ML20204H764

From kanterella
Jump to navigation Jump to search
Rev 4 to Procedure RDW 5.5, Spent Fuel Receipt,Handling & Empty Cask Shipment
ML20204H764
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/28/1984
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20204H448 List:
References
RDW-5.5, NUDOCS 8411120381
Download: ML20204H764 (8)


Text

.

RDW 5.5 MINOR Revision 4 09-28-84 SPENT FUEL RECEIPT, HANDLING

~

AND EMPTY CASK SHIPMENT 1.0 GENERAL Spent fuel casks are shipped to PBNP via exclusive use vehicles. A shipment will normally consist of a single cask covered by a steel cage on the back of a trailer. Since the cage restricts personnel access to the cask, the trailer is considered as a closed transport vehicle.

Procedures pertaining to exclusive use, closed transport vehicles are applicable in this situation.

2.0 REFERENCES

2.1 10 CFR 20.205 2.2 10 CFR 71 2.3 49 CFR Parts 100 to 199

[ 3.0 RECEIPTS

'i

. 3.1 Upon arrival at the south gate, the DSS or an authorized repre-sentative will sign the receipt section on the incoming bill of lading and authorize the vehicle on site. The following paper-work will be received from the driver:

3.1.1 A copy of the bill of lading, 3.1.2 Radioactive material shipping documents, 3.1.3 Exclusive use documents, 3.1.4 Outgoing survey from shipper.

4.0 TIME LIMITS (10 CFR 20.205) 4.1 ' Casks received at PBNP will be surveyed for external contam-ination and radiation levels within the following time limits:

Time of receipt Time of survey During normal working hours 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ,

outside normal working hours 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> 4.2 Normal working hours are 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> to 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> Monday through

, Friday.

t 841112Og1 0 00 6 PDR ADO PDR ,

P

. RDW 5.5 Page 2 5.0 RADIOLOGICAL SURVEYS 1Gle NRC.and the DOT have both established radiation and removable contamination limits for the vehicles and casks. Depending on the levels of radiation or contamination found, certain immediate noti-fications are required.

5.1 NRC Limits (10 CFR 20.205)

If the casks exceed the removable contamination limits specified below, immediately contact the Health Physicist or Superintendent

- Chemistry & Health Physics.

5.1.1 Cask removable contamination limits:

Contaminant Max Permissible (dpm/100 cm2 )

Beta gamma emitters 22,000 Radionuclides with half-lives less than 10 days 22,000

( Natural uranium, thorium

.U-235, U-238, Th-232, Th-228, Th-230, when contained in ores or physical concentrates 22,000 Alpha (other than noted above) 2,200 5.1.2 Upon notification and verification of a violation, the Health Physicist or a plant superintendent, normally the Superintendent - EQRS, will immediately notify the final delivery carrier and the NRC Office of Inspection and Enforcement by telephone and in writing by telegram, mailgram, or equivalent. The address and phone number are:

Office of Inspection and Enforcement U. S. NUCLEAR REGULATORY COMMISSION, REGION III 799 Roosevelt Road Glen Ellyn, IL 60137 Telephone: 312/932-2500 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

The Health Physicist or a plant superintendent will also notify the final delivery carrier of the violation by telephone and written communication. This should be done as soon as practical after the NRC notification.

. _ - . _ _ ~ _ - _ _ _ _ . ~ __ .._.-. . . _ _ _ _ _ _ _ _ - . ___ -_

RDW 5.5 Page 3 5.2 DOT Limits (49 CFR 173.441 and 173.443)

~~

If the vehicle exceeds the radiation or contamination limits given below, notify the CHP Supervisor.

5.2.1 Vehicle removable contamination limits Contaminant Max Permissible (dpm/100 cm2 )

Beta gamma emitting nuclides 22,000 Radionuclides with half-lives less than 10 days 22,000 Natural uranium, thorium U-235, U-238, Th-232, Th-228, Th-230, when contained in ores or physical concentrates 22,000 Alpha (other than noted above) 2,200 5.2.2 Radiation limits (49 CFR 173.441)

a. 2 mrem / hour anywhere in the driver's compartment or sleeper.
b. 1000 mrem / hour on the accessible surface of the cask.
c. 200 mrem / hour at any point on the external surface of the vehicle including the upper and lower surfaces.
d. 10 mrem / hour at any point two meters from the verticle planes projected by the outer edges of the vehicle.

