ML20024A774

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8004 Re Personnel Dosimeter program,HNP-8016 Re Shipment of Radioactive Matl & HNP-4622 Re Control Room Operators
ML20024A774
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/26/1983
From: Nix H, Rogers W
GEORGIA POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20024A773 List:
References
GM-83-457, PROC-830426, NUDOCS 8306220310
Download: ML20024A774 (181)


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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE A

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PROCEDURE AUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X )

NON-SAFETY RELATED (

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APPROVED APPROVED REV.

DESCRIPTION DEPT.

PLANT DATE HEAD MANf ER

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AWHOvAL PHOL t DUML NQ E. l. HATCH NUCLEAR PLANT HNP-BOO 4 See Title Page atv - v oait 15 h

See Title Page 1 of 22 PERSONNEL DOSIMETRY PROGRAM A.

PURPOSE To describe a procedure for the issuance and use of personnel dosimetry equipment for plant personnel, visitors, and construction workers while within the operating buildings.

B.

REFERENCES Code of Federal Regulations, 10CFR20' l

A.P.T.

Computer Exposure Records System D'SCRIPTION OF DOSIMETRY EOUIPMENT C.

E 1.

Thermoluminescent Dosimeter (TLD Badge)

The TLD Badge is a small badge containing two or more lithium fluoride TLD chips for measuring external beta gamma

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radiation.

These badges are supplied by a TLD badge vendor "i

and will be processsed at monthly intervals during normal operations, and at more frequent intervals during maintenance outages or when conditions require.

The TLD badge vendor will read and evaluate the badges and report the results to a Laboratory Supervisor.

The record of l

accumulated external radiation exposure received by individuals is obtained principally from the interpretation of the TLD badge.

2.

Direct reading pocket dosimeter The direct reading pocket dosimeter is a pencil shaped ion chamber used primarily to provide day-by-day indication of external Jamma radiation exposure.

A dosimeter with a range of O-200 MR is provided for normal use.

For special requirements higher range dosimeters will be issued as necessary by the Health Physics staff.

3.

Neutron Dosimetry The Health Physics staff will review the R.W.P.'s each dosimetry period for personnel who may have become exposed to neutron radiation.

The TLD badges for these individuals will be mailed to the TLD badge vendor requesting tha t the badges be read both for beta gamma exposure and neutron exposure.

The report for these badges will be handled the same as in paragraph C.1.

MANUAL SET

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Other issue

- ~~lfs deemed appropriate the Health Physics staff will i.e. Finger rings, TLD other personnel monitoring devices, bracelets, chirpers, etc. for monitoring personnel radiation exposure.

ISSUANCE _OF TLD BADGES AND POCKET DOGIMETERS D.

TLD l

Prior to issuance of any TLD badge or dosimeter Form 1, 1.

See Section G.

BADGE AND DOSIMETER ISSUE must be completed.

for details.

Issuance of any TLD badge may be made only by a member of

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2.

the Health Physics staff.

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Issuance of pocket dosimeters may be made only by a member b

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of the Health Physics staff.

Prior to entering the operating buildings where radiation J..

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exists all individuals assigned TLD badges and dosimeters j~

will pick them up and wear the oevices as in Section E.

Daily dosimeter reading will,be logged as in Section G.

I NOTE Dosimeters that have been used, and then placed in the "OUT" rack, will be re-zerced prior to the start of the next work day, if a reading of 40 mrem, i

or greater, has been reached.

E.

WEARING AND USE OF TLD_ BADGE AND DOGIMETER The TLD Badge and dosimeter are to be worn adjacent to each other v

between the waist and neck on the front part of the body.

As per Health Physics discretion, an individual may be instructed to if it is wear the dosimeter and TLD on another part of the body, determined the dose rate at that part of the body is likely to be When wearing protective higher than that between waist and neck.

clothing, the TLD badge and dosimeter are clipped inside the (Outside pocket) of the coveralls and pocket breast pocket The TLD badge shall always be worn with the face of the closed.

badge facing out.

Each' individual should exa'mine his dosimeter in a radiation controlled area.

No individual periodically while should allow the dosimeter reading to exceed 150 mR or 75% of full scale regardless of any prescribed exposure allowance, without having his dosimeter recharged and reading r,ecorded.

finding self reading dosimeters off-scale shall Personnel immediately leave a Radiation Control Area unless involved in controlling an. emergency and shall notify the Health Physics MANUAL SET 3

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Staff.

The loss of any personnel monitoring device requires the immediate notification to the Health Physics staff.

NOTE If at anytime the dosimeter is dropped or erratic readings are noted by the user,.the Health Physics Staff should be notified in order that another dosimeter can be issued if deemed necessary.

F.

WEARING AND USE OF EXTREMITY DOSIMETRY The following criteria should be used for the use of extremity dosimetry:

1.

Extremity dosimetry is defined as finger rings, or as per H.

P.

discretion, TLDs taped to one of the extremities.

The extremities of the body are hands, forearms, feet, and j

ankles.

-1.

I 2.

Health Physi.cs shall determine the need for extremity monitoring on an individual job basis.

Factors involved in making this determination are dose rates, stay times, etc.

Extremity dosimeters will be provided for those individuals requiring this coverage.

3.

Guidelines for using extremity dosimetry are as follows:

a.

When the extremity exposure rate is likely to be four times the whole body exposure rate AND the extremity exposure rate is likely to be > 400 mrem /hr.

b.

When performing primary systems sampling, manipulating

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higWiintensity calibration sources, or performing any task for which extremity dosimeters are required by H.P.

i 4.

Extremity dosimetry will be issued and returned on a daily basis, unless specified differently by H.P.

