ML20079H901
| ML20079H901 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/07/1983 |
| From: | Thomas Greene, Nix H, Rogers W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20079H889 | List: |
| References | |
| PROC-831207-01, NUDOCS 8401240106 | |
| Download: ML20079H901 (133) | |
Text
4-4 GEORGIA POWER COMPANY a
HAT,CH NUCLEAR PLANT m
(
PROCEDURE
-. Pulmonary Function Screening Program PROCEDURE TITLE HNP-8035 .._
. PROCEDURE NUMBER Lab -
RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANA R O New Procedure 5 //
_ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ v_
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REBUESTED BY \
Name: } DEPARTMENT HEAD APPROVAL
- Date: Sign 4ture: 'l Date: *- !
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SAFETY RELATED Y NON-SAFETY RELATED ( )
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PROCEDURE CHANGES MODE OF 0 ATION OR I S DESCRIBED IN FSAR:
PROCEDURE INVOLVES: "
-( ) An unceviewed Safety Guestion ( ) Tech. Specs. .
not addressed in FSAR f M None of these ( ).A condition (See back foe Safety Evaluation if required).
t vE-2:s Attach copy of procedure 16 this . form. --
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~83-217 PRO Number il-D-D Date 3' T -
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F SAFETY EVALUATION *
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APPROVAL M OUReNO
. E.1. HATCH NUCLEAR PLANT HNP-8035 See Title Page aevisaw wO oAre
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k/ See T'itle Page GeorgiaPower -
1 of 10 !
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PULMONARY FUNCTION SCREENING PROGRAM )
l A. PURPOSE ,
To provide adequate and qualified on-site pulmonary function screening in co-operation with the approved physician to determine whether or not personnel are physically able to use respiratory protection equipment.
B. REFERENCES
- 1. 10 CFR 20, Para 20.103
- 2. Nu Reg 0041, Sec. 7.4
- 3. ANSI Z-88.2 (1969), Sec. 3.7 -
- 4. Regulatory Guide 8.15 (Oct 1976), Sec. C, para. Ah
- 5. The Jones Pulmonor Waterless Spirometer-Instruction Manual TDC-6000M
}
C. SAFETY There are no abnormal safety requirements for this procedure.
D. MEDICAL REQUIREMENT All personnel who wear respirators will be evaluated by competent medical personnel prior to an assignment requiring such use. The physician will determine what health and physical conditions are pertinent. The medical status of each respirator user will be reviewed annually by a physician and records maintained by Health Physics.
E. GENERAL Pulmonary function screening shall consist of the following:
- 1. A Resgiratory Medical History to be filled out completely by the potential respirator user.
- 2. Screening Vital Signs which will include blood pressure -
sitting, chest sounds and heart pulse will be taken by the approved paramedical personnel.
("% 3. Pulmonary Functions Test which will be a single forced
(/ expirograph (of at least two usable tracings) on the Jones Pulmonor Waterless Spirometer administered by approved spirometer qualified paramedical personnel.
- MANAL SET.
- F
V, .
APPROVAL PROCEDURE NO
. E. l. HATCH NUCLEAR PLANT HNP-8035 See Title Page a6visaw so n-s- See T'itle Page Geo iaPower A ~ ~o 2 of 10
- 4. __The above data will be recorded on Form 1 (Figure 3) for
' evaluation by the approved physician.
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NOTE
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Any quest ~ionable findings by the screening technician or physician as to respirator -
fitness will result in the respirator user being evaluated in person by the approved physician.
F. SCREENING TECHNICIANS Only qualified personnel, approved in writing by the physician, may administer the pulmonary function screening for that physician. These approved paramedical personnel will be Emergency Medical Technicians or equivalent qualified in pulmonary spirometry and will be reviewed annually by the -
approved physician.
G. PULMONARY FUNCTION SCREENING RECORDS
- 1. Form 1, Hatch Respiratory Protection Medical History and
() Pulmonary Function Test Report (Figure 3).
- a. The purpose of this form is to obtain an adequate respiratory medical history from the respirator user.
It is also used to record the pulmonary function test data to be sent to the approved physician for evaluation.
- b. Procedure for recording information on Form 1 (Figure 3).
(1) The respirator user shall complete the form except for the heavy black box labeled " Technician Use Only". The technician shall assure that the respirator user understands the medical terminology and questions.
(2) The " Technician Use Only" box shall be completed by the approved screening technician.
- c. The single forced expirograph will be attached to Form 1 (Figure 3) for physician review.
- 2. Form 2, Respiratory Protection Medical Approval (Figure 4)
,S This form will be attached to completed Form 1 (Figure 3) to
() be sent to the approved physician. After approving or disapproving the respirator user physically able to wear respirators the Form 2 (Figure 4) will be retugn,ed to Plant '
Hatch Health Physics to be kept on file and ma M SEE443.
APPROWA PROCEDURE No
- E. l. HATCH NUCLEAR PLANT HNP-8035 See Title Page a6vew so O
n V
See Title Page GeorgiaPower -
3 of 10
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- 3. Form 3, (Figure 5) Physician's Technician Authorization Form
- a. The purpose of this form is to signify the personnel _~
approved ,to administer the pulmonary screening for that physician. .
- b. The comleted form will be returned with the' physician's signature. It will be transmitted to documentation for retention.
- 4. Pulmonary Functions Screening Log This log book will contain a daily record of all persons screened and will include name, social security number, TLD number, occupation and employer.
H. DESCRIPTION OF THE SPIROMETER -
Refer to Jones Pulmonor Waterless Spirometer-Instruction Manual TDC-6000M and Figure 1.
I. PULMONARY FUNCTION TESTING .
O 1. Testing Readiness
- a. Make sure timer is connected to power supply.
- b. Place graph on timer plate with 0.0 liter edge nearest cabinet (Figure 2, #3).
- c. Make sure timer plate and graph are in the upward ready position.
- d. Set inkless stylus to graph for tracing (Figure 2, #7).
- e. Place new disposable mouthpiece on breathing tube.
- f. The tests are done with the subject standing so that the graph is out of his view.
- 2. Examinee Preparation For best results tell your subject what is required for single forced expirograph prior to test. This may be done by explanation and demonstration.
NOTE Demonstration does not have to be with machine use. .
namin.
APPRO M PROCEDURE esO
. E.1. HATCH NUCLEAR PLANT HNP-8035 See Title Page asum =O oarE - O n - Georgia Power -
\_/ See Title Page O 4 of 10
- 3. __ Administering Pulmonary Function Test NOTE Personal instructions to the subject'may be - -
adapted'to the technician for best results.
- a. Instructions for single forced expirograph.
(1) To the subject "Whenever you are ready, hold ,
your nose. Take a deep breath, as much as you can, and place your mouth on the mouthpiece. Then push out.ALL the air as comgletely and rapid 1r_as gossible."
(2) The technician will place his finger on the timer switch (Figure 2). He shall turn it on just before the suject begins to place his mouth ove.r the mouthpiece.
(3) Coach the subject just as be begins to exhale, "That's the way! Push! Push! All the way out!
All the way out!" As soon as the stylus.on.,the f'T graph shows no further increase in volume an'd at
's# least four seconds (four graph squares) say, "That's-fine . . . Thank you!" Then release the switch and stylus.
- b. Reset timer plate with same graph and set stylus to graph for tracing.
- c. Repeat test step I.3.a at least once for validation of results.
- d. Enter required results of pulmonary function test on Form 1 (Figure 3) and attach expirograph.
J. DISINFECTION OF PULMONOR II
- 1. The Pulmonor II has been designed for sterilization without need for disassembly. Wescodyne or Betadine solutions are approved for proper disinfection. The Pulmonor II should be disinfected after each days use.
- 2. Use a two quart solution of water and 2 ounces of Wescodyne or Betadine solution. Pour the entire contents through the breathing tube into the bellows.
gg 3. Push the "T-Bar" (Figure 2, #8) into the unit until the
(_) stylus reads at about "zero" volume position. Using a #4 rubber stopper plug off the bellows with the stylus in the .
"zero" position. After removing the plastic tube, the stopper is plugged into the metal breathing tuSANWR449,ctor. '
t NAL PROCEDURE feO
. E. l. HATCH NUCLEAR PLANT HNP-8035 See Title Page atosa w care .
O See Title Page 5 of 10
- 4. With the timer still connected to the cabinet, lean the unit ov_er on the timer's side, jostling it gently for one
, minute. After the minute, then lean the unit over onto the ,
rubber stopper, side, jostling it gently for one minute.
- 5. Position the unit upright and remove the stopper. Replace the plastic breathing tube, then lean the unit clear over the breathing tube side pouring the solution back into the two quart container. Put the "T-Bar" upward to the 3600 ml position to facilitate drainage. The fixed bellows plate has been spun into a saucer shape to facilitate good drainage. A small amount of residual fluid is permissible.,
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MANUAL SET, 1 . . _ __
6 APPROVAL
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, See Title Page E. l. HATCH NUCLEAR PLANT HNP-8035
~ aevisc~ ~O
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See Title Page GeorgiaPower A ~~
6 of 10
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4 NN sprometer s wdelyaccepted as a standard for practical.chnical '
pulmonary functon tevng. Tests performed are nowin the rndlons
.. exceeded by no other resprometer.
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. See Title Page E. l. HATCH NUCLEAR PLANT HNP-8035 Re m,0,, ,,o See Title Page Georgia Power d -
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~. FIGURE 2 NOTE:
New Pulmonor units do not require use ut the "Zero setting nng (10). and without it can utilize the larger range. 714 hter graon paper (Type JP1006AL Older Pulmonor its can remove the nng and also use the no. graon paper. -
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- 3. Timer Piete & Gropb 1T 4. Inkles Styiss &
"M - T.~ . . Rocker Assembly -
! ,: M _ j , ,l , 5. Volsme (Sensitivity) Pin
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- 6. Direct Reading Volume Pin /
_ -. y f' Rocker Po sition 55 '6 'j. I r,
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- 7. "On.Off" 5tyle Knobs
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- 8. 'T " Bar
) I l 9. Standard Linkage Line 18 ! I 3.f k' ,II t .. . ,%
- 10. "Zero" 5.eting Ring
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- 11. Double 5en sitivity Pin /
k O Roder Position
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- 12. Bellows Linkage Tube
[ -* I 13. Linkoge Adivitn mt Screw
,i 14. For Left Handed Operation
- 15. "Ze=" Retention Screw g-dc C 3. ;
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Figure 9 THE PULMONOR 11 SPIROMETER A distinguishing chorocteristic of trie Pulmonor ll is that the stylus automo.
tically resets to the "Zero" of base line. A special "W" spring configuation that does this requires no adjustment.
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HATCH RESPIRATORY .dOTECTION MEDICAL HISTORY r+ r+
& PODegn( f usicfrosT TE37 iEPdKT N N
, l 4 . 4 PRIN; FORM 1 ' T "O TAAE SSN DATE W b '
SEE DATE OF BIRTH
'$ c W"3 T E~A N T S S HETCiiT OCCUPATION EHa@h ER S
- 1. Do you have or have you ever had 9 any of the following; 5. a. Never Smoke Used to Smoke Now Smoke
- b. Began Smoking at age ,
Stopped at age $ """
A. CHRONIC BRONCHITIS -YESNO DATE C. Number of cigarettes esoked per day .
" cigare " " "
- B. EMPHYSEMA C. PNEUMONIA
" pipe " " " 3 Z D. CORONARY ARTERY DISEASE E. ASTHMA
- 6. Do you have any allergies or S
Q M F. ANY UTHER CHRONIC OR RESTRICTIVE skin conditions (such as acne.
C.
LUNG DISEASE or ectema) which might be aggrgwated by using a face 9 Q N.
CORONARY INSUFFICIENCY HEART ATTACE maskJ YES NO 3 ~' 1
- 1. 13 J.
HYPERTENSION (HICH BLOOD PRESSURE) 81h00 DISORDERS
- 7. Have you ever had ill effects 3 M 2 K. CANCER from wearing respiratory O C L. CATARACTS protective equipment? YES NO C M. (")
N.
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FEAR OF BEING IN CLOSED SPACES THRYOID DISORDER
- 8. Do you have or have you ever had any other disease. condition 3 2 (T]
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CYSTIC FIBROSIS or disability which might make E Q.
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EPILEPSY DIABETES the use of respiratory protective equipment unwise or unsafe in
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S.
STROaE FACI AL AbM*MALITIES your case f YES NO 2
T. KIDNEY DISEASE II "YES" esplain on back. 3 U. HEARING LOSS 3
V. SERIuuS VISION PROBLEM .
W. RUP1pRED EARDRUMS If you answered "YES" to any of the above questions. 3 E. $tENTAL ILLNESS _
please give complete details on the back of thle form 2
I: Ount L"Jln"T SENSE or MWpN- - - - - - - - - - - - --
S q SHELL I BLOOD PRESSURE / I CHEST q
- 2. Are you or have you ever Cl. EAR / NOT-CLEAR 0 -
been an alcholic? HEART-PULSE E YES NO ri r gm 1. Are you presently taking PUlJe0 NARY FUNCTION TEST l
g 3
c s any an.dacation? YES NO I 2 Fredicted g 9 CD FEVg , ,
E IF "YES". what kinds? > m h *8 us on g measured -
3 k h I T
/l 4. Date of your last physical Re3TcEdI" l' j O 6
2 y esaminataan, E
g'O e- o a l (13 f A we # The informatton above na true and complete to the best echnician g fue ol my knowledge and recollectson. *3 .o "4 Remarka 8 ti O I E g
{lcNATuRE [ DATE
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PROCEDURt NO
. E. l. HATCH NUCLEAR PLANT HNP-8035 See Title Page o,,,3 ,,o DATE O
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See Title Page Georgia Power 9 of 10 FIGURE 4 N7$nN's'a's Os*s '"
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GeorgiaPower
% Edwen I. Halch Nuclear Plant RESPIRATORY PROTECTION MEDICAL APPROVAL' NAME 55f To assure compliance with 10CFR20.103 it is requested that the physician answer the following question.
Oc you believe there is any reason, f rom the health standpoint, that this individual could not engage in duties requiring utilization of respiratory protective equipment?
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-YES l JREMARKS NO l lREMARKS NAME OF EXAMINING PHYSICIAN ADDRESS TELEPHONE DATE SIGNATURE OF EXAMINING PHYSICIAN
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HNP-8035 ROO l'] Figure 4
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e APPRQvg
' E. l. HATCH NUCLEAR PLANT N-sO3s agy:Scq go see Title Page DATE O NOf See Title Page 10 of 10 FIGURE 5
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PHYSICIAN'S TECHNICIAN AUTHgRIZATION FQRM The following personnel are approved to administer the pulmonary screening program as per M -8035 for me.
Physicsan's Signature Date Address O
HNP-8035 ROO Figure 5 0 . ..
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GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT
. " PROCEDURE C
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Maintenance and Operation of Portable High Efficiency Particulate Atm_sghere o (HEPA) Filtration Units PROCEDURE TITLE HNP-8040 '
. PROCEDURE NUMBER Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-SAFETV RELATED ( )
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER
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SAFETY EVALUATION
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MAINTENANCE AND OPERATION OF PORTAGLE HIGH EFFICIENCY
,_ PARTICULATE ATMOSPHFRE (HEPA) FILTRATION UNITS A. PURPOGE' -
- 1. To outline the~ requirements for filter change and general maintenance of the HEPA filtration units. -
- 2. .To define operational surveillance of the HEPA filtration units.
- 3. To provide a system of HEPA filtration Unit readiness verification. -
- 4. To provide a system of HEPA filtration unit inventory and control.
D. REFERENCFG _
- 1. Decontamination HNP-SOOG
- 2. HNP-8008 Radiation Work Permit O C. SecErr Ensure that the HEPA filtration unit has been disconnected from all electrical power sources prior to performing any unit maintenanca.
D. EGUIPMENT DESCRIPTION
- 1. The portable HEPA filtration units are designed for a variety of uses within the nuclear industry.
The unit may be utilized to provide exhaust ventilation for containment tents or structures when uniiltered release of atmospheric contaminants could inadvertently expose personnel.
- 2. The unit may also be utilized to provide filtered exhaust ventilation with a corresponding air circulation for void spaces and tanks with oxygen deficient atmospheres where airborne radioactive contaminante may be present.
- 3. The filtration unit consists of the following primary components,
- a. A 1000 GCFM antifugal blower driven by a 440 VAC, 60 r~ Hz, 3h electric motor which pulls air through the k -} unit. A transformer must be utilized to step down welding outlet power supplies.
NAMNE SET.
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- b. A filter housing which provides support for and flow direction through the spark arrestor screen, roughing prefilter and the HEPA filter.
- c. Two magnahelic differential pressure indicators to provide._ continuous differential pressure indication -
across the spark arrestor screen / coughing prefilter combination and the HEPA Filter.
- d. A spark arrestor screen to provide protection for the Filtration media when the unit is used in conjunction with welding or flame cutting operations,
- e. The roughing prefilter P/N 2184, this filter will collect large particles to preclude premature blockage of the more expensive HEPA filter.
F. The HEPA filter, P/N 2186, provides for filtration of atmospheric contaminants with an efficiency of 99.98%.
E. MA T NTEb_1ANCE_ PROCEDURE
- (~)
- 2. Initiate a HEPA filtration unit maintenance check off list, FORM 1 (Figure 2).-
- 3. Establish a con,tamination control area for filtra tion unit maintenance in the decon area of Unit 1 Rx 185' elevation.
CAUTigN If radiation levels on contac t wi th the Filtra tion unit housing are 2 10 mr/hr in the vicinity of either filter element initial opening and filter element, removal must be accomplished inside a containment tent.
- 4. Remove the front and rear panels from the Filtration unit.
Decontaminate and remove these panels from the area. Retain the hand cranks stored inside these panels for filter removal.
- 5. Utilizing the hand crank (s) relax the tension on the HEPA filter support frame.
- 6. Carefully remove the roughing prefilter from the unit into a plastic bag and dispose of it as radioactive waste.
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() 7. Carefully remove the HEPA filter from the unit.
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- 8. Inspect both the inlet and outlet surfaces of the HEPA
- filter for any irregularities. Enter the inspection results on the HEPA Filtration Unit Maintenance Check-Off List, FORM
, 1.(Figure 2).
. NOIE If no surface irregularities are evident and HEPA filter differential pressure is <_ 1.5"'H2O as noted on FORM 1 (Figure 2), retain the HEPA filter for re-use.
- 9. Inspect the spark arrestor screen and clean with a wire brush and decontamination solution as necessary to eliminate any buildup which could restrict unit air flow. Initial step 5 of FORM 1 (Figure 2) to signify completion.
- 10. Decenteminate the HEPA filtration unit inside and outside in accordance with Reference 1. Enter decontamination resubts of FORM 1 (Figure 2).
- 11. Install an acceptable HEPA filter into the filtration unit housing.
