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2013, Dresden Initial License Exam, Written Exam References
	ML13354B924
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Site:	Dresden
Issue date:	11/25/2013
From:	Walton R; NRC/RGN-III/DRS/OLB
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	Walton R
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S U R V E Y NU M B E R 13-0029 R W P N U M B E R 13-0010 BUILDING Training EL E VATION 603' AREA/ROOM/SYSTEM Rad Worker Exercise Ar ea DATE 10-13-13 TIME 8: 00 PURPOSE Weekly % POWER 100 Legend: All radiation r eadings are in mrem/hr and a ll smears are in dp m/100cm2 unl ess otherwi se noted. O - S me a r - Alpha - Bet a - Gamma - neutro n */ - Contact/30cm [ ] - Hot Spo t XX XX - Bound ary Bkgd - Backgr ou nd SOP - S tep Off Pa d MDA- Mini mum Dete c tabl e Act ivit y CA - Con tamin ation Are a HPZ - Hot Part icle Zone RA - Ra diation Are a HRA - High Ra diation Are a LHRA - Locked High Ra diation Are a ARA - Airborne Ra diation Area 0.5 0.5 0.5 10 SOP SOP XXX XXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXX XX XX RA/CA 9 8 20 7 20 6 MU 4 6 XXXXXXXXXXXXXXXXXX 45 MU-16 60 *20 00/1 20 90 30 90 HRA/HCA MU26 3 5 4 Pu m p 30 XXXXXXXXXXXXXXXXXX Cooler MOD EL NUMBER LI NUMB ER CA L DUE DA TE R S O-5 2.7.1 4 8 11/1 0/13 L B-5 1 0 0 2.1 2.2 6 10/3 1/13 N A X X X XX X X X X X XX X X X X X X X X X X X X X X RADI OLOGICAL SU RVEY FORM Training1.ppt

INSTRUMENTS USED PREPARE D BY: NAME (Prin t) APP RO VE D BY: NAME (Prin t) REVIEW ED BY: NAME (Prin t) SIGN AT URE SIGN AT URE SIGN AT URE DATE DATE DATE PA G E_ OF_ PA G ES S mear # Smear Location d p m/1 0 0 c m 2 1 S O P <32 <3 0 2 F l o o r 9 , 975 <3 0 3 F l o o r 19 , 476 <3 0 4 F l o o r 18 , 958 <3 0 5 F l o o r 120,745 <3 0 6 F l o or 8 1 , 047 <30 7 F l o or 1 , 788 <30 8 F l o o r 9 , 267 <3 0 9 F l o o r 9 , 546 <3 0 10 F l o o r <3 2 <3 0 M D A 32 30

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 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

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

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 documentat ion of dose data from the monitoring licensee is unobtainable. The quantity associ ated 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 exc eeding 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 individual's 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/cm

2. 2.6. Planned Special Exposure (PSE)

An infrequent exposure to radiation, separate from and in addition to the annual expos ure 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/cm

2. 2.8. Total Effective Dose Equivalent (TEDE)

The sum of the deep dose equivalent (external exposure) and the committed effect ive 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 Prot ection 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 admin istrative 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 Protecti on Manger shall review an individual's 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 hi story documentation includes an absent/

no record (A) dose type, then REDUCE the individual's 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 applic able 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 Generati ng Stations Emergency Plan has been initiated, emergency exposure authorizations shall be performed in accordance with the station's 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 t he department requesting approval shall complete Section I of and submit the request to the Radiation Protection Department indicating:

The name, identification number, and signat ure 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 s hall complete Section II Attachment 1 or computerized equivalent. 4.2.4. Pending investigations or calculati ons of internal exposure shall be reviewed and evaluated to determine the individuals TEDE. 4.2.5. Non-Exelon Nuclear and non-ROG dose equi valent shall be included in the dose to determine the worker's 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. T o raise the ADCL up to and including 3000 mrem TEDE in a calendar year, written a pproval is required by the Radiati on Protection Manager and the work group supervisor.

