ML050880076

Radiation Work Permit No.04-182

ML050880076
Person / Time
Site:	Point Beach
Issue date:	04/22/2004
From:	Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2004-0282, RWP-04-182
Download: ML050880076 (9)

Text

Nuclear Power Business Unit RADIATION WORK PERMIT Revision:

P2 RWP Number:

04-182 Controlling Work Document:

W.O. 0407919 RG 1.16 Class:

6 Estimated Dose:

1.500 Rem Job

Title:

Replace Cono-Seal bullet Job Location:

U-I CTMT Rx Cavity Job

Description:

Replace Cono-Seal bullet and Associated work Radiological Assessment of WVork Significant increase in radiation levels is likely?

QYes ZNo Reason:

Significant increase in contamination levels is likely?

jYes ZNo Reason:

Potential for internal dose?

0Yes EINo Reason:

Airborne caused by high contamination disturbance RWP Tasks Task 1:

Replace Cono-Seal Bullet and Associated work Task 2:

Task 3:

Task 4:

Task 5:

Task 6:

Task 7:

Task 8:

Task 9:

Task 10:

Task 11:

Task 12:

RWP Review and Approval Prepared By:

CJD 04-21-04 Initials Date ALARA Review By:

BJC 4-21-04 ALARA Review No.:

E N/A 3

2004-0027 Initials noDate Approved By:

r4/

f RP Supervisor lDate Terminated By:

RP Supervisor Date 4

3 PBF.4031 Revision 12 12/10/03 HP l.10/P6.8 Page 1 of`4

Nuclear Power Business Unit RADIATION WORK PERMIT Revision:

0 RWN'P Number:

04-182 TASK 1: Replace Cono-Seal bullet and Associated work Radiation Protection personnel are authorized to suspend work activities in the event of a change in job scope, changes in radiological conditions, or a failure of personnel working under the RWP to abide by the RWP conditions.

Stop WVork Dose Rate:

5000mR/hr ED Dose Rate Alarm:

2500mR/hr ED Dose Alarm:

1200rnrem Radiation Protection Hold Points:

ON/A Contact RP prior to entering any High Radiation Area Workers shall not handle any debris or foreign material without a survey and permission from RP When accessing a LHRA notify RP supervision prior to the entry and Immediately upon completion of the entry.

Authorized Radiological Work Areas: Any RWVP permits entry into RCA(s), RMA, and RA.

0 t-0D HRA 0 LHRA a VHRA E Ctmt. Reactor Critical m2 0D CA ED HCA 0D HPCA 0

Airborne Radioactivity Area 3

Expected Radiological Conditions:

Data From:

Current Su El Historical Data E Estimated Radiation: GA 150 to 2000 mrern/hr

Contact:

1200 to 2500 mren'hr Contamination:

20K to

>IE6 dprr'I00 cm2 Internal Contamination:

N/A to N/A dpmIl00 cm2 (I estimated)

Airborne Radioactivity:

<1.0 DAC 09 P ED 1, El NG El OH (ED Estimated / El Actual DAC)

RP Job Coverage: E Routine 0 Direct

[

Start of Job C System Breach 0 Pre-Job Briefing Required Special Instructions:

Timekeeping will be the primary means of dose control with Teleview being used to monitor exposure as secondary means. Telex radios to be used for communication.

Radiological Survey Requirements:

A. Radiation:

0 Prior to/Start of Work El System Breach E Other Special Instructions:

Verify conditions prior to entry. RP perform hot particle survey after exit from cavity.

Additional surveys as per RP.

B. Contamination:

E Prior to/Start of Work D System Breach 0 Other Special Instructions:

Survey of man-basket upon job completion, Decon as necessary. Additional surveys as per RP.

C. Airborne:

C Priorto/StartofWork El SystemBreach 0 Other Special Instructions:

PIF-403 1 Revision 12 12/10/03 HP 1.10/P6.8 Page 2 of 4

Nuclear Power Business Unit RADIATION WORK PERMIT Revision:

0 RNVP Number:

04-182 III.

