Text

2013, Dresden Initial License Exam, Written Exam References
	ML13354B924
Person / Time
Site:	Dresden
Issue date:	11/25/2013
From:	Walton R; NRC/RGN-III/DRS/OLB
To:	;
	Walton R
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ML11355A018	List: ML13347B096; ML13354B850; ML13354B863; ML13354B869; ML13354B870; ML13354B924; ML13354C049;
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SLC System 3.1.7 Dresden 2 and 3 3.1.7-5 Amendment No. 237/230 Figure 3.1.7-1 (page 1 of 1)

Sodium Pentaborate Volume Requirements

SLC System 3.1.7 Dresden 2 and 3 3.1.7-6 Amendment No. 237/230 Figure 3.1.7-2 (page 1 of 1)

Sodium Pentaborate Temperature Requirements 60 70 80 90 100 110 120 130 140 150 13 14 15 16 17 Sodium Pentaborate Concentration (% by Weight)

Temperature (F)

Acceptable Operating Region (14%, 73.5 F)

(16.5%, 83 F)

(14%, 150 F)

(16.5%, 150 F)

SURVEY NUMBER 13-0029 RWP NUMBER 13-0010 BUILDING Training ELEVATION 603 AREA/ROOM/SYSTEM Rad Worker Exercise Area DATE 10-13-13 TIME 8:00 PURPOSE Weekly

% POWER 100 Legend:

All radiation readings are in mrem/hr and all smears are in dpm/100cm2 unless otherwise noted.

O - Smear - Alpha - Beta - Gamma

- neutron */ - Contact/30cm [ ] - Hot Spot XXXX - Boundary Bkgd - Background SOP - Step Off Pad MDA-Minimum Detectable Activity CA - Contamination Area HPZ - Hot Particle Zone RA - Radiation Area HRA - High Radiation Area LHRA - Locked High Radiation Area ARA - Airborne Radiation Area 0.5 0.5 0.5 10 SOP SOP XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX RA/CA 9

8 20 7

20 6

MU46 XXXXXXXXXXXXXXXXXX 45 MU-16 60

2000/120 90 30 90 HRA/HCA MU26 3

5 4

Pump 30 XXXXXXXXXXXXXXXXXX Cooler MODEL NUMBER LI NUMBER CAL DUE DATE RSO-5 2.7.148 11/10/13 LB-5100 2.12.26 10/31/13 N

A XXXXXXXXXXXXXXXXXXXXXXXXXX RADIOLOGICAL SURVEY FORM Training1.ppt INSTRUMENTS USED PREPARED BY:

NAME (Print)

APPROVED BY:

NAME (Print)

REVIEW ED BY:

NAME (Print)

SIGNATURE SIGNATURE SIGNATURE DATE DATE DATE PAGE_

OF_

PAGES Smear Smear Location dpm/100cm2 1

SOP

<32

<30 2

Floor 9,975 <30 3

Floor 19,476 <30 4

Floor 18,958 <30 5

Floor 120,745 <30 6

Floor 81,047 <30 7

Floor 1,788 <30 8

Floor 9,267 <30 9

Floor 9,546 <30 10 Floor

<32 <30 MDA 32 30 2

1

CATEGORY 1 UNIT 2(3)

DOA 0202-01 REVISION 38 3 of 12 DD:

Subsequent Operator Actions (NOMINAL FEEDWATER HEATING) (HARD CARD):

Is running Pp speed 68% AND FCL 67.8%?

Is FCL

< 55%?

Monitor MSL &

off gas rad monitors for increased activity.

Closed tripped recirc pump discharge valve(s)

MO 2(3)-0202-5A MO 2(3)-0202-5B Notify QNE to monitor core parameters.

IF running recirc pump speed is > 77%

AND FCL 90.0%,

THEN reduce recirc pump speed to 77%

(75 to 79%)

Insert CRAM Rods per DGP 03-04 to reduce Rx power to 25 to 30%

Reduce running Recirc Pp speed to:

Unit 2 < 35%

Unit 3 < 60%

CAUTION DO NOT reduce Rx power to < 10%

with Recirc Flow Notify Chemistry to take samples per TS and ODCM if power change was 20% thermal in one hour.

AFTER 5 minutes, IF SDC NOT in operation, THEN open recirc pump discharge valve previously closed.

YES YES NO NO Continue in Subsequent Operator Actions (Continued) on page 5.

Is OPRM TS 3.3.1.3 Required Action A.3 or B.1 in effect?

YES NO Scram reactor and enter DGP 02-03 At least one OPRM channel operable per RPS trip system?

NO START YES

CATEGORY 1 UNIT 2(3)

DOA 0202-01 REVISION 38 4 of 12 D:

Subsequent Operator Actions (REDUCED FEEDWATER HEATING) (HARD CARD):

Is FCL

< 55%?

Monitor MSL &

off gas rad monitors for increased activity.

Closed tripped recirc pump discharge valve(s)

MO 2(3)-0202-5A MO 2(3)-0202-5B Notify QNE to monitor core parameters.

IF running recirc pump speed is > 77%

AND FCL 90.0%,

THEN reduce recirc pump speed to 77%

(75 to 79%)

Insert CRAM Rods per DGP 03-04 to reduce Rx power to 25 to 30%

Reduce running recirc pump speed to:

Unit 2 < 35%

Unit 3 < 60%

CAUTION Do NOT reduce Rx power to < 10%

with Recirc Flow Continue in Subsequent Operator Actions (Continued) on page 5.

Notify Chemistry to take samples per TS and ODCM if power change was 20% thermal in one hour.

AFTER 5 minutes, IF SDC NOT in operation, THEN open recirc pump discharge valve previously closed.

YES NO YES NO YES NO Is running Pp speed 91%?

AND FCL 65.3%?

Scram reactor and enter DGP 02-03 At least one OPRM channel operable per RPS trip system?

Is OPRM TS 3.3.1.3 Required Action A.3 or B.1 in effect?

START NO YES

LS-AA-1120 Revision 15 Page 13 of 103 Reportability Reference Manual REPORTABLE EVENT RAD 1.4:

Liquid Effluent Release Requirement:

10 CFR 50.73(a)(2)(viii)(B) 10 CFR 20.2203 (a)(3)

§ 50.73(a)(2)(viii)(B): The licensee shall report... any liquid effluent release that, when averaged over a time period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , exceeds 20 times the applicable concentrations specified in Appendix B to 10 CFR 20, Table 2, Column 2, at the point of entry into the receiving waters (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases.

§ 20.2203(a)(3):... each licensee shall submit a written report... after learning of...

levels of radiation or concentrations of radioactive material in -

(i)

A restricted area in excess of any applicable limit in the license; or (ii)

An unrestricted area in excess of 10 times any applicable limit set forth in this part or in the license (whether or not involving exposure of any individual in excess of the limits in 10 CFR 20.1301).

Time Required Notification(s):

Limit NONE No immediate notification is required for this Reportable Event.

Time Required Written Report(s):

Limit 30 DAYS Submit a written report to the NRC within 30 days of discovery of levels of radiation or concentrations of radioactive material in excess of the limits of

§ 20.2203(a)(3). Prepare and submit the report in accordance with the requirements of § 20.2203(b) and (c). [10 CFR 20.2203(a)(3)]

60 DAYS Submit a Licensee Event Report to the NRC within 60 days of discovery of the occurrence of any liquid effluent release that exceeded the limits of

§ 50.73(a)(2)(viii)(B), if the release occurred within 3 years of the date of discovery. [10 CFR 50.73(a)(1), 10 CFR 50.73(a)(2)(viii)(B)]

LS-AA-1120 Revision 15 Page 14 of 103 Reportability Reference Manual REPORTABLE EVENT RAD 1.4 (Contd)

Discussion:

o NRC guidance on this Reportable Event is provided in NUREG 1022, Revision 2, Section 3.2.9.

o The occurrence of this event may require activation of the Emergency Plan. In that case, notification will be made per the Emergency Plan, and a duplicate notification per this Reportable Event is not required. [See SAF 1.1]

o "Unrestricted Area" means any area at or beyond the site boundary, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, and any area within the site boundary used for residential quarters or industrial, commercial, institutional and recreational facilities.

o The location used as the point of release for calculation purposes should be determined using the expanded definition, listed above, for an unrestricted area as specified in NUREG 0133 to maintain consistency with the TS.