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() 12. Utilizing the hand cranks raise the HEPA filter support frame evenly until the HEPA filter outlet side gasket is compressed.
CAUTION Qo not overtorque the filter support Freme lifting mechanism. Overtorquing could strip tiie frame gearing and render the unit inoperable.
NOIE If the HEPA fil ter support frame lifting frame is inoperable and the unit must be placed in service, gasket compression may be achieved by utilizing wooden wedges between the filter support frame and the lifting platform. Ensure even filter _ gasket comgression.
- 13. Install a new roughing prefilter.
- 14. Install the front and rear panels on the filtration unit housing. Ensure that the hand cranks are installed in the clips provided inside the covers.
(~( 15. Verify ~the differential pressure sensing lines are properly
\J connected as marked on the side of the filtration unit housing and the differential pressure gauges.
NAMNESET, a, , ,_
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- 16. Attach a Unit Readiness Verification Sticker, Figure 1
__across the closure seams on both the front and rear housing panels in such a manner that the sticker would be destroyed if either panel were removed or tampered with. Indicate
' co'mpletion of this step on FORM 1 (Figure 2). Ensure the appropriate use area is indicated on the sticker.' '-
- 17. Submit FORM 1 (Figure 2) to the H.P. Foreman for review and entry of the HEPA unit into the HEPA filtration unit control record, Data Package 1 as available for use.
4 NOTE Filtration units which have been serviced and are available for use will be stored in a locked cage on the Unit 2 TO 112' elevation.
- 18. Filtration units will be issued from the Health Physics office and this issure recorded on Data Package 1. _
- 19. Filtration units will be inventoried monthly and the service location recorded on Data Package 1 verified.
F. OPERATING PROCFOURE ,
(# \
- 1. Ersure all connections between containroent structure / tent are securely sealed.
- 2. After starting unit verify both the roughing prefilter/ spark arrestor and the HEPA filter differential pressuces are 6 1.5" H20.
- 3. Verify inward ventilation flow through the tent / structure inner airlock door.
- 4. Periodically monitor all filter differential pressures. If either filter differential pressure exceeds 3" H2O monitor filtration unit flow closely and service the unit during the next work stoppage.
- 5. Prior to electrically disconnecting the HEPA filtration unit at the completion of work requiring HEPA filtration unit ventilation or a filter change is imminent, obtain the data required by FORM 1 (Figure 2), steps 1.a and 1.b.
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FIGURE 1 UNIT READINESS VERIFICATION STICKER s
,, l. TliIS UNIT HAS BEEN SERVICED AND IS READY FOR USE IN AN UNCONTAMINATED /
CONTAMINATED AREA ONLY. (CIRCLE ONE)
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FIGURE 2
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tjEPA FILTRATION __ UNIT MAINTENANCE CHECK _,OEE__ LIST
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F_QQtL1 HCPA FETRATigy_tf1!T MAINTCNANQE CF((H,QFE LieT _ d
- 1. Pre-maintenance test operation data for KPA filtratson unst NO.___ .._.,_.
- a. Spark arrestor / roughing profilter differential pressure
- H20.
- b. HEPA filter differential pressure H".'.O .
- 2. FCPA filtration unit maintenance RWP NO. _____, .
- 3. FCPA ii1ter visua1 n5pect:on results igli11gilgglf9D131111gilgigs, (ctrcle ore) 4 HEPA filter acceptable for re-use gigggighlglyngiiggighlt.
(ctrcle one) t' 5. Spark arrestor screen cleaned . .
C. . HCPA filtration unst decontamsnated,
- a. Avaslable for use in uncontaminated areas. yes/no (circle one)
- b. Available for use in contaminated areas only. yes/no (circle one)
- 7. Unit Readiness Versficatson Stickers, Figure 1 installed on unit. yes/no (circle one)
- 8. HCPA (sitratten unit NO. avaslable for use.
Completed Dy . . _
H.P. Technscsan/Date d
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PROCEDLRC DATA PACKAGE coCuMEnT NO:. HrP epigd.,_- -..
SERIAL NO: ROO-PFL NO: _ N/A RTYPE:__Q15 14 XREF: N/A TOTAL SHEETS:__g
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FREQUENCY; As_Rgsg1ggd_
COMPLETED BY:
DATE COrfLETCO: .
I HA'.'C REVIEWCD THIS DATA PACwAGE FOR COMPLETErESC APO AGAIPCT ACCCPTArKC CRITEPIA IN ACCORDANCC WITH HrF-830.
ACCEPTADLC UNACCCPTADL E REVIEWCD DY CATE REVIEWP.J:
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FCPA FitJR_ATigP.t.If_41T_QO.rJTROL _ --
RECOPQ TYPC CCRIAL ARCA PC9 SON DATC AOSIGtG RETURfCD/ BY EQUIPMCNT NO. AS$!GNCD ASSIGPG BY AVAILABLE
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. PROCEDURE
_ Continuous Air Monitors Models AM-3D and AM-33-1 Operation and Calibration PROCEDURE TITLE HNP-8109 -
PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
APPRO*ED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER _
10 Pages 1. 3-5, 8-14 6 C 16 and 18 k T.
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PROCEDURE REVi!*; ION REGUEST
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ul Revision No. ___ /[_____
- REGUESTED OY DEPARTMENT HEAD FPROVAL Date: Signa u e-tJame: '
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v REVISION dtANGEG1hCD': OF CF ERATION GR INTENTy DESCRIGED ,IN FSAR:
$ ( ) Yes ( W No 7
Cl-lANGE NUOLVES: ( M either
( ) An unreviewed Gafety Question ( ) Tech. Specs.
(See back f o r- Safety Evaluation if required).
Non-Safety Related ( )
PRESENT STATUS: Gaiety Related (
The abour. Safety /Non-Safety Status har changed ( ) Yes to _______
Attach mar 4<ed up copy of procedure to this form.
REASON FOR PEGUEST: __ffff dh#fjjj d'(/jg t.- # ' ~
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SAEEIy._EVALLB. TION
_.Thi.L.rsti.fi.on._d_o_e..s._n_o t_c o_n_s_t i tu t e a n _u n rev i dwed s a f_e ty q_ u_e s_t i_o_n_a_s__e I. U*
t!elow.
L-_T..he probab.i.l..i_ty of occurrence and the consequences of an accident or
__'m..alfuncti._o.n. of eguip.m.ent im_p_o_r_ tant to safety are not increased above
~-
- 1.hp.pe analned. in the FSAR due to this revision because the r'evision p.qe.s_not change 'the purpose _ _ot,perf_omance of the qy/D _
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- i 5 --..-_2_-Th_q.y_o_ss_ibilit.y of a.n_ accident or malfunction of a different type than
. ara _1_yJed i.n the_ FSAR does not res. ult frcm this revision because the - _ _ _ . . _ _
_ . . _ _ - - r -
- ___.M. . - &tM. -re.sp.o._nd_s__a_nd_
is operated as before the revision.
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L, The maroin of safety, as defined in the Technical Specifications is
--.n.ot re_d_u_ced__due to this revision because the revision does not change any limited safety system settings which would allow a safety limit to be exceeded or allow a limiting condition for operations to be
! exceeded as stated in Technical Specifications.
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CONTINUOUS _ AIR MONITORG_MODELS AM-3D_AND AM-33-1 OPERATION AND CALIDRATION A. PURPDGE
, ~.
To ensure that the ' instruments are calibrated properly and to provide operation guides for the user. -
D. REFERENCES
- 3. Determination of Concentrations of Airborne Radioactivity, George L. Helgeson, Health Physics Journal 1963 Vol. 9, pp.
931-942, TDC #0E02 .
C. gAEEIY Observe Radiation Protection Procedures.
D. TEST _EOUIPMENT ,
bs 1. Minipulser MP-1 or equivalent
- 2. C1 check source and source holder
- 3. Da check source and source holder 4 Magnehelic gauge E. DESCRIPTION OF INSTRUMENT The NMC models AM-3D and AM-33-I monitors use a continuously moving filter paper so that replacement of the filter is required only infrequently. The Function of these instruments is to measure the radioactivity From air particulates and gaseous activity by concentrating these particulates on a filter, detecting, and graphing the activity on a graphic recorder.
In the AM-3D and AM-33-I, air is drawn through a special filter paper at a controlled rate. The build-up of activity on the filter paper is detected by a Geiger-Mueller detector which, in turn, operates a count ratemeter, solid state voltmeter alarm system and a graphic recorder. The alarm system in the AM-3D and AM-33-I particulate channel provides two levels of alarm based g
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(_ Spon the level of radio-activity. A high level alarm provides for continuous sounding of a loud bell or sonalert and operation of a_ red lamp. The low level alarm is used as a fail-safe indicator that the detectable radioactivity is below that expected in a properly functioning instrument. This provides a can' tin u'ous l y lighted amber lamp.
~ .
In addition to part~iculate air activity, the model AM-33-I also monitors the filtered air for iodine and gaseous activity. These gases are collected by a fixed activated charcoal cartridge. The Iodine-131 activity build-up on the charcoal cartridge is detected by a scintillation detector. The scintillation detector is coupled to a single window spectrometer system. The spectrometer is provided with a window-width' control and high voltage control that is. set at the Iodine-131 energy base.
The AM-33-I incorporates a discriminator system, count rate meter, solid state voltmeter alarm system and a graphic 2 channel recorder. The AM-33-I iodine channel has a single (high) alarm system based on the level of iodine and gaseous activity _
deposited on the charcoal cartridge. This high level alarm provides for continuous sounding as previous described.
F. DGSCRIPTION OF CONTROLS
~
() 1. External Controls
- a. Master switch - Turns power on to the counting ratemeter and moving filters drive unit.
- b. H.V. switch - Turns on high voltage for detector operation.
- c. H.V. Test switch - Displays the detector voltage on the rate-meter (AM-33-I).
- d. Input Mode Switch - In the TEST position, inserts a 3600 CPM signal to the ratemeter input for instrument check. In the OPERATE position it places the GM detector in service for normal operation.
- e. D, and Du switch positions are the boundries of the spectrometer window and operate from the gamma scintillation probe, (AM-33-I).
- f. N. switch position is the window position and normal operating condition (AM-33-I).
- g. Window Width Switch-Provides 11 window levels from 0 to 5%. The instrument is optimized for the 5% window f- (setting 5). This setting should be used unless there
(_)3 is significant interferente from some other emitter with an energy peak close to that of iodine 131.
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- h. Alarm Reset Pushbutton - Resets the alarm circuit after
-, alarm condition.
- i. ~
Meter Reset Pushbutton - Resets the meter to minimum when depressed. .. -
~
- j. Blower Power Switch - Turns blower ON or DFF.
- k. Continuous-Stepwise Switch in CONTINUOUS position, filter paper advances continuously. In STEPWISE position, filter paper advances only when the Fast Advance.pushbutton is depressed,
- 1. Magnehelic gauges:
(1) AM-3D Indicates air flow rate through filter paper. An adjustment screw on the guage provides adjustment of the flow rate control. Clockwise adjustment increases the flow rate. -
(2) AM-33-I (Photohelic) Indicates air flow rate through filter paper and charcoal cartridge assembly. Flow rate adjustment is accomplished by
- dual set point controls. The lef t set point
(_s) control governs the minimum flow rate setting.
The right set point contrcl governs the maximum flow rate setting.
- m. Flow jag indicator lamps- mounted on the right end of the cart. Yellow lamp ON continually indicates blockage of filter paper. Red lamp ON continually indicated rupture, loss of filter paper or a leak in the system.
- 2. Internal Controls
- a. H.V. Adjust - Allow setting of high voltage on G.M.
i tube.
- b. High potentiometer - Adjusts high alarm setpoint on alarm assembly module.
- c. Low potentiometer - Adjusts low alarm setpoint on alarm assembly module.
- d. The AM-33-I monitor is labeled "I" or "G" to indicate iodine or G-M detectors adjustment.
- e. Bias potentiometer - Calibrates low end of ratemeter
/~i scale.
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- f. High potentiometer - Calibrates high end of ratemeter scale.
'g . Low potentiometer - Calibrates mid-scale of ratemeter scale.
~ '-
G. OPERATION OF_ INSTRUMENT
- 1. Install filter paper roll per instructions in paragraph 5.7. Instruction-Manual (AM-3D) or paragraph 2.1 (AM-33-I) also insert the charcoal cartridge in the detector shield plug. (AM-33-I).
- 2. Switch the Continuous-Stepwise Taggle' switch on filter transport mechanism to CONTINUOUS.
- a. The filter paper speed can be varied for either monitor as per paragraph 4.7.1 (AM-3D) or paragraph 1.3 and programming key on Drawing # DOO5923 (AM-33-I).
- 3. Plug the instrument into a 115 V.A.C receptacle.
- 4. Switch the Olower Power switch to CN. Adjust air flow rate to 5 CFM using adjustment on Magnehelic gauge after about 24 7 hours of operation (AM-3D). Adjust AM-33-I photohelic.
(,3) gauge flow set point controls to 3.5 CFM and readjust after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if necessary.
- 5. Switch the Master Switch to ON.
- 6. Place the Input Mode switch to TEST and observe count ratemeter and recorder. Reading should be 3600 1 400 CPM, if not report findings to the Health Physics Foreman.
- 7. Switch the High Voltage switch to ON. The red indicator light should be on.
- 8. Return the Input Mode switch to "OP" (AM-3D) or "N" (AM-33-I).
H. INTERPRETATION OF 1NSTRUMENT RESPONSE
- 1. Dackground Radioactivity The normal. background before collecting may be in the vicinity of 50 C/M. Upon collecting, this count will rise rapidly due to the presence of radon gas and its radioactive daughters in the air. The count should rise to a level between 100 and 5000 C/M, depending upon the environment, the air cleaning used in the facility and atmospheric conditions at the time. This is an exceedingly sensitive
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A fail-safety alert level is set at 10-50 C/M. Whenever the
--counting meter indicates below this level, the amber lamp on
' top of the instrument cabinet will light. This is to show that the instrument is operating below the preset level.
, The amber light will also remain lit after changing or upon
,~
advancing the filter paper.
- 2. Long Half-Life Radioactivity In the moving filter CAM, the GM tube only " detects" one half of the activity at any given time because as the paper moves into the suction area, it is just starting to collect particulates, whereas, as the paper moves out of the suction area, it has collected its maximum number of particulates, hence, a factor of 2 is needed to correct for this.
Furthermore, the sampling time is limited, i.e., after the filter paper has moved out of the suction area, it stogs collecting _particulates. -
The following formula (1) applies:
C = 5.3 x 10 ~ OAs Where C= Concentration in uCi/cc Fga A= Count rate in CPM
(,)s s= Speed of filter paper in in./hr.
a= Suction area in inches F= Flow rate in SCFM g= Detector efficiency The speed of the filter paper is set at one (1) inch per hour. Ghorter speeds can be set; however, a speed of one inch per hour allows greater sensitivity and the added ability to earlier detect changing air concentrations.
The above formula (1) is derived with the ba,ic assumption that airborne radioactivity concentrations are constant during the sampling period of concern. Sudden changes in airborne concentrations will be discussed later.
The average efficiency of the AM-3D, and AM-33-I continuous air monitors is about .20 (20.0%) and .080 (8%)
respectively. A concentration vs count rate graph is attached to each unit. Thus, during periods of " static" conditions the average air concentrations can be determined. By applying the filteg speed and 104,5x 103, CAM detectgr10 efficiency and substituting 10, 10 , ,
and 10b counts per minute respectively we can exhibit the average concentration for a given count rate.
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See Title Page 6 of 18 V("A Substituting formula (1).
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~ Column 2 (5.3x10-0 )(1) (cpm)* = uCi/cc=(2.65x10 )(cgm 1 (5)(0.2)(2) (factor for 20%
efficency)
- Am-3D -
Column 3 (5.3x10~O )(1) _ (cpm)*=uCi/cc= (5.3E~O) (caml (3.5)(.080)(2) (factor for 8%
efficency)
AM-33-I
- Instrument background has been subtracted.
TAOLE 1 COLUMN 1 COLUMN 2 COLUMN 3 A (cpm) c(uCi/cc for AM-3D) c(uCi/cc for AM-33-I) 10 2.65x10-12 9.46x10-13 ~
100 2.65x10-11 9.46x10-12 1,000 2.65x10-10 9.46x10-11 1,320 3.49x10-10 1.24x10-10 1,600 4.24x10-10 1.51x10 .10 10,000 2.65x10- 9 9.46x10-10
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s-i 50,000 1.32x10- 8 4.73x10- 9 10 5 1.32x10- 7 4.73x10- 8 10 6 2.65x10- 7 9.46x10- 8
- 3. Rising Air Concentrations Formula (2) C = 0.1Gx10~'O (A) fgts Assumes that the cor.cen t ra t io n is constant only over short intervals. We can determine the rate of rise in cpm / minute and t (sample time) becomes 1 minute (for graph interpretation).
By this method we can observe any portion of the rise or peak activity and determine the concentration for that period. For example: If the air concentration for any given CAM rose from a " static" condition of 200 cpm to 1200 cpm in 10 minutes then:
Average rate of rise = (rise) (static) = 100 cpm / min (in cpm / min) 12OOcam - 200 cgm (o A) 10 min.
(rise time)
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C= (.1Gx10~ ) (A) Where: C = Concentration in pCi/cc fgts A= cpm Formula (2) F = Flow rate in SCFM g = Detector efficency t, = Sample time The above formula may be reduced by determining the average rate of rise as previously mentioned.
Then: C= (.1Gx10~I") (4LA1 Where: AA= cpm / min.
Fg Gubstituting'the detector efficiencies and flow rates of the AM-3D and AM-33-I CAMS the following results in Table 2 can be graphed.
Column 2 (.1Gx10~') (cpm / min)~= pCi/cc = (1.GOx10-")(cgm / min)
Fg (factor for 20%
efficency) AM-3Ds Column 3 (.1Gx10~IO) (cpm / min) = pCi/cc = ( 5. 71 E - 8 ' ) ( cgm / min )
Fg (factor for 8% efficency)AM-33-I
,, TADLE 2_ ,
COLUMN _1 COLUMN 2 COLUMN 3 c(pCi/cc for AM-3D) c(pCi/cc For AM-33-I) c(pCi/cc for AM-33-I)
(PARTICULATE) (PARTICULATE) (IODINE) 1.GOx10-10 5.71x10-10 8.79x10-10 4.80x10-10 1.71x10- 9 2.G3x10- 9 8.OOx10-10 2.85x10- 9 4.39x10- 9 1.GOx10- 9 5.71x10- 9 8.79x10- 9 4.OOx10- 9 1.42x10- 8 2.19x10- 8 8.OOx10- 9 2.85x10- 8 4.39x10- 8 1.GOx10- 8 S.71x10- 8 8.79x10- 8 8.OOx10- 8 2.85x10- 7 4.39x10- 7 1.GOx10- 7 5.71x10- 7 8.79x10- 7 8.OOx10- 7 2.85x10- G 4.39x10- G 8.OOx10- 6 2.85x10- 5 4.39x10- 5 The following rate of rise rates are equal to the administrative limits of 1x10-9 uCi/cc.