If personnel need extremity dosimetry more than once a month, they will be issued the same extremity dosimeter (finger ring, etc.)

for the duration of the month.

Form 5, Extremity Badge Issue Log will be completed as needed.

I G.

ESTIMATING NEUTRON EXPOSURE 1.

Until an individual's TLD is read and the actual neutron exposure determined, an estimate will be generafed in the following manner:

Form 11, NEUTRON DOSE ESTIMATES will be used to record neutron dose.

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As per survey data, calculate a neutron-to gamma ratio by dividing the neutron dose rate by the gamma dose rate.

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b.

Multiply the neutron-to-gamma ratio times the gamma dose recorde,d by the pocket dosimeter.

Add this product to the gamma dose to obtain the total c.

whole body exposure.

d.

Example of above method:

(1)' Gamma dose rate:

60 mR/hr Neutron dose rate:

30 mR/hr

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Dosimeter reading:

80 mR (2)

Neutron-to-gamma ratio:

30/60 = 0.5 (3)

Estimated neutron dose:

(80 mR)(0.5) = 40 mR (4)

Total whole body dose:

80 mR + 40 mR = 120 mR

,1)

Input the total whole b,ody dose to the computer via e.

DDUDAT Program or use Form 2 of this procedure if the computer is disabled.

H.

RADIATION PROTECTION ORIENTATION All new employees shall receive a radiation protection I

orientation prior to their assignment of work in Radiation Control Areas or have an escort by someone who has demonstrated understanding of radiation protection practices and procedures.

See HNP-8018.

The orientation will cover all pertinent radiation protection practices and procedures to a degree sufficient to allow an employee to perform his assignment without incurring unnecessary ra,iation exposure or contamination.

Each employee d

will be required to demonstrate an understanding of these procedures prior to being allowed to enter a Radiation Control Area unescorted.

I.

PERSONNEL DOSIMETRY RECORDS 1.

. Form 1, TLD Badge and Dosimeter Issue The preparation of this form is the responsibility of f

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l ll the Health Physics Department.

The purpose of the form is to record all information required by 10CFR2O for personnel wearing monitoring devices.

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Procedure for recording information on Form 1.

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The individual shall complete the upper part of 1

I the form down to the heavy black line.

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Health Physics Department shall complete the bottom part of the form.

(3)

The form shall be filed and maintained in the dosimetry office until termination.

t 2.

Form 2, Weekly Pocket Dosimeter Record This form provides a means for recording personnel a.

h pocket dosimeter results daily and will assist in evaluating each person's integrated dose to keep exposures as low as reasonably achievable and below

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exposure limits of 10CFR20.

The form will be used if the computer exposure record l.

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system described in I.9 becomes disabled and when visitors are issued dosimeters and TLD's.

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b.

Procedure for recording information of Form 2 Form 2 for the current week will be maintained by (1) the Health Physics Staff.

(2)

Separate sheets of Form 2 will be kept for each type of personnel.

(3)

The individual whose name appears on Form 2 will record or have recorded his dosimeter reading on entering the operating buildings (IN DLOCK) and on exiting the operating buildings (DUT BLOCM) at the end of the work day.

It will then be calculate or

!have calculated the indicated exposure by determining the difference between the IN and OUT 9, blocks and will log the result in the NET block.

l (4)

The Health Physics staff will log each individual's accumulated quarterly exposure in the l

OTR block at the beginning of each week.

l (5)

The Health Physics staff will determine total daily exposure by adjusting the indicated exposure with exposures determined from. Form 3, Dosimeter Re-zero Record and other methods as necessary.

These adjustments will be logged in the ADJ. block and will be added to the NET exposure to determine MANUAL SET

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the tot'al exposure for the day and recorded in the

. TDT block.

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(6)

The Health Physics staff will determine the accumulated weekly exposure for each individual by summing the TDT block for the day and the WK block for the previous day.

(7)

The Health Physics staff will adjust the quarterly (GTR) exposures to reflect official exposures as 1

determined from the processing of TLD badges during the current quarter.

3.

Form 3, Dosimeter Re-Zero Record This form is used when an individual's pocket dosimeter is re-zerced while within the operating buildings.

DDUDAT f

cards may be used in lieu of Form 3.

The form will he located at each dosimeter charger station.

It shall also be used when zeroing special pocket dosimeters as issued by the Health Physics staff (Indicate special in the Remark i

Column).

Exposure data from Form 3 shall be entered on Form j

2 or in the computer record system from each individual..

H See I.2 or I.9 of this procedure.

4.

Current TLD Occupational Radiation Exposure Report i

a.

This report will be furnished by the TLD vendor at a frequency based on badge exchange intervals.

The report is approved for use in lieu of NRC Form 5.

b.

Results of TLD exposure analysis will be entered into 1

the computer exposure record system on a monthly basis or with greater frequency, as this data is provided by the vendor.

Current NRC Form 5 information may be obtained from the computer system at any time on an indiDidual or departmental basis by using the INDDRP or

-the DDLIST program respectively.

5.

Form 4 Replacement Exposure for Lost or Damaged TLD Badge This form will be completed as necessary to estimate personnel exposure during a period when a TLD badge has been lost or damaged.

Exposure determined on this form will be entered on the Current TLD Occupational Radiation Exposure Report through the use of a letter to the TLD vendor as shown in Form'8 and into the computer exposure record system.

MANUAL SET

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6.

Form 5, Extremity Badge Issue' Log

,_, Form 5 will be filled out as needed and completed by the end

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of each month.

The extremity dosimeters will be mailed to O

the vendor at the end of the month for analysis, and the results are supplied by the vendor on the. Current TLD Occupational Radiation Exposure Report.

7.