Related Reportable Events:

o RAD 1.1, Events Involving Byproduct, Source or Special Nuclear Material That Cause or Threaten to Cause Significant Exposure or Release o

RAD 1.2, Events Involving Loss of Control of Licensed Material That Cause or Threaten to Cause Exposure or Release

References:

o NUREG 1022, Revision 2 o

NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants o

NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes, September 1985 o

10 CFR 50.73 o

10 CFR 20.2203

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-1 Amendment No. 185/180 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

NOTES -----------------------------------

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to APRM indication not within limits, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the APRM is indicating a lower power value than the calculated power, and for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the APRM is indicating a higher power value than the calculated power.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required channels inoperable.

A.1 Place channel in trip.

OR A.2 Place associated trip system in trip.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12 hours B.

One or more Functions with one or more required channels inoperable in both trip systems.

B.1 Place channel in one trip system in trip.

OR B.2 Place one trip system in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 6 hours (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-2 Amendment No. 239/232 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more Functions with RPS trip capability not maintained.

C.1 Restore RPS trip capability.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months D.

Required Action and associated Completion Time of Condition A, B, or C not met.

D.1 Enter the Condition referenced in Table 3.3.1.1-1 for the channel.

Immediately E.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

E.1 Reduce THERMAL POWER to < 38.5% RTP 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months F.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

F.1 Be in MODE 2.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-3 Amendment No. 185/180 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME G.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months H.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

H.1 Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Immediately

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-4 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS

NOTES -----------------------------------

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2

NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 25% RTP.

Verify the absolute difference between the average power range monitor (APRM) channels and the calculated power is 2% RTP.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.3 Adjust the channel to conform to a calibrated flow signal.

In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-5 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.4

NOTE-------------------

Not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform a functional test of each RPS automatic scram contactor.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap.

Prior to fully withdrawing SRMs SR 3.3.1.1.7

NOTE-------------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-6 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.9 Calibrate the local power range monitors.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 Deleted.

SR 3.3.1.1.11 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.12 Calibrate the trip units.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 Verify Turbine Stop ValveClosure and Turbine Control Valve Fast Closure, Trip Oil PressureLow Functions are not bypassed when THERMAL POWER is 38.5% RTP.

In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-7 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.15

NOTES------------------

1.

Neutron detectors are excluded.

2.

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering MODE 2.

3.

For Function 2.b, not required for the flow portion of the channels.

Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.16 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.17

NOTES------------------

1.

Neutron detectors are excluded.

2.

For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-8 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.18 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.19

NOTES------------------

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within limits.

In accordance with the Surveillance Frequency Control Program

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-9 Amendment No. 237/230 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.

Intermediate Range Monitors a.

Neutron FluxHigh 2

3 G

SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.17 SR 3.3.1.1.18 121/125 divisions of full scale 5(a) 3 H

SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.17 SR 3.3.1.1.18 121/125 divisions of full scale b.

Inop 2

5(a) 3 3

G H

SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.18 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.18 NA NA 2.

Average Power Range Monitors a.

Neutron FluxHigh, Setdown 2

2 G

SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.18 17.1% RTP b.

Flow Biased Neutron FluxHigh 1

2 F

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 0.56 W 67.4% RTP and 122% RTP(b)

(continued)

(a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.56 W + 63.2% and 118.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-10 Amendment No. 239/232 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2.

Average Power Range Monitors (continued) c.

Fixed Neutron Flux-High 1

2 F

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.18 SR 3.3.1.1.19 122% RTP d.

Inop 1,2 2

G SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.18 NA 3.

Reactor Vessel Steam Dome PressureHigh 1,2 2

G SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 1045 psig 4.

Reactor Vessel Water LevelLow 1,2 2

G SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 2.65 inches 5.

Main Steam Isolation ValveClosure 1

8 F

SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 9.5% closed 6.

Drywell PressureHigh 1,2 2

G SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.18 SR 3.3.1.1.19 1.94 psig (continued)

RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-11 Amendment No. 239/232 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 7.

Scram Discharge Volume Water LevelHigh a.

Thermal Switch (Unit 2)

Level Indicating Switch (Unit 3) 1,2 2

G SR 3.3.1.1.1(c)

SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12(c)

SR 3.3.1.1.17 SR 3.3.1.1.18 37.9 gallons (Unit 2) 38.7 gallons (Unit 3) 5(a) 2 H

SR 3.3.1.1.1(c)

SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12(c)

SR 3.3.1.1.17 SR 3.3.1.1.18 37.9 gallons (Unit 2) 38.7 gallons (Unit 3) b.

Differential Pressure Switch 1,2 2

G SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 37.9 gallons (Unit 2) 38.7 gallons (Unit 3) 5(a) 2 H

SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 37.9 gallons (Unit 2) 38.7 gallons (Unit 3) 8.

Turbine Stop Valve-Closure 38.5% RTP 4

E SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 9.5% closed 9.

Turbine Control Valve Fast Closure, Trip Oil PressureLow 38.5% RTP 2

E SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 466 psig 10.

Turbine Condenser VacuumLow 1

2 F

SR 3.3.1.1.5 SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.18 SR 3.3.1.1.19 20.5 inches Hg vacuum 11.

Reactor Mode Switch Shutdown Position 1,2 1

G SR 3.3.1.1.16 SR 3.3.1.1.18 NA 5(a) 1 H

SR 3.3.1.1.16 SR 3.3.1.1.18 NA 12.

Manual Scram 1,2 1

G SR 3.3.1.1.8 SR 3.3.1.1.18 NA 5(a) 1 H

SR 3.3.1.1.8 SR 3.3.1.1.18 NA (a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(c)

Specified SR performance only required for Unit 3.

TRM Fire Water Supply System 3.7.i Dresden 2 and 3 3.7.i-1 Revision 0 3.7 PLANT SYSTEMS 3.7.i Fire Water Supply System TLCO 3.7.i The Fire Water Supply System shall be OPERABLE with:

1.

A flow path for the Unit 2/3 fire pump capable of taking suction from the Unit 2/3 intake canal and aligned to discharge to the fire water supply header;

2.

A flow path to the Unit 1 fire pump capable of taking suction from the Unit 1 intake canal and aligned to discharge to the fire water supply header;

3.

Automatic initiation logic for each fire pump;

4.

Fire water supply header piping with sectional control valves to the yard loop, the front valve ahead of the water flow alarm device on each sprinkler or water spray system, and the standpipe system.

APPLICABILITY:

At all times.

ACTIONS

NOTE------------------------------------------

Separate Condition entry is allowed for each fire pump.

CONDITION REQUIRED ACTION COMPLETION TIME A. One fire pump or water supply inoperable.

A.1 Restore equipment to OPERABLE status.

OR A.2 Prepare a corrective action program report.

7 days 7 days

TRM Fire Water Supply System 3.7.i Dresden 2 and 3 3.7.i-2 Revision 46 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Two fire pumps or water supplies inoperable.

B.1 Establish a backup water supply.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Required Action B.1 and associated Completion Time not met.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.i.1 Verify the electrolyte level of each battery for each diesel driven fire pump is above the plates.

31 days TSR 3.7.i.2 Verify the overall battery voltage for each diesel driven fire pump is > 24 volts.

31 days TSR 3.7.i.3 Verify the unit 1 diesel driven fire pump fuel storage day tank contains > 150 gallons of fuel and the unit 2/3 diesel driven fire pump fuel storage day tank contains > 208 gallons of fuel.

31 days (continued)

TRM Fire Water Supply System 3.7.i Dresden 2 and 3 3.7.i-3 Revision 0 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.i.4 Start each fire pump from ambient conditions and operate each fire pump on recirculation flow for

> 30 minutes.