AM-30 AM-33-I Particulate D + Y activity 27 cpm / min 22 cpm / min Iodine-131 --
12 cpm / min s A rate of rise graph will be attached to each air monitor.
- 4. Determination of Airborne Iodine Concentrations.
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- a. The Model AM-33-I air monitor incorporates a scintillation detector and fixed charcoal cartridge to access the Radio-iodine levels. Gecause the collecting media is fixed and the collecting efficency for Iodine is not 100% the following formulas are necessary to Collection '-
determine the airborne concentrations.
efficency'of the F & J cartridge is 99% or O.99.
For " Static" conditions where there is no appreciable rate of rise formula (3) applies; Column 4 C=(1.6x10~" )(4A1 Where: AA= cpm / min (F) (dts)(g)(Ce) F'= Flow rate in SCFM At3 = Sampling time min.
g = Detector efficency Ce = Filter Media Collection Efficency C = Concentration in uCi/cc. -
Dy assuming the flow rate, detector efficiency and filter media collection and the absorption factor is accounted for during detector calibration formula (3) can be reduced to: ,
I_._ i C = @(i Where M' = 1Gx10'
- tg FgCe 40 Then k' .1Gx10 = 5.77E-11 and C =A (5.77E-111 (3.5)(.08)(.99) tg F g Ce From the above data the average Iodine-131 airborne concentration can be determined. For example, if
" Static" conditions exist (slow rise or no rise on the chart 6 10 cpm / min). The counting rate is 200 cpm and the sample has been on for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> then:
(2OO)(5.77E-11)_ =9. GEE-11 uCi/cc 120 min.
- b. The average concentration for a change in airborne activity may be determined by subtracting the stable airborne concentration from the peak concentra tion and dividing the difference by the elapsed time period of stable and peak activity. Use formula (1) to determine the results.
(concentration at tg - concentration at t 1 = AA t - t, (in minutes)
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'~
t, = static condition time t
2 = peak condition time For example, over the last two hours the counting rate for Iodine-131 has risen from 0 to 200 cpm but over the last 30 --
minutes the concentration has risen from 200 to 800 cpm.
Then: _800-2OO)(S.77E-11)
( = 1.15E-9 uCi/cc 30 (t,g- t,)
A graph is attached to each CIM exhibiting a static condition and a rate of rise condition. The charcoal cartridge shouldbechangejwhenthecollectedactivity uCi/cc ( ~ 8500 cpm) in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
indicates a level of 5x10' The charcoal cartridge will be further assessed by leboratory counting methods. Normally the charcoal cartridge (CEGCO) will be changed once per week. The _
following graphs will be attached to the CIM:
Graph #1. Assumes the Iodine 131 concentrations are essentially constant during the collection periods of 2 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
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Graph # 2. Assumes the Iodine 131 concentrations are essentially constant during the collection periods of one to seven days.
Graph # 3 Assumes the Iodine 131 concentrations are constant only during short intervals, where t g is reduced to one minute. (rate of rise in cpm / min).
NOTE Gecause Iodine-131 has a long half-life, compared with ta,or t) (radioactive decay is not accounted for in the derivations) 3jtd is essentially zero and 4-2 j td = C*
= 1, alsotajts may be expanded neglecting all but the first tuo terms;
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Cj =
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FgCe(1-4.-2jts) FgCe gits - (Lits)21...)
(1-1+1! - 2 !
Cj = 0.16x10 LOA Formula (3)
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U Where: ts = sample time td = delay in minutes before the sample is counted Aj = the decay constant of a particular isotope.
Cj = concentration of a particular isotope.
A = cpm (counting rate on the filter media).
F = flow rate in SCFM. -
g'= detector efficiency Ce = collection efficiency of the filter media.
- 5. Other observations for moving and fixed filter CAMS.
- a. Down trend in chart recorder.
(1) This could be due to long half-life activity which has stopped forming and the filter is moving out of the detection area.
(2) A decrease in long half-life airborne concentrations. _
(3) Short half-life material decaying, showing a stop or decrease in activity.
(4) A combination of these reasons. ,
~
- b. Horizontal line straight across chart.
(1) Sudden increase in background from sources or casks.
(2) Extremely high airborne radioactivity.
(3) CAM Filter paper not moving, activity buildup.
I. CAM LOCATIONS AND OPERATION
- 1. The CAM units shall be placed in areas where the occupation factors and the possibility of airborne problems are most predominant.
l 2. If possible the CAM's should be placed near air exhaust vents to better assess overall airborne concentrations.
- 3. The CAM's shall be equipped with an air sample intake extension in that the sample collected is representative of a " breathing zone" for personnel.
- 4. The distance from the airborne source should also be taken into account.
fm
(_), 5. The alarm level shall be set in the following manner.
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- a. The CAMS shall be operated for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period to estabitsh a relative Ra-Th equillibrium.
- b. The CAM alarm point is set at the administrative level of 3.0 x 10-9 pCi/cc. The actuai alarm setting will ,
vary depending on Ra-Th concentration, area background and CAM e'fficiency. Using the long lived graph the number should be written 1500 cpm i 10%(AM-3D). For example, if the CAM background is 500 cpm and the 1x10'"9 pCi/cc criterion is equal to 1500 cpm then the alarm point is set at 2000 cpm.
The CIM alarm point is to be set'at'the administrative level of 3.0 x 10-9 pCi/cc. The actual alarm setting will vary depending on area background and cim efficiency. A rate of rise of 12 cpm / min or 720 cpm /hr is equal to 1x10-9 pCi/cc. (See formula 3 and its variations). It the background is 100 cpm then the alarm point is set at 820 cpm. -
J. CALIDRATION AND CHECMS
- 1. Daily or Shift Check n ~
(). a. Insure the AM-3D and AM-33-I air flow is maintaining a 5 and 3.5 SCFM flow rate; adjust as necessary. l
- b. Observe the chart and insure the pen is inking.
- c. Calculate the present air concentration using the appropriate praph (graph #1). If any spikes or a rate of rise is indicated determine the concentration during the rise and notify the H.P Supervisor (provided the rate of rise is or was in excess of administrative limits-3.0 x 10~9 pCi/cc).
- d. Insure there is a sufficient filter paper supply (24 inches per day) and draw a vertical line across the filter paper. The line is used as a reference point to determine if the filter paper is advancing.
- e. N,te the flow, concentration, date and time on the char t paper and initial the chart paper.
- 2. Weekly Check (AM-JD)
- a. Check flow rates oF cams and cim-cams to assure proper flow on magnehelic or photohelic guages and record on Q4TA SHEET 1, Data Package 1.
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- b. Place the Input Mode switch to TEST and observe ratemeter and recorder. Reading should be 3 GOO 1 400 CPM. Record results on Data Sheet 1, Data Package 1.
Weekly Continuous Air Monitor Check. Mark " TEST" on the chart paper, turn the pump off, and open or remove the detector shielding. - -
- c. Place radioactive check source provided to the center of the detector and check the instrument response and alarm setpoint. Record results and complete Data Sheet 1, Data Package 1. Note on the chart paper and insure the c/m meter and chart readout match. If the detecter efficiency is low, calibrate the' CAM in accordance with the Semi-Annual checks prescribed below.
For the Model AM33-I CAM, place the radioactive check source on the end of a metal rod and insert the source gently into the detector chamber. Insure the source is centered and against the detector window. Proceed a.s mentioned in the previous paragraph.
- d. After completion of the above checks return the CAM to operation and note on the chart paper the time, date and calibration completed by initial.
('}
~'
- e. The CIM (AM-33-I) may be source checked in the following manner.
(1) With the pump off, remove the filter holder-detector shield plug, remove the charcoal cartridge, and place the Da 133 check source in the filter holder-detector shield plug. Reinsert the detector shield.
(2) Check the instrument response and alarm setpoint.
Record the results and complete Data Sheet 1, Data Package 1. Note the results on the chart paper and check the count rate meter and chart readout coincide. If the detector efficency is low, calibrate the cim in accordance with the Semi-Annual checks prescribed below.
(3) Semi-Annual Calibration.
(a) Test Shop will calibrate the magnehelic or Photohelic on the cam or cim-cam (MR's are to be written by Instrument Techs) semi-annually.
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(b) Note on the chart paper the Semi-annual
__ calibration is occuring. Turn the instrument high voltage off and remove the probe connector.
(c) Connect the output of the Minipulser from
~ positive.(red lead) to pin "F" of the input connector (located on left side of probe -
connector), (AM-3D) Ground the other lead (black) to the frame. Remove the probe connector to the scintillation detector (AM-33-I) and connect output of the Minipulser from positive'(red lead) to pin "F" of the connector.
(d) Switch the input mode on the counting ratemeter to "OP" or D.
(e) Set the minipulser at 1.0 volt amplitude.-
Set the counting rate of the minipulser to 100, 1000, 10,000, 40,000, and 800,000 cpm.
Adjust the bias, low and high-end controls as s necessary to correspond to the input pulse
,3
) being generated. ,
V N NOTE Am-3D's scale reads to 50,000 cpm only.
Disreguard 800,000 cpm step.
.F) After this calibration insert the check source as prescribed in J.2 and perform a plateau check. (Instrument high voltage back on). See the instruction manual Section IV 4.4. If the high voltage plateau has not drifted and instrument efficiency is within 10% of the last efficiency check, return the instrument to operation. (AM-3D).
(g) The cim detector Iodine 131 operating voltage is set by inserting the Da 133 source as prescribed in Section J.2.e. With the input mode selector switch in "N" position, adjust the 10- turn high voltage control until the c/m meter indicates the optimum value. Then l set the high voltage control 1% lower than indicated reading.
(h) Replace calibration sticker and initial chart.
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~.
NOTE The AM-30 and Am-33-I is designed to measure -.
general air trends and changes in these trends.
~
Any unusual rises in airborne activity shou'd be .
verified by additional air sampling (high or low volume); isotope identification should be made and documented (by Geli count).
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PROCEDm E DATA PACHAGE DOCUPENT NO:JW-8109:1 .,
SERIAL NO:_R_11- .
MPL NO: __
RTYPE:_g15.14 XREF:
TOTAL SECTS: _2 FREQUENCY: Weekly .
COMPLETED BY:
DATE COMPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COPPLETENESS AND AGAINGT ACCEPTANCE CRITERI A IN ACCORDANCE WITH INP-830.
ACCEPTADLE UNACCEPTABLE REVIEWED BY:
DATE REVIEWED:,
REMARMS:
Page 1 of 2 FM -8103 R11 D.
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PROCCDURC OATA PACHAGC
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SCRIAL NO: R11-POL NO:_
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TOTAL SICCTS:
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I HAVC REVICLCD THIC DATA PACHACC FOR COMPLETDC50 AND AGAlfCT ACCCPTANCC CRITCPIA IN ACCOPDANCC WITH HNP-830.
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, . - - - _ - , .______-_________---4 PROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE s
FEAD MANAGER 2 Pages 1 - 7 - -
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PROCEEURE NO. HNP- f/3[__ _. SHEET,100F-/ ;
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Rev1oion No.__ d ^ 1. i:
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DErggTMENT HF/nD APPROWNL -
REGUESTED DY Date: Si n ture: Dat *.-
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REVISION CHANGES l'UDE OF CPERATION GR INTENT AS DESCRIGED IN FSAR:
< ( ) Yes ( No CHANGE IN'JOLVES:
( ) An unreviewred S,afety Question ( ) Tech. Specs. ( Jeither (See tiack F o r- Safe ty Evaluation if required). ,
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Safety Related (V) Non-Saf ety Relate'd'; f(w. :L) .
PRESENT GTATUS: .
The abour. Saf ety /Non-Sa-f ety Sta tus has changed ( ) Yes to -
At tach mar t<ed up copy of procedure to this form. ,
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SAFETY
-- EVALUATION. _
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1._Yeprobabilityofoccurrenceandtheconsequencesofanaccidentor malfunc_tig.n of_egu_,i,pment i important to safety,are not increased abo "
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4 d.qe_S_not change'the purpose oi performance of the system.
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The oossibili,ty of an a,ccident or malfunction of a different type tha i
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.gys.t.e._m_re.sp.o.nd_s and is operated as before the rev s on.
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The margin of safety,-as defi_n_ed in the Technical Specificatio -_
h not reduced due to this revision because the revision does not c an ld allovt a safety limit j
-.any limited _ safety system settings which wou s i
dition for operations to be -
--_..t_o_ be exceeded or allevt a limiting con
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, HAND AND FOOT MONITOR HFM-4A OPERATION AND CALIBRATION S i i 4, . ' PURPOSE
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/< .Tc.unsur,e that the instrument is calibrated properly and to w
provide operation guides to the user. -
B ., REFERENCE
- 1. Technical manual for hand and foot monitor, model HFM-4A.
TDC# 0519M l
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.1 j- C. SAFETY
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y Observe radiation protection procedures,
'Z **,O.* , -EQUIPMENT - g 1.- P-lO gas (10% methane, 90% argon). _
4 2.' (Electrostatic'ioltmeter.
i 3.' ' Assorted check sources.
E. DESCRIPTTON f) s 1. The HFM-4A provides a' fast 30/no go indication of beta" gamma
' contamination on the hands and shoes of personnel. The instrument design allows an individual to monitor himselF/herself.
The instrumant is entirely digital. All controls are interns 11y mou7ted. Indications as to the status of the instrument and whether a person being monitored has an
. unacceptable level of radioactive contamination are provided on the F-ront panel by solid state LED's and an audible alarm.
4 The instrument has three channels, esch monitoring I
beta gamma radiation. Each channel has a separate alarm
,'? switch for p. eta gamma. Each channel monitors Ats own j background continuously in pre-set time segments while the HFM-4A is unoccupied. The most recent background count is stored in memory and is subtracted whenever someone steps
> onto the HFM-41 to be monitored.
t; The electronics of the HFM-4A are solsd state, mostly integra+ a circuits. All major circuits are plug-in circuit boards.
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/m . a; V If. ' Indi c.ators:
, ,a. Front panel, visual
- 1. Counting. background yellow light-emitting diode.
(LED).
- 2. Counting activity yellow LED
- 3. Recount - red LED
- 4. Of( - green LED.
- 5. High background - red LED.
- 6. Fail - red LED
- 7. Hands beta - gamma - red LED.
- 8. Left foot beta gamma - red LED.
- 9. Right foot beta gamma - red LED.
- 10. Inlet gas flow - flow meter (20 - 240 cc/ min.).
- 11. Outlet gas flow - flow meter (20 - 240 cc/ min.).
- b. Front panel, aural: The Sonalert " squealer" is actuated when any of the following alarm conditions ,
exists.
- 1. Recount
- 2. High background
- 3. Fail
I^) 4. Ilands beta - gamma
- 5. Left Foot beta gamma
- 6. Right foot beta - gamma The Sonalert also " beeps" (approximately a 3OO -m i l l i s e c on d tone) when the count time for a person being monitored is complete and also if the gas inlet pressure falls below the recommended level.
- 3. ' Detectors
- a. General
- 1. Window thickness: 3 mg/cm2 aluminized mylar.
- 2. 4 pi beta efficiency: Approximately 20%
- 3. Gamma sensi tivi ty: Approximately 50,000 cpm /mr/hr.
- 4. Counting gas: P-lO (10% methane, 90% argon)
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LH (Lef t' hand) Simulate Switch: Perfarms the same j function electronically as the switch which is actuated when a hand is inserted into the left hand cavity. -~~
Dutton mu'st be depressed to accomplish function; used when monitoring right hand only. -
- b. PH Simulate Switch: Same as above except used when monitoring left hand only.
- c. Gas Flow: Screwdriver slo + gas flow control valve used in conjunction with the frant panel mounted flow meters '
to set gas flow rate through detectors. -
- 2. Back panel
~
- a. 115/230 VAC Switch: Change: the configuration of thy power transformer primary +3 appropriate for the e indicated voltage. ,
- b. Power: Turns instrument ON and OFF.
- c. Reset Start: Resets c o u n i. . g circuits to zero an) starts new count when CYCLL switch is in the MANLAL position. -
- 3. Intern Control board (10721 00)
- a. GPN (operational) MODE swi -h - determines the channel er combination oF channels or which the counting
. ctrcuitry is active: [EE i UANDG OR FEET AND HANDS.
- b. MODEL switch - Provides th- Logic manipulation required by the instrument. Model _utch should be set for MODEL "A".
- c. CYCLE switch - In the "AUTE" position, all sensor switches are interlocked i M the counting electronics. In the " M A N U f- _ " position, a new counting cycle is initiated by the ". SET - START switch.
- d. DISPLAY switch - Enables 7parator to choose which channel is displayed on tF- internal 4 - digit beta -
gamma display. Instrument also designed for ALPHA detection, but alpha logic as been omitted.
- e. LINE FREGUENCY switch - Celects 50 or 60 Hz as n applicable for the in c omi r. ] lin y.
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t/ f. COUNT TIME switch - Selects, in the timing,cir,t'o- WC the proper output of a " divided - by" counteel cuitry@$CTK -'W?
provide either a 6 or 30 second count time..w dC ' ' ?$% .
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- g. TIME MULT switch - In the XI position the-count; time.5 71%.
selected by the COUNT TIME switch (above)~.is d ~ $2M4 unaffected. In the X2 position, the ~ count timeg signal :.[:fg-is put through a divide - by 2 counter andTeither a 12. -
or GO second count time is provided. ~, 6:5 * *-
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- 4. Internal - Channel Counter Ocards (10720-00) -
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- a. OETA - GAMMA ALARM digit switches - set into,tNe .
counting circuitry, a number which is added.todthe most..., '
recent background count. Iia'
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- 5. Internal - Large Mother Daard (10731-00) .?
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- a. SONALERT switch - in the ENADLE posi tion, provided to the Sonalert so that when an .alarmf% 5} Q-i.s ~
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p,#Chr;Q condition exists and a' path to ground isestelisheD4pW the Sonalert sounds. In the OFF position t W BlVDC M hy $
path to the Canalert is interrupted. hk .*~Qp'G 3MQ .
m.g G. Internal Amplifier / Discriminator Ooseds (10722qQQ) .f--' .E;&#f
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L/ a. ANT I --CON switch - In the IN position this switch ~
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controls the. output of one section of the amplifier.
- b. OETA - GAMMA TiiLD (threshold) potentiometer , varies the reference vo?.tage at the beta gamma-comparator. ,
- 7. Inte-nal - Small Mother Daard
~
- a. HI VOLTAGE switch - determines v.hether power is -
supplied to the high voltage power supply. ON or OFF.
- b. III VOLTAGE ADJUST potentiometer - changes the output of the high voltage power supply.