4.2.7. T o raise the ADCL to between 3001 and 4000 mrem TEDE in a calendar year, written a pproval is required by the Radiation Pr otection Manger, a work group supervisor, a nd 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 ex posures above 1000 mrem for employees with High Lifetime Exposure. 4.3.2. A supervisor from the departm ent 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 follow s for any employee who is categorized as having High Lifetime Exposure:

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

Individual's 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 excepti onal 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 departm ent 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 leve l 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 expos ure 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 dos e equivalents and previous doses in excess of routine occupational limits must be deter mined from records for each individual who will participate in the PSE. Doses rece ived 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 li sted 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 recor ded 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 TE DE is to be limited to once in a lifetime. 4.5.2. Emergency personnel are to be informed "bef ore 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 volunt ary on the part of the involved individual.

4.5.5. CONSULT the Emergency Plan Implementing Pr ocedures regarding approval to exceed NRC exposure limits.

5. DOCUMENTATION 5.1. RETAIN completed exposure authorizations, in cluding 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, "Notificati ons and Reports to Individuals." 6.2.2. 10 CFR 20, "Standards fo r Protection against Radiation." 6.2.3. USNRC Regulatory Guide 8.7, "I nstructions for Recording and Reporting Occupational Radiation Exposure Data," Revision 1, July 1992. 6.2.4. USNRC Regulatory Guide 8.35, "P lanned 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. Attachment 1, Dose Control Level Extension Form. 7.2. Attachment 2, High Lifetime Do se Control Level Extension Form. 7.3. Attachment 3, Planned Specia l 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 SI GNATURE: _________________________ 1. Are other qualified individuals with a lower current y ear 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 mr em 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 gr eater 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 r equired. 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 dos e 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 appr oved 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 wi th Attachment 1. Exceptional circumstances should exist to allow individuals with high lifetime dos e to exceed 2000 mrem TEDE in a year.

- - High lifetime exposure controls do not apply to Non-Exelon employees in Mi dwest 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: _______________

ENTRYCONDITIONSDrywellpressureabove2.0psigDrywelltemperatureabove160°F(UseTR2(3)-1340-1Points5and6)Torusbulktemperatureabove95°FToruswaterlevelbelow-4.5in.

ORabove-1.5in.Drywellortorushydrogenabove3.5%PRIMARYCONTAINMENTPRESSUREIFTHENCannotholdpressurebelow2.0psigGoto t.BEFOREDrywellpressurereaches9psigCAUTION:ExceedingLPCINPSH/VortexLimits(FigsV-X)maycausesystemdamage.1.Tripallrecircpumps.2.Tripalldrywellcoolingfans.

3.Startdrywellsprays.Donotusepumpsneededforcorecooling.OKtouseexternalspraysourcesifyoucanrestoreandholdtorusbottompressureandprimarycontainmentwater levelinsideFigD,PrimaryContainmentPressureLimit.ReducingprimarycontainmentpressureaffectsmargintoNPSHlimits.CheckFigsW-Y,NPSHLimits.

IFTorusspraysrunning THENBeforetoruspressuredropsto0psig,stoptorussprays.

t(Torusspray)DrywellspraysrunningBeforedrywellpressuredropsto0psig,stopdrywellsprays.Toruswaterlevel

?Atorabove27.5ftBelow27.5ft.CAUTION:ExceedingLPCINPSH/VortexLimits(FigsV-X)maycausesystemdamage.Starttorussprays.Donotusepumpsneededforcorecooling.OKtouseexternalspraysources.ReducingprimarycontainmentpressureaffectsmargintoNPSHlimits.CheckFigsW-Y,NPSHLimits.WAITuntildrywellpressureisabove9psigBelowFigK,DrywellSprayInitiationLimit