31 days TSR 3.7.i.5 Verify a sample of fuel from the diesel driven fire pump fuel storage tank, obtained in accordance with ASTM-D4057-95, is within the acceptable limits specified in Table 1 of ASTM-D975-98b with respect to viscosity, water content, and sediment.

92 days TSR 3.7.i.6

NOTE------------------------

Not applicable for nickel cadmium batteries.

Verify the specific gravity of each battery for the diesel driven fire pump is appropriate for continued service of the battery.

92 days TSR 3.7.i.7 Verify that each valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

184 days TSR 3.7.i.8 Perform a system flush.

12 months TSR 3.7.i.9 Verify the battery and battery racks for each diesel driven fire pump show no visual indication of physical damage or abnormal deterioration.

18 months (continued)

TRM Fire Water Supply System 3.7.i Dresden 2 and 3 3.7.i-4 Revision 52 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.i.10 Verify the battery-to-battery and terminal connections for each diesel driven fire pump are clean, tight, free of corrosion and coated with anti-corrosion material.

18 months TSR 3.7.i.11 Perform a system functional test, which includes simulated automatic actuation of the system throughout its operating sequence and:

a.

Verify that each automatic valve in the flow path actuates to its correct position;

b.

Verify that the Unit 2/3 fire pump develops

> 3000 gpm at a system pressure > 126 psig; and

c.

Verify that the Unit 1 fire pump develops

> 2500 gpm at a system pressure > 136 psig.

18 months TSR 3.7.i.12 Perform a system functional test in accordance with NFPA 20-1976.

18 months TSR 3.7.i.13 Cycle each testable valve in the flow path through one complete cycle.

18 months (continued)

TRM Fire Water Supply System 3.7.i Dresden 2 and 3 3.7.i-5 Revision 0 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.i.14 Perform a flow test of the system in accordance with the "Tests of Water Supplies" chapter of the Fire Protection Handbook published by the National Fire Protection Association.

36 months TSR 3.7.i.15 Inspect the diesel of each diesel driven fire pump in accordance with procedures prepared in conjunction with the manufacturer recommendations for the class of service.

72 months

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-1 Revision 0 3.7 PLANT SYSTEMS 3.7.j Water Suppression Systems TLCO 3.7.j The Water Suppression Systems shown in Table T3.7.j-1 shall be OPERABLE.

APPLICABILITY:

Whenever equipment protected by the suppression systems is required to be OPERABLE.

ACTIONS

NOTE------------------------------------------

Separate Condition entry is allowed for each Water Suppression System.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Water Suppression Systems inoperable.

A.1 -------NOTE---------

1. Not applicable for Unit 2/3 mezzanine 534 ft elevation area and hydrogen seal oil areas.

2. Not applicable for inaccessible areas.

3. Not applicable for areas with OPERABLE detection.

Establish an hourly fire watch patrol with backup fire suppression equipment.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-2 Revision 70 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

NOTE----------

1. Not applicable for Unit 2/3 mezzanine 534 ft elevation area and hydrogen seal oil areas.

2. Not applicable for inaccessible areas.

3. Applicable for areas with OPERABLE detection.

Establish a once per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months fire watch patrol with backup fire suppression equipment.

AND A.3

NOTE----------

1. Not applicable for Unit 2/3 mezzanine 534 ft elevation area and hydrogen seal oil areas.

2. Not applicable for accessible areas.

Establish a once per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months fire watch patrol with backup fire suppression equipment.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-3 Revision 70 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4

NOTE----------

Applicable for Unit 2/3 mezzanine 534 ft elevation area and hydrogen seal oil areas.

Establish a continuous fire watch with backup fire suppression equipment.

AND A.5.1 Restore the system to OPERABLE status.

OR A.5.2 Prepare a corrective action program report.

OR A.6

NOTE-------

Only Applicable following completion and implementation of approved technical evaluation.

Enter 3.0.g 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 14 days 14 days Immediately

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-4 Revision 0 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.j.1 Verify each manual, power operated, or automatic valve in the flow path is in the correct position.

184 days TSR 3.7.j.2 Cycle each testable valve in the flow path through one complete cycle of full travel.

12 months TSR 3.7.j.3 Perform a system functional test, which includes simulated automatic actuation of the system, and verify that automatic valves in the flow path actuate to their correct positions.

18 months (continued)

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-5 Revision 0 SURVEILLANCE FREQUENCY TSR 3.7.j.4

NOTES-----------------------

Not required to be performed for sprinkler piping inaccessible during plant operations.

Perform visual inspection of the sprinkler piping to verify its integrity.

18 months TSR 3.7.j.5

NOTES-----------------------

Not required to be performed for nozzles inaccessible during plant operations.

Perform visual inspection of each nozzles spray area to verify that the spray pattern is not obstructed.

18 months TSR 3.7.j.6

NOTES-----------------------

Only required to be performed for sprinkler piping inaccessible during plant operations.

Perform visual inspection of the sprinkler piping to verify its integrity.

24 months TSR 3.7.j.7

NOTES-----------------------

Only required to be performed for nozzles inaccessible during plant operations.

Perform visual inspection of each nozzles spray area to verify that the spray pattern is not obstructed.

24 months (continued)

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-6 Revision 57 SURVEILLANCE FREQUENCY TSR 3.7.j.8 Perform a flow test through each open head spray nozzle to verify the discharge pattern of the nozzles and that each open head spray nozzle is properly aimed.

36 months

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-7 Revision 60 Table T3.7.j-1 (page 1 of 2)

Water Suppression Systems I. Preaction sprinkler system 1.

Unit 2 HPCI Room Preaction System.

2.

Unit 3 HPCI Room Preaction System.

3.

Instrument Air Compressor 2-4706 Preaction System.

4.

Unit 2 Hatchways and Stairways El. 570' - 0" and 589' - 0" Cols 43, 44 42 N to M Preaction System.

5.

Unit 3 Around Hatchways el. 570' - 0" and 589' - 0" Cols 45, 46 - N M Preaction System.

6.

Mezz. Floor Cable Concentration Area Col. Row 33 to 38 G to H Preaction In-Tray Sprinkler System.

II. Wet pipe sprinkler systems 1.

Unit 2/3 Diesel Generator Day Tank Wet Pipe Sprinkler System 2.

Unit 2 ACAD Air Compressor Wet Pipe Sprinkler System 3.

Unit 3 ACAD Air Compressor Wet Pipe Sprinkler System 4.

Unit 2 Condensate Pump Room Wet Pipe Sprinkler System

5.

Unit 3 Condensate Pump Room Wet Pipe Sprinkler System

6.

Unit 2 CRD and CCSW Pumps Wet Pipe Sprinkler System

7.

Unit 3 CRD and CCSW Pumps Wet Pipe Sprinkler System

8.

Clean and Dirty Oil Tank Room Wet Pipe Sprinkler System

9.

Unit 2 Below Turbine South Side Wet Pipe Sprinkler System

10.

Unit 3 Below Turbine South Side Wet Pipe Sprinkler System

11.

Unit 2 Reactor Feed Pump and Speed Increaser Wet Pipe Sprinkler System

12.

Unit 3 Reactor Feed Pump and Speed Increaser Wet Pipe Sprinkler System

13.

Unit 2 Below Turbine North Side Wet Pipe Sprinkler System

14.

Unit 3 Below Turbine North Side Wet Pipe Sprinkler System

15.

Unit 2 Trackway and area between Column 33 and 35 F and G Wet Pipe Sprinkler System

16.

Unit 3 Trackway Wet Pipe Sprinkler System

17.

Unit 2 Diesel Generator Day Tank Wet Pipe Sprinkler System

18.

Unit 3 Diesel Generator Day Tank Wet Pipe Sprinkler System

19.

Unit 2 and 3 Cable Tunnel Wet Pipe Sprinkler System 20.

Unit 2 and 3 Turbine Building Common Mezzanine Area Wet Pipe Sprinkler System

21.