Form 6, Request for Employee's Previous Radiation Exposure A letter shall be written to an employee's previous employer (s) if the employee does not have his previous exposure-record and indicates that he may have received occupational radiation exposure while employed there.

The

  • 8 letter shall be provided on Georgia Power Company stationary a

and in the general format as shown on Form 6, Request for Previous Radiation Exposure.

B.

Form 7, Report to Former Employees and Visitors of Exposure to Radiation.

j' On request by former employees a report showing expos'ure to a

radiation shall be furnished within 30 days from the time j

the request is made, or within 30 days after exposure of the individual has been determined, whichever is later.

The report shall cover each calendar quarter of the individual's time within the Protected Area involving exposure to radiation or such lesser period.as may be requested.

The report (Form 7) shall be xeroxed from individual's file and shall be transmitted with a cover letter (form 9) on Georgia Power stationary and in the general format as shown on Employee and Visitor Radiation Exposure Report, Form 9.

When an individual terminates employment or an individual assigned to work in Radiation Control Areas at the Hatch Nuclear Plant, but not employed by Georgia Power, completes his work

  • assignment the individual and the Nuclear Regulatory Commission will receive a report on his exposure to radiation and radioactive material incurred during the period of employment or work assignment.

Such report shall

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be funished within 30 days after the exposure of the individual has been determined or 90 days after the date of termination of employment or work assignment, whichever is l

earlier.

The report shall be provided on Georgia Power

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stationary and in the general format as shown on Form 7, Employee.and Visitor Radiation Exposure Report.

The l

original report may be obtained by accessing the computer l

exposure record system using the TERMN8 program, or from the Current TLD Occupational Radiation Exposure Report (para.

I.4).

MANUAL SET

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l PHQCLUURL Ped HNP-8004 E. I. HATCH NUCLEAR PLANT otv.,,0 See Title Page 15 o^' t 8 of 22 See Title Page 9.

Computerized Personnel Exposure Records la.

A computer for up-dating personnel exposure data on a

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day to day basis has been developed.

Pocket dosimeters are read by a Health Physics technician and the reading entered in the computer.

The computer updates the individual's exposure record to reflect the latest dosimeters reading.

Daily, weekly, monthly, quarterly, yearly and life time exposure information is made available to the Health Physic staff, plant supervision, and the individual through the use of various computer printout formats.

See APT Automated Personnel Dosimetry Records System Manual.

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Schedule of input and output of exposure information i

via the computer exposure records system.

(1)

Dailr -

Pocket dosimeter will be read on a daily

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basis.

I Entries will be recorded by the computer on a daily basis using the DDUDAT 0

program.

Where dosimeters are re-zerced in the Prim'ary Protected Area, the dose recorded on Form 3 shall also be entered into the computer using the DDUDAT program.

(2)

Weekly -

A listing of daily exposures for all personnel on site for each day of the week will be obtained at the end of each week using the DDPRNT program.

(3)jMonthly - The net dose indicated for each worker l

listed in the " Time Record" section of all Radiation Work. Permits issue during a given month shall be entered into the computer exposure record system prior to entry of the TLD data for the respective period, using the CWPUDT program.

TLD data will be entered into the computer exposure record system each month using the CLDUDT program as this information is provided by the v.endor.

Corrective or supplemental TLD data may be entered into the computer exposure record system using the HLDUDT program.

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9 of 22 NOTE Programming has been established to determine the discrepancy

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between the TLD and pocket dosimeter.

A discrepancy greater j

than 25% for exposures over 100 mR will be evaluated.

An investigation shall be conducted and documented on Form 10, Dose Discrepancy Investigation.

The TLD reading will be retained as the r6 cord exposure unless the investigation justifies use of i'.

pocket dosimeter totals.

Data files will be removed from the TMPDOS exposure record file each month for personnel terminating their stay at the plant whose final TLD data has been provided by the vendor.

The TERMN8

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program will be used to accomplish this

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and will produce the original letter of f

notification of exposure for the l

individual, as well as a copy of his

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final dosimetry file contents.

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(4)

Annual -

The NRCRPT program will be run after the~

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TLD results for each year has been entered into the computer.

A compilation of information to satisfy 10CFR2O annual reporting requirements will be provided by the program after the exposure information for an entire year has been recorded.

(5)ds reguired The PDFMAK program is utilized to enter new personnel information into the computer exposure records, to add identification or prior exposure information.

The DELETE program is used to transfer a personnel record from the active files to the TMPDOS file at the end of his 4

stay.

The record is retained in this file pending receipt of final TLD data

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from the vendor.

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10 of 22 The HLDUDT program allows the ~ entry of TLD information for individuals at times other than the regular monthly entry of

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TLD data on a plant basis.

The individual dose r,eports covering all NRC Form 5 information can be obtained using the INDDRP program.

The DDLIST program can be used to l

provide on a plant basis the same information.that the INDDRP program

'r supplies for a particular individual.

4 Whenever required, particularly during 1

an outage, the DDPRNT program may be utilized to obtain a listing of dose for each day of the current wrek and the margin between the cummulative exposure and the most restrictive exposure 1imit, for_each person on site.

j The Applied Physical Technology 4

Automated Personnel Dosimetry System i

l Instruction Manual may be referenced for information'on organization of data files and operation of programs.

10.

Form 9, Reply to Request for Previous Radiation Exposure When a request is received by Georgia Power Company from a previous employee or visitor for the purpose of providing his new employer (or facility being visited while in the employment of his new employer) with a record of occupational radiation exposure received at Plant Hatch, Form 9, Reply to Request for Previous Radiation Exposure, shall be used to supply this information.

'h J.

MANAGEMENT REVIEW OF RADIATION EXPOSURE DATA The H.P. Superintendent will be responsible for preparing a Radiation Exposure Report for the management meeting.