?No YesIFTHENKeeptryingtolowerdrywellandtoruspressuresbelow9psig.CannotstayinsideFigL,PressureSuppression

PressureGoto y.BEFORETorusbottompressurereachesFigD,PrimaryContainmentPressureLimit(Vent)VenttostaybelowFigD,PrimaryContainmentPressureLimit(DEOP500-4).OKtoexceedreleaseratelimits.

yDRYWELLTEMPERATUREIFTHENHolddrywelltemperaturebelow160°Fusingdrywellcooling.DrywelltemperatureaffectsRPVwaterlevelindication.CheckDetailA.Cannotholddrywelltemperaturebelow160°FGoto i.BEFOREDrywelltemperaturereaches 281°F1.Scram.2.ENTERRPVCONTROL

EnterDEOP100whilecontinuinghere 3.BLOWDOWN:EnterDEOP400-2whilecontinuinghere i(Drywellspray)TORUSTEMPERATUREIFTHENHoldtorusbulktemperaturebelow95°Fusingtoruscooling.Cannotholdtorusbulktemperaturebelow95°FGoto o.StartallavailabletoruscoolingDonotusepumpsneededforcorecooling.BEFORETorusbulktemperaturereaches 110°F IF THENCannotholdtorusbulktemperaturebelowFigM,HeatCapacityLimit o(Scram,EnterDEOP100)1.Scram.2.ENTERRPVCONTROL

EnterDEOP100whilecontinuinghere.HoldtorusbulktemperaturebelowFigM,HeatCapacityLimit.1.IF.........THEN..youarenotinRPVFlooding(DEOP400-1)orSteam Cooling(DEOP400-3),

lowerRPVpressuretostaybelowFigM,HeatCapacityLimit.OKtoexceed100°F/hrcooldownrate.2.IF.........THEN..youstillcannotstaybelowFigM,HeatCapacityLimit, BLOWDOWN:EnterDEOP400-2whilecontinuinghere.CAUTION:ExceedingLPCINPSH/VortexLimits(FigsV-X)maycause systemdamage.TORUSWATERLEVELIFTHENHoldtoruswaterlevelbetween-4.5in.and-1.5in.narrowrange.Samplethetorusbeforedischargingwater.LowLevel:Cannotholdlevelabove-4.5in.Goto s.HighLevel:Cannotholdlevelbelow-1.5in.Goto a.a sHighLevel(Above-1.5in.)HYDROGENIFTHENMonitorhydrogenandoxygenconcentrationsindrywellandtorus(DOP2400-1).HydrogenoroxygenmonitorisunavailableSamplethedrywellandtorusforhydrogenandoxygen.Hydrogen(atorabove1%)oroxygen(atorabove5%)isdetected inthedrywellortorusHolddrywellandtoruspressuresbelow2.0psigusingSBGTanddrywellpurge(DOP1600-1).BLOWDOWN:EnterDEOP400-2whilecontinuinghere.

IFDrywellspraysrunning THENBeforedrywellpressuredropsto0psig,stopdrywellsprays.BelowFigK,DrywellSprayInitiationLimit

?No YesIFTHENKeeptryingtolowerdrywelltemperaturebelow160°F.DrywelltemperatureaffectsRPVwaterlevelindication.CheckDetailA.Cannotrestoredrywelltemperaturebelow281°F andholditthereLowLevel(Below-4.5in.)ENTERHYDROGENCONTROL

EnterDEOP200-2whilecontinuinginothersections ofthisprocedure.HydrogenoroxygenconcentrationinthedrywellortorusisunknownENTERHYDROGENCONTROL

EnterDEOP200-2whilecontinuinginothersections ofthisprocedure.StartallavailabledrywellcoolingOKtodefeatdrywellcoolingisolations(DEOP500-2).IFTHENHoldtoruswaterlevelabove12ft.(HPCIexhaust).Cannotholdlevelabove11ft.(downcomers)1.Scram.2.ENTERRPVCONTROL