Unit 2 Wet Pipe Sprinkler System at Ceiling above Stator Cooling and H2 Seal Oil

22.

Unit 3 Wet Pipe Sprinkler System at Ceiling above Stator Cooling and H2 Seal Oil

23.

Unit 2 MG Set 2A-251 and 2B-251 Fluid Drive Wet Pipe Sprinkler System

24.

Unit 3 MG Set 3A-251 and 3B-251 Fluid Drive Wet Pipe Sprinkler System

25.

Unit 2 Turbine Bearing Lift Pump (Col-36) Wet Pipe Sprinkler System

26.

Unit 2 Turbine Bearing Lift Pump (Col-41) Wet Pipe Sprinkler System

27.

Unit 3 Turbine Bearing Lift Pump (Col-47) Wet Pipe Sprinkler System

28.

Unit 3 Turbine Bearing Lift Pump (Col-53) Wet Pipe Sprinkler System

29.

Unit 2 and 3 Turbine Building Common Area Corridor Elev. 517-6 Wet Pipe Sprinkler System 30.

Unit 2/3 Cribhouse Lower Level Wet Pipe Sprinkler System 31.

Unit 2/3 Cribhouse Upper East Wet Pipe Sprinkler System

32.

Unit 2/3 Cribhouse Upper West Wet Pipe Sprinkler System

33.

Unit 2 Mechanical Opening Outside of Safe Shutdown Heat Exchanger Room Wet Pipe Sprinkler System 34.

Unit 3 Mechanical Opening Outside of Safe Shutdown Heat Exchanger Room Wet Pipe Sprinkler System 35.

Unit 2 Ladderway 587-0, Col. 38 M, Wet Pipe Sprinkler System 36.

Unit 3 Ladderway 587-0, Col. 50 M, Wet Pipe Sprinkler System 37.

Unit 1 Diesel Fire Pump Wet Pipe Sprinkler System

38.

Unit 2 Oil Storage Area Wet Pipe Sprinkler System

39.

Unit 1 West Aux Bay South Wet Pipe Sprinkler System

40.

Unit 1 West Aux Bay North Wet Pipe Sprinkler System

41.

E.H.C. Units 2-5614 and 3-5614 Wet Pipe Sprinkler System (continued)

These Wet Pipe Sprinkler Systems do not have fire detection systems in the same area.

TRM Water Suppression Systems 3.7.j Dresden 2 and 3 3.7.j-8 Revision 52 Table T3.7.j-1 (page 2 of 2)

Water Suppression Systems III. Water spray (open head) systems 1.

Unit 2 Turbine Oil Reservoir Deluge System.

2.

Unit 3 Turbine Oil Reservoir Deluge System.

3.

Unit 2 Hydrogen Seal Unit Deluge System.

4.

Unit 3 Hydrogen Seal Unit Deluge System.

5.

Diesel Fire Pump and Day Tank Deluge System.

6.

Main Power Transformer #2 Deluge System.

7.

Main Power Transformer #3 Deluge System.

8.

Auxiliary Transformer #21 Deluge System.

9.

Auxiliary Transformer #31 Deluge System.

10.

Reserve Auxiliary Transformer #22 Deluge System.

11.

Reserve Auxiliary Transformer #32 Deluge System.

12.

Unit 2 Bus Duct Penetration Deluge System.

13.

Unit 3 Bus Duct Penetration Deluge System.

14.

Cribhouse Cable Tray Open Head Water Spray System.

15.

2/3 D.G. Cooling Water Pump Deluge System.

RP-AA-203 Revision 3 Page 1 of 12 Level 3 - Information Use EXPOSURE CONTROL AND AUTHORIZATION

1.

PURPOSE 1.1.

This procedure describes the program by which the Radiation Protection Department evaluates and controls personnel occupational exposure.

2.

TERMS AND DEFINITIONS 2.1.

Absent/ No record (A): Dose type used for monitoring periods entered under 10CFR20 for which hard copy dose documentation of dose data from the monitoring licensee is unobtainable. The quantity associated with A dose type is always XX or intentionally left blank.

2.2.

Administrative Dose Control Level (ADCL): An Exelon established dose guideline established to prevent personnel form exceeding the Federal dose limits and to help ensure equitable distribution of dose among workers with similar jobs.

2.3.

Emergency Exposure: Exposure received during lifesaving, protection of valuable property, protection of large populations, or any immediate action taken in response to a situation or occurrence of a serious nature developing suddenly and unexpectedly.

2.4.

High Lifetime Exposure: The cumulative TEDE (routine plus any PSE) in rem that is equal to or exceeds an individuals age in years.

2.5.

Lens Dose Equivalent (LDE): The external exposure of the lens of the eye and is taken at the dose equivalent at a tissue depth of 300 mg/cm2.

2.6.

Planned Special Exposure (PSE): An infrequent exposure to radiation, separate from and in addition to the annual exposure limits (Refer to Table 1).

2.7.

Shallow Dose Equivalent (SDE): The external exposure of the skin or an extremity taken at a tissue depth of 7 mg/cm2.

2.8.

Total Effective Dose Equivalent (TEDE): The sum of the deep dose equivalent (external exposure) and the committed effective dose equivalent (internal exposure).

2.9.

Total Organ Dose Equivalent (TODE): The sum of the deep dose equivalent and the committed dose equivalent to the organ receiving the highest dose.

3.

RESPONSIBILITIES

RP-AA-203 Revision 3 Page 2 of 12 3.1.

Responsibility for approval of exposures in excess of administrative dose control levels resides with the Radiation Protection Manager (RPM), the Station/Plant Manager, and the Site Vice President.

4.

MAIN BODY 4.1.

Limitations 4.1.1.

Exposures shall not exceed the 10CFR20 Exposure Limits as described in Table 1, NRC Exposure Limits.

TABLE 1 - NRC EXPOSURE LIMITS Individual and Limit Type TEDE LDE SDE TODE (1) Occupational Worker, Minor, Routine Annual 0.5 rem 1.5 rem 5 rem 5 rem (2) Occupational Worker, Adult, Routine Annual 5 rem 15 rem 50 rem 50 rem (3) Occupational Worker, Adult, PSE Annual 5 rem 15 rem 50 rem 50 rem (4) Occupational Worker, Adult, PSE Lifetime 25 rem 75 rem 250 rem 250 rem (5) Declared Pregnant Woman Dose equivalent to the embryo/fetus of 500 mrem, or 50 additional mrem if the dose equivalent to the embryo/fetus exceeds 450 mrem at the time the female declares, in writing, her pregnancy. (Note: The dose equivalent to the embryo/fetus equals the DDE to the declared pregnant woman plus the dose equivalent to the embryo/fetus from radionuclides in the embryo/fetus plus the dose equivalent to the embryo/fetus from radionuclides in the declared pregnant woman.)

(6) Member of The Public The total effective dose equivalent to individual members of the public shall not exceed 100 mrem in a year.

RP-AA-203 Revision 3 Page 3 of 12 NOTE:

Any request to raise the administrative dose control level for a minor shall be approved and documented by the Radiation Protection Manager.

4.1.2.

Administrative dose control levels have been established for Total Effective Dose Equivalent Limits as follows:

2000 mrem routine cumulative TEDE/yr.

200 mrem TEDE for minors.

NOTE: In the Midwest Regional Operating Group, controls for High Lifetime Exposure are not applicable for non-Exelon employees due to the limitations of the Exposure Tracking System.

4.1.3.

An administrative dose control level of 1000 mrem TEDE plus PSE has been established for employees with High Lifetime Exposure.

4.1.4.

The Radiation Protection Manger shall review an individuals occupational exposure when the dose equivalent reaches 80% of the NRC Limits for Lens Dose Equivalent (LDE), Shallow Dose Equivalent (SDE), and Total Organ Dose Equivalent (TODE).

The 80% threshold values are as follows:

12 rem LDE.

40 rem SDE.

40 rem TODE.

4.1.5.