Dose Assessment: TLD and EPD required.

Special Instructions:

Relocation o serates Timekeeping required when working in a dose rate >1,500 mR/hr and the worker could receive more than 25 mrem.

I\\.

Protective Clothing 0

Coveralls, Booties, and Rubber Gloves (Minimum requirements for entering a contaminated area) a Labcoat, Booties, and Rubber Gloves may be used only with RP permission.

03 Coveralls, Double Booties or Booties and Rubber Totes/Boots, and Double Rubber Gloves for HCA entry.

a Double coveralls, Double Rubber gloves, Double Booties, Rubber Totes/Boots.'

El Plastic suit, or water resistant coveralls, Double Rubber Gloves, Double Booties, Rubber Boots, Hood, and Face Shield for entry to cavity. '(Face Shield not required when wearing a respirator)

El Surgeon's Gloves may be substituted for Rubber Gloves with RP permission.

O Hood and Face Shield required.

0 Other: See Special Instructions Safety review may be required for additional coveralls or plastics.

Special Instructions:

Additional requirements as per RP.

V.

Respiratory Protection:

ON/A E TEDE ALARA Review:

Special Instructions:

VI.

Engineering Controls:

Special Instructions:

Shielding to be provided by adding 2ft of water above the reactor vessel flange.

PBF-4031 Revision 12 12/10/03 IP I J. O/P6.8 Page 3 of 4

Nuclear Power Business Unit RADIATION WORK PERMIT Revision:

0 RWP Number:

04-182 VII.

ALARA Requirements:

A See ALARA Review LDWA:

To be identified by RP.

Special Instructions:

Foreign debris found within the refueling cavity may be highly radioactive and shall not be handled without RP permission.

• When working in these areas or handling equipment from these areas (such as refueling tools) workers shall monitor at approximately every two hours.

Contact RP immediately if, during monitoring of protective clothing, the worker discovers

>10,000 cpm above bkg using a frisker or >5 mRem/hr above bkg using an open window beta instrument.

Contact RP immediately if, during monitoring of skin, personal clothing, or modesty garments any contamination above bkg is discovered.

PBF-403 I Revision 12 12/10/03 HP 1.1O/P6.8 Page 4 of 4

Point Beach Nuclear Plant Level 3 Pre-Job ALARA Review ALARA Review Number: l 2004-0027 U1R28 Estimated dose:

1.500 Rem Part 1: Job Description A. Job Description Replace bullet nose on thermocouple port column. This will entail working from a man (Attach work list if appropriate) basket hanging from the polar crane. Two maintenance workers will enter the refueling cavity in the man basket to replace the bullet nose. The o-ring will be replaced, the bullet nose placed over the thermocouples, and the retaining clip installed. The total time for the evolution is expected to be 30-45 minutes in the cavity.

The dose rate at the thermocouple port column is expected to be 2000 mR/hr. If RP cannot perform an adequate survey from the manipulator bridge then a survey from the man basket will be required. RP should use a teletector or equivalent to maintain as much distance as possible between the man basket and the upper internals. This activity is expected to take 15 minutes in the refueling cavity and cost 0.100 person-rem.

The activity of placing the bullet nose over the thermocouples is expected to take 30 minutes and cost 1.300 person-rem.

Additional dose for support activities is expected to cost 0.100 person-rem.

B. Controlling job procedures.

W.O. 0407919 C. Job History/O.E/Lessons No job history exists.

Learned See attached for O.E.

D. Dose history.

No dose history exists for this job.

Part 2: ALARA Checklist NOTE: The following exposure reduction measures should be considered during job planning.

Section 1: Pre-Job Planning/

E. Designated low dose Low dose areas will be on the 66' of the containment building and will be identified by blue waiting/staging areas.

triangles.

F.

Remote job coverage Timekeeping will be the primary means of dose control.

equipment.