As a minimum, the report will consist of a tabulation of exposures by department, including the average dose received per worker and the maximum dose.

Also to be included will be a tabulation of exposures on specific maintenance work during,the month, if significant work has been performed.

Other significant exposure information will be discussed during the meeting as appropriate.

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.i See Title Page Bi-Weekly (every two weeks) updates of personnel exposure are provided to each department.

These records provide supervisors l

as well as workers information on radiation exposure accumulation and will aid in minimizing exposure to individuals by more l

efficient worker utilization.

In case of some problem, such as a computer malfunction, when the Bi-weekly update listing cannot be made then H.P.

supervision will be informed.

As soon as the problem is resolved the computer listing will be updated and the distribution to the different departments will be resumed.

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TLD BADCE AND DOSIMETER ISSUE

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(

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MAINT. CLCCT.(

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COUTHCPN GERVICCS INC.

(

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OPERATICNG

(

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TCCT DCPT.

(

)

A.D.A.

(

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L/0/HP

(

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OPCRATIONS

(

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(

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(

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LADORATORY-(

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(

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(

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OFFICE

(

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  • C.E.

(

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  • PLEACE DCCCRIDC:
  • CONTRACTOR

(

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s

  • CIVE NArE. OF Cut,PANY:

4 k

  • Have you worked at or visited a Nuclear Facility other than Hatch in the last three months?
  • YES ( ) NO (

)

l

  • If YCS, wh,at facility f

GICHATLRE Have you been at Plant Hatch in the last three snonths? YES(

) NO(

)

If visitor, escort's name TLD Dadge No.

PKtC Form 4 completed

)

Authorized Quarterly Esposure edlem*

[

Issued Dy Reviewed Dy

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wm If 18 years old limit esposure to 700 mitem/ quarter.

t If current quarter esposure is unknown, limit is 300 nrftem.

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FORM 3 DOGIMETER RE-ZERO RECORD 1

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i FORM 4 REPLACEMENT EXPOGURE FOR_ LOST TLD_ BADGE EGCleGEPCNT EltLV."C ERR _L92T TLo o^ocg 1.0. Dadge No.:

Date:

Name:

TLD No.:

Soc. Sec. No.:

R.D Dadge Was:

Lost (

)

Damaged (

)

  • 0ther (

)

  • If 'Other* Explain:

TLD Last Worn:

First Day of Current TLD Period!

JVE ASSQE@T Did Individual enter a radiation area today?

Yes (

)

No (

)

If

'No", cornplete items 1 and 2; if 'Yes' complete all items.

g mR l

1.

Sum of Dosimeter readings recorded during period:

i 2.

Source of above Dose Data: ttf2-BOO 4, Form 2:

00PRNT:

00UDAT:

COPPUTER

.r.

J'

?

3.

What Radiation areas did the individual enter today?

~

4.

How long was the individual in each area?

5.

What were the Dose Rates in these areas?

6.

What RWP No. was the individual working under?

7.

What esposures were received by others in the area?

Name; Dose:

Time in area:

Name:

Dose:

Time in area:

B.

Hased on the above information, what is the individual'smR.

estimated esposure for today?

Y e H.P. Representative Employee itd>-DOO4 R15 rann 4 ii MANUAL SET

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I 1

APPHQVAL W8C.LLDUML NO HNP-8004 E. l. HATCH NUCLEAR PLANT "tvoo m See Title Page 15 1

[

DAIL GeorgiaPower

~~

See Title Page o

16 of 22 FORM 5-EXTREMITY BADGE ISSUE LOG EMOUI.QEGJWJM f

@ TH:

YEAR

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  • Locotton of where L.H. denotes Left Hand Desseetry soms worn R.H. denotes Ragt.t Hand L.F.A. denotes Left Forearsi R.5". A. denotes Re gret Foreman L.f".

denotes Left Foot R.F. denotes Re ght Foot L.A. denotes Lett Ankle R.A. denote s Right Ankle e_.

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CM fMJVOL P6KLt DUHt NO E. I. HATCH NUCLEAR PLANT HNP-8004 See Title Page me. r.o om 15 See Title Page 17 of 22 FORM 6 REGUEST FOR PREVIOUS RADIATION EXPOSURE

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se.iev, c.oro a sists It

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Georgialbwer Edwin L Hetch Nuclear Plant l

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DATE:

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[

Subject Radiation Exposure Record Gentlemen:

The fotlowing IndMount has indicated that he received radiation exposure while working for your organization.

i, We would appreciate receiving copies of your exposure records for this emptoyee.

g j

Nemo of Employee SS/No (From)

(TO)

I very voir yours.

Laboretury Foreman i

i neren, aum.ue a reieas. of = enov. int-mauon.

v, (Date)

(Signature of Employee)

HNP.8004 R15 Form 6 MANUAL SET l

Pru.LDuHt ~o N'PHuVAL HNP-8004 E.1. HATCH NUCLEAR PLANT See Title Page aiV,s

~o 15 c

o^'t Georgia Power 18 of 22 t

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r See Title Page i

FORM 7

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Post Offace Scu 839 Sassey. Georgia 31$13 S3F 444 GeorgiaPbwer Edels 8. Match Noties, Plant DATE NAN

$$/NO:

ADDRESS:

..g DATE OF BIRTH:

/

SUBJECT:

RADIATION E3P05URE REPORT DEAR 511:

f, FLEASE BE ADVISED THAT WHILE EMP14TED OR VISITING AT THE EDVIN I. HATCH NUCLEAR F1 ANT DURING THE FOLIMING WORK PERIOD (S), TOU RECEIVED THE FOLIMING EXPOSURE TC IONIZING W IATION.