If an individual's current year dose history documentation includes an absent/ no record (A) dose type, then REDUCE the individuals allowable exposure (normally 2000 mrem TEDE for the year) by 1250 mrem TEDE for each quarter of the current year for which dose history documentation is absent/ no record (A), until all of that dose is resolved.

4.1.6.

If an individual is suspected of exceeding any of the NRC exposure limits in Table 1, then PROHIBIT the individual from entering the RCA until a detailed evaluation of the individual's actual dose equivalent has been conducted. Future access will depend upon the results of the evaluation.

1.

If an exposure in excess of the applicable exposure limit has occurred, then PROHIBIT the individual from entering the RCA until the end of the current calendar year.

2.

If an exposure in excess of the applicable exposure limit has not occurred, then the individual may be permitted to re-enter the RCA.

RP-AA-203 Revision 3 Page 4 of 12 4.1.7.

During a condition where the Generating Stations Emergency Plan has been initiated, emergency exposure authorizations shall be performed in accordance with the stations Emergency Plan Implementing Procedures.

4.2.

Authorization To Raise Administrative Dose Control Levels (ADCLs) 4.2.1.

USE Attachment 1, Dose Control Level Extension Form, or a computerized equivalent, to authorize exposures for adult individuals in excess of 2000 mrem routine TEDE in a year.

4.2.2.

A supervisor from the department requesting approval shall complete Section I of and submit the request to the Radiation Protection Department indicating:

The name, identification number, and signature of the individual for whom a dose extension is being requested.

Whether or not other qualified individuals with lower dose are available to perform the work.

A detailed explanation of why the dose extension is necessary.

The requested annual TEDE limit for the individual (expressed in 500 mrem increments, i.e. 2500 mrem, 3000 mrem, etc.)

4.2.3.

The Radiation Protection Department shall complete Section II Attachment 1 or computerized equivalent.

4.2.4.

Pending investigations or calculations of internal exposure shall be reviewed and evaluated to determine the individuals TEDE.

4.2.5.

Non-Exelon Nuclear and non-ROG dose equivalent shall be included in the dose to determine the workers current TEDE.

NOTE:

An individual shall not be approved to receive greater than 2000 mrem TEDE if that person has any absent/ no record (A) dose equivalent for the year.

4.2.6.

To raise the ADCL up to and including 3000 mrem TEDE in a calendar year, written approval is required by the Radiation Protection Manager and the work group supervisor.

4.2.7.

To raise the ADCL to between 3001 and 4000 mrem TEDE in a calendar year, written approval is required by the Radiation Protection Manger, a work group supervisor, and the Station/Plant Manager.

NOTE:

An individual being considered for approval greater than 4000 mrem TEDE for the year should not have significant estimated dose equivalent.

4.2.8.

To raise the ADCL above 4000 mrem, not to exceed 5000 mrem, written approval is required by the Site Vice President.

RP-AA-203 Revision 3 Page 5 of 12 4.3.

Authorizations For High Lifetime Exposure 4.3.1.

USE Attachment 2, High Lifetime Dose Control Level Extension Form, or a computerized equivalent, to authorize exposures above 1000 mrem for employees with High Lifetime Exposure.

4.3.2.

A supervisor from the department requesting approval shall submit a request to the Radiation Protection Department indicating:

The name and identification number of the individual for whom a dose extension is being requested.

A detailed explanation of why the dose extension is necessary.

The requested annual TEDE for the individual.

4.3.3.

The Radiation Protection Department shall complete Section II of Attachment 2 or a computerized equivalent.

4.3.4.

Written approval is required as follows for any employee who is categorized as having High Lifetime Exposure:

Individuals supervisor and RPM for end of year dose equivalent exceeding 1000 mrem TEDE, not to exceed 2000 mrem TEDE.

Individuals supervisor, RPM, Plant Manager, and Site Vice President for end of year dose equivalent exceeding 2000 mrem TEDE.

4.4.

Planned Special Exposures (PSEs)

NOTE:

PSEs are not the same as emergency doses. PSEs only apply to adult workers.

4.4.1.

PSEs are to be authorized only in exceptional situations when alternatives that might avoid the dose estimated to result from the PSE are not available or are deemed impractical.

4.4.2.

A manager from the department requesting a PSE shall submit a request to the Radiation Protection Department, indicating:

The name and identification number of each individual for whom a PSE is being requested, and The nature of the task for which a PSE is being requested, and A detailed explanation of why the PSE is necessary.

4.4.3.

Prior written approval is required before the PSE occurs.

RP-AA-203 Revision 3 Page 6 of 12 4.4.4.

Prior to participating in a PSE, individuals involved shall be:

1.

Informed of the purpose of the PSE.

2.

Informed of the estimated dose and associated potential risk or conditions involved in performing the PSE.

3.

Instructed in dose reduction measures and techniques for the PSE.

4.4.5.

PSE approval is granted when the PSE document is signed (by hand) and dated by:

The individual(s) for whom a PSE is being requested, and The work group manager or other level of supervisory authority for the individual as chosen by the RPM or designee, and The RPM or designee, and The Plant Manager, and The Site Vice President.

NOTE:

If there are any periods of exposure during the life of the monitoring individual that have not been determined or documented (i.e., Absent/ No record), then participation in a PSE is not permitted.

4.4.6.

All of the individual's previous PSE dose equivalents and previous doses in excess of routine occupational limits must be determined from records for each individual who will participate in the PSE. Doses received in excess of the routine occupational dose limits in effect at the time of exposures during accidents and emergencies must also be determined and subtracted from the limits for PSEs.

4.4.7.

DOCUMENT each individual's current year and previous years:

PSE dose equivalents, and Dose equivalents in excess of the exposure limits in effect at the time of the exposures (rows (1) and (2) of Table 1, NRC Exposure Limits, and the former 10 CFR 20.101), and Dose equivalents in excess of any non-NRC exposure limits.

4.4.8.

The maximum authorized dose equivalent an individual may receive for a PSE shall be limited to an amount that does not cause the individual to receive a dose equivalent in excess of the limits listed in rows (3) and (4) in Table 1.

4.4.9.

DOCUMENT the Planned Special Exposure on Attachment 3, Planned Special Exposure PSE Approval Form, and MAINTAIN all records in accordance with 10CFR20.1205.

4.4.10.

SUBMIT a written report to the Administrator of appropriate regional office within 30 days following the PSE in accordance with 10CFR20.1206.

RP-AA-203 Revision 3 Page 7 of 12 4.4.11.

SUBMIT a written report of the PSE assigned dose to the individuals involved within 30 days of the PSE.

4.4.12.

The dose equivalent received from a PSE is always tracked separately from routine occupational exposure.

4.4.13.

Once an exposure is authorized as a PSE, it cannot later be treated as a routine occupational exposure. It must be recorded as a PSE, and all the unique limitations, reporting, and record keeping requirements for PSEs shall apply.

4.5.

Emergency Exposure Limits (CM-1) 4.5.1.

Emergency exposure in excess of 25 rem TEDE is to be limited to once in a lifetime.

4.5.2.

Emergency personnel are to be informed before the fact of possible health effects at the anticipated exposure levels.

4.5.3.

For the control of personnel exposures under emergency conditions, LIMIT an individual's dose equivalent per activity as follows:

TABLE 2 - EMERGENCY EXPOSURE LIMITS (REM)

TEDE LDE SDE TODE ACTIVITY 10 30 100 100 Protecting Valuable Property 25 75 250 250 Lifesaving or Protection of Large Populations

> 25

> 75

>250

> 250 Lifesaving or Protection of Large Populations to Workers Fully Aware of the Risks Involved 4.5.4.

Emergency exposures shall be voluntary on the part of the involved individual.

4.5.5.

CONSULT the Emergency Plan Implementing Procedures regarding approval to exceed NRC exposure limits.

5.

DOCUMENTATION 5.1.

RETAIN completed exposure authorizations, including Attachments 1, 2, and 3, in accordance with the station records management program. This records program will include appropriate controls for storage and preservation.

RP-AA-203 Revision 3 Page 8 of 12

6.

REFERENCES 6.1.

