individual is assumed to be in this location for the duration of the sampling process. During this period (2:46:27) the dose received by this individual is conservatively estimated to be

, . 1,387 mrem.

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' TABLE 2A PASS DOSE ASSESSMENT Entry to Sample Room, Without Cart (a)

Area Distance Radiation Time Req'd Dose (See Figs. 1&2) Traveled (ft) Zone '(min:sec) (mrem) Remarks 31 144 II 0:36 5.0 31 II 0:02 0.3 door entry 24 52 II 0:13 1.8 24 II 0:02 0.3 door entry 25 32 II 0:08 1.1 33 II 5:00 41.7 anti-C cloth-ing station, pre-entry.

25 116 II 0:29 4.0 25 II 0:10 1.4 security door entry 207 12 III 0:03 4.2 207 III 0:02 2.8 door entry 82 56 III 0:14 19.4 82 36 IV 0:09 125 82 IV 0:02 27.8 door entry 78 28 III 0:07 9.7 TOTALS 7:17 244.5 (a) Corresponds to Activity 2 in Tables 1 & 2.

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TABLE 2B PASS DOSE ASSESSMENT (a)

Exit From Sample Room, Without Cart (a)

I " Area # ' Distance Radiation Time Req'd Dose (See Figs.1 & 2) Traveled (ft) Zone (min:sec) (mrem) Remarks 78 28 III 0:07 9.7 78 III 0:02 2.8 door exit

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82 36 IV 0:09 125 82 56 III 0:14 19.4 82 III 0:02 2.8 door exit 207 12 III 0:03 4.2 207 III 0:10 14.0 security door

, exit 25 88 II 0:22 3.1 22 II 5:00(b) 41.7 anti-C clothing station, post-entry 3 25 60 II 0:15 2.1 25 II 0:02 0.3 door exit l, 24 52 II 0:13 1.8 24 II 0:02 0.3 door exit 31 144 II 0:36 5.0 V

TOTALS 7:17 232.2 (a) Corresponds to Activity 3 in Tables 1 & 2.

(b) Activity 7(a) (see Tables 1 & 2) begins 1 minute after the start of this step.

Total elapsed time attributed to Activity 7(a) is 0:00.

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TABLE 2C PASS DOSE ASSESSMENT

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' Entry to Sample Room, With Cart a

. Dose Remarks Radiation Time Req')d .(mrem)

Distance . Zone (min:sec

' Area # Traveled (ft) 10.0 (See Figs.1 & 2) 1:12 II door entry 144 0.3 31 0:02 II 3.6 31 0:26 52 II door entry 0.3 24 0:02 II

- 2.2 24 0:16 II 32 41.7 anti-C cloth-25 5:00(b) ing station, II

'. pre-entry 33 9- 8.0 0:58 security door II Q40 116 1.4

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25 0:10 entry II 25 8.3 0:06 5/A- III door entry g'; 207 12 III 0:05 7.0 38.8 207 0:28 III 1 56 250 0:18 W'

S4F 82 36 IV 0:05 70.0 door entry 82 IV

- 11.2 82 0:08 III 16 ,....,,-

a 78 452.8 9:12 TOT /is 1 & 2.

k' Corresponds to Activity 20dinto Tacles Activity 20 starts J73^

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The amount of elapsed time attributeSteps (b) ()and16(b).

- - . - 4 minutes into this step. iconcurrently ity 20 is 3:18. with Ac b',ki;

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. TABLE 20 Page 1 of 2 PASS DOSE ASSESSMENT Exit From Sample Room, With Cart (a)

Area # Distance Radiation (See Figs. 1) Traveled (ft) . Zone

. (min:sec Time Req)'d(Dosemrem)

Remarks 78 16 III 0:08 11.2 78 III 0:02 2.8 door exit 82 36 IV 0:18 250 82 56 III 0:28 38.8 82 III 0:02 2.8 door exit 207 12 III 0:06 11.2 207 III 0:10 13.9 security door exit 25 32 II 0:16 2.2 25 II 0:10 13.9 Security door entry to hot laboratory 30 32 II 0:16 2.2 30 II 2:00 16.7 unload samples and place in hot cell 30 N/A (1:00) 5.3 dose due to sample handling.(b)

Concurrent with the above activity 30 32 II 0:16 2.2 30 II 0:10 1.4 security door exit from hot laboratory 25 72 II 0:36 5.0 22 II 5:00(c) 41.7 anti-C clothing station, post-entry

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TABLE 2D PASS DOSE ASSESSMENT Exit From Sample Room, With Cart (a) Page 2 of 2 Area # . Distance Radiation Time Req'd. Dose (see Figs 1 & 2) Traveled (ft) Zone (min:sec) .(mrem) . Remarks 25 60 II 0:30 4.2 25 II 0:02 0.3 door exit 24 52 II 0:26 3.6 24 II 0:02 0.3 door exit 31 144 II 1:12 10.0 TOTALS 21:12 439.7 (a) Corresponds to Activity 22 in Tables 1 & 2 (b) Extremity dose due to this action is 165 mrem.

(c) Activity 23 (see Tables 1 & 2) begins 1 minute after the start of this action.

Total elapsed time attributed to Activity 23 is 18:48.

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-TABLE 3 POST ACCIDENT SAMPLING SYSTEM CONTAINMENT ISOLATION VLAVES Reactor Coolant PASS Containment Air PASS k Influent Isolation Valves: Influent Isolation Valves:

HV-4168......IRC(1) HV-5559......IRC ly HV-5558..... 0RC i HV-4169......IRC(2)

HV-4170..... 0RC HV-5561......IRC HV-4182(3) .. 0RC HV-5560..... 0RC Effluent Isolation Valves: Effluent Isolation Valves:

HV-7311..... 0RC HV-5556..... 0RC HV-7312......IRC HV-5557......IRC E (1) IRC designates valves "Inside Reactor Containment".

(2) ORC designates valves "Outside Reactor Containment".

All valves designated "0RC" are in the Safeguards Bldg.

I. (3) Valve HV-4182 isolates the sample path from the RHR system.

This path samples the Containment Sump water when in the recirculation mode of operation.

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