REC 0FDED EXPOSURE (REM)*

DATLS PONITORED FROM TO WHO!E B09Y -

SKIN EXTREMITIES 4

4 EXPOSURE DETERMINED BY TLD BADCT UNLESS OTHERWISE NOTED REMARKS 810-ASSAY RESL1.TS:

THIS "BF. PORT,15 FL1tNISHED TO YOU UNDER THE FROVISIONS OF THE NUCLEAR REGULATOPY CottilSSIO*1 RECU1At!0:t 10 CFR PART 19. YOU SHOULD FRESERVE THIS REPORT FOR TURTH REFERENCE.<j, IAA0kATORY SUrt'kVISOR XCs DIRECTOR. HNEACTMENT AND PROCFAM ANALYSIS U.S. IPJCLEAR RECULATORY COMMISSION WASHINGTON, D.C.

20555 FILE NNF-8004 P15 Fors 7 i

f MANUAL SET 0

=

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f muu punt No man 4 HNP-8004 E. I. HATCH N'UCLEAR PLANT I

atemo See Title Page 15 i

DAIL 19 of 22 3

See Title Page FORM 8 Gee.gia Peeer Company Pe.t Othee Bos 4;9 8.new, Coorgia 3:513 Tewonene St2 36F FF#1 912 S37 6444 m

Georgiahn EM L Hatch briest Plant

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l Eberline Instrument Corporation P. O. Box 2108 i

Santa Fe, New Foxico 87501 i

Attention: Dosimetry Services 4

Centlement I ---

The Georgia Power Company Plant E.

I.

Hatch TLD Occupational Radia' tion Exposure Report does (or will) not reflect exposure received by the following person for the indicated period because of

'. lost or damaged TLD badge.

Based on plant exposure records, we estimate the individual's exposure to hat TLD NO,

NAME 3.3. NO.

DATES COVERED EST. EXPOSURE fprM)

From:

U.B.

Skin Ext To Please adjust this individual's record to re flec t the above estimated' exposure.

f Tours truly, health Physics i

i

/

co: Individual's File MNP-P,004 EIS Forn 8 MANUAL SET r

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maciount No p

Ah movat HNP-8004 E.1. HATCH NUCLEAR PLANT revuon ~o See Title Page 15 oAn 20 of 22 See Title Page EORM 9.

i Gears a Poe,e Compaar rose o e.e. ses a+9 e.wv. c.ees. 3 50 e $ u kb a Georgiaher

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SUBJECT:

RADIATION EXPOSURE REPORT DEAR SIR.

ATTACHED IS A COPT OF THE EXPOSURE REPORT TURNISHED (NAME)

UPON TERMINATION OF VISIT OR EMPIDYMENT AT (SSAN)

PIAhi BATCH.

ALL EXPOSURE IS* DETERMINED BT TLD BADCE ENLESS OTHERWISE NOTED ON ATTACHED.

j TB15 REPORT IS WRNISHED TO YOU UNDER THE PROVISIONS OF 10 CFR 39.13.

LABORATORY FOREMAN ze: File

,I

'4 t

l nNP-40oi sis Form 9 l

MANUAL SET l

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rHCCLUuHL NO ArPHovAL HNP-B W

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E. l. HATCH NUCLEAR PLANT 1

  • m,0~ ~o See Title Page 15

[i GeoreiaPower 21 of 22

~~

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See Title Page k

FORM 10.

DDSE DISCREPANCY _ INVESTIGATION,

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~

02K DICmf.'.et&L1!.%2I196I173

_/TLDe_

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Individuals Namel to Period of Esposu,re.

er Reported TLD Dose or Recorded Dosimeter Dose

..g T,'

INVESTICATION FitOINGS:*

w e

l l

.1.

Investigating Techniciants!

4 u.

mr Record Exposure Accepted

/

Individual's Supv. notified _

/

Lab Foreman Review /Date approval Exposure entered into computer by*

Name/Date Eberlipe notified via Form B N.:nne /Date 9

  • Investigation w.ay include the following:

a.

Survey Results b.

Esposure Time Doses of other performing similar work.

c.

d.

Location of devices vorn on the body.

(

Type of Dosimeter, High Range or Low Range.

e.

f.

RWP totals.

4 ter-D004 n15 FORM lo

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NEUTRON DOSE ESTIMATES

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GEORGI A FOVER COMPANY HATCH NUCLEAR PLANT PROCEDLiR5

_ G__h_i ment Of Rad i nn ct i ve__M_a 6e.r s'a l E

__x PRDCEDURE TITLE H_NP-ROl6

- = -

PROCEDL!RE NUMBER 4

-_ Lab-.

RESPGNSIPLE SECTION SAFETY RELATED ( X)

NON-SAFETY RELATED (

)

APPROVED APPROVED i

REV.-

DESCRIPTION DEPT.

PLANT

.DATE HEAD MANAG-

______8 12 Page 15,16 & 18

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.__ _- O_F_P_ A_.R '.T.M_ E N_ T _l_iF_,tn _ A.- _ _:_< _.,.. _. - __-_ _

Date:

Dvte; Signatura:

Nota *;

S D Y" $

___3__,fC _h_________/__ _ GEM I jl V

_____ __7 _ _ _ _CCE OF.CPERATION OR INTENT

'a DEGCRIDED IN FSAR:

(

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(

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REV.ISIO:: CH.aa:GC : M i

(

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(

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..CHANGU INVOt.VES:

(See bacl< f or Saf ety Evaluation 10 required).

}

i Non-Safety Related

(

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Safety Related

(

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Safety /tton-safety Status Change (

) Yes

(

Attach mariced up copy of procedure to thi s f orm.