EnterDEOP100whilecontinuinghere 3.BLOWDOWN:EnterDEOP400-2whilecontinuinghereTripHPCI.Evenifcorecoolingwillbelost.Cannotholdlevelabove12ft.(HPCIexhaust)IFTHENHoldtoruswaterlevelbelow18.5ft(ringheader).Cannotholdlevelbelow18.5ft(ringheader)1.Scram.2.ENTERRPVCONTROL

EnterDEOP100whilecontinuinghere3.Stopinjectionfromoutsidetheprimarycontainmentnotneeded forcorecoolingortoshutdownthereactor.4.IF.........THEN..youcannotrestoretoruswaterlevelbelow18.5ft andholditthere,BLOWDOWN:EnterDEOP400-2whilecontinuinghere.DEOP200-1PRIMARYCONTAINMENTCONTROLDresdenNuclearPowerStationUnits2(3)EMERGENCYOPERATINGPROCEDUREPRIMARYCONTAINMENTCONTROLDEOP200-1 TitleNumber 10RevCATEGORY1 DPrimaryContainmentPressureLimit0102030405060708090100 93PrimaryContainmentWaterLevel(ft)TorusBottomPressure(psig) 70 60 50 40 30 20 10 00500010,00015,00020,00025,00030,00035,000TotalECCSFlow(gpm)WideRangeTorusWaterLevel(ft) 11 10.5 10 9.5 9 VECCSVortexLimitCAUTION:ExceedingLPCINPSH/VortexLimits(FigsV-X)maycausesystemdamage.1.Tripallrecircpumps.2.Tripalldrywellcoolingfans.

3.Startdrywellsprays.Donotusepumpsneededforcorecooling.OKtouseexternalspraysourcesifyoucanrestoreandholdtorusbottompressureandprimarycontainmentwater levelinsideFigD,PrimaryContainmentPressureLimit.ReducingprimarycontainmentpressureaffectsmargintoNPSHlimits.CheckFigsW-Y,NPSHLimits.

KDrywellSprayInitiationLimitDrywellPressure(psig) 20 18 16 14 12 10 8 6 4 2 0DrywellTemperature(°F)TR2(3)-1340-1Points5and6 600 500 400 300 200 1001011121314151617181920WideRangeTorusWaterLevel(ft)

LPressureSuppressionPressure 10.9TorusBottomPressure(psig) 40 30 25 20 15 10 5 0 35 18.6 MHeatCapacityLimit66psigUseonlywhentoruslevelisatorbelow17ft.SeeTSGsfortoruslevelsabove17ft.010020030040050060070080090010001100RPVPressure(psig)TorusBulkTemperature(°F) 230 190 180 170 160 150 140 130 200 210 220 CMinimumUsableIndicatingLevelsFuelZone(+60"to-340")-297-297-298-299-300-301 32 to 100 101 to 200 201 to 300 301 to 400 401 to 500 501 to 558Drywelltemperature(°F)TR2(3)-1340-1,Point9or10Medium/NarrowRange AllRxBldgTemps

(+60"to-60")Medium/NarrowRangeRxBldgTemps 181°Forless

(+60"to-60")WideRange(+330"to-70")-38-39-41-43-43-43-60-60-60-60-60-60-68-51-211768107DrywellTemperature(°F)TR2(3)-1340-1,Point9or10 ORReactorBuildingTemperature(°F) 600 500 400 300 200010020030040050060070080090010001100RPVPressure(psig)

BRPVSaturationTemperature ARPVWaterLevelInstrumentsCAUTION:RPVwaterlevelinstrumentsmaybeunreliableduetoboilingintheinstrumentrunswhendrywellorreactorbuildingtemperaturesneartheinstrument runsareaboveFigB,RPVSaturationTemperature

.AnRPVwaterlevelinstrumentmaynotbeusediftheinstrumentreadsatorbelowitsMinimumUsableLevel(DetailC).