Commitments 6.1.1.

CM-1 LaSalle Station AIR 1-81-330 regarding provisions for exposures to individuals during an emergency (Section 4.5.).

6.2.

User References 6.2.1.

10 CFR 19.13, "Notifications and Reports to Individuals."

6.2.2.

10 CFR 20, "Standards for Protection against Radiation."

6.2.3.

USNRC Regulatory Guide 8.7, "Instructions for Recording and Reporting Occupational Radiation Exposure Data, Revision 1, July 1992.

6.2.4.

USNRC Regulatory Guide 8.35, "Planned Special Exposures," July 1992.

6.2.5.

EPA-400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents."

7.

ATTACHMENTS 7.1., Dose Control Level Extension Form.

7.2., High Lifetime Dose Control Level Extension Form.

7.3., Planned Special Exposure (PSE) Approval Form.

RP-AA-203 Revision 3 Page 9 of 12 ATTACHMENT 1 Dose Control Level Extension Form Page 1 of 1 Section I: Reason For Extension NAME: ____________________________

SSN: ___________________________

INDIVIDUAL SIGNATURE: _________________________

1.

Are other qualified individuals with a lower current year routine TEDE available to perform this work?

Yes___ No___ N/A ___

Remarks___________________________________________________________________

2.

State why an extension above 2000 mrem routine TEDE for the year is necessary for this individual.

3.

It is requested that the individual named above be permitted to receive a TEDE for the current year of

_____________mrem.

Requestor ____________________________

Date ___/___/___

Section II: Dose Summary CURRENT YEAR ROUTINE RECORD TEDE (mrem): _____________

CURRENT YEAR ROUTINE ESTIMATED TEDE (mrem)*: _____________

CURRENT YEAR ROUTINE TOTAL TEDE (mrem): ______________

LIFETIME DOSE (mrem): ______________

Verified By:

Date: ____________

Section III: Approvals**

The individual named above is approved to exceed 2000 mrem but must remain below 5000 mrem routine TEDE for the current year.

Specific Approval Level in mrem TEDE: ______________

1. Work Group Supervisor _________________________

Date ___/___/___

2. RP Manager __________________________________

Date ___/___/___

3. Station Manager _______________________________

Date ___/___/___

4. Site Vice President _____________________________

Date ___/___/___

An individual being considered for approval greater than 4000 mrem TEDE for the year should not have significant estimated dose equivalent from a non-ROG facility. Additionally, an individual shall not be approved for greater than 2000 mrem TEDE if that person has any absent/ no record dose equivalent for the year.

To raise the ADCL up to and including 3000 mrem, signatures 1 & 2 are required. To raise the ADCL to between 3001 and 4000 mrem, signatures 1,2, & 3 are required. To raise the ADCL above 4000 mrem, signatures 1,2,3, & 4 are required.

RP-AA-203 Revision 3 Page 10 of 12 ATTACHMENT 2 High Lifetime Dose Control Level Extension Form Page 1 of 1 Section I NAME: ____________________________ AGE: _______ SSN: _______________________

INDIVIDUAL SIGNATURE: _________________________

1.

State why an extension in excess of the administrative dose control level listed below is necessary for this individual.

2. It is requested that the individual named above be permitted to receive a TEDE for the current year of

_____________mrem.

Requestor ____________________________

Date ___/___/___

Section II: Dose Summary CURRENT YEAR ROUTINE RECORD TEDE (mrem): _____________

CURRENT YEAR ROUTINE ESTIMATED TEDE (mrem):

CURRENT YEAR ROUTINE TOTAL TEDE (mrem): _____________

LIFETIME DOSE (mrem): ______________

Verified By:

Date: ____________

Section III: Approvals The individual named above is approved to exceed 1000 mrem TEDE.

Specific Approval Level in mrem TEDE: ______________

1. Work Group Supervisor _________________________

Date ___/___/___

2. RP Manager __________________________________ Date ___/___/___

3. Station Manager _______________________________ Date ___/___/___

4. Site Vice President _____________________________ Date ___/___/___

To raise the ADCL to 2000 mrem, signatures 1 & 2 are required.

- To raise the ADCL above 2000 mrem, signatures 1,2,3 & 4 are required. If approval is being made to exceed 2000 mrem TEDE, this form should be used in conjunction with Attachment 1. Exceptional circumstances should exist to allow individuals with high lifetime dose to exceed 2000 mrem TEDE in a year.

- - High lifetime exposure controls do not apply to Non-Exelon employees in Midwest due to the limitations of the Exposure Tracking System.

RP-AA-203 Revision 3 Page 11 of 12 ATTACHMENT 3 Planned Special Exposure (PSE) Approval Form Page 1 of 2 Employee Name: ___________________

SSN: _________________

Requested By: _______________________

Date: _________________

Exceptional Circumstances for Scope of Activity:

Actions Necessary:

Justification Why Actions Are Necessary:

Estimated Individual Exposure: _________

Actual Individual Exposure: ___________

Estimated Collective Exposure: _________

Actual Collective Exposure: ___________

Techniques used to maintain exposure ALARA:

Annual Dose (mrem)

Life Time Dose (mrem)

Previous PSE Dose Life Time Annual (mrem) (mrem)

Dose in excess of limits (mrem)

Proposed PSE Dose (mrem)

Proposed Annual Dose (mrem)

TEDE LDE SDE-ME SDE-WB TODE

RP-AA-203 Revision 3 Page 12 of 12 ATTACHMENT 3 Planned Special Exposure (PSE) Approval Form Page 2 of 2 STATEMENT OF UNDERSTANDING:

I have been informed of the purpose of the planned operation, the estimated doses, and the potential risks or other conditions that may be involved in performing this task. I have been given the opportunity to ask questions and understand the operation and the Planned Special Exposure estimate.

Employee Signature: _________________________________

Date: _______________

Employee Name: _________________________________

SSN: _______________

APPROVALS:

Work Group Manager: _____________________________

Date: _______________

Radiation Protection Manager: _______________________

Date: _______________

Plant Manger: ____________________________________

Date: _______________

Site Vice President: _______________________________

Date: _______________

Secondary Containment Isolation Instrumentation 3.3.6.2 Dresden 2 and 3 3.3.6.2-1 Amendment No. 185/180 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.2-1.

ACTIONS

NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels inoperable.

A.1 Place channel in trip.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Functions 1 and 2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 1 and 2 B.

One or more Functions with isolation capability not maintained.

B.1 Restore isolation capability.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

Secondary Containment Isolation Instrumentation 3.3.6.2 Dresden 2 and 3 3.3.6.2-2 Amendment No. 185/180 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and associated Completion Time not met.

C.1.1 Isolate the associated penetration flow path.

OR C.1.2 Declare associated secondary containment isolation valves inoperable.

AND C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation.

OR C.2.2 Declare associated SGT subsystem inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour

Secondary Containment Isolation Instrumentation 3.3.6.2 Dresden 2 and 3 3.3.6.2-3 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS

NOTES -----------------------------------

1.

Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.3 Calibrate the trip unit.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program (continued)

Secondary Containment Isolation Instrumentation 3.3.6.2 Dresden 2 and 3 3.3.6.2-4 Amendment No. 237/230 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program

Secondary Containment Isolation Instrumentation 3.3.6.2 Dresden 2 and 3 3.3.6.2-5 Amendment No. 237/230 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.

Reactor Vessel Water LevelLow 1,2,3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6 2.65 inches 2.

DrywellPressureHigh 1,2,3 2

SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 1.94 psig 3.

Reactor Building Exhaust RadiationHigh 1,2,3, (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 14.9 mR/hr 4.

Refueling Floor RadiationHigh 1,2,3, (a),(b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a)

During operations with a potential for draining the reactor vessel.

(b)

During movement of recently irradiated fuel assemblies in secondary containment.

Dresden Annex Exelon Nuclear June 2013 DR 4-4 EP-AA-1004 (Revision 33)

Figure 4-1:

Dresden Station PAR Determination Flowchart Evaluate Dose Assessment results to determine if a PAR upgrade is required.