G. OPERATION _OF_INSTRUMELQ
- 1. With the power switch in the OFF position, and the=AC switch set to the appropriate line voltage, plug the AC power cord into an outlet. _
~
- 2. Ensure the gas Flow is at least JO cc/ min. -
- 3. Turn HI VOLTAGE switch on small mother board to the DFF position. Turn the POWER switch to the CN position.
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- h. At this time, the FAIL light will come on (due to no high 1 voltage at the detectors) if the HIGH BACKGROUND and RECOUNT
. lights appear, there is no need for concern. The condition
~ill w reset itself after 34 seconds.
- 5. ' Turn HI VOLTAGE switch to the ON position, FAIL light should
' ~~~
go out. ,
- 6. Instrument is now ready for use. -
- 7. Step onto instrument, place hands in hand cavity, and press down to start count cycle. COUNTING ACTIVITY L.E.D. should be on.
- 8. At the end of the count cycle, the O.K. L.E.D. will light and the Sonalert will sound. If contaminated, the " HANDS" or " FEET" L.E.D.'s will be on and the Sonalert will sound.
NOTE If contaminated, call Health Physics.
H. Weekly Monitor Checks
- 1. Observe gas flow and record on DATA PACHAGE 1. Fl ow -c,a te
() should be approximately 30 cc/ min.
- 2. Remove top cover or open cover door and place CYCLE switch j to the MANUAL position.
- 3. Adjust TIME MULT switch for a 1 minute count time.
- 4. Press RESET button on the rear of the monitor to begin background counts.
l S. When the counting light goes out on the front of the monitor, turn the display switch to channel 1 and record results on DATA PACMAGE 1 as background CPM for hands. Turn
, display switch to channel 2 and record results as background l
' CPM for left foot. Turn display switch to channel 3 and record results as background CPM for the right foot.
- 6. Adjust display switch to channel 1. Place source against the center of the outside left hand detector. Press RESET button. When the counting light go=s out record results on DATA PACKAGE 1 in the correct column.
- 7. Duplicate step 6 for inside left hand, inside right hand, and outside right hand detector.
- 8. Adjust the display switch to channel 2. Lay the source in
(~)'
'- the center of the left foot detector. Press RESET button.
When the counting light goes out, record resul+ in the correct column on DATA PACKAGE 1. %% 5f f, y
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k w) D. Turn display switch to channel 3 and repeat step 8 for right foot detector.
~~
- 10. Return CYCLE switch to AUTO position and TIME MULT switch for a 6 second count.
- 11. Step onto the monitor. Observe and ensure counting activity -
L.E.D. and 0.K. L.E.D. are operational.
- 12. Step off the monitor and ensure BACKGROUND L.E.D. is l operational.
- 13. Step onto the monitor. Lift left hand before counting time expires. Observe and insure the RECDUNT light comes on.
- 14. Duplicate step 13 'for the right hand, right foot, and left foot.
- 15. Place source in left hand detector side. Activate counting mode, and ensure alarm and lights comes on for hands. _
Record results on DATA PACKAGE 1. Perform the same procedure on the right hand detector.
- 16. Remove protective covering from foot detectors and repeat Step 15 for each foot detector. .
- 17. Record alarm set points on channel boards on DATA PACKAGE _1.
- 18. Install top cover or close lid and return instrument to service.
- 19. Replace paper covering on foot detectors if necessary.
- 20. Complete DATA PACKAGE 1, calculating efficiency of the detectors. If any detector efficiencies are less than 20%
or greater than 50%, repair or replace detector. Allow new detector sufficient punge time. Then repeat section H.
NOTE Alarm set points will be determined by a Laboratory Foreman using 20% worst possible detector efficiency before detector would i
be changed.
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PROCEDURE DATA PACHAGE DOCUMENT NO: HNP-8135-1 SCRIAL NO: RO3-MPL NO:
RTYPE: 015.14 t
XREF:_
TOTAL SiiEETG:_Q FRCGUCNCY:
COMPLETED DY:
DATE COMPLETED:
I HAVC REVICWD THIG DATA PACl(AGC FOR COMPLCTENCCG ANO A';AINGT ACCCPTANCE CRITCRIA IN ACCORCANCC WITH HNP-330.
ACCEPTARLE UNACCCPTABLE REVIEWCD DY:
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LOCATION: ,,,_ M.P.L. NO: SERIAL NO:
SOURCC NO: COURCE D.P.M.
GAS FLOW: cc/ min GAS PRCMC: _
BACHGROUND CFECHG:
HAPOS cpm; LEFT FOOT cpm; 'RIGHT FOOT cpm MCC.,CLC, Clig:
SOURCE CPM-BKG DIVIDE SOURCE DPM X 100 - EFF. .
REIECIER source CM._CEU__EECauCPM; SOURCE @ d..QEIECICE_EEE- 6LaEU.SEI ECE L.H. QUISir#
L. H. INSIDE R. H. INSIEE L H. MITSICE tEFT FOOT EICHT FOOT Og Nl tmc IF DCTECTOR CFFICIENCY IG LESS THAN 20% OR GRCATER TilAN 50%, REPAIR OR REPLACC DETCCTOR.
& ARM CHCCM9:
LCFT HAND: ACCCPTAGLE UNACCEPTADLE RIGHT HAND: ACCCPTABLE UNACOCPTACLE LCFT FOOT: ACCCPTADLE t.rJACCCPTADLC RIGitT FOOT: ACCEPTADLE Lt4ACCCPTACLC COMPLFT2D GY: __, DATC t
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RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )
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APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 0 NEW PROCEDURE
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Revision No. 2.,
REGUESTED BY __ DEPARTMENT HEAD APPROVAL h Name:. Date:
Signeture: Date: .
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REVISION CHANGES MODE OF CPERATION OR INTENT. AS/ DESCRIBED IN FSAR:
- { $*.' ( ) Yes ( d No e
CHANGE INVOLVES:
l ( ) An unreviewed Safety Guestion ( ) Tech. Specs. ( d Neither l (See back foe Safety Evaluation if required).
?
, PRESENT STATUS: Safety Related ( /) Non-Safety Related ( ) ,
The abovr. Safetv/Non-Safeiy Status has changed ( ) Yes to -
Attach maeL<ed up copy of procedure to this form.
REASON FOR REGUEST: T~e h M k b -\ %. _ b w s b 6 4 M A b o h e_ % e.
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Revision N'o, 3
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'[ REGUE5IED_BY DEPARTMENT WEAD APPROVAL Name-: Date: Signature: Date:
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.. REVISION CHANGES NGOE O!~ CPERATION OR INTENT 6 DESCRIGED IN 'FSAR: -
(~ ) Yes ( , No I
t i CHANGE INVOLVES: ,
i ( ) An unrevieweri Safety Guestion ( ,A -Tech. Specs. ( ) Neither I- (See back for Safety Evaluation 'f required). .
. PREEENT STATUS: Safety Related ( ; Non-Safety Related' ( )
/
The abour. Safety /Non-Safety Status has changed ( A Yes to -
Attach mar'ed w up copy of procedure to this form.
PEAEON FOR REGUEST: h MA%%d --
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PRO RECCMNF OS APPROVAL: (dVes ( )No V PR9 Secretary T8 8 - l 8 '9 y _f 9.g3
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PRB Number Date
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s i ----SAFETY EVALUATICN
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' __This revi_s_ ion does,_no_t con _stitute ar unresidwed safety'qtiettion~as explained
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- 1. . The probability of occurrence and the consequences ofTan' accident or 4 W. M,&
3 - .Ja.lfunction_o_f_.egu_i.pment important to safety cre.not$ increased above I i.i ,
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tj)pse anaj p_e_d_in the FSAR due to this revision because the revision l3
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_svstem resp _ond_s and is operated as before the rev nion'. ,
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- 3. The mar _qin of safety _ as defined in the Techr.ical Specifications is
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_ _,. any limited safety system. settings which would,a.llow a safety limit be exceeded or allow a limiting condition 'for 'o erations to be
- -...to-ex_ceeded as_ stated in Technical Specifications.
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dL OPERATION OF WASTE SEPARATION AND TEMPORARY STORAGE FACILITY
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A. PURPOSE The purpose of this procedure is to provide instructions in the -
operation of the waste separation and temporary storage facility.
D. SAFETY Observe Radiation Protection Procedures.
C. REFFRENCES HNP-8012 HNP-801G HNP-8028 D, GPFCIAI EGUTPMENT _
- 1. Appropriate survey instruments.
- 2. Appropriate protective clothing.
- 3. Appropriate signs, placards, and labels.
E. DETERMINATTON OF MATERTAL O TO CE TRANCFERRED TO THE WAGTE GEPARATION AND TEMPORARY OTOPAGF FACILITY-(WS-TGF)
- 1. All waste transferred to the WC-TCP will be transported in such a manner as to prevent the release of contamination to the environs during transport.
- 2. Liquids should not be transferred to the WG-TGF. This includes wet or damp mop heads, rags, 3 .- oil soaked blankets. Transfer of any liquids must be approved by the H.P. Supt. or his designee.
- 3. Each bag or piece of material should be surveyed by a Health Physics Technician prior to leaving the operating buildings. HNP-8020.
- 4. There should be no external surface con tamination on the container. Also, no waste reading in excess of CG mr/hr contact will be transferred to the WC TOF wi thou t the approval of the Health Physics Guperintendent or his designee.
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- 5. Each container or piece of material must be labeled with a Radioactive Material label containing the following information:
- a. A general description of the waste.
b.- Surface contamination results.
- c. Highest contact dose rates.
- d. Date
- e. Surveyor's name.
NOTE Any material with a contact dose rate greater than 50 mr/hr must be taken to the Unit II -
radwaste trash compacting area on the R/W 132' elevation, unless exempted per Paragraph E.4.
F. TRANSFER Gr WAGTE TO Tite WAGTE GEPARATION AND_TEMPGRARY' STORAGE FACILITY (tjg;TgF1
- 1. Material shall be -transported to the WG-TGF by truck or other appropriate means. The vehicle will be loaded in an area designated by a llealth Physics foreman or supervisor.
C. During the loading, transporting, and unloading of waste from the vehicle, the vehicle shall be posted " Radioactive Material" on the front rear and each side of the vehicle.
- 3. _After the loading of waste onto the transport vehicle has been completed, the vehicle shall be locked and sealed and shall remain locked and sealed, until the commencement oF un)oading at the WS-TSF. If transpor.t vehicle is a flat bed trailer, locks and seals do not apply.
- 4. The vehicle shall ce surveyed prior to leaving the protected area. Dose rates outside the vehicle should be within limits specified in D.O.T. regulations. If no t, notify the Lab Supervisor for approval to proceed with the transfer.
Gurvey results will be documen ted on Figure 1 of HNP-8012.
- 5. The vehicle should travel unimpeded and by the quickest route to the WS-TOF. There shall be no unauthorized stops along the way. Emergency stops (such as mechanical failure, flat tire, etc.) shall require the immediate notification of a Health Physics Foreman.
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- 6. After the vehicle has been unloaded, a survey shall be
__ performed. The interior of the vehicle or the surface of the flat bed trailer will be smeared for surface contamination, Survey results will be logged on Figure 1 of
- procedure HNP-8012.
G. RECEIPT OF WASTE AT*THE WASTE SEPARATION AND' TEMPORARY STORAGE FACILITY -
- 1. Upon receipt of waste at the WS-TSF, all waste should be separated or classified according :o dose rate and type of waste.
- 2. Waste reading less.than 5 mr/hr should be set aside for processing by the waste separation facility. Waste reading greater than 5 mr/hr should be prepared For shipment for burial.
- 3. Non-compactable waste should be set aside for packing B-25 shipping containers or equivalent.
- 4. Compactable con taminated waste should be set aside for compacting.
- 5. All bags containing waste should be opened and investihated for salvageable protective clothing and equipment.
NOTE
/iny deviation From the above guides requires approval From a Health Physics Foreman or Supervisor.
- 11. WASTE SEPARATION
- 1. Dags of waste reading less than 5 mr/hr contact should be opened and the waste should be placed on the waste sorting tables for inspection.
- 2. All waste shall be scanned with an RM-14/MP-210 probe or an E-120 or equivalent. Waste found to be reading 100 cpm above background at one half inch will be considered contaminated and will be processed as Radioactive Waste.
The remaining material will be placed in green plastic bags and sent to the landfill as non-contaminated trash.
- 3. Before any clean waste is released to the landfill, each bag is to be checked with a micro-R meter or a PRM-4A/ SPA-3.
This check is to be performed at the landfill by an ANSI qualified H.P. Any bag of clean trash reading greater than two times background will be returned to the waste separation facility for reprocessing.
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- 4. A written log will be kept of all materials leaving the
_ WS-TSF as non-contaminated trash. This log should contain:
- a. Date b.' lime
- c. Number of bags of trash ~~
- d. Type of trash
- e. Surveyor's name
- f. Instrument serial number I. PROCESSING OF RADIOACTIVE WASTF
- 1. All radioactfve waste packaged for shipment will be in an appropriate DDT shipping container. Non-comgactable waste is normally packaged in 0-25 or equivalent shipping containers. Com2 actable waste is normally packcged in 0-25 or equivalent shipping containers and/or DOT 17 H 55 gallon drums when compacting in a D-25 box place all material greater'than 20 mr/hr in the center of the box in order to limit the surface dose rates. The highest average-reading on all sides of the boxes should not exceed 100 mr/hr.
- 2. All shipping containers will be labeled with a radioactive materials sticker and the following information: ,
- a. I.D. number
- b. General des crip ti on o f contents
- c. liighest contact dose rate
- d. Container. contamination levels
- e. Gross weight
- f. Date and surveyor's name
- 3. A written record will be kept on each package or container.
See Data Package 1, Data Sheet 1.
- 4. Containers should be numbered cons 7cutively with the numbers preceded by HNP and the year.
Example: HNP-82-1 UNP-82-2
- 5. Radioactive LSA stickers will be placed on two opposite sides of each con taine r.
G. Containers should be stored in such a way as to limit exposure and allow easy access.
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- When containers are shipped, Ne containers that were gacka_ qed :-
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J. ROUTINE GURVEYS -
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- 1. Routine contamination and radiation survey nwill be performed at least once per day during mamiing of the facility or following any event which might cause a change in conditions. Curvey results are to be logged on Figure 1, 2, or 3 of HNP-8012.
k-K. RADIATION ANC CONTAMINATION CONTROL Tn - -
L-
- 1. Personnel working in the WS-TOF will be'requiredLto wear pocket dosimeters and TLDs at all times. . i;{ ,
- 2. All entries into a radiation controlled areaLinside the W3-TGF will require an RWP (Radiation Work Permit).
J. All exits from contaminated areas will have[ step-offpads and frisker stations. Any p e r s on e x i ting .~al contaminated area r,ust perform a whole body frisk.
NOTE .
T Any material leaving or taken out-'
of the WC-TCF must be surveyed by~an-H.P. staff person.
- 4. The storage area will be inspected monthly for signs of container deterioration or leakage. Appropriate corrective action will be taken 10 damaged containers are found.
Documantation will be on Data Cheet 2 of Data Package 2.
- 5. Any water that accumulates in the F-loor sump _.will be sampled and analyzed by Health Physics. If the liquid contains radioactive material other than natural radioa'ctivity, it will be transferred to the radwaste system for processing.
When liquid is found, the source should be identified and stopped. .
G. When the building is not in use, llealth Physics will perform a survey of the building interior en a weekly basis.
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' DOCUMENT NO; HNP-0400-1 SCRIAL NO: P03-MPL NO:
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FREQUENCY: As Reggired COMPLETCD DY:
DATE COMPLETED:
I HAVC REVIDED TitIG DATA PACMACC FOR COMPLETCrCOG AND AGAINGT ACCCPTANCE CRITERIA IN ACCCaDArtCE WITil HNP-830.
ACCCPTAOLE tr4ACCCPTADLC PCVICWCD OY:
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DATA PACNAGE 1 Q6Io ELSEI_1
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ITEM WAGTE MR/HR WT. STORAGE DATE DATE-
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I HAVC REVIDED TIII" DATA PACl(AGC FOR COrCLCTCtC".G AND As;AINST ACCCPTANCC CRITERIA IN ACCCRDANCC WITH HNP-830. -
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STORACF ARCA MONTliLY INGPCCTION SHECT ,._
INCFCCTOR: DATE: ,
ACCEPTr.0L; UNACCEPTABLE TRAQi OR DCDRIS DUILDUP (ADDITIONAL EMPHASIG ACOUND WORM ARCAS)
DCTERIORATION OF CONTAltCRG (i.e. RUST,llOLES, ETC.)
PROPER POOTING M ERE APPLICA0LE DOCE RATCG ##C WITHIN LIMITG POOTT D GPILLS (WATER OR DIL)
GENERAL CLFANLINCOS NOTC IF UNACCCPTAOLE. NOTIFY AN tP FOREMAN I M DIAT Q'/.
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PROCEDURE
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Model RD-2A O E eration And Calibration -
PROCEDURE TITLE HNP-8137 PROCEDUR5 NUMBER - - ,
Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-UAFETY RELATED ( )
APPROVED APPROVED HEV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER
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PROCEDURE NO. HNP- ff/[7 SHEET 1 OF___
Revision No. /
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D'sPETdENT FEAD APPROVAL
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REVISION .HANGES inODE OF CPERATION OR INTENT ( d 'o IS DESCRIGED IN FSAR:
( ) Yes CHANGE INVOLVES:
( ) An unrevieu.>ed Safety Guestion ( ) Tech.Spbcs. ( N eithee (See back for Gofety Evaluation if required).
PRESENT STATUS: Gaiety Related ( V Non-Safety Related ( )
The abovs. Safety /Non-Gafeiy Status has changed ( )~Yes to -_
Attach marked up copy of proc: dure to this form.
t.;ss REASON FCR REGUEST: OI ;f[ r//j&'j; My #& C M /' /
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d , ,,,,,, EAFETY EVALUATION tion as explained This revision dces not constitute an unrev 7
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below. -__ __ __ - _ .
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1hT.heproba_bilityofoccurrenceandtheconsequ_e_nc_es_o_fanaccidentor _ ._ _ ___
" malfunction of equipment __important to safety _are not increased above _
those__analyled_ in t'he FSAR due to this revision because the revision d.o_e.s not change 'th_e purpose oQerfortnance of the system. --
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ana_1yJed in the__FSAR does not result from this revision because the __
.s.rst_em re.s..gond_s and is operated as before the revision.
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L,_The margin of safety as defined in the Technical Specifications is reduced due t_o this revision because the revision does -__ _ riot - _ change
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.a..ny limited safe _ty system settings which would allow a safety limit to be exceeded or allow a limiting condition for operations to be
..e.x..ceeded as _ stated in Technical Specifications.
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x_s PORTABLE ION CHAMBER _
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MODEL RO-2A OPERATION AND CALIGRATION A. PURPOSE - -
To insure instrument is calibrated properly and to provide guides -
for the user.
B. REFERENCES
- 1. Portable Ion ~ Chamber Model RO-2A Technical Manual, TDC #538. l
- 2. Gamma Calibrator Procedure.