WLPCI/CoreSprayNPSHLimitECCSFlowUpTo10,750gpm0100020003000400050006000LPCI/CoreSprayPumpFlow(gpm)TorusBulkTemperature(°F) 250 200 150 100 503.5psig5psig10psig15psigTorusBottomPressure(psig)

XLPCI/CoreSprayNPSHLimitECCSFlowUpTo25,500gpm0100020003000400050006000LPCI/CoreSprayPumpFlow(gpm)TorusBulkTemperature(°F) 250 200 150 100 503.5psig5psig10psig15psigTorusBottomPressure(psig)01000200030004000500060007000HPCIFlow(gpm)TorusBulkTemperature(°F) 250 200 150 100 503.5psig5psig10psig15psigTorusBottomPressure(psig)

YHPCINPSHLimit E N T R Y C O N D I T I O N S D i f f e r e n t i a l P r e s s u r e a t o r a b o v e 0 i n.A r e a r a d i a t i o n a b o v e m a x n o r m a l (D e t a i l T)V e n t r a d i a t i o n a b o v e 4 m r/h r F l o o r d r a i n s u m p w a t e r l e v e l a b o v e h i-h i a l a r m A r e a t e m p e r a t u r e a b o v e m a x n o r m a l (D e t a i l S)A n y o f t h e f o l l o w i n g i n t h e r e a c t o r b u i l d i n g: C o r n e r r o o m w a t e r l e v e l a b o v e 0 i n.C A U T I O N: H i g h t e m p e r a t u r e o r l o w w a t e r l e v e l i n t h e s p e n t f u e l p o o l c a n a f f e c t r a d i o l o g i c a l c o n d i t i o n s a n d w a t e r l e v e l s i n t h e r e a c t o r b u i l d i n g a n d a d j a c e n t a r e a s.R e a c t o r b u i l d i n g a c c e s s m a y a l s o b e r e s t r i c t e d b y s t e a m.I F T H E N R e a c t o r b u i l d i n g e x h a u s t r a d i a t i o n a b o v e 4 m r/h r V e r i f y:

R e a c t o r B u i l d i n g V e n t i l a t i o n i s o l a t i o n

S B G T s t a r t R e a c t o r B u i l d i n g V e n t i l a t i o n i s o l a t e s A N D R e a c t o r b u i l d i n g e x h a u s t r a d i a t i o n b e l o w 4 m r/h r S t a r t R e a c t o r B u i l d i n g V e n t:

O K t o d e f e a t h i g h d r y w e l l p r e s s u r e a n d l o w R P V w a t e r l e v e l i n t e r l o c k s (D E O P 5 0 0-2).T E M P E R A T U R E/R A D I A T I O N I s o l a t e a l l d i s c h a r g e s i n t o a f f e c t e d a r e a s e x c e p t s y s t e m s n e e d e d f o r:

F i r e f i g h t i n g

O t h e r D E O P a c t i o n s I F T H E N P r i m a r y s y s t e m d i s c h a r g i n g i n t o r e a c t o r b u i l d i n g A N D D i s c h a r g e c a n n o t b e i s o l a t e d G o t o k S h u t d o w n t h e r e a c t o r.B E F O R E A n y a r e a t e m p e r a t u r e , r a d i a t i o n , o r w a t e r l e v e l r e a c h e s m a x s a f e v a l u e (D e t a i l s S , T , U)1.S c r a m.