Classification is a General Emergency?

No PARs Required Evacuate 2-Mile Radius & 5-Miles Downwind No Release via Controlled direct containment vent with a duration < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ?

Dose Projection < 1 Rem TEDE AND < 5 Rem CDE (thyroid)

No Yes Yes Is this the Initial PAR?

Evaluate Dose Assessment results to determine if a PAR upgrade is required Yes Yes Yes No No No Shelter 2-Mile Radius & 5-Miles Downwind.

Has the utility been informed by the State that there are impediments to evacuation?

Is there a Hostile Action Event in progress?

Yes No 2 Mile Radius, 5 Miles Downwind WD (from)

Subareas 002º to 046º 1, 3. 4, 7 047º to 182º 1, 3. 4 183º to 292º 1, 3, 4, 12 293º to 299º 1, 3, 4 300º to 338º 1, 3, 4, 9 339º to 001º 1, 3, 4, 7, 9

ENTRY CONDITIONS Drywell pressure above 2.0 psig Drywell temperature above 160°F (Use TR 2(3)-1340-1 Points 5 and 6)

Torus bulk temperature above 95°F Torus water level below -4.5 in.

OR above -1.5 in.

Drywell or torus hydrogen above 3.5%

PRIMARY CONTAINMENT PRESSURE IF THEN Cannot hold pressure below 2.0 psig Go to t.

BEFORE Drywell pressure reaches 9 psig

£ CAUTION: Exceeding LPCI NPSH/Vortex Limits (Figs V-X) may cause system damage.

1. Trip all recirc pumps.

2. Trip all drywell cooling fans.

3. Start drywell sprays.

Do not use pumps needed for core cooling.

OK to use external spray sources if you can restore and hold torus bottom pressure and primary containment water level inside Fig D, Primary Containment Pressure Limit.

Reducing primary containment pressure affects margin to NPSH limits. Check Figs W-Y, NPSH Limits.

IF Torus sprays running THEN Before torus pressure drops to 0 psig, stop torus sprays.

t (Torus spray)

Drywell sprays running Before drywell pressure drops to 0 psig, stop drywell sprays.

Torus water level

?

At or above 27.5 ft Below 27.5 ft.

CAUTION: Exceeding LPCI NPSH/Vortex Limits (Figs V-X) may cause system damage.

Start torus sprays.

Do not use pumps needed for core cooling.

OK to use external spray sources.

Reducing primary containment pressure affects margin to NPSH limits. Check Figs W-Y, NPSH Limits.

WAIT until drywell pressure is above 9 psig Below Fig K, Drywell Spray Initiation Limit

?

No Yes IF THEN Keep trying to lower drywell and torus pressures below 9 psig.

Cannot stay inside Fig L, Pressure Suppression Pressure Go to y.

BEFORE Torus bottom pressure reaches Fig D, Primary Containment Pressure Limit (Vent)

Vent to stay below Fig D, Primary Containment Pressure Limit (DEOP 500-4).

OK to exceed release rate limits.

y DRYWELL TEMPERATURE IF THEN Hold drywell temperature below 160°F using drywell cooling.

Drywell temperature affects RPV water level indication.

Check Detail A.

Cannot hold drywell temperature below 160°F Go to i.

BEFORE Drywell temperature reaches 281°F

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here

3. BLOW DOWN:

Enter DEOP 400-2 while continuing here i

£

£ (Drywell spray)

TORUS TEMPERATURE IF THEN Hold torus bulk temperature below 95°F using torus cooling.

Cannot hold torus bulk temperature below 95°F Go to o.

Start all available torus cooling

Do not use pumps needed for core cooling.

BEFORE Torus bulk temperature reaches 110°F IF THEN Cannot hold torus bulk temperature below Fig M, Heat Capacity Limit o

(Scram, Enter DEOP 100)

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here.

£ Hold torus bulk temperature below Fig M, Heat Capacity Limit.

1. IF.........

THEN..

you are not in RPV Flooding (DEOP 400-1) or Steam Cooling (DEOP 400-3),

lower RPV pressure to stay below Fig M, Heat Capacity Limit.

OK to exceed 100°F/hr cooldown rate.

2. IF.........

THEN..

you still cannot stay below Fig M, Heat Capacity Limit, BLOW DOWN:

£ Enter DEOP 400-2 while continuing here.

CAUTION: Exceeding LPCI NPSH/Vortex Limits (Figs V-X) may cause system damage.

TORUS WATER LEVEL IF THEN Hold torus water level between -4.5 in. and -1.5 in. narrow range.

Sample the torus before discharging water.

Low Level: Cannot hold level above -4.5 in.

Go to s.

High Level: Cannot hold level below -1.5 in.

Go to a.

a s

High Level (Above -1.5 in.)

HYDROGEN IF THEN Monitor hydrogen and oxygen concentrations in drywell and torus (DOP 2400-1).

Hydrogen or oxygen monitor is unavailable Sample the drywell and torus for hydrogen and oxygen.

Hydrogen (at or above 1%) or oxygen (at or above 5%) is detected in the drywell or torus

£ Hold drywell and torus pressures below 2.0 psig using SBGT and drywell purge (DOP 1600-1).

BLOW DOWN:

Enter DEOP 400-2 while continuing here.

IF Drywell sprays running THEN Before drywell pressure drops to 0 psig, stop drywell sprays.

Below Fig K, Drywell Spray Initiation Limit

?

No Yes IF THEN Keep trying to lower drywell temperature below 160°F.

Drywell temperature affects RPV water level indication.

Check Detail A.

Cannot restore drywell temperature below 281°F and hold it there Low Level (Below -4.5 in.)

ENTER HYDROGEN CONTROL:

Enter DEOP 200-2 while continuing in other sections of this procedure.

Hydrogen or oxygen concentration in the drywell or torus is unknown

£ ENTER HYDROGEN CONTROL:

Enter DEOP 200-2 while continuing in other sections of this procedure.

Start all available drywell cooling

OK to defeat drywell cooling isolations (DEOP 500-2).

IF THEN Hold torus water level above 12 ft. (HPCI exhaust).

Cannot hold level above 11 ft.

(downcomers)

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here

3. BLOW DOWN:

Enter DEOP 400-2 while continuing here Trip HPCI.

Even if core cooling will be lost.

Cannot hold level above 12 ft.

(HPCI exhaust)

IF THEN Hold torus water level below 18.5 ft (ring header).

Cannot hold level below 18.5 ft (ring header)

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here

3. Stop injection from outside the primary containment not needed for core cooling or to shut down the reactor.

4. IF.........

THEN..

you cannot restore torus water level below 18.5 ft and hold it there, BLOW DOWN:

Enter DEOP 400-2 while continuing here.

£

£ DEOP 200-1 PRIMARY CONTAINMENT CONTROL Dresden Nuclear Power Station Units 2(3)

EMERGENCY OPERATING PROCEDURE PRIMARY CONTAINMENT CONTROL DEOP 200-1 Title Number 1 0 Rev CATEGORY 1 D

Primary Containment Pressure Limit 0

10 20 30 40 50 60 70 80 90 100 93 Primary Containment Water Level (ft)

Torus Bottom Pressure (psig) 70 60 50 40 30 20 10 0

£

£ 0

5000 10,000 15,000 20,000 25,000 30,000 35,000 Total ECCS Flow (gpm)

Wide Range Torus Water Level (ft) 11 10.5 10 9.5 9

V ECCS Vortex Limit CAUTION: Exceeding LPCI NPSH/Vortex Limits (Figs V-X) may cause system damage.

1. Trip all recirc pumps.

2. Trip all drywell cooling fans.

3. Start drywell sprays.

Do not use pumps needed for core cooling.

OK to use external spray sources if you can restore and hold torus bottom pressure and primary containment water level inside Fig D, Primary Containment Pressure Limit.

Reducing primary containment pressure affects margin to NPSH limits. Check Figs W-Y, NPSH Limits.