C. SeEEIY Observe Radiation Protection Procedures. _
D. TEST EOUIPMENT
- 1. Gamma Calibrator.
~
/'4 2. Calibrated Deta Source.
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- 3. 92 mci CS-137 Source.
E. DESCRIPTION OF INSTRUMENT The_ Ion Chamber, Model RO-2A, is a portable air ion chamber instrument used to detect beta, gamma and X-ray radiation. The RO,2A has four linear ranges of operation to measure dose rate.
The ion chamber is vented to atmospheric pressure and is specifically designed to have Flat energy response into the X-ray region.
F. DESCRIPTION OF CONTROLS
- 1. Function Switch: Eight position rotary switch that turns the instrument OFF, checks the condition of the batteries, checks instrument ZERO, and selects the range of operation to be used.
- 2. ZERO Mnob: Used to set the meter to zero when ZERO switch position is selected, or when in an insignificant radiation field.
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- 3. Calibration Controls: Four variable resistors, or.e for each
. range.
G. TERATION OF INSTRUMENT
- 1. Turn the function switch to DAT 1, and then to DAT 2 -
position. The meter should read above the SATT cut-off line in both cases. -
NOTE If BAT check on any range does not indicate good, tag instrument out with TO SHOP tag.
- 2. Turn the function switch to ZERO position. Check that the meter reads zero. If not, set it to zero with the ZERO knob.
- 3. Get the function switch to the desired range of operation.
The switch position selected is the full scale reading of_
that range.
NOTE When selecting the most sensitive range 50 mr/hr switching
(~} transient noise may cause a-temporary deflection of th'e
\> needle. This can be avoided by turning the function switch through the ranges slowly stopping at the 300 mr/hr and letting the needle settle, and then switching to the 50 mr/hr range.
- 4. When measuring beta or low energy gamma or X-ray emissions, open the sliding beta shield on the bottom of the case and Face the bottom of the instrument toward the radiation source. To open or close the shield, depress the friction release button on the left side of the case ano manually move the slide or let it fall due to gravi ty. When the shield is open, protect the thin face agaxnst damage by puncture and radioactive contamination. .
NOTC The effective center of the ion chamber is marked by dimples at the front and sides of the instrument case.
The zero setting oF the instrumen t may be checked in radiation fields by merely selecting the ZERO position.
Gince the ion chamber is vented to atmospheric pressure, it is sensitive to changes in both air pressure and temperature. Tables 2-1 and 2-2 in the Technical Manual 7s gives correction factors which should be used if the
() instrument is used in conditions of significant differences
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from the calibration conditions.
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H. DOSE RATE INTERPRETATION
- 1. ~ Gamma radiation.
a.. When no significant difference is seen in the needle deflection with the beta wi.>dow open-and the beta .
window closed, the radaation should be reported as gamma only. When high gamma dose rates are present low beta dose rates may go undetacted unless a smear is taken and removed From area and surveyed for beta dose rate,
- b. When significant differences are seen in the needle deflection with the beta window open and beta window closed, the gamma exposure iate is the meter reading with the beta window shut. The indicated beta exposure is the difference between tr . reading with the beta window open and closed.
00IG The meter reading above wit. reflect true dose rate exposure only for true tie' dose rate. This is when the intensity of the radie* un in all parts of the
, ^) chamber is practically the me. .Cmall beams, point
\_f sources, and small line :c ues will give meter readings less than actual e assure rates and must be evaluated on an trit.idual ' a :> i s .
- 2. Beta radiation.
The beta contact dose rate for r source at least as large as the window on the PO-2A is meter eading window open less meter reading window closed tim:_ beta correction factor on the side of the instrumen+.
UCIE The beta correction factor only for a source at least as large as +he tata indow. Sources smaller will have to be evaluated on ind_vidual basis.
I. GAMMA CALIGRATION OF _ INGTROM((jT_(Q3;; jJr lyl_
C_A_U_T_ ION.__
The gamma field inten s i tie s r w_ red for calibration of the RO-2A are potentially hazardous to personnel. Observe precautions to prevent over e x p.. sur e. .
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'"It is very important that the ir. side .of the chamber assembly be kept dry to avoid leakage currents due to moisture. IF the desiccant becomes saturated and the RO-2A becomes erratic due to moisture, renew the desiccant crystals and --
cycle the instrument between room temperature (or lower) and i 140' F. three or four times to flush thecchamber air across the desiccant.
CAUTION Avoid any contact with electrical components with the hands as damage to the amplifier will occur.
- 1. Turn the function switch to CAT 1, and then' BAT 2' positions. The meter should read acave the.BATT cut-off lines in all cases.
U9IG . l The entire chamber assembly raus t be in the 'amma g field.
- 2. Turn the function switch to zero, check'zero off-se,t.., If
(~3 not on zero, turn the ZERO knob u 'ti the needle comes*to l (/ the zero position.
- 3. Turn the function switch to 50 mr/Se, place the instrument I
in about a 10 m.'/hr and 40 mr'hr gamma field respectively, and check the readings. Record the '2adings on the i Instrument Calibration Data Cheet 'rigure 1) in the "As l Found" column.
1
- 4. Turn the function switch to 500 no Sr. Check zero off-set.
- 5. Repeat Step I.3 for about 100 mi 'h c and 400 mr/hr fields, respectively.
G. -Turn the function switch to 5 R/hr. Check zero off-set.
- 7. Repeat Step I.3 for about 2 R/hr- ar.c 4 R/hr gamma field, respectively,
- 8. Turn the function switch to 50 P/h.. Check zero off-set.
- 9. Repeat Step I.3 for the 10 R ,' b r a r. d 40 R/hr gamma field, respectively,
- 10. If the instrument reads within 1 00% of the actual dose rate
~s in Step I.3 thru I.9, write all saluestrecor,ded in the "As
('#) Found" column into the "As Left" calumn, ; proceed to
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- 11. If the instrument does not read within i 20% of the actual dose rates in each field, continue with Step I.12.
- 12. Turn the function switch to 50 mr/hr. Check zero off-set.
Place instrument in about 10 mr/hr and adjust the 50 mr/hr control resistor until the meter indicates the field reading .
or i 20% of this value, also check the 40 mr/hr dose rate using a field of about 40 mr/hr. Record meter values in the "As Left" column.
- 13. Turn the funct'on switch to 500 mr/hr. Check zero off-set.
i Place instrument in about 100 mr/hr field and adjust the 500
+
3 mr/hr control resistor until the meter indicates the fxeld reading i 20% of this value, also check the 400 mr/hr dose rate. Record meter value in the "As Left" column.
- 14. Turn the function switch to 5 R/hr. Check zero off-set.
, Place instrument in about 2 R/hr and adjust the 5 R/hr control resistor until the meter indicates the field reading or 1 20% of this value, also check the 4 R/hr dose rate.
Record meter values in the "As Left" column.
- 15. Turn the function switch to 50 R/hr, check zero off-set.
Place instrument in about 10 R/hr and adjust the 50 R/,hr control resistor until the meter indicates the field c'eading (3
(/ or i 20% of this value, also check the 40 R/hr dose rate.
Record meter values in the "As Left" column.
J. OgIA_ CAL 10R6ITON OF__INSTRUMGNT_1Guarterly1_
- l. Zero RO-2A, place instrument on center of the beta source slab (beta window closed) and measure gamma radiation, record in the "As Found" column. Open beta window (as in G.4) and measure radiation level, record in the "As Found" column. Gubtract the gamma reading from the beta, gamma reading. This is the beta indication.
Determine a beta multiplication factor by dividing 230 (Deta
-slab reads 230 Mrad beta) by the indicated beta dose rate.
Record this value on Figure 1.
After calibration is complete, replace calibra tion sticker and beta multiplication factor on instrument.
CAUTION _
When RO-2A needs to be removed from its can, use caution when replacing can, beta window on detector can be punctured by the bolt on the tension bar in the can.
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When adjusting control resistors is complete, replace caps on resistors while.in field so if resistor turns while caps
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ar'e being rep 1, aced causing meter reading to change, it can be determined. ,
LOTE If changing mylar i s necessary on RO-2A, be sure to check mylar with a ohm meter and put conductive side to the inside of the detector.
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PROCEDURE t <
V Offsite_Eadiningica.1_Eny.irnnman.ta1 M.onitar.irg_Qur.ing._Erary.nc.ies PROCEDURE TITLE HNP-4827 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON--SAFETY RELATED ( )
- ___ _ ____.._______________.f________________4________________ p_______.
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MAN ~ER
.___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________ ______ p__ ____ _____ _ p_______.
O New Procedure r___
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1 Pages 1 thru 15 .
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______ ..____________________ ________________ p________________+ _ _ _ _ _ _ _ .
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F_______________ -______--
._____ ____________________ r________________ p________________. _ _ _ _ _ _ _ .
______ ____________________ p________________ p________________.. _ _ _ _ _ _ _ .
r____________________ y________________ p________________.- _ _ _ _ _ _ _ .
r____________________ p________________ p________________+ _ _ _ _ _ _ _ .
._____ ____________________ F________________ p________________ r_______.
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- PROCECURE NO. HNP-' M 78 "7 SHEET 1 OF_/ i
.. , s Revision No. 1 -
DEPARTMENT HEAD APPROVAL !
' ' _ , REGlJESTED OY Date: Signature: Date: i Name:
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9 as il l9/ n , I REVISION CH4JGES MODE OF CFERATION OR INTENT AS DESCRIDED IN FSAR:
( ) Yes ( ) No CHANGE INVOLVES: ( Neither
( ) An unroviewed Safety Question ( ) Tech. Specs.
(See tiack for Safety Evaluation if required).
PRESENT STATIJS: Safety Related f V) Non-Safety Related (. )
The abovs- Safety /Non-Safety Status has changed ( ) Yes to A'M_
Attach marled up copy of procedure to this form. ,
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REASON FOR REGUEST: _
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PRO RECOMMF. S APPROVAL: (dves ( )No ,
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- 1. The probabjj.i_tY of o_ccurrence and the consequences of an accident or_ _
inilfunctign_of equipment important to safety are not increased,above _
tj)ne analg.e,d in t_h,_e FSAR due to this revision bfcause the revision
& f; n6...r* cehn,pjgd/r/j/
p.qn_not change .the purpose oi ,perf,onnance of s.m -
2.,__,T[e possibility of an_ accident or malfunction of a d'ifferent type th
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. analyzed in the FSAR does -- ' ' .not7 2 result
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d d e to this revision because the revision does not change
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any limited safety sys_ tem settings which would allow a safety limit __
to be II i _--
,.t.o be exceeded or allow a limiting condition for operat ons l !, _
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. exceeded _a_s _s_t_at_ed__i.n_ Technical Specifications.
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1 of 15
. OFFSITE RADIOLOGICAL ENVIRONMENTAL MONITORIbG DURING__ EMERGENCIES NOTE This procedure supercedes HNP-4625 Rev. 5 and HNP-4725 Rev 5.
A. PURPOSE To provide a method for the determination of radiological conditions in the plant environs, due to the release of radioactive materials from the plant under accident conditions.
Also, this procedure will rrovide instructions for integrated offsite survey teams consisting of some combination of state, local, and GPC personnel.
- 8. DEFINITIONG AND TERMS
- 1. EDF - Emergency Operations Facility
- 2. REC - State Radiological Emergenc;: Coordinator
- 3. RET - Radiological Emergency Team 7~
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- 4. Dose Assessment Management - Integrated state, local, and GPC personnel collectively consisting of the Dose Assessment Manager, the REC, end lead personnel from local civil defense organizations.
C. SCOSE
- 1. The activities of the offsite monitoring teams will generally be performed in the Emergency Planning Zones (EPZ), from the plant to distance of approximately (but not limited to) 10 miles.
- 2. Offsite monitoring teams will be under the direction of the Dose Assessment Management in the EOF.
NOTE It is understood that the ultimate responsibility for offsite radiological environmental monitoring rests with the State.
D. REFERENCES
- 1. HNP-4620 " Site Area Emergency"
- 2. HNP-8142 " Stabilized Assay Meter SAM-2 Operation and Calibration"
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2 of- 15 E. ORGANIZATION
- 1. Team Composition .
- a. The teams are expected to generally consist of 3 or 4 persons, depending upon the avilability of personnel and the nature of the mission to be performed.
Functions to be performed may include:
(1) Driver (2) Navigator (3) Data Recorder (4) In-transit Instrument Reader Field Sampler <
(5)
(6) Communicator (7) Sample Taker (8) Sample Analyzer
- b. The Dose Assessment Management shall designate a team captain for each monitoring team. The team captain shall assign responsibility for each of the above functions (as applicable) to individual team members.
Team members may be assigned responsibility for i multiple functions. The team captain is responsible for assuring that all necessary actions are performed.
- 2. Team Resgonsibilities
- a. Collect environmental media.
- b. Conduct radiological field measurements (plume monitoring) with readings by location. ,
- c. Conduct air monitoring by location.
- d. Communicate sample analysis data, dose rate information, and personnel dosimetry to the EDF.
F. ACT1DNS
- 1. Radiological Emergency Team personnel should mest in the EDF to get instructions, find out the events that have taken place, and to be assigned to a monitoring team.
- 2. The Dose Assessment Management is to divide personnel into teams using combinations of state, local, and CPC personnel. Teams should consist of a max of 4 people (avg.
3).
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OPHO v AL PHULtDvRt NO E.1. HATCH NUCLEAR PLANT HNP-4827 See Title Page atme w an 3 See Title Page 3 o f 15
- 3. .Offsite teams may use vehicles equipped with two-way communication devices belonging to GPC, the state, or the locals as appropriate. In addition, portable radios.and antennas obtained from the EOF will be used as alternative communications. If personal vehicles Jre used, the portable radios and antennas will be the primary communication system and the Bell system as an alternative.
~
- 4. The Dose Assessment Management shall designate a team captain for each team.
- 5. Once the teams and team captains have been designated, each team captain will be responsible for assigning each member of his team certain tasks, ie, driver of the vehicle, navigator, data recorder, in-transit instrument reader, field sampler, communicator, sample taker, and sample analyzer.
- 6. Upon the classification of an ALERT level emergency, the offsite teams may be activated at the discretion of the Dose Assessment Management. If the classification is a SITE AREA or GENERAL Emergency, teams shall be activated. The Dose Assessment Management directs the staffing and deployment.
O 7. Obtain a survey team kit at the EDF.
- 8. Complete the checklist in Data Package 1, Data Sheet 1.
- 9. After the equipment is checked for operability, the monitoring team will establish communications with the EOF.
- 10. Turn on survey instruments, allow them to warm up, and verify response with the check source provided.
- 11. Install glass fiber filter and silver zeolite cartridge in sample holder of air sampler. Turn on sampler and confirm proper operation. Turn off.
- 12. Proceed to area specified by Dose Assessment Management.
- 13. While in transit, survey meter for measuring dose is tur- 1 on. The instrument is positioned for continuous view:ag d ready eccess for recording readings. If readings above background are detected, record appropriate information on Data Package 2, Data Sheet 1.
- a. Indicate observed readings on survey map. (Report any indication of a plume to the EDF). Record on Data Package 2, Data Sheet 1.
- b. Record time entering the plume as indicated by the survey meter reading on Data Package 2, Q(ta Sheet 2. - -
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- c. If dose rate is in excess of 5 mr/hr, report reading to the EDF.
NOTE Minimize traversing of the plume as much as practical to maintain exposures ALARA. Contact the EDF prior to exceeding any administrative exposure guidelines. Provide periodic personnel exposure updates to the EOF when exposures are considered significant. Record personnel exposure data in Data Package 2, Data Sheet 1.
- 14. Upon arrival at the sampling location, perform a dose rate survey in the following manner:
- a. At waist level, hold GM probe HP-210 or GM survey meter (or equivalent), read meter, and record results on Data Package 2, Data Sheet 2.
- b. At 2" above the ground, hold GM probe with detector window facing the ground, read meter and record results on Data Package 2, Data Sheet 2.
O c. At waist level, hold high range survey meter horizontal, read and record dose rate on Data Package 2, Data Sheet 2.
- d. Repeat step c above, but at 2" ^~om the ground.
- 15. Take air sample at designated area when requested by Dose Assessment Management as follows:
- a. Place a silver zeolite (AgX) cartridge in the sample head, and mark the cartridge to specify the inlet side of the cartridge. Place a particulate filter upstream of the AgX cartridge, and place the sample head in the air sampler.
- b. With the enoine running, connect the air sampler power leads to the vehicle battery, taking care to connect the positive and negative cables to the positive and negative battery terminals respectively.
- c. Start air sampler and record time on Data Package 2, Data Sheet 2.
- d. Check air flow indication and record flow rate. ,
- e. Run air sampler 10 minutes, record flow rate from calibration sticker on Data Package 2, Data Sheet 2.
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W % VAL NADUMA NO E. l. HATCH NUCLEAR PLANT HNP-4827 See Title Page *voca w can 3 See Title Page 5 of 15
. rJOTE Dose Assessment Management may request other sample times.
- f. Make radiation survey as in step 14 above while running the air sampler.
^
NOTE If levcis are greater than 10 mr/hr report reading to the EDF and await instruction from the Dose Assessment Management.
- g. Remove the AgX cartridge and particulate filter from the sampler head, and place in separate plastic bags.
- h. Air samples should be labeled and a log entry made in the log book of the fc110 wing information:
Date and start time of s&mple Duration of sample Flow rate of sample
(). Location of sample point (map location, landmarks, etc.)
Survey team name Air sampler number SAM-2 Analyzer serial number (if used)
NOTE During air sampling, monitoring teams should observe the dose rate instrument for significant changes in dose rates. Report any significant changes to the EDF. Record personnel doses on Data Package 2, Data Sheet 2 while sampling.
- i. Insert GM survey meter probe (HP-210) into sample holder (SH-4A) and record background reading.
-j. Place glass fiber filter in SH-4A holder and obtain reading (CPM). Calculate airborne concentration per Data Package 2, Data Sheet 3.
- k. Place silver realite cartridge (which has been placed in plastic bags) directly against probe (HP-210).
Obtain reading (cpm) and calculate airborne concentration per Data Package 2, Data Sheet 3. (pci/cc)
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APPHQv &L PQ(OyHg peQ E. l. HATCH NUCLEAR PLANT HNP-4827 See Title Page aeven w care 3 See Title Page 6 of 15
. NOTE If SAM-2 Counters are available, cartridges may be counted using HNP-8142 and HNP-4826.
Record data on Data Package 2, Data Sheet 2 as CPM (net).
- 1. Place sample filters in envelopes and record on envelopes time, location, fl ov:, sample time, cpm, background, and air activity. Hold for further analysis at place EDF.
- 16. Collect soil, vegetation and water samples when requested by the Dose Assessment Management, as follows:
- a. Take bag (mark it soil) and small scoop, fill with surface soil from a bare spot, tape closed, and tag with the date, time, and location.