NOTE: THE REMOVABLE CONTAMINATION LIMITS SPECIFIED ABOVE ASSUME A SMEAR EFFICIENCY OF 10%. IF SMEARS OF GREATER EFFICIENCY ARE USED, THEN THE LIMITS MAY BE ADJUSTED ACCORDINGLY. (49 CFR 173.433(a))

6.0 INSPECTIONS AND PRECAUTIONS 6.1 A general inspection should be performed to check the physical condition of the cask and vehicle. Contact the CHP or OPS Supervisor if any damage is noted. ,

6.2 In accordance with the WE Safety Manual, standard safety methods will be followed when lifting and handling the cask and associated equipment. (10 CFR 20.205(d))

-- -. . . . . - ~ . , - . , , - - . . , - ~ , - - - , , , .

.- - ~-,---..,- ,-,. ,.-- . - - ,,, n, , . , , . - - - - - - - , . . - - - - -

RDW 5.5 Page 4 7.0 GENERAL - HANDLING SFENT FUEL CASK 7.1 Procedure 7.1.1 HP will perform a gamma radiation and contamination survey of the trailer. The gamma radiation survey is to be performed using a teletector. The readings are to be taken on contact, 1 meter, and 2 meters from the trailer and in the cab and sleeper. The contamination survey should consist of about 25 smears, approximately 23 of which will be taken on the trailer, and the remainder will be taken in the cab. The smears will be counted for 0.5 minutes (Sy). In addition, approximately 20% of Jthe smears will be randomly selected and counted 1 minute for alpha.

NOTE: THIS SURVEY IS NORMALLY PERFORMED OUTSIDE THE SOUTHGATE PRIOR TO ENTRY ON SITE. IN THE CASE OF INCLEMENT WEATHER, THE SURVEY MAY BE PERFORMED IN THE TURBINE HALL. THIS WILL BE DETERMINED BY HP.

7.1.2 The DSS, OPS Supervisor, or HP will determine if the cage will be removed in the turbine hall or truck i access. When the cage is removed, HP is to rope off and post the trailer as a contaninated area, and set up a step-off pad at the entry point to the trailer. HP will ensure radioactive placards are covered after cage removal.

7.1.3 HP will perform radiation and contamination surveys of the cask. The contamination survey should consist of approximately 50 smears, about 46 of which will be taken on t.)e cask, and the remainder will be taken on the

>- impact limiters. The smears will be counted for .5 minutes ($y). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute 1

for alpha. The radiation survey is to consist of gamma, beta, and neutron scan surveys on contact with the cask.

Also perform a gamma and beta survey of the checkpoints.

s If the vehicle and cask are surveyed in the turbine

, hall, a contamination survey of the turbine hall floor should be performed after removal of the trailer as determined by HP.

.I

RDW 5.5 Page 5 I

1 All smears performed for Step 7.1.3 must be counted  !

prior to commencing any work on the cask. i i

NOTE: IMMFDIATELY NOTIFY THE CHP SUPERVISOR ASSIGNED TO RADWASTE AND THE HEALTH PHYSICIST IF ANY SMEARS TAKEN IN STEP 7.1.3 EXCEEDS 22,000 DPM/CM2 FOR INSTRUCTIONS ON DETERMINING SMEAR EFFICIENCY AND NOTIFICATION TO THE NRC. DO

\NOTALLOWWORKOTHERTHANSURVEYSTOBEPERFORMED

~ ON THE CASK UNTIL SURVEYS ARE COMPLETED AND EVALUATED BY HEALTH PHYSICS.

7.1.4 The irpact limiters will be removed. Then the cask will be removed from the trailer and placed in the decon pit.

The cask is then prepared for fuel unloading.

NOTE: HP IS TO ENSURE THAT A LOW VOLUME AIR SAMPLE IS STARTED PRIOR TO THE CASK BEING PLACED IN THE DECON PIT.

~

NOTE: DIRECT HP COVERAGE IS REQUIRED IN THE DECON PIT WHENEVER THE SHIPPING CASK INNER HEAD IS NOT INSTALLED AND TORQUED.

(

7.1.5 .HP is to monitor changes in radiation levels during fuel cask preparations. Obtain a water sample from the cask and deliver it to the chemistry lab with a form CHP-24.

7.1.6 The trailer is to be wiped down in the drip tray area and in any area found in step 7.1.1 to be greater than MDA. A contamination survey should be performed in the drip tray area consisting of approximately 20 smears.

The smears will be counted for 0.5 minutes (Sy). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha. The trailer drip tray must be <1000 dpm/100 cm 2 (Sy) and SMDA alpha.

l NOTE: STEP 7.1.6 MAY BE COMPLETED AT ANY TIME PRIOR TO STEP 7.1.10.