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The revisicn of this orocedure does not co_n_s.t._i t_u_t_e_a.n__u_n.r.ev_i_e_r_ed _c a_fe_t_y question as exclained below.

a_nd _t_h.e. c_q.n.w,m_u_e_n.c_es _o f__a n__et_c.c..i.d_e_n_t____

o 1

_T h_e_ _n r_o_b a..b. i_l_i_t y_o..f...o..c.c u_r_r.e., n c_a or dal~ function o f equipment imp _or_t_an._t t_o__s_a_fe_ty_.a.re__n.o._t _i_n.c..r..e.a_s_e_

a.b..o_v.e._t_h.o..s.a. a n a lin _th.e CS AB du.e 10. ti.nS.a rb.atLnRS_he.C.ad!se. _

m the revision does not chance the nurD.o.s_e _o_r_ne_r_f.o.rm_a._n_c.e. o_f _the_

_s.1_s_t_e m_._

The possibili ty of an_a_c_c_i_de_nt _or__m.a._l.f.u_nc_t.i.on o.f._a_ di f fere_nt._tv_o_e__ ____

2 th a n a ca_l.yz e_d_i_n th_e_FS_A_R__do_e s_' _no_t_._r_e_su_l t__f ro_m__t_h _i s__

  1. 8'-

- -_th._e_.s1s_t.e..m._r_e_s.c._on d_s_ a nd _i s ope ra te_d a.s._b_e_f.o.re _t_h.e.

c_h_a_n.c.e_.__________-

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fo_r____

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__s_a_fet'y l,.i_m_it__t_o_b_e_ exceed _e_d or to allow a limi tino.c_o_n_di_t_ on o_c_e_r_a t_i_o_n_s_t_o__b_e _e_.x.c._e.e d e.d.__as__s_t.a._t e.

__________________________u__q________.:-_--__------

J

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _. _ _ _ _ 1 _ _

MANUAL SET

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i-s.

MYMt.)WAL IM $ UVN NO E. l. HATCH NUCLEAR PLANT HNP-801G See Title Page

  • smo r@

oa 13 D

See Title Page 1 of 48 SHIPMENT OF RADIOACTIVE _ MATERIAL A.

PURPOSE To assure that all shipments of radioactive material meet the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) requirements.

B.

@AEETY Observe Radiation Protection Procedures.

C.

REFERENCES 4

1.

49 CFR 100-199 i

2.

10 CFR 71 3.

A review of the Department of Transportation (DOT)

Regulations for Transportation of Radioactive Materials, I

August 1976.

q:

4.

Control and' Accountability of Radioactive Material, HNP-8017 5.

Health Physics Journal, Vol 31, No.

5, November 1976.

6.

Barnwell site Disposal Criteria, HNP-8401.

D.

SPECIAL EGUIPMENT 1.

Appropriate survey instruments.

2.

Appropriate DOT labels and placards.

l

. 3.

Radioactlye Shipment Record (RSR) form.

CAUTION The technician is to visually inspect each package for integrity, dents, loose caps, or ruptures.

All packages MUST DE approved by a Laboratory Foreman, Laboratory Supervisor, or Health Physics Superintendent.

These persons must be knowledgeable in NRC, DOT regulations, Chem Nuclear requirements, and Georgia Power Company procedures for radioactive shipments.

MANUAL SET

. -. ~

1 N1UUHL NO AWHuyAL HNP-801G E. l. HATCH NUCLEAR PLANT See Title Page

-t m.u~ ~u 13 vus 2 of 48 See Title Page E.

MATERIAL _CLASSIE1C6 TION _AND__ TYPE OF PACKAGE __ DETERMINATION NOTE

~ ~ ~ ~

This procedure specifies steps to consider when preparing any radioactive material for shipment.

Shipment of fissile material requires special consideration to ensure against nuclear criticality due to the fissile nature of the materials.

1.

Determine what isotope (s) is to be shipped and whether fissile or non-fissile.

2.

Determine what quantity of.each isotope is to be shipped and the total aggregate quantity.

If a counting room quantitative analysis is impractical, estimate the aggregate quantity using radiation surveys and Section N.

1 3.

Determine what is the form of the isotope, i.e.,

NORMAL FORM or SPECIAL FORM.

See Figure 1 and Section R, Definition.

a.

If normal form, determine which transport group the radioactive material is classified by referring to 49

)

CFR 173.390 or the Table 1 below.

t TABLE 1

II Manganese 54 IV Plutonium 239/

I II Strontium 90 g IJranium 235 III Zinc G5 IV Zirconium 95 III

  • For mixtures of radionuclides see 49 CFR 173.390 (c).

b.

Special form material is not classified by transport group.

4.

Determine the package type as follows:

a.

Determine if the material is a small or exempt quantity, low specific activity material, or radioactive device by Table 2 below.

If the material does not exceed the limits in Table 2, proceed to Sections F, G, or H.

MANUAL SET

7

~

.1 4 W AL EM(OUHL W HNP-801G E. l. HATCH NUCLEAR PLANT See Title Page atv e w 13 om See Title Page 3 of 48 T/.El,E 2 ACTIVITY LTl!ITS F O!t S!! ALL OtI A!;TITIE0 1 DEVTCES Al!D i.0W SPECIFIC ACTIVITY M ATElil ALS_

7 p ;, n n ; o r t.