- b. Take bag (mark it vegetation) and scissors. Cut vegetation approximately two (2) inches above ground, fill bag, tape closed, and tag with the date, time and location. (If possible, choose vegetation that might
() be ingested by animals).
- c. Ft.1 poly bottle with surface water, close and tag with date, time and location.
- 17. Record time out of the plume on Data Package 2, Data Sheet 2, and determine total stay time.
- 18. Report all results to EDF and await further instructions.
Document all results in Data Package 2.
- 19. When directed by the Dose Assessment Management, proceed to environmental TLD and air sample cabinet locations. Change out TLD and filters at the stations noting time and date of change out. Return samples to the EDF.
- 20. . Return all data sheets to the EDF for review, analysis and temporary storage. These data sheets shall be permanently stored in Document Control upon termination of the emergency condition.
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9 of 15 PROCEDLRE DATA PACKAGE DOCtDENT NO: HPP-4827-1 SEIRIAL NO: RO3-PFL NO:
RTYPE:__gis.03 XREF:
TOTAL CHEETS: 2 FREQUENCY: ,
COPPLETED BY:
DATE COPPLETED:
I HAVE REVIEWED THIS DATA PACHAGE FOR COPPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HPP-830.
ACCEPTABLE UNACCEPTASLE REVIEWED BY:
DATE REVIEWED:
REMARMS:
Page 1 of 2 FeP-4827 RO3 O
s - -
FIGURE 3 gg at ,
Page 1 of 2
APPHQv&L PROL&DvNt NO E. I HATCH NUCLEAR PLANT " -Asa7 See Title Page iv,wo uo oart 3 See Title Page 10 of 15 QATA PACHAG W
!51t!1IQBING TEAM CMGEIST Data Sheet 1 A. Invedory Nit and verify Neiessary Itemi
- 1. SAM-2 Analyzer (optional)
- a.
- Battery and source check _
- 2. Survey In s t rtment s
- a. Battery and source check
- 3. AgX Cartridges
- 4. Particulate Filters
- 5. Calculator
- 6. Stop Watch
- 7. Log Book
- 8. Sample Gags ,.
- 9. Pocket dosimeters _ ,
- 10. TLDs
- 11. EOF Telephone Numbers (in log book)
- 12. Airborne Activity Calculation Form
- 13. Gloves
- 14. Tweezers
- 15. Labeling Materials (labels, pens, etc)
- 16. Maps and Procedures
- 17. Spare Batteries
- 18. Blank Smears
- 19. Portable Air Sampler
- 20. Sample Bottles
- 21. HP 210 Probe / Holder D. Erior to de2arting the EOFu verify the followingi
- 1. Survey instrument in cab and on lowest scale
- 2. Team members equipped with dosimetry '
- 3. Maps in cab
- 4. Vehicle radio check completed Page 2 of 2 HPP-4827 RO3
[sw) 4 d%s
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FIGURE 3 i Page 2 of 2 mmW M
e weseovat PHULEDuHk NO wp-4sa7 E. l. HATCH NUCLEAR PLANT aeose ~o See Title Page cart & 3 P
See Title Page GeoreiaPower v al ~ ~o 11 of 15 4
PROCEDURE DATA PACKAGE DOCLPENT NO: Hre-4Bg7-2 SERIAL NO: RO]-
PFL NO:
RTYPE: Gli 02 _ _ _
XREF:
TOTAL SFCETS:_L FREGUENCY:
COMPLETED BY:
DATE COMPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH HrP-830.
ACCEPTADLE UNACCEPTADLE REVIEWED BY:
DATE REVIEWED:
REMARKS:
Page 1 of S FNP-4827 RO3
)
' ~
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FIGURE 4 Page 1 of 5 masW Mt .
Ah*Now AL PHOL4DvHt W
. E. l. HATCH NUCLEAR PLANT HNP-4827 See Title Page atv e au haft ."3 pV See Title Page Georgia Power l 12 of 15 DATA F'ACH Rg -
Data Sheet 1 e
seenstocans Tee. Page es Date FEM RATE APC EXP(RfgE p(ASPEPENT DATA FGH.
se LDCATIGe ?!PE MfrWV CRt1M' LEW1. PD100C. n!NECT T1st INRTIUEPff EEmi NAT 31 READDg Wgn 6 v7 mm.
s a P OTHER 2 metoe t =eter centact tes=e ms=e 'emme PcRTen (ad/hr9 t ed /he 9 tad /hrI ( ed ) ( AA > 4 ed )
/ -,sg - .......................... . ...........
9 ... ...
C@R1,Ill2f ACTIG4
- t. Esp 8sure rete 2s senhr na resiste4 ne sa. Pet ssium seesee twas recessendee, m ecatin -ne. =ectee.
18- Il att as not knee. unless esteeted otherwase er Dese este merker. darectson, Accessment Management. destance, reed esps, tenenecks, tsor O*s, etc.
da. Total espesure 100 ap. 2a. Centact Dese Assessment Management and advise.
- b. Total emessuse 3 R. b. Evecuatten recesenended, unless derected othe.wase er Dese Assesstset Management.
- c. Total eseosure as R. c. Eveeuata3n mandatory, contact Dese Assessment management.
sig: Anrei.e esee te a mihr cre,.reness * . e .ctivstri, oes. Assess ent men. w ,
must ne cone.s re e te ere.ter se ..
ctee, s . sector n . a.as P
- Samete Point it.23 Page 2 of 5 HW-4827 RO3
'4 V
A Au FIGURE 4 T' '
Page 2 of 5 8MMI M -
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- 4 LPPHQv&L PROLEDtF*t NU E. l. HATCH NUCLEAR PLANT WP-4827 See Title Page " " " *
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13 of 15 QATA PACKAGE _g Data Sheet a OFTSITE EFERCENCY_MQt!1IQR_It!G_ TEAL 9 Team Date Time entering
- plume Time Esiting Plume Plume Stay Time -
Sample: Location _ Sample Time On Sample Time OFE-Flow Rate: LPM Sampler Type Serial Number GRQQg_elRDORNE_AGIly1_Ty (Glass Fiber Filter)
(Sample t background CPM) CPM (Background CPM) ____ CPM (Sample t background CPM)-(background CPM)= Corrected CPM CPM (net)*
From Figure 1 particulate airborne concentration = uci/cc'*
Instrument Type Serial Number igQlt!@_0lRDOR T AQT1y1Ty (AgX Fi1ter)
(Sample t background CPM) CPM (Background CPM) a __
(Sample t background CPM)-(Background CPM)= Corrected CPM CPM (net)*
From Figure 2 Iodine Airborne concentration = uct/cc**
From Data Sheet 3 Thyroid Dose Rate mc/hr Instrument Type Serial Number GOUNT/DOSq_Belg_gggyqy Count / dose rate while in transit CPM Mr/hr Count rate @ waist level CPM Count rate 9 2" trom genund (window facing ground) CPM Dose rate @ waist level Mr/hr Dose rate e 2" from ground Mr/hr Ins +rument type Serial Number Instrument type Serial Number Page 3 of 5 HPP-4827 R03
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FIGURE 4 Page 3 of 5 mM M -
LPPMQW A PHQ([DUMt NQ E. l. HATCH NUCLEAR PLANT HNP-4827 See Title Page at. 3.u~ w WE 3 0 .
See Title Page Georgia Power O 14 of 15
@TA PAQH_ AGE 2 (CONT)
Data Sheet 2 OFFSITE EPERGENCY MONITORING TEAM PJR"N DOSINETRY*** Time Team member
- Dose mr Team meeber Dose mr Team member Oose mr Team member Oose mr SAMPLE 3_EQUAEIEQ Oirect radiation TLD's Milk Vegetation Well Water Soil Orinking Water from surface source Other (specify) _
Other (specify)
- Note
- If SAM-2 used record CPM (net) as instrument reading.
- Note: If activity (CPM), flow rate (LPM), or sample time 9 (min) are different from information on Figures 1 & 2, use Data 0., Sheet 3 for calculations and record results on Data Sheet 2 ().tci/ c c ) .
- Note: Read and record personnel doseimtry at least one time while at each sample location. (More frequently if does rates are high).
Page 4 of 5 A HPF-4827 RO3 U
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FIGURE 4 gg Page 4 of 5
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See Title Page 15 of 15 QATA PAG _MAQg_g Data Sheet 3 ENVIROMENTAL AIREQRfC ACTIVITY CALCtLATION FORM 1
Net Particulate (CPM) (from Data Sheet 2)
- 3. Sample time min. (from Data Sheet 2) 4 Flow cate. LPM (from Data Shret 2)
P_g;11j;ylg13
- 5. Cross Airborne Concentration =
Particulate
( CPM (net) (4.5E-9)
= pci/cc
( LPM) I min.)
Indint A 6. Airborne Concentration =
U Iod3.se
( CPM (net) (4.5E-85
......................... . pei/cc
( LPM) ( min.)
- 7. Thyroid Dose Rata =
(line 6 pci/cc) x (1.85Et3 mr/hr/pci/cc) =
mr/hr
- Iffollowing a SAM-2must is used the graphs are not usable. The formula be used:
(Net CPM) (1.5 E-9) for charcoal cartridge (volume in liters)
! (Net CPM) (1.58 E-9) for silver reolite (volume in liters)
Page 5 of 5 FN)-4827 RO3 b'N 4 ~
u FIGURE 4
- maeWI 58%
Page 5 of 5 l
S 7 GEORGIA POWER COMPANY e
HATCH NUCLEAR PLANT O PROCEDURE Eberline Model PM-G Portal Monitor PROCEDURE TITLE
- HNP-815_8_ --
PROCEDURE NUMBER
~
Ogerations -
RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANA R
_ _j ) , _ _ ., _
O New Procedure - ~ .L4 / J, p--.
.--------------------- -. sa3c ---------------- - -----
,_) - - - - - - . -------------------- .----------------.. - - - - - - - - - - - - - - - - . ---------
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. FCR NEW PROCEDURES yyg yn, y_ . gjgg -
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EEMESTED GY
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SAFETY RELATED ( ) NON- HELATED ( ) ,
... PROCEDURE CHANGEG MODE OF OPERATION OR INTE AS DESCRIDED IN FSAR:
" .( ) Yes ( No'
' / ' '. PROCEDURE IN"v'OLVES: .
( ) An onceview d Safety Gues on ( .) Tech. Specs. ( l'.A condition not addressed in FSAR ( ) Non's of these (See back for- Safety Evaluation if required). ,, .
.,,.... Attach copy of procedure to this .&orm. ~
" ,-:."- f, . , *
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PRD RECOM!nENDS APPROVAL:(dyes ( )No mM W -
. ., . PRO Secretary
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88-217 JI .Ja-U O . FRO Number
. Date -
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, i htansat set
._,m_. _ _ . . _-,,__.,_.-,.y._,,__ .__-,.,,__,_-,.m,. _ , , . _ . _ - -
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- e SAFETY EVALUATION i
. l
__..__..._____.........___.................._________..._____...._.... f
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P Thi 9rocedure does not constitute an unreviewed safety.guestio_n__a_s.e.x.pla_in.e.d...-.
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EN
- AWRUyg MM.lLLDuMt W E. I. HATCH NUCLEAR PLANT HNP-8158 See Title Page ae viw. w g
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1 of 12 EBERLINE MODEL PM-6 PORTAL MONITOR A. PURPOSE To ensure that the instrument is calibrated properly and to provide operation guides to the user.
B. SAFETY Observe radiation protection procedure.
C. REFERENCES SX-S10244, Model PM-6 Technical Manual D. TEST EQUIPMENT
- 1. P-10 Gas (10% methane, 90% argon)
- 2. Electrostatic voltmeter
- 3. Assorted check sources E. DESCRIPTION - GENERAL The Eberline PM-6 monitor is a microprocessor based radiation detection system which provides a quick indication of beta-gamma contamination on the clothes and shoes of personnel. The micro-computer provides a sophisticated and flexible means of acquiring and manipulating data and presenting operational conditions and alarms on the alpha-numeric gas discharge display and status indicator lights.
All functions of the monitor are automatic with the parameters preset into the microcomputer. It is capable of operation as a walk through type monitor or as a pause type. During use the display will indicate whether the occupant is clean (non-contaminated) or contaminated and the zone in which the alarm occurs if the alarm setpoint is exceeded.
F. DESCRIPTION OF CONTROLS AND INDICATORS:
- 1. External
- a. Ultrasonic sensing unit: Senses one's approach to the monitor and initiates counting activities in the walk through mode,
- b. Display Chassis: It is composed of the display module,
() ready light, alarm light, trouble light, and a counting light. All of which indicate the operating condition of the monitor and display the appropriate message to the occupant of the monito~r. ,,,,{ gg ,
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pNv4 e ouovut w E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page -ev%A w
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2 of 12
- c. Photoelectric Sensor: Indicates to the monitor that it is occupied or if the occupant has exited the monitor before the count cycle has been completed. (This is functional in the pause mode only.)
- 2. Internal Right Column
- a. Power Switch: Provides on-off capabilities for 110 volt AC power.
- b. Flow Gauges: Indicates inlet and outlet flow rates in cc/ minute for both left and right side detectors. The inlets flow rate gauges are adjustable.
- c. Pressure Regulator: A dual gauge fully adjustable control for the P-10 gas used in the detectors. It is mounted en a type 1A gas cyclinder and is connected to the instrument by 3/16" Id Tygon Tubing (Bottle #2).
- 3. Internal Left Column
- a. Keyboard: A 16 key control board that serves as the
()
,s interface for communication between operator and machine,
- b. Operate / Test Switch: Controls the operation of the monitor between the normal operation mode and its test and maintenance routines.
- c. Pressure Regulator: A dual gauge fully adjustable control for the P-10 gas used in the detectors. It is mounted on a type lA gas cylinder and is connected to the instrument by a 3/16" Id tygon tube. (Bottle #1)
- d. Program Header Switch: Located on the computer board determines the mode of operation of the monitor according to the model in use,
- e. HV Switches: Two switches that provide on-off capabilities for each of 2 high voltage sections.
- f. HV Adjust: Two potentiometers that provide a reference voltage to each of the high voltage power supplies enabling control of the high voltage setting.
G. OPERATION GF INSTRUMENT
- 1. Initial Set-up
~
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6
e APPeov44 PROCEDUAL NQ E. I. HATCH NUCLEAR PLANT HNP-8158 See Title Page atvew
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3 of 12
- a. P-10 gas hook up: Install the P-10 gas bottles in both sides (bottle #1 is on the left, bottle #2 is on -the right) connect the pressure regulators on bottles 1 & 2 and connect the 3/16" tygon tubing to the outlet side of the regulators.
- b. Gas Flow and Pressure Adjust: Adjust the pressure regulators to 5 psig and the flow regulator to 50 cc/ minute.
CAUTION Do not exceed 50cc/ minute or damage to the detectors may occur,
- c. Initial Purge: Allow approximately 4 to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> purge time at 50cc/ minute to insure that the system is completely purged of outside air and moisture. The flow rate can then be adjusted to 25cc/ minute for normal operation.
t
() d. Power Connection: The instrument uses 110 volt AC power. It may be plugged and turned on at this time.
- 2. Normal Use Operate vs. Test If the OPERATE / TEST switch above the keyboard is set to operate, the monitor will run in its main routine, measuring and storing background for all channels, checking for high background alarm levels, low count failure, and low gas pressure conditions until the actuation of sensing switches calls the personnel monitoring rcutine. This routine causes all channels to check for high activity alarm conditions with automatic background subtraction, according to the protocol of one of the three operating modes in which the monitor has been set to operate:
Mode 1 Preset All Mode 2 Maximum Sensitivity Mode 3 Minimum Count Time If the OPERATE / TEST Switch S1 isset to TEST, the monitor runs in its test and maintenance routines. In this mode, the keyboard is active and the other sensors are inactive.
O J m am.at set .
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O See Title Page ceo iaeower A ~ ~e 4 of 12 Background measurements and related computations are suspended while in TEST, and all parameters are avail'able for display and/or modification as listed in Table 1. The display prompts the operator with the name of the parameter list ready for examination or, within a list, the name of the variable being displayed and its present value. The keyboard protocol is such that touching the "+" key causes the " " key causes a an increment decrement to the to the nextitem prior item,d an the ENTER key causes entry to that list. EDIT and ENTER allow modification of appropriate items as indicated by E in the table,
- a. Routiae Monitoring (Operate)
(1) Walk through mode: A typical measurement in the walk through mode involves nothing more than walking through the frame. The ultrasonic unit senses one's approach, which initiates a minimum of five seconds worth of individual counting intervals. After the person has departed and the five second sensor delay has expired, the PM-6 g will resume background counting. (The program
.> header switch should be set with the number 2 and 3 switches open. All of the others should be closed for the PM-6 to operate in the walk through mode).
(2) Pause Mode: In the pause mode it is necessary to stand in the frame blocking the light beam for the duration of the counting time. A chime and a
" count OK" or a " Contaminated" message signals the end of a count. (The program header switch should be set with the number 4 switch open and all others closed for the PM-6 to operate in the pause mode.)
manalut .
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APPRov% PROCEDuptPs0 l E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page " * * *
- oare 0 0 See Title Page Georgia Power ~~
5 of 12
- b. Test Mode TABLE 1 TEST MODE MENU OPERATING MODE Mode 1 Mode 2 Mode 3 PARAMETER LIST PRESET ALL MAX. SENS. MIN.CT.
AND ITEM TIME DISPLAY SYSTEM PARAMETERS Identification and Type H H H Mode (1,2, or 3) E E E Sigma Factor (SF) E E E Weighting Factor (W) E E E Alarm Hold Time (seconds) E E E Count Time, Test (seconds) E E E Count Time, (T, seconds) 3 E C Min. Count Time (Mode 1 only) C NA NA Max. Count Time (Mode 3 only) NA NA E DISPLAY CI!ANNEL PARAMETERS 7one or Channel Identification Average Background cps (R B) M M M Alarm Setting cps (RA) E C E Min. Glarm Limit (Mode 1 only) C NA NA Max. Alarm Limit (Mode 2 only) NA E NA (Repeats for each zone or channel)
COUNT RATE MODE Zone or' Channel cps M M M (Repeats for each zone or channel)
DISPLAY TROUBLE LIST (available only if trouble light is on) l Zone or Channel Identification High Background M M M High Count Fail M M M Low Count Fail M M M Bottle #1 Empty M M M Bottle #2 Empty M M M Failure ** Out of Gas! M M M O
v
, SMid
4 LPPROVAL PROCtDURL NO
- E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page *v.so= ~o o^'t 0 lSeeTitlePage_ 6 of 12 OPERATING MCDE Mode 1 Mode 2 Mode 3 PARAMETER LIST PRESET ALL MAX. SENS. MIN.CT.