2.E N T E R R P V C O N T R O L:

E n t e r D E O P 1 0 0 w h i l e c o n t i n u i n g h e r e.W A I T u n t i l 2 o r m o r e a r e a s a b o v e m a x s a f e v a l u e s o f s a m e p a r a m e t e r (D e t a i l s S , T , U)B L O W D O W N:

E n t e r D E O P 4 0 0-2 w h i l e c o n t i n u i n g h e r e.W A T E R L E V E L S I F T H E N O p e r a t e s u m p p u m p s t o h o l d f l o o r d r a i n s u m p l e v e l b e l o w t h e h i-h i a l a r m s e t p o i n t a n d r e m o v e w a t e r f r o m r e a c t o r b u i l d i n g a r e a s.F l o o r d r a i n s u m p l e v e l c a n n o t b e r e s t o r e d b e l o w t h e h i-h i a l a r m s e t p o i n t O R W a t e r c a n n o t b e r e m o v e d f r o m a n a r e a G o t o j j O p e r a t e a r e a c o o l e r s a n d R e a c t o r B u i l d i n g V e n t i l a t i o n.

R e a c t o r b u i l d i n g t e m p e r a t u r e a f f e c t s R P V w a t e r l e v e l i n d i c a t i o n.C h e c k D e t a i l A.I F T H E N A n y a r e a t e m p e r a t u r e o r r a d i a t i o n a b o v e m a x n o r m a l (D e t a i l s S , T)G o t o j k (S c r a m , E n t e r D E O P 1 0 0)W A I T u n t i l 2 o r m o r e a r e a s a b o v e m a x s a f e v a l u e s o f s a m e p a r a m e t e r (D e t a i l s S , T , U)E N T R Y C O N D I T I O N S O f f-s i t e r e l e a s e r a t e a b o v e G S E P"A l e r t"l e v e l (D r e s d e n E A L s)

D E O P 3 0 0-1 S E C O N D A R Y C O N T A I N M E N T C O N T R O L

D E O P 3 0 0-2 R A D I O A C T I V I T Y R E L E A S E C O N T R O L*O p e r a t e T u r b i n e B u i l d i n g V e n t i l a t i o n.

I s o l a t e a l l p r i m a r y s y s t e m d i s c h a r g e s o u t s i d e p r i m a r y a n d s e c o n d a r y c o n t a i n m e n t s e x c e p t s y s t e m s n e e d e d f o r o t h e r D E O P a c t i o n s.I F T H E N P r i m a r y s y s t e m d i s c h a r g i n g o u t s i d e p r i m a r y a n d s e c o n d a r y c o n t a i n m e n t s A N D D i s c h a r g e c a n n o t b e i s o l a t e d B e f o r e o f f-s i t e r e l e a s e r a t e r e a c h e s t h e "G e n e r a l E m e r g e n c y"l e v e l (D r e s d e n E A L s):

1.S c r a m.

2.E N T E R R P V C O N T R O L:

E n t e r D E O P 1 0 0 w h i l e c o n t i n u i n g h e r e.

3.B L O W D O W N:

E n t e r D E O P 4 0 0-2 w h i l e c o n t i n u i n g h e r e.D r e s d e n N u c l e a r P o w e r S t a t i o n U n i t s 2 (3)