K Drywell Spray Initiation Limit Drywell Pressure (psig) 20 18 16 14 12 10 8

6 4

2 0

Drywell Temperature (°F)

TR 2(3)-1340-1 Points 5 and 6 600 500 400 300 200 100 10 11 12 13 14 15 16 17 18 19 20 Wide Range Torus Water Level (ft)

L Pressure Suppression Pressure 10.9 Torus Bottom Pressure (psig) 40 30 25 20 15 10 5

0 35 18.6 M

Heat Capacity Limit 66 psig Use only when torus level is at or below 17 ft.

See TSGs for torus levels above 17 ft.

0 100 200 300 400 500 600 700 800 900 1000 1100 RPV Pressure (psig)

Torus Bulk Temperature (°F) 230 190 180 170 160 150 140 130 200 210 220 C Minimum Usable Indicating Levels Fuel Zone

(+60" to -340")

-297

-298

-299

-300

-301 32 to 100 101 to 200 201 to 300 301 to 400 401 to 500 501 to 558 Drywell temperature (°F)

TR 2(3)-1340-1, Point 9 or 10 Medium/Narrow Range All Rx Bldg Temps

(+60" to -60")

Medium/Narrow Range Rx Bldg Temps 181°F or less

(+60" to -60")

Wide Range

(+330" to -70")

-38

-39

-41

-43

-60

-68

-51

-21 17 68 107 Drywell Temperature (°F)

TR 2(3)-1340-1, Point 9 or 10 OR Reactor Building Temperature (°F) 600 500 400 300 200 0

100 200 300 400 500 600 700 800 900 1000 1100 RPV Pressure (psig)

B RPV Saturation Temperature A

RPV Water Level Instruments CAUTION: RPV water level instruments may be unreliable due to boiling in the instrument runs when drywell or reactor building temperatures near the instrument runs are above Fig B, RPV Saturation Temperature.

An RPV water level instrument may not be used if the instrument reads at or below its Minimum Usable Level (Detail C).

W LPCI / Core Spray NPSH Limit ECCS Flow Up To 10,750 gpm 0

1000 2000 3000 4000 5000 6000 LPCI / Core Spray Pump Flow (gpm)

Torus Bulk Temperature (°F) 250 200 150 100 50 3.5 psig 5 psig 10 psig 15 psig Torus Bottom Pressure (psig)

X LPCI / Core Spray NPSH Limit ECCS Flow Up To 25,500 gpm 0

1000 2000 3000 4000 5000 6000 LPCI / Core Spray Pump Flow (gpm)

Torus Bulk Temperature (°F) 250 200 150 100 50 3.5 psig 5 psig 10 psig 15 psig Torus Bottom Pressure (psig) 0 1000 2000 3000 4000 5000 6000 7000 HPCI Flow (gpm)

Torus Bulk Temperature (°F) 250 200 150 100 50 3.5 psig 5 psig 10 psig 15 psig Torus Bottom Pressure (psig)

Y HPCI NPSH Limit

ENTRY CONDITIONS Differential Pressure at or above 0 in.

Area radiation above max normal (Detail T)

Vent radiation above 4 mr/hr Floor drain sump water level above hi-hi alarm Area temperature above max normal (Detail S)

Any of the following in the reactor building:

Corner room water level above 0 in.

CAUTION:

High temperature or low water level in the spent fuel pool can affect radiological conditions and water levels in the reactor building and adjacent areas. Reactor building access may also be restricted by steam.

IF THEN Reactor building exhaust radiation above 4 mr/hr Verify:

Reactor Building Ventilation isolation

SBGT start Reactor Building Ventilation isolates AND Reactor building exhaust radiation below 4 mr/hr Start Reactor Building Vent:

OK to defeat high drywell pressure and low RPV water level interlocks (DEOP 500-2).

TEMPERATURE / RADIATION Isolate all discharges into affected areas except systems needed for:

Fire fighting

Other DEOP actions IF THEN Primary system discharging into reactor building AND Discharge cannot be isolated Go to k Shut down the reactor.

BEFORE Any area temperature, radiation, or water level reaches max safe value (Details S, T, U)

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here.

WAIT until 2 or more areas above max safe values of same parameter (Details S, T, U)

BLOW DOWN:

Enter DEOP 400-2 while continuing here.

WATER LEVELS IF THEN Operate sump pumps to hold floor drain sump level below the hi-hi alarm setpoint and remove water from reactor building areas.

Floor drain sump level cannot be restored below the hi-hi alarm setpoint OR Water cannot be removed from an area Go to j j

Operate area coolers and Reactor Building Ventilation.

Reactor building temperature affects RPV water level indication. Check Detail A.

IF THEN Any area temperature or radiation above max normal (Details S, T)

Go to j k

(Scram, Enter DEOP 100)

WAIT until 2 or more areas above max safe values of same parameter (Details S, T, U)

ENTRY CONDITIONS Off-site release rate above GSEP Alert level (Dresden EALs)

DEOP 300-1 SECONDARY CONTAINMENT CONTROL DEOP 300-2 RADIOACTIVITY RELEASE CONTROL

Operate Turbine Building Ventilation.

Isolate all primary system discharges outside primary and secondary containments except systems needed for other DEOP actions.

IF THEN Primary system discharging outside primary and secondary containments AND Discharge cannot be isolated Before off-site release rate reaches the General Emergency level (Dresden EALs):

1. Scram.

2. ENTER RPV CONTROL:

Enter DEOP 100 while continuing here.

3. BLOW DOWN:

Enter DEOP 400-2 while continuing here.

Dresden Nuclear Power Station Units 2(3)

EMERGENCY OPERATING PROCEDURE Radioactivity Release Control DEOP 300-2 Title Number Rev CATEGORY 1 0 2 HPCI Room Shutdown Cooling Pump Room Shutdown Cooling Ht X Room Clean Up Demin Room Clean Up Pump & Ht X Area Isolation Condenser Area Area Max Normal Temperature (°F) 150 150 150 150 150 150 210 180 180 210 210 180 Max Safe Temperature (°F)

S Reactor Building Area Temperatures HPCI Cubicle, Unit 2(3)

East LPCI Pump Area West LPCI Pump Area East CRD Module Area West CRD Module Area Vessel Instrument Rack Area Area Max Normal Radiation (mr/hr) 150 (100) 12 9

30 50 30 2500 2500

2500

2500

2500

2500

Max Safe Radiation (mr/hr)

Clean Up System Area 30 2500

Isolation Condenser Area, Unit 2(3) 10 (2500 * )

Measured by local survey.

T Reactor Building Area Radiation Levels 2500 East Corner Room Floor West Corner Room Floor Area Max Safe Water Level (in.)

8 8

U Reactor Building Area Water Levels Dresden Nuclear Power Station Units 2(3)

EMERGENCY OPERATING PROCEDURE Secondary Containment Control DEOP 300-1 Title Number Rev 09 CATEGORY 1 C Minimum Usable Indicating Levels Fuel Zone

(+60" to -340")

-297

-298

-299

-300

-301 32 to 100 101 to 200 201 to 300 301 to 400 401 to 500 501 to 558 Drywell temperature (°F)

TR 2(3)-1340-1, Point 9 or 10 Medium/Narrow Range All Rx Bldg Temps

(+60" to -60")

Medium/Narrow Range Rx Bldg Temps 181°F or less

(+60" to -60")

Wide Range

(+330" to -70")

-38

-39

-41

-43

-60

-68

-51

-21 17 68 107 Drywell Temperature (°F)

TR 2(3)-1340-1, Point 9 or 10 OR Reactor Building Temperature (°F) 600 500 400 300 200 0

100 200 300 400 500 600 700 800 900 1000 1100 RPV Pressure (psig)

B RPV Saturation Temperature A

RPV Water Level Instruments CAUTION: RPV water level instruments may be unreliable due to boiling in the instrument runs when drywell or reactor building temperatures near the instrument runs are above Fig B, RPV Saturation Temperature.

An RPV water level instrument may not be used if the instrument reads at or below its Minimum Usable Level (Detail C).

>

ML13354B924

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