Teleview will be used to monitor worker exposure as a secondary means of dose control.

G. Communication devices used.

Telex radios will be used for the workers to communicate.

H. Services required. (lighting, air, The polar crane will be used for the man-basket. No other special services wvill be required.

electrical)

I.

Designated work area U-I containment 66' el.

access/exit points.

J.

Coordination with other groups.

Maintenance and RP for the actual cavity work.

Operations wull fll the reflieling cavity to the required level.

PBF-4195a Revision 5 08/15/03 H P 15.3/P6.8 Pa,,e I of 3

Reference:

Ni'4.2.1

Point Beach Nuclear Plant Level 3 Pre-Job ALARA Review ALARA Review Number:

2004-0027 UIR28 Estimated dose:

1.500 Rem K. Work performed outside of Man basket preparations will be made on the 66' of containment in a low dose area.

radiation areas:

Prefabrication Disassembly Assembly L.

Post-job cleanup requirements.

The man basket will require a survey after the job is complete and may require decontamination.

M. Special tools/equipment used to None minimize time and exposure.

(Use contaminated tools when practicable)

N. Radwaste minimization.

No Radwaste will be generated from this activity.

0. Work activities/equipment Draining of the refueling cavity would result in a loss of shielding.

status that could result in Polar crane malfunction could cause job delays.

significant interruption of job or changes in radiological conditions.

Section 2: Radiological Controls P.

Describe temporary shielding to Water level in the upper cavity will be raised until it is approximately two feet above the be used.

reactor vessel flange. This will provide shielding from the reactor vessel and portions of the upper internals.

Q. What systems/components will None be filled with water or flushed to reduce job area dose rates?

R. Engineering controls to control No engineering controls will be used. The bullet will not be contaminated and the airborne activity. (HEPA thermocouple contamination levels are low. Approximately 20,000 dpm/lOOcm2.

filters, glove bags, etc.)

The upper internals are dry and highly contaminated. Experience shows that attempting to wet or mist the upper internals causes airborne activity in the cavity and on the 66'.

The possibility exists that air currents caused by performing work from the man basket could cause airborne activity in the upper cavity. Past history shows that strong air currents can cause airborne activity on the 66'. See TEDE ALARA review for this work.

S. Attach applicable survey data.

Dose rate information should be discussed at pre-job briefings. The dose rate information used to create the dose estimate for this job is based on previous surveys. Actual dose rate information will be obtained prior to starting work. RP Supervision shall authorize the start of work based on actual survey data.

PBF-4195a Revision 5 08/15/03 HP 15.3/1'6.8 Page 2 of 3

Reference:

N P 4.2.1

Point Beach Nuclear Plant Level 3 Pre-Job ALARA Review ALARA Review Number: l 2004-0027 U1R28 Estimated dose:

1.500 Rem Section 3: Worker Preparation and Training T.

Consider the following:

Workers experienced in installing the bullet noses will be used.

Experienced workers selected.

Special training, photos.

drawings. video tapes available Rehearsal Mock-up training Use of fewer workers evaluated Method of shift turnovers ALARA-As Low As Reasonably Achievable RWP-Radiation Work Permit HEPA-High Efficiency Particulate Air PBF-4195a Revision5 08/15/03 HP 15.3/P6.8 Page 3 of 3

Reference:

NP 4.2.1

POINT MBE/

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'UCLEAR PLANT AL SURVEYS

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COUNTED BY N

REVIEWED BY:

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1) All readings in mrem/llr

2) *Designates hot spots

3) Designates routinely updated posting

4) 'Potential Hazards' identified are indicated on map f

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Point Beach Nuclear Plant TEDE ALARA EVALUATION RW`P 04-182 DESCRIBE TIlE WORK TO BE PERFORMED (DOSE RATES, EST. AVERAGE AIR CONCENTRATIONS, CONTAMINATION LEVELS):

Replace bullet nose on thermocouple port column. This will entail working frons a man basket hanging from the polar crane. Two nraintenancc workers will enter the refueling cavity in the man basket to replace the bullet nose. The o-ring will be replaced, the bullet nose placed over the thermocouples, and the retaining clip installed. The total time for the evolution Is expected to be 30-45 minutes in the cavity.