7 .1.7 The cask will be removed from the decon pit and placed in the spent fuel pool for fuel unloading. During fuel cask unloading, HP is to monitor radiation levels. Upon completion of fuel unloading, the cask will be removed from the spent fuel pool. A radiation and contamination survey should be performed of the spent fuel pool area l

upon removal i

I e

4

.--y .,..m.-...y., , ,, m.,- .w,w - , . ,,v---.-.--v_,m. -

.%,---7-- -.y.,.v y - , , , - - - - . - , - .

g RDW 5.5 Page 6 of the cask. This survey should consist of general area radiation levels and approximately 20 smears. The smears will be counted for 0.5 minutes ( y). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha.

7.1.8 Upon removal from the spent fuel pool, the cask will be placed in the decon pit for reassembly. HP is to monitor for any changes in rad levels during reassembly.

Upon completion of reassembly, decon will begin. HP is

~to fill in the decon time sheet.

NOTE: DIRECT HP COVERAGE IS REQUIRED IN THE DECON PIT WHENEVER THE SHIPPING CASK INNER HEAD IS NOT INSTALLED AND TORQUED.

7.1.9 Upon completion of the decon, HP should perform a post decon contamination survey of the cask consisting of approximately 50 smears. The smears will be counted for 0.5 minutes (Sy). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha. All smears must be <1000 dpm/100 cm2 (py) with SMDA alpha or the cask must be redeconned and i resmeared.

7.1.10 After all the smears taken in step 7.1.9 have been counted and determined to bc <1000 dpm/100 cm2 (py) and SMDA alpha, the cask will be placed on the truck.

7.1.11 After the cask has been removed from the decon pit, HP should perform a radiation and contamination survey of the decon pit. The survey is to consist of general area radiation levels and approximately 20 smears. The smears will be counted for 0.5 minutes ( y). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha.

7.1.12 With the cask on the truck, HP should perform the final outgoing contamination survey of the cask. The contam-ination survey of the cask is to consist of approx-imately 50 smears. The smears will be counted for 1 minute (Sy). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha. All smears must be <1000 dpm/100 cm2 (py) with SMDA alpha or the cask must be wiped down and resmeared.

NOTE: STEP 7.1.12 SHOULD BE COMPLETED NO MORE THAN 4 HOURS PRIOR TO THE VEHICLE'S DEPARTURE.

l 1

I i

I l

+

  • RDW 5.5 Page 7 7.1.13 HP will perform the final outgoing radiation survey of the cask. It will consist of a gamma and beta survey of the checkpoints. Also included is a scan of the entire cask with the highest reading noted on the map.

Immediately contact the CHP Supervisor if any readings on the surface of the cask exceeds 50 mrem / hour or the transport index is >1.0.

4 NOTE: THE CASK MAY BE COVERED WITH PLASTIC AS DETERMINED BY HP OR THE OPS SUPERVISOR.

7.1.14 Normally a DOT Yellow II label will be affixed to both sides of the cask. Contact the CHP Supervisor to determine what information is required on the labels. A marking stating " Radioactive Material, LSA, n.o.s. UN 2912" must also be affixed to both sides of the cask.

If manufactured marking is not available, then the marking may be hand lettered on white duct tape with waterproof ink in letters at least 1" high.

7.1.15 As determined by HP, normally 10 smears will be taken on the top surface of the cask and impact limiters prior to installing the cage to ensure the cask has not been

{ contaminated by the overhead crane. The smears will be counted for 1 minute (Sy). In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha.

7.1.16 HP will perform the final outgoing radiation and contamination survey on the trailer. The contamination survey should consist of approximately 25 smears on the trailer. The smears will be counted for 1 minute ( y).

In addition, approximately 20% of the smears will be randomly selected and counted 1 minute for alpha. All smears must be <100 dpm/100 cm2 (Sy) and SMDA alpha.

The radiation survey is to be performed with a tele-tector on contact, 1 meter and 2 meters from the trailer, also in the cab and sleeper. Immediately contact the CHP Supervisor if any readings at 1 meter exceed 1 mrem / hour or if the reading in the cab or sleeper exceed 2 mrem / hour.

4 I .

f i

_ , . . , , , _ . , . . _- _ , , _ _ , . . , _ , . _ , . . , , . , . . , - , _ . _ , . - , - . . , _ , . . , , . _ _ _ _ , , , . . . _ . , , - . , , _ , . _ , . _ . . . . . . ~ . . . -

4 RDW 5.5 Page 8 f.

No placarding is required on the vehicle if it is

~

7.1.17 carrying a cask labeled Yellow II. In that situation, radioactive placards on the cage or the vehicle must be covered. Contact the CHP Supervisor to determine placarding requirements for vehicles carrying casks with other than Yellow II labeling.

7.1.18 Prior to the trailer being removed from the controlled side, perform tire smears to verify the truck and trailer meet the limits for release to the clean side.

5

-( ,

6 1

-