E M E R G E N C Y O P E R A T I N G P R O C E D U R E R a d i o a c t i v i t y R e l e a s e C o n t r o l D E O P 3 0 0-2 T i t l e N u m b e r R e v C A T E G O R Y 1 0 2 H P C I R o o m S h u t d o w n C o o l i n g P u m p R o o m S h u t d o w n C o o l i n g H t X R o o m C l e a n U p D e m i n R o o m C l e a n U p P u m p&H t X A r e a I s o l a t i o n C o n d e n s e r A r e a A r e a M a x N o r m a l T e m p e r a t u r e (°F)1 5 0 1 5 0 1 5 0 1 5 0 1 5 0 1 5 0 2 1 0 1 8 0 1 8 0 2 1 0 2 1 0 1 8 0 M a x S a f e T e m p e r a t u r e (°F)S R e a c t o r B u i l d i n g A r e a T e m p e r a t u r e s H P C I C u b i c l e , U n i t 2 (3)E a s t L P C I P u m p A r e a W e s t L P C I P u m p A r e a E a s t C R D M o d u l e A r e a W e s t C R D M o d u l e A r e a V e s s e l I n s t r u m e n t R a c k A r e a A r e a M a x N o r m a l R a d i a t i o n (m r/h r)1 5 0 (1 0 0)1 2 9 3 0 5 0 3 0 2 5 0 0 2 5 0 0*2 5 0 0*2 5 0 0*2 5 0 0*2 5 0 0*M a x S a f e R a d i a t i o n (m r/h r)C l e a n U p S y s t e m A r e a 3 0 2 5 0 0*I s o l a t i o n C o n d e n s e r A r e a , U n i t 2 (3)1 0 (2 5 0 0*)*M e a s u r e d b y l o c a l s u r v e y.T R e a c t o r B u i l d i n g A r e a R a d i a t i o n L e v e l s 2 5 0 0 E a s t C o r n e r R o o m F l o o r W e s t C o r n e r R o o m F l o o r A r e a M a x S a f e W a t e r L e v e l (i n.)8 8 U R e a c t o r B u i l d i n g A r e a W a t e r L e v e l s D r e s d e n N u c l e a r P o w e r S t a t i o n U n i t s 2 (3)

E M E R G E N C Y O P E R A T I N G P R O C E D U R E S e c o n d a r y C o n t a i n m e n t C o n t r o l D E O P 3 0 0-1 T i t l e N u m b e r R e v 0 9 C A T E G O R Y 1 C M i n i m u m U s a b l e I n d i c a t i n g L e v e l s F u e l Z o n e

(+6 0" t o-3 4 0")-2 9 7-2 9 7-2 9 8-2 9 9-3 0 0-3 0 1 3 2 t o 1 0 0 1 0 1 t o 2 0 0 2 0 1 t o 3 0 0 3 0 1 t o 4 0 0 4 0 1 t o 5 0 0 5 0 1 t o 5 5 8 D r y w e l l t e m p e r a t u r e (°F)

T R 2 (3)-1 3 4 0-1 , P o i n t 9 o r 1 0 M e d i u m/N a r r o w R a n g e A l l R x B l d g T e m p s

(+6 0" t o-6 0")M e d i u m/N a r r o w R a n g e R x B l d g T e m p s 1 8 1°F o r l e s s

(+6 0" t o-6 0")W i d e R a n g e

(+3 3 0" t o-7 0")-3 8-3 9-4 1-4 3-4 3-4 3-6 0-6 0-6 0-6 0-6 0-6 0-6 8-5 1-2 1 1 7 6 8 1 0 7 D r y w e l l T e m p e r a t u r e (°F)

T R 2 (3)-1 3 4 0-1 , P o i n t 9 o r 1 0 O R R e a c t o r B u i l d i n g T e m p e r a t u r e (°F)6 0 0 5 0 0 4 0 0 3 0 0 2 0 0 0 1 0 0 2 0 0 3 0 0 4 0 0 5 0 0 6 0 0 7 0 0 8 0 0 9 0 0 1 0 0 0 1 1 0 0 R P V P r e s s u r e (p s i g)B R P V S a t u r a t i o n T e m p e r a t u r e A R P V W a t e r L e v e l I n s t r u m e n t s C A U T I O N: R P V w a t e r l e v e l i n s t r u m e n t s m a y b e u n r e l i a b l e d u e t o b o i l i n g i n t h e i n s t r u m e n t r u n s w h e n d r y w e l l o r r e a c t o r b u i l d i n g t e m p e r a t u r e s n e a r t h e i n s t r u m e n t r u n s a r e a b o v e F i g B , R P V S a t u r a t i o n T e m p e r a t u r e.

A n R P V w a t e r l e v e l i n s t r u m e n t m a y n o t b e u s e d i f t h e i n s t r u m e n t r e a d s a t o r b e l o w i t s M i n i m u m U s a b l e L e v e l (D e t a i l C).

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ML13354B924

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