Dose rates in the work area are expected to be 2000 mR/hr. Expected contamination levels are 20,000 dpm/lOOcm2. Air currents caused by movement of the man basket In the refueling cavity could cause airborne activity. Contamination levels on the upper Internals are expected to be 60 to 80 mrad/hr beta/gamma. Long-lived alpha contamination levels are unknown. Although alpha contamination levels are unknown, an estimate can be made using the

-paa ratio from areas that connect to the underread area. i.e. conoseals. A conoseal contamination survey Indicated that the P-.yu ratio is approximately 100,000150 dpnVI00cm2. If the beta-gamma contamination is 60-80 mRad, then the estimated alpha contamination (using 1 mRad = 100k) Is 3000 dpm/100cm2. From IIPIP 4.40, the alpha adds approximately OA to the DAC-fraction for a normal ventilation area.

Estimated work duration is 15 minutes per worker per entry at the job site. The estimated beta/gamma DAC fraction from IMPIP 4.40 for routine maintenance work in a normally ventilated area Is in the range of 1.8 to 2 DAC.

DESCRIBE TIlE ENVIRONMENTAL CONDITIONS AND EFFECTS ON PERSONNEL SAFETY:

The work area is located in the refueling cavity. Normal containment ventilation.

DESCRIBE PROCESS AND ENGINEERING CONTROLS TO BE USED:

None.

DESCRIBE TIIE PROTECTIVE EQUIPMENT AND CLOTIHNG, INCLUDING TIlE RESPIRATOR, TO BE USED AND TIIEIR EFFECTS ON WORKER EFFICIENCY:

The work involves work In a high contamination area. Protective clothing will consist of normal dress for a high contamination area. Worker efficiency will not be Impaired.

DESCRIBE POTENTIAL POST-ACTIVITY NEGATIVE IMPACTS (E.G., PERSONNEL DECONTAMINATION AND SKIN DOSE ASSESSMENTS, PORTAL MONITOR ALARMS):

Due to the high contamination levels, It is possible that without the use respiratory protective equipment personnel could become contaminated. This would result In portal monitor alarms, the need for personnel decontamination, skin dose assessments, whole body counting and internal dose assessment.

DOSE WITHOUT RESPIRATORY PROTECTION:

[Time (hrs) x Dose rate (mR/h)]

0.25 x 2000

= 500 mrem. external dose

[Time (hrs) x DAC fraction x 2.5 mRJDAC-h)]

0.25 x 2.4 x 2.5

=

1.5 mrem, internal dose Est. dose for implementating engineering or process controls

=

0 mrem Total

=

502 mrcm DOSE WITII RESPIRATORY PROTECTION:

[Time (hrs) x Dose rate (mR/h)]

500 x 1.15

=

575 mrem. external dose

[Time (hrs) x DAC fraction x 2.5 mR/DAC-h / Respirator PF1 1.7/50

=

0 mrem, internal dose Est. dose for implementing engineering or process controls 0

mrem Total

=

575 mrem Note: Time value should reflect worker efficiency impact due to respirator use.

ALARA RECOMMENDATIONS:

X Without respirator With respirator Type:

E Negative Pressurc/PAPR O Airline/Hood a

SCBA As indicated below Justification/Comments: The chance of airborne activity asaresult of this job is slight. The work is being performed on equipment that hasa low contamination level. The only concern is that air currents could cause airborne activity from the highly contaminated upper internals. The work is tay-ing place in very high dose rates and the extra dose that would be received al.j result 9f lower worker efficiency is not justified.

Preparer (Name/Date): Bri=n berry 4/ 0 Approver (Name/Date):

• 7 2

(6 PB3F-4230a Revision I 02/00/02 FHI' 15.12