Sna11 or Manft Articles and Radioactive Low Specific

~~~n~

Exempt.

Devi ces !!axiraum Quantities Activity

,; r e, u Ouantitics Por Device Por l'ackage Materi. yin I

0.01 mci 0.0001 Ci 0.001 Ci 0.0001 mci /ct.

I 0.1 mci 0.001 Ci 0.05 Ci 0.005 mci /gn 111 1 mci 0.01 Ci 3 Ci 0 3 mC1/cn IV 1 mci 0.05 Ci 3 Ci 0 3 mci /cm V

1 mci 1 Ci

~

l Ci VI 1 mci 1 Ci 1 Ci

'i vir 25 C1 25 Ci 200 Ci (Soc ni.so Noto Irttium oxide (2) 0.5 mei/ml (2)

(1) below)

Special

' r o r r.

1 mci 0.05 C1 20 Ci V.235 15 ses 15 gms (rissile material)

I NOTE l}

(1)

Also objects of non-radioactive material externally contaminated with radioactive material, if the radioactive material is not readily dispersible and,the surface contamination does not exceed 0.0001 mci /cm ~

Group I or O.001 mci /cm% all other groups.

Such objects inust be suitably wrapped when shipped in a closed vehicle (except aircraft; see Section P)

(2)

Aqueous solution.

Total activity per package not more than 3 curies.

b.

If the radioactive material does exceed the limits

!in Table 2 determine the package requirement from g Table 3 below, then proceed to Section I.

TABLE __3 TYPE A AND TYPE B PACKAGE GUANTITY LIMITS TRANSPORT TYPE A PACKAGE TYPE B PACKAGE GROUP GUANTITY (CURIES).

Quantity (Curies)

  • I O.001 20 II O.05 20 III 3

200 IV 20 200 V

20 5000 VI, VII 1000 50,000.

Special Form 20**

5000 MANUAL SET

r

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b

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o

.,,,.um HNP-8016 E. l. HATCH NUCLEAR PLANT See Title Page

-t u:~ao 13 oa't 4 of 48 See Title Page Quantities exceeding type B a'e "large quantity (large r

radioactive source).

These quantities involve all of the

-Type B package requirements plus other provisions unique to the specific package design.

Refer to 49 CFR.173.395 (c) or 49 CFR 173.394 (c) for packaging requirements.

Except for Californium 252, wherein the limit is 2 Ci.

F.

SHIPMENT OF SMALL OR_ EXEMPT GUANTITY MATERIALG (Table 2 and 49

~

CFR 173.391) 1.

Package the material to meet the.following conditions:

Strong tight package to prevent leakage during transit.

a.

b.

Surface dose rate not greater than 0.5 mrem /hr at any point.

c.

No contamination on external surface of package.

Refer to Section M.

)

d.

Mark outside of inner container " Radioactive".

-]:

2.

Complete a Radioactive Shipment Record (RSR).

Refer to Sectiou K.

Mark the RSR with "No Label Required" immediately following the description.

G.

SHIPMENT OF MANUFACTURED ARTICLES (Table 2 and 49 CFR 173.391) 1.

Package the material to meet the following conditions:

a.

Strong tight package to prevent leakage during transit.

b.

Dose rate for any unpackaged device not greater than 10 mrem'/hr 0 4 inches f rom device.

9 Surfa,ce dose rate not greater than 0.5 mrem /hr at any c.

point if shipped as mixed cargo.

d.

Surface dose rate not greater than 2 mrem /hr at any point for exclusive use shipments.

e.

No contamination on external surface of package.

Refer to Section M.

2.

Complete a Radioactive Shipment Record (RSR).

Mark the RSR with "No Label Required" immediately following the description.

Refer to Section K.

MANUAL SET

~

l

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,,u -m E. l. HATCH NUCLEAR PLANT HNP-801G See Title Pege uwm una 13 Georgia Power

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g,,71,1,p,,,

s,, og H.

@H P

_OF LOW SPECIFIC _ ACTIVITY' MATERIALS (Table 2 and 49 CFR

.~

1.

Mixed Shipments (173.395) a.

Package the material to meet the following conditions for normal form material.

(1)

For L.S.A.

quantities which do not exceed Type "A"

quantities (see Table 3) use Specification 7A container (49 CFR 178.350).

Refer to Figure 2.

Refer to section 49 CFR 173.393 (g) for liquid radioactive material.

(2)

For L.S.A.

quantities which do not exceed Type "B"

quantities, refer to 49 CFR 173.395 (b) for container requirements and Figure 2.

(3)

For quantities greater than Type "B"

quantities refer to note in Table 3.

')

(4)

A package must be used so that the external dose rate is not greate,r than 200 mrem /hr at any point on the surface and tne transport index is not greater than 10 (i.e.

10 mr/hr 0 3 feet).

b.

If package weight exceeds 110 pounds, mark the' weight plainly and durably on the outside of the package (49 CFR 172.310 (a).

NOTE Not required for exclusive use vehicle.

See 49 CFR 173.392 (b).

c.

Assure that the package has been labeled " Type A" or

" Type B" with letters at least 1/2 inch high and that

(

the letters are durable and plain.

(49 CFR 172.310 (a)

(2).

d.

Survey the package for dose rate anc. contamination to assure acceptability for shipment.

(Refer to Section

{

M).

e.

Label the package as specified in Se'ction J of this procedure.

f.

Complete the radioactive shipment record (RSR) per Section K.

f MANUAL SET f

, n

.~- - - -

i

, _,~

HNP-801G j

-.um E.1. HATCH NUCLEAR PLANT aime r.o See Title Page 13 i

GeorgiaPower d wt

~~

G of 48 9

See Title Page Placard the vehicle in which the package is to be shipped 10 a Radioactive Yellow III label is required.

[

g.

t See Figure 3 for placard design.

' ~ '

NOTE

,l For shipping via aircraft see Section P for special details.

2.

Sole Use Vehicles Excent_ Aircraft (49 CFR 173.392 c)

Package the material to meet the following conditionsi a.

(1)

Strong tight package to prevent leakage during transit.

Type B and large quantities must be shipped in Type B containers per 10 CFR 71.