AND ITEM TIME SYSTEMS DIAGNOSTICS Display Test A A A Keyboard Test OI OI OI Alarm Ack A A A
- One Hand A A A Light Test A A A Chime Test A A A Read / Write Memory Test A A A Program Memory Test A A A USAGE Personnel Counter / Elapsed Time M M M LEGEND H - Fixed by hardware configuration E- Edit / Enter via keyboard C - Computed variable by microprocessor M - Measured variable NA- Not Available A - Auto Sequence OI- Operator Input
- - PM6-2 (Hand and Foot Portal) only (1) Operating Mode (a) Preset All, Mode 1 In this mode the alarm setpoint RA for each channel, and the counting time T and sigm-factor SF for all channels, are entered via the keyboard. A personnel alarm occurs if the count N in the counting time T is such that N> RB T and Rg T The high background alarm occurs if SF RB T> Rg T
..a.s
. ~ . . _t . . - - . . - - . .
APPROv&L PROLEQuRE NQ E. I. HATCH NUCLEAR PLANT HNP-8158 See Title Page aevuw ~o
^"
O See Title Page Geo iaPbwer A -
7 of 12 (b) Maximum Sensitivity, Mode 2 In this mode the maximum alarm limit R counting time T, and SF are entered viaAma the' keyboard. Each time the background is updated a new alarm setting RA is computed for each channel.
)
RA = SF QRB /T A personnel alarm occurs if N 2* RB T+RA T
The high background alarm occurs if RA 2[ RAmax (c) Minimum Count Time, Mode 3 In this mode, R SF and maximum count time T max areentereb,Eachtimebackgroundis (3
s_/
updated a new count time is computed from T= (SF)2 RB/(RA I based on the channel with the highest RB Personnel alarm occurs if NhRB T+R g T
The high background alarm occurs if T 21 Tmax (2) Sigma Factor (SF): A user entered variable that is a multiplier of the background standard deviation used in determining alarm setpoints.
(a) Mode 1, the SF is used in determining the alarm setpoint for the high background alarm when l SF 3 RB T 2* RA T the alarm will occur
(~)'
'- (b) Mode 2, the SF is used in determining the personnel alarm setpoint - RA assul not where RA = SF q RB /T 9
1 APPROVJ.L PROCEQyRE NQ
- E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page aeme =o ons o
~ ~o O See Title Page Georgia Power 8 of 12 (c) Mode 3; the SF is used in determining the minimum count time, where the alarm setpoint Rg is preset and the highest average background R is used where count time T =
(SF) RB/(RA -
NOTE The value of the Sigma Factor will vary based on which of the 3 modes of operation is to be used. Determine values for the variable represented in the formulas based on the location and operating conditions of the monitor. Use these to arrive at an acceptable value for the SF that will produce the most sensitive operation with the least amount of false alarms.
(3) Weighting Factor (W) : A number that is used in compensating for background variation. An increase in the W value results in an increased confidence level for false alarms, but at the same
() time it increases the amount of time it takes to respond to real changes in the ambient background. A value between 10 and 20 is recommended.
(4) Alarm Hold Time: The length of time the sonar alert and the display module remain activated during an alarm condition. (Operator determined 1 to 9 seconds).
(5) Count Time, Test: The length of time that the system counts in the " Count Rate" mode, normally used for source checking individual channels.
(Operator determined 1 to 900 seconds).
(6) Count Time (T): (Modes 1 & 2) A predetermined period of time for the count duration of the background update and the personnel count.
(Operator determined 1 to 10 seconds) .
(7) Maximum Count Time (Tmax); (Mode 3 only) - The maximum amount of counting time, (T) allowable before a high background alarm will occur when T ?>" Tmax-SEU N -
0
(
LPPRQyJ4 PHCCEDURL NO E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page atvew ao can 0 O See Title Page ceorgiaeower C'
-e 9 of 12 (8) Alarm Setting (RA): (Operator determined -
Modes 1 and 3) The maximum amount of counts (N) collected before a contamination alarm will occer when N = RA+RB .
RA can be solved for given T, RB , Rb, Z and W. Rb is taken to be equal to RB as it is the best estimate of Rb*
Rg = Ra -Z Ra+Rb Rb T
4 ________
T(2W +1)
Z is determined by choosing the desired confidence level tha.t will produce an acceptable false alarm rate, and still maintain the confidence level as high as possible. This determination should be based on the location of the monitor and the conditions under which it is to be used.
' For 99.9 percent confidence level, F(z) = .999, z
= 3.090 For 99.0 percent confidence level, F(z) = .990, z t/ = 2.126 ~
For 95.0 percent confidence level, F(z) = .950, z
= 1.645 For 90.0 percent confidence level, F(z) = .900, z
= 1.282 For 75.0 percent confidence level, F(z) = .750, z
= 0.674 For 50.0 percent confidence level, F(z) = .500, z
=0 (9) Max Alarm Limit: (Mode 2) Preset amount of counts that will cause a high background alarm if the setpoint is exceeded.
Variable Legend Rg Alarm Setpoint (Limit)
Ra Activity Count Rate RB Average Background Rb Individual Background Count N Personnel Count SF Sigma Factor T Count Tinie T max Maximum Count Time Z Confidence Level Value
- 3. System Failure If the instrument indicates trouble or failure notify a health Physics instrument technician of the problem so SEIug can be resolved.
o
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LPH40 VAL P64QCtDyR1 NO
- E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page aev*
- w ons 0 n ,
See Title Page Georgia Power
~~
10 of 12 H. WEEKLY SOU_RCE CHECK NOTE Due to the frequency of the routine source check. other periodic calibration is unnecessary.
- 1. Observe and record the pressure in bottles 1 & 2 and the regulated pressures to the instrument. The regulated pressure should be 5 psig. Adjust if necessary.
- 2. Observe and record on Data Package 1 gas ficw on the gauges for both sides. The flow should be 25cc/ minute. Adjust if necessary.
- 3. Switch the Operate / Test switch tc Test. Advance the display to " Display Channel Parameters" using the "+" key. Press
" Enter" to gain access to the program list. The display will show the zone identification number. Press " Enter" to gain access to the individual Zone / Channel parameters. Use
"+" to step through the list recording the " Average Background" and the " Alarm Level". Continue through the 11 Zone / Channels in the above manner recording the required data. If the instrument is being used in the " Maximum
(-)'
Sensitivity, Mode 2", also record the " Max Alarm" setting.
- 4. Advance the display using the "+" key to the " Count Rate Mode". Press " Enter" to gain access to Zone / Channel #1.
Center the source against the detector screen. Allow 2 count cycles to occur before recording the results of the 2nd count. Continue through all 11 Zone / Channels using the
"+" advance recording the data on Data Package 1.
- 5. Backup to the " Display System Parameter" list using the " "
key. Press " Enter" to gain access. Press "+" to increment through the list recording the parameters for the following: Mode (1, 2, or 3), Sigma Factor, Weighting Factor, Alarm Hold Time, Count Time, Test, and Count Time.
- 6. Note whether the monitor is being used in the Pause or Walk through mode.
- 7. Return the Operator / Test Switch to Operate. Allow the monitor to background count momentarily. Place the source on Zone #1 while standing in the monitor. Indicate on the data sheet in the Alarm Acceptable Column whether or not the channel alarms. Step out of the monitor, allow the alarm to clear. Continue through the remaining zones in the above manner.
(~)%
\_
- 8. Calculate the efficiency for each Zone and Channel completing the Data Package. I-f the detector ef ficiency is below 20% it is not acceptable. Replace the detector asuRM WI initiate repairs to return the efficiency to an acceptable level.
b M VAL PRUClouHL ~o E. l. HATCH NUCLEAR PLANT HNP-8158 See Title Page aevis.o~ ~o cart 0 O See Title Page ceorgia o
power ~~
11 of 12 PROCEDURE DATA PACKAGE DOCUMENT NO: HNP-8158 - I SERIAL NO: ROO-MPL NO:
RTYPE: G15.14 .
XREF: N/A TOTAL SHEETS:_E FREGUENCY: Weekly COMPLETED BY:
DATE COMPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPI ANCE CRITERIA IN ACCORDANCE WITH Ffe-830.
ACCEPTABLE UNACCEPTABLE REVIEWED BY:
DATE REVIEWED:
REMARKS:
6 Fage 1 of 2 HNP-8158 ROO
%..]
FIGURE 1 8W "
- Page 1 of 2
e AJPHOvdA PROCEDURt NO E.1. HATCH NUCLEAR PLANT HNP-8158 See Title Pace s REv@ON NO oare 0 O See Title Page ceohiaeower A
~ ~e 12 of 12 DATA PACKAGE 1 PM-6 WEEKLY MONITOR CHEq!iS Location: MPL # Serial #
Source #: Source D.P.M.
Gas Pressures: 1. PSI Regulator Gas Flow 1. __ _ c-/ min
- 2. PSI Regulator Gas Flow 2. _ cc/ min Source CPM-BKG Divided By Source D.P.M. X 100 = EFF.
Detector Source Average Net Source Detector A". arm Alarm Zones CK CPM BKG. CPM CPM EFF% Setpoint Acceptable 1
2 _ _ _ _ _ _ _ _ .. ___.___..
_____.-___{.._______..
3 ...________
Q y
4 5 _-___ __ ._--__.-_ ______.___
6 -------- -------- ------~~~~
- . - - - - _ - _ ........_- . _ _ - _ _ - . ---_~.-___-
7 ---------' - - - - - - - - - -
8 -------- -------- - - - - - - - - - -
9 _.- _.. . __.-___ . -.--_-__.
10 _____--- ..-___--_ . - _ . _ _ _ _ - -
.1 __.- -_.-_.-_-._,----- -._-
Walk or Pause Mode. .................
Mode (1, 2, or 3) . .................
Sigma Factor. ....................
Weighting Factor. . .................
Alarm Hold Time . . .................
Count Time rest . . .................
Max. Alarm Limit Mode 2 . . . . . . . . . . . . . . .
Count Time (Pause rode Only). . . . . . . . . . . . .
COMPLETED BY:
DATE COMPLETED:
O (s Page 2 of 2 HNP-8158 ROO
- n FIGURE 1 WNMI M Page 2 of 2
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT (x
PROCEDURE Shigment Of Radioactive Motorial PROCEDURE TITLE .
HNP-8016 _
PROCEDURE NUMBER Lab RESPONSIRLF SECTION SAFETY RELATFD ( X ) NON-SAFETY RELATED ( )
APPROVFD APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAG
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12 Page 15,16 & 18 j9
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Revision No. I iA DL.PARTKCNT h EAD APPROw&
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.( ) An unceviewed Safety Question (See back for Safety Evalua Non-Safety Related' ( )
~
Safety Related (
PRESENT STATUS: ( ) Yes to ____.____ l t
~ T'he above Safety /Non-Safety Status has changed .
Attach mar kod up copy of procedure to this form. S ,
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- REASON FOR REGUEST:
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_____._____._ in the Technical Specifications is -
The margin of s_a_fety_ as definedrevigion does not change
_.___L i ion because the ft limit .
not reduced due to this rev s tings which wouldIllow be a sa .A e y any limited safety system set iting conditipn' for operation , ..___._,
to be exceeded or allow a lim l Specifix./ations. - -
exceeded as stated___ in Technica _
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Name: Date: Signeture:
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.-( , ) Yes No u-
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I vT Ne i tt.e r-llD C ) An unreviewr:<: Gefety Guestion (
(See ,t a ck (or SMety Evaluation required).
Safety Related ( ) Non-Safety helated ( )
PRESENT STATUS:
The abour- Safety /Non-Safety Status has changed ( ) Yes to __
T l
Attach inar kod up copy of procedure to this form.
(f*fy y zse d McW,,3f.fyj,gyg,4 ,jgg. __ ___ __
REASON FOR REGUEST: ,
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- _ _ _ s; lfunction of a different type than -
__ P,.u_,Ae T .possibil_it,y_,of an accident or ma I, lt from this revision because - _the
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_..____..5Yitef_Eesponds,,and is operate .
~ - . _ - . -
1 - . _ _ _ _ - -
in the Technical Specifications is The margin of safety as d_efined -
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not' reduced due to thishich revision because the revis l_
___ . would allow a (afety limit
._an,ylimitedsafetd,ys_temsettingsw -
to be I' .
itihg condition for operations - - _ _ __
._____,_,t_o_be exceeded or allow a lim -- -
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1 APPRQW% PROC &Oupt NQ E. l. HATCH NUCLEAR PLANT HNP-8016 See Title Page aevisa w o^'E 14
~~
O lSee Title Page Georgia Power 1 of 17 SHIPMENT OF RADIOACTIVE MATERIAL A. PURPOSE To assure that all shipments of radioactive material meet the Department of Transportation (DOT), Nuclear Regulatory Commission (NRC) requirements, and all state, local and burial site criteria.
B. REFERENCES
- 1. 49 CFR 100-177
- 2. 10 CFR 71
- 3. 10 CFR 61
- 4. Con +rol and Accountability of Radioactive Material, HNP-8017
- 5. Barnwell, Hanb_rd and Bealty Disposal Site Criteria.
3 C. SAFETY s)
Observe Radiation Protection Procedures.
D. PROCEDURE
- 1. The shipment of all radioactive material will be done in compliance with 49 CFR parts 100-177, 10 CFR parts 61 and 71 and all burial site criteria.
- 2. In addition to the requirements of D.1 above, the following additional requirt.ments will also be applied.
- a. Exclusive use venicles loaded for shipment must have approval of a Lab Supervisor or higher authority to exceed 165 mr/hr at the surface or vertical plane of
~ vehicle, 8 mr/hr at D meters from surface or vertical plane of the vehicle or 1.6 mr/hr at the surface of the rear of the cab.
- b. The survey performed at the rear of the cab for exclusive use vehicles will be done with an instrument which is graduated to read dose rates 4 2 mr/hr such as a teletector or an E-400.
- c. Truck surveys for exclusive use shipments will be documented on Data Package 1, Data Sheet 2A or 28.
(v")
mand 5d
fJPNQWAL PWJCtDURL NQ E. l. HATCH NUCLEAR PLANT HNP-8016 See Title Page at's*
- o^n 14
~ ~o O>
' See Title Page Georgia Power 2 of 17
- 3. Activity Determination
- a. Expanded resin NOTE Extremity and high range dosimeters shall be wLrn when obtaining samples of expended resin when dose rates are expected to exceed 100 mr/hr whole body and four times greater than whole body for extremities.
(1) Operations shall notify Health Physics when tanks are full and shall supply the recirculation start time and tank volume. Recirculation is required to insure that a representative sample 17 obtained. The recirc time for Reactor Witer' Cleanup Phase Separater Tank is 30 minutes ano for condensate phase separator tank is 60 ,inutes.
(2) After the required recirculation time, collect about 25 ml. of the slurry in a one liter bottle.
() The Unit One Sample Points are located on the discharge side of the CPS mixing pump for CPS resin, and on the discharge side of the cups mixing pump for CUPS resin. The Unit Two Sample point for both CPS and CUPS is located in the Waste Skid Room on Unit 2, Radwaste 132' elevation. If sample points are not operable, corrective action should be taken, and dip samples obtained in the interim.
(3) Place a 5 micron millipore tilter in a petri dish and weigh. Record results on Data Package 1 (Data Sheet 3).
(4) Ensure that the filter holder is clean.
(5) Place the millipore filter in the filter holder of the vacuum flask.
(6) Place upper filter holder over filter and secure.
(7) Filter about 5 ml of sample through the filter disc using the standard vacuum filter flask. Pull a vacuum across the filter for approximately 1 minute or until resin is dewatered.
(8) Remove the filter disc, and place it in petri dish.
(9) Reweigh the filter and petri dish. RecordX reggdjhut on Data Package 1 (Date Sheet 3).
_ l
a *wa' N. I. Hatch Nucl:Cr Pl:nt ==o= ~o HNP. 8016 Sze Title Page newsuou so o.m GeorgiaPower d ..ee .
Gee Title Pace 3 of 17
,G :
'U (9) Reweigh the filter and petri dish. Record results
. on Data Package 1 (Date Sheet 3).
f (10) Obtain an isotopic analysis of the~ sample using a Ge(Li) detector. Gample size and geometry should be selected such that dead time of the detector is less than 10% and the counts are quantifiable.
The isotopic analysis should be in units of uCi/cc. This can be obtained by dividing the sample weight in grams by the density of resin which is taken to be 0.3 qm/cc.
(11) If the specific activity for isotopes greater than five year half life is greater than 1 uCi/cc, then the resin.must be dewatered in a high integr ty containee and if it is less than 1 uCi/cc, then the resin should be dewatered in a steel liner.
For administrative purposes the following limits shall be adhered to:
uCi/cc Action
<O.90 Dewater in a steel liner i,._s) >O.90 but 40.95 Resample tank; if 4 0.95
'~'
uCi/cc dewater in steel liner, if > O.95 dewa ter in a high integrity container
>O.95 but 4350 Dewater in a high integrity container
>350 Resin must be solidified Exceeding administrative limits must be approved by a Laboratory Supervisor or higher authority.
(12) Complete Data Package 1 (Data Cheet 3).
(13) Curie content of the shipment liner can be determined by the following formula:
Activity in Curies = Total activity (uCi) x 10-CC Ci x volume of resin cu ft x 28317 (cc )
uCi ft3
(~T b. Trash in a B-25 box.
%)
gauh 4 n
MPFOvA PRCCEDURE NO
. E. l. HATCH NUCLEAR PLANT HNP-8016 See Title Page aavsaw ~o out 14
~ ~o km See Title Page Georgia Power 4 of 17
_/
~
(2) Average the highest readings collected at each point (mR/hr).
(3) Estimate the Curie content using the formula below:
mci = 92 x D.R. x (x)
Where D.R. is average dose rate in mR/hr from step D.3.b.(2).
(x) is read directly from the curve on Table 1.
- c. Trash or absorbed oil in a 55 gallon drum.
(1) Measure the exposure rate at 3 feet from surface of the container in mR/hr.
(2) Average the highest readings collected at each point (mR/br).
(3) Estimate the Cc le Cu. tent using the formula below:
mCh = (6.9)(D.R.)(X)
{ }.
Where D.R. is average dose rate in mR/hr from step D.3.c.(2)
(X) is read directly from the curve on Table 2
- 4. Cask Handling
- a. Refer to appropriate PRB reviewed cask handling procedures provided by vendor.
- b. To assure all critical functions are performed, the cask handling check-off forms shall be completed. Use the cask handling form titled " User Check-Off Sheet"
. Data Package 1, Data Sheet 4.
- 5. Shipping Papers
- a. Shipments to Barnwell Disposal Site shall include the following forms:
(1) Bill of lading (2) Chem-Nuclear Radioactive Shipment Form q
t.s/ (3) (Resins Cnly) Solid Radwaste Decision Log *, Data Sheet 3.
man set
4Nyal PROGDuRE NO
. E. l. HATCH NUCLEAR PLANT HNP-8016 See Title Page aev.se ~o one 14 o/ GeorgiaPower o
~ ~o ws See Title Page 5 of 17 (4) Isotopic analysis *
~
(5) Truck Survey *, Data Sheet 2A or 28 (6) (Cask only) Cask Handling Form *, Data Sheet 4 (7) Prior Notification Form (8) South Carolina Certification Form
'9) Exclusive Use Statement
- b. Shipments to Hanford Disposal Site shall include the following forms.
(1) Bill of lading (2) U.S. Ecology Radioactive Material Shipping form.
(3) (Resins only) Solid Radwaste Decision Log *, Data Package 1, Data Sheet 3.
(4) Isotopic Analysis *
(( ) ,
t ra ) Truck survey *, Data Sheet 2A or 29 (6) (Cask only) Cask Handling Form *
(7) Prior Notification Form (8) Exclusive Use statement (9) Dept of Social / Health Services Certification Form (10) (Broker shipments only) Broker Certification Form
- c. Shipments to all other locations will include, as a l
minimum, the following forms.
l (1) GPC Radioactive Shipment Record (2) (exclusive use only) Truck Survey Form *, Data Sheet 2A or 2B (3) (if required by receiver of Radioactive material) isotopic analysis *.
)
- Indicates forms in which the original remains at Plant Hatch and duplicates accompany shipping papers. All other forms not denoted by an asterisk (*) willbeduplicatedafter,,,,(gt ,
completion and attached to Data Package 1. (
dN4 PROCEDURL PeQ E. I. HATCH NUCLEAR PLANT " -8016 See Title Page aviso =~o om 14 O'/ Georgia Power -
See Title Page o 6 of 17 1
- d. All forms li.sted in 5.a., 5.b., and 5.c., will be completed in accordance to 49 CFR parts 100-177,,.10 CFR I parts 61 and 71 and all state and burial site criteria.
l l e. Due to the state and burial site requirements to use specific form types for radioactive shipments, and to avoid redundancy, Data Par.kage 1, Data Sheet 1 will be used for the documentation of radioactive material shipments.
- 6. Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments.
l Record, every semi-annual period, on Data Package 2 the f following information.
f at Cubic meters and total curies of spent resins, filter sludges, evaporator bottoms, etc. For 6 month period.
- b. Cubic meters and total curies of dry compressible waste, contaminated equipment etc. For 6 month period.
- c. Cubic meters and total curies of irradiated components, f'#)
control rods, fuel channels, etc. for 6 month period.
- d. Other items that contain licensable amounts of radioactive materials not covered above for 6 month period.
- e. Breakdown of percent and curies of major nuclides for each of the four categories above.
- f. Number of solid waste shipments, mode of transportation and destination of the shipments.
- g. Number of irradiated fuel shipments, mode of transportation and the destination of the shipments.
- 7. Inspection of Shipping Containers
- a. 55 gallon drums and B-25 boxes used for the shipment of Radioactive Waste should be visually inspected prior to filling. This inspection is a check for defects in the package which could possibly cause a release of its contents during waste compacting, packaging and shipping.
("h V
4 manut not
APPHOvat NOURE NO
. l. HATCH NUCLEAR PLANT HNP-sol 6 See Title Page RtWl5CN NO QATE "
PAa No See Titie Paga O@a Nur 7 of 17
- b. After the waste compacting and packaging process, all 55 gallon drums and B-25 boxes used for the shipment of Radioactive material will be visually inspected as described in D.7. above.
- c. 55 gallon drums or B-25 boxes which do not pass the inspections of D.7.a. and D.7.b. will not be used for the shipment of Radioactive material.
O i
lo 1
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<-== E. l. Httch Nucircr Plcnt *= a maa~o HNP. 8016 Sao Title Page nemio= ~o o.m Georgia Power d .. .
See Title Page 8 of 17 r%
(V' TABLE 1 ACTIVITY DETERMINATION FOR 6 x 4 x 4 LGA BOX
.! ! I l l l 1
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. 02. .ats .os .or .fo .a. d4 .tb .// .2.0 .2.2. 24 .f6 .M ..
(y) ,rv//,ewie.c per suhic ff. per nrj!/
O U
manut set
e a aova E. l. Hitch Nucirr Pl:nt aaoceoua. ~o H NP- EOl6 S2o Title Paga aevisio= ~o
'+
om Georgia Power d ..m.
See Title Paae 9 of. 17
- t TABLE _a WEIGHT OF DRUM IN POUNDS y
- :: CL _ - T~ _ _
~
k x q == ==
2 Z ZZ Z ZZ Z
~
.iZ:-
-~
_3 __ __ _ ._ __ _
Q ggy:7-]rrrz
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9
_ _. _\ _ _ ._ _
_ _ _ _ ._ . _.. _ _ _ _ .._ .__ 2 EZZ Z $Z __.Z
- ~ ~
__ _ _ 'Z ; GJ x x x x x:_ _ _ x _ =- - -
- T 1 1.
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= = = = ._ _
=__ _ __ _ __
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_s ._ _ __ ___ ____ __ _ _
x" s m
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Z Z:T Z Z Z .__ .__ . __
y p _ _ __ ____
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4 4 U_ _
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$ m x xx x x _ __ _ e i
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=
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< 5 9_ ___ __ _
, x T- r uzzz -
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.: = = = = ===== -
-\-' - - -
.c
== === = - - - -
x _ _ __
- : : ?'~~R :~ :
~~ ~~ ~~~ -~~ ~ ~~ '
- = == -
_ _ = = == -- --
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l kkkk kkk$$$ $ $
mandd 1
. t aova E. l. H;tch Nucle:r Picnt ea===asao HNP. 8016 Gro Title Page nevision o
- o. GeorgiaPower d a.
See Title Page 10 of 17 0
PROCEDtRE DATA PACHAGE DOCUMENT NO: l@ -8015-1 9 -
SCRIAL NO:_R_14-MPL NO: N/A RTYPC:_GlQzi4 XREF: N/A TOTAL SHEETS: 6 FREQUENCY: As Reagin d _
COMPLETCD DY:
DATE COMPT _CTED:
I ttAVC REVICWCD THIG DATA PACHACC FOR COMPLETCNCES APO AGAf tCT ACCCPTAPCC CRITCRIA Ir4 ACCCRDANCE WITH HNP-330.
ACCFPTAOLC UNACCCPTADLE REVIEWCD DY:
DATC PCVICWCD:
RCMARKS:
Page 1 of C.
- I tJP -dol 6 R14 A
L)
FIGURE __1 Page 1 of 6- g{g m
. =om E. I. Hitch Nucirr Picnt a=ce== =
HNP- 8016 Sao Title PeSa MYWON NO o= Georgia Power mA ..os .
Gee Title Pace 11 of 17 (3
i/
v QAIA EM!iML1 DATA SHEET 1 Shipment Number Date:
Shipment to Hanford Other Shipments Shipment to Barnwell Disposal Site Disposal Site Bill of Lading Bill of Lading GPC R9R Form U.S. Ecology RSR Truck Survey Chem-Nuclear RSR Form Form Solid Radwaste Isotopic Analysis Golid Radwaste Decision Log Decision Log
!sotopic Analysis Isotopic Analysis Other (List Below)
Cask Handling Form Cask Handling Form
-__.4 .---______. .______________.______
Prior Notification Prior Notification Form Form
___.. .._______......____.. _ _ _ ...______... ._______e South Carolina Dept. Social / Health Certification S6? vices Certifica-(' ') .. . . . . . . . _ . . . . . . . _ _ _ _ _ . . . . .
tion Form Exclusive Statement Broker Certifica-tion Form
~. . . . . - _ _ _ _ _ . . . _ _ _ . . - - . ..... ________ _____.-
Truck Survey Truck Survey Others (List Others (List Delow) Below)
~.__ -_-__...... _____
r To indicate type of shipment, place a check ( v[) in the space to the left of the column heading. Also indicate forms attached by placing a check ( g/ ) in the space to the left of the form title. Write NR for Forms not required. All formc which are denoted by a check (9/ )
will be attached to this data package. :
i Page 2 of 6 HNP-8016 R14 .
O) n.,
FIGURE 1
- Page 2 of 6. -
maahan' set e
~
. /raos E. I. Hctch Nucl:cr Pirnt ~xt=as ~o HNP. 8016 S n Title Page asYisio= ~o o.m GeorgiaPower d ... P.o.
Gee Title Page 12 of 17 m
1 J
QATA PACHAG L1 (Data Sheet 2A)
TRuCM SLRVEY MAP-VM OR FLATRED TRUCH e
94!P6 NO. _
L.
- tM DADED LOADED TIE LOCAT19e
- IPETR S -
9ER I A PET S i .i h"M (Lpa m) 00 E RATE LJ4.0ADED MAeLTh d*
LOCAICN (!R.5tFACE)mr/hr LOCATICN il
- t. F
@@ @ @ D@
liLOMED)* OGE RATE ar/hr -
MICM MJtFACE '6' AWAY RECGtO H!CSEST
@ 2 3 READING fEAGLRED 4 AT DISTANCE CF 5 _ INTEREST i%) 6 7
e i CEMRAs VO41CLE CapetTION VEHICLE CPERATCyt 1 6 TED BY i
REMARMS DATE
!EAL Nu'S SURVEYED BY DATE REVIEnED BY DATE M.A4.TH PHYSICS SLPERVISOR E
TM RADIATICM LEVEL SGA D PCT EXCCC 165 mr/hr AT 'UtFACE. 8 mr/hr AT 6 FT.
ANAY FRCN !RJtFACE ADO 1.6 mr/hr AT ANY PELMA4.1Y OCCLPIED POSITICN. EXCEEDING T)E!E @!NISTRATIVE LIMITS PtJST BE APPROVED BY A LJecytATCytY SLPERVISGI OR HIG>ER AUT)(ptITV.
- Record results in dpe/100 cm 2 .
Assure that seats have been atta* bed to all vehicles after loading. For incoming unloaded
- Sole use Vehicle's* the foltooeing limits that! apply 9EARABLE CtNTAMINATICN d2200 OPM/100 cm3 9 ETA, GApem M e 6 220 ,
OPM/100 cmA ALPHA. FIXED CCNTMt!NATICH 4 5 mr/hr AT SJtFACE.
I!NP C01C R1*
FIGURE 1 Page 3 of 6- g'gg ,
=ao= E. l. Hr.tch Nucl3 r Plent aaocewa No H NP- 8016 Sao Title Page aevisic.. No oA1 Georgia Power d .A N.
See Title PeJe 13 of 17 U
QSTA PACHAQ W '
(Data Sheet 20)
TRuCM knNVEY MAF* C4adC 941PDENT P43.
*; . t tJa namn LOADED
_M TipE b ! d LfEAT ICDS u /& ! IsimAENT ,
g .;g __. St1AL PC'S SEAR SRWY I hh @h@ h (Lp(OADED) 00lE RATE LDCATICN URPFACE)me/hr LOCAI1(N 1
tsLOADED PAL 1J :" 1 R N T9
- AV <
2 Pali.J c b 3 PALLT 3 N s e O'- 1.-
h -(LOADED)* D E RATE mc/hr LOCAICN SJtFACE '6' AWAY _
RECCNIO HIGEST a READING PEMRRED Q
v-
~
4 AT DISTANCE CF 5 INTEREST V ,
H CDERAL WNICLE CCPC171CN VENICLE CPERATCyt I M C1ED BY .
DATE ys
!EAL P47eERS:
i DATE l StJtVEYED BY DATE REVIEWED BY tEALTH PHYSICS SLFERVISGt
!EIfs TE RADIAT.CN 1.EVEL 90A.D PCT EXCEED 165 mr/hr AT SJtFACE. 8 mr/hr AT 6 FT.
EXCEEDING i
AWAY FRCN SLJtFACE #S 1. 6 mr/hr AT ANY NGtMALLY OCCtFIED POSITICN. j
! TE!E ADMINISTRATIVE LIMITS 14.ET 8.! APPROWD BY T)E LABORATCytY SLFERVIScyl Cyt l l .
HIGER AUTMit1TY.
- Record results in dpm/ LOO cm 2 . See Section M and G for limits.
For incoming Assure that seals have been attached to all vehicles after loading. _
unloaded " Sale use vehicle's* the followsng limits shall apply!.
!3EARABLE CCNTAMINATICM f 2200 OPM/100 cui BETA, C#N4 MO A 220 DPM/100 cm 3 ALPHA. FIRED CCNTh41*TICN 6 5 me/hr AT SLRFACE.
l rap 4 or C 3 I N 3016 1114
[v}
FIGURE _1 Page 4 of G. -
aam a{ set
P a == E. l. H;tch Nucl=r PI:nt aaoce =a. =
HNP. 8016 S n Title Pega ,,m,o,, ,
om GeorgiaPowerd r. . .
See Title Page 14 of. 17 m' :
l
%l QATA PAQ!{AQg_i_iq0NT)
DATA CHEET 3 SQLID RA0 WASTE OJCISION,__LQQ
~
UNIT: TAbH: __ ,, __ DATE:
TYPE OF .*ESIN: PObOEX BEAD 9 .
Gross weight = gm Tare weight = gm Not weight = gm . . .
ICOTOPEG SPFCTFIC ACTIVITY FOR ICOTOPE WITH T 1/2 > 5 years (uCi/cc)
...._ ... - . . . . . . . _ . . . . . . _ . _ _ _ _ _ _ _ . . _ . . - _ . . . . . . . . . _ ...._______ f, TOTAL GPECTFTC At'TIVITY IGOTOPgg T 1/ ,' > G YEARC _ ,
Tvpe of linar used: Steel O righ Integrity O Volume nf res in - trans f er re d: Cubic Feet O
(v/ Liner Gerial Number 4
Cuale contant of the liner a total activity (ggi) x 10 Gi_
cc uCi x OS31T ( cc ) x volurne a f r e 5 iti (cu ft) cu ft
=( ) ( ) ( ) ( ) = Curies
- CCRTIFICATTrVI 9TATCM NT FOR DIGrrCAI,gF kNVIRONGAFC fC HIQt TNirgp I rv CONTAitE't F~or the l~NVIRObCAFE" liigh Integrity Containers to be disposed of f at Chem-Nuclear's Barnwell, South Carolina Low-Level Radiuective l Waste Ourial Facility and identified by sertal sumcars I (Company) Georgia Power Cgmp;3nv - IIs t;h Nu ri -ar Plant laws eby certifies tr.at its use of such cnntainers %s cwp1 t a J wi ir. tow '
certesin Carolina Department of f!ealth and C9vircnu nt=1 Cwntrui, Ouremt of Padinlogical fiasith, No. DM CC IC ' L 0C* , c.u all amendman+s thereto.
CCMPAtN: M rjia P owe s Co.
lla tch Nuclear i 1an 3 t
GY: TITLE:
DATED:
Page G of G -
irr-solc R14 p
t L
FIGURE 1 Page 5 of 6 _ gggt .;
h
.v -,,n -
==a E.1. Hatch Nucl::;r PI:nt aaOCs= = ~0 HNP. 8016 Sao Title Pa92 tensio ~o
-e Georgia Power d pm o See Title Page 15 of 17 t'h QATA PACHAGg_1 (CONT)
DATA SEET 4 gggR C TCH-OFF SEET Oate Shipment NuAdr- _ Waste Identifitation Worker (s) if Technician (s) 9 -
Driver __
Time of arrival on site Time of departure from site
.=___ -- - --- __
Please snitial when completed, Worker (W), Supervisor (S)
- 1. Disposen liner closure devices replaced (W) (S)
- 2. Primary lid gasket inspected (W) (S)
- 3. Secondary lid gasket inspected (W) ,, (S) 4 Primary 1sd fasteners torquod * (W) . (8)
- 5. Secondary lid fasteners torqued (W) , ,. (S)
~
- 6. Cask sealed with lead seats (W) (S)
- 7. Cask lie down inspected (W) ___ (5)
- 8. Cask hold-down fasteners torqued (W) (S)
- 9. Vehicle placarted (W) (S)
I h'ereby certify that the above statements are correct and the cash has asen lo9 ded and tested an accordance wath approved procedrres.
Workertsl e
Healtttphysics Team (s)
Supervisor (s)
- CASM ID M W ALtKS (FT. (QM d CPd31 14-195 Large lad 200 1 10 Cteil 21-300 Small tid 50 1 5 CNGI 8-120 420 1 42 PaPAC 14/210 (Refer to PLPAC prs.cedure for torquod values)
Page 6 of G HNF -8016 R14 O
L; FIGURE 1 Page 6 of 6. J7 (gt
, a*"* W %
n
- ^"ama E. I. Hrtch Nucl=r Pl nt Hocioua. o HNP. 8016 S2o Titio Pcge news o,, ,,o o i. Georgia Power d ..
See Title Page is of 17 l C\
V PROCEDURE DATA PACKAGE DOCUMENT NO: HNP-301@-2 7 -
i SERIAL NO: R14-MPL NO: N/A RTYPE:_G & 14 XREF: N/A TOTAL CHEETS:_@
FRCOUCNCY: As Reguired _
COMPLETCD DY:
DATE COMPLETED:
l I HAVC REVIEWCD THIS DATA PACKAGE FOR COMPLCTENCGS AND AGAINST ACLEPTANFC CRITCRIA IN ACCCRDANCC WITil HNP-830.
ACCEPTvPLC UNACCCPTADLC REVIEWCD CY; DATE REVIEWCD:
REMARMS:
-m l
Page 1 of C
' t iNP-3010, R34 O FIGURE R ,
Page 1 of 2- samtal18%
I
saa ova' E. l. H;tch Nucl:~r Pirnt' mocama6 *a HNP- 8016 Sea Title Pega r evisio~ ~o
-. Georgia Power d .... ~o See Title Pace 17 of 17 O
v OATA PACHAGG_Q l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLIDWA2TE ANO1RRADIATED FUELSHIPMENTS FOR UNIT A.SolDY.'ASTE SHIPPED OFFSITE FOR BURIAL OR DISPCSAL (fJotinadiated fuell un: **"*"'" E st T* *'. .
- 1. TYPE of waste PwW Emer. %
- a. $ pent rise.s. :dter sN15:s. enporator en 8 E bnttoes. etc. Ci E E
- b. Dry compreuisie waste, contacunatc2 _.
m' . E equip, e::. Ci E t
- c. l. rad ated componenu. con.ici m' E tty:s. etc. Cl I E
- d. Other (desenos) m' E C4 . E . E 1 Esttmste of maior nuclide composi: ion (by typ of waste)
ISOTOPE PERCENT CURIES 3.
b.
%s C.
d.
- 3. Soud Weste Disposition l Number of shipments Mode of Tr2nsportation D:stinstron l
! E IRRADIATED FUEL $;t!PMCJTS (Disronition)
\
Number of Shier-ents Mode ef Transpor stion Destination COMPLETED BY DATE ,
i l
t Page C of 2 ier-colc n 1.+
O O
!, FIGURE 2 l Page 2 af 2. .
m{#
i
. , _ _ _ . , - . _ _ _ _ . _ , __ _ _ _ _ _ . _ . .