NOTE When shipping material in special casks, refer to the handling and loading procedure for that cask.

-(2)

No contamination on external surface of package.

I Refer to Secton M.

(3)

External dose rate does not exceed:

(a) 1000 mrem /hr 0 3 feet from external surface of package, (closed vehicle).

(b) 200 mrem /hr at external surface of vehicle (closed vehicle).

(c) 10 mrem /hr at 6 feet from vehicle surface.

.S 9,(d) 2 mrem /hr in any normally occupied position in vehicle.

t!OIE After the truck is loaded and the final radiation survey is to be performed a Laboratory Foreman will accompany the technician to survey the truck.

The radiation level can not eYteed the DOT limits l

of 200 mr/hr contact, 10 mr/hr at 6 feet and 2 mr/hr in a normally occupied position in

(

the cab.

f For administrative purposes the following limits should be adhered to:

MANU3L SET m..-

my m@ w ~s: W &nL '

~1

_-_--_m i

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e w- -

A6414Uy AL swy ggag w HNP-801C.

E.1. HATCH NUCLEAR PLANT

  • vw.w See Title Page 13 om See Title Page 7 of 48 Surface at vertical plane of truck - 165 mr/hr

'f ~'

Surface at truck underbelly - 165 mr/h'r Six feet from vertical plane of truck -

8 mr/hr NOTC

(

For casks, measurements must be made 6 feet from the cask surface.

Surface at rear of truck cab - 1.6 mr/hr Exceeding the administrative limits must be approved by a Laboratory Supervisor or higher authority.

The radiation measurement in the cab shall be surveyed with an'E-400 or teletector which reads less than 2 mr/hr and is calibrated at a point less than 2 mr/hr.

The shipment should also be surveyed with two different

?

instruments to insure you do not have a low reading instrument.

Final measurements for the truck will be made using instruments assigned solely for radwaste shipments.

b.

Stencil or mark the outside of the package with

" Radioactive - L.S.A.".

c.

Survey package as required for RSR.

d.

Perform survey of vehicle before loading.

Refer to Sect, ion M.

There must not be any loose radioactive material in vehicle.

Also refer to Section G for vehicle used full time for transporting radioactive materials only.

e.

Load vehicle with package (s).

See Darnwell Site Disposal Criteria, HNP-8401.

f.

Brace package as necessary to prevent shifting or leaking during transit.

1 l

} g.

Survey outside of vehicle to confirm requirements of l

l Section H.2.a.

are not exceeded.

Record results on i

Data Sheet 1 of Data Package 2 or Data Sheet 2 of Data Package 3 and file the data sheet with the pink copy of j

the R.S.R.

i t

hj MANUAL SET 3

~ _s

~ -...

L

- - _ _. _ _ =.

k 7

HNP-801G

]

E. I. HATCH NUCLEAR PLANT See Title Page 13 ji; m.w. o d

j om

~~

Georgia Power 8 of 48 e

See Title Page

\\ )

i Placard the vehicle with' radioactive placards on the y

F h.

and on each side.

See Figure S for front, rear, placard designs.

^

NOIE For shipping via aircraft see Section P for special details.

l See Complete the radioactive shipment record (RSR).

1.

Section H.

SHIPMENT OF TYPE A AND 9 GUANTITIES I.

NOTE

}.

Refer to Figure 2 for typical Type A and 8 packaging.

All

?

packages must be approved by a Laboratory Foreman or a higher These persons must be knowledgeable in NRC, DOT' classification.

I regulations, Chem-Nuclear requirements, and Georgia Power Company r

Procedures for radioactive shipments.

(49 Package the material to meet the following conditions 1.

f CFR 173.393)-

The package must be a DOT specification Type A or B a.

container and so labeled.

Also see handling and loading procedure for the specific cask.

b.

The package must incorporate a seal which is not readily breakable and while intact, will be evidence that the package has not been illicitly opened.

The smallest outside dimension must be at least 4 c.

inches.

Shielding efficiency and leak tightness under d.

conditions normally incident to transportation must be maintained, For large quantities see 49 CFR 173.394 (c), 173.395 e.

(c).

For pyrophoric materials see.49 CFR 173.393 (f).

f.

and (n) (7).

For liquid materials see 49 CFR 173.393 (g) g.

(Refer to h.

No contamination on surface of the package Section M).

MANUAL SET O

.z CATHOCAL WRA,10VHtNO E. I. HATCH NUCLEAR PLANT HNP-8016 See Title Page m m uO oan 13 9 of 48 See Title Page 1.

For mixed loading shipment, dose rate must not exceed:

(1) 200 mrem /hr at the surface.

(2) 10 transport index (10 mr/hr at 3 feet).

J.

For sole use shipments, dose rate must not exceed:

(1) 1000 mrem /hr at 3 feet from package surface (closed vehicle).

(2) 200 mrem /hr at the surface of the vehicle.

(3) 10 mrem /hr at 6 feet from surface of vehicle, 2 mrem /hr in any normally occupied area of vehicle.

NOTE After the truck is loaded and the final radiation survey is to be performed a Laboratory Foreman I,.

will accompany the technician to survey the truck.

The radiation level can not exceed the DOT

'?

and 2 mr/hr in a normally occupied position in the limits of 200 mr/hr contact, 10 mr/hr at 6 feet cab.

For administrative purposes the following limits should be adhered to:

Surface at vertical plane of trucit - 165 mr/hr Surface at truck underbelly - 165 mr/hr

(

Six feet from vertical plane of truck - 8 mr/hr f

NOTE 9'

For casks, measurements must be made 6 feet from the cask surface.

Surface at rear of truck cab - 1.6 mr/hr Exceeding the administrative limits must be approved by a Laboratory Supervisor or higher authority.

~

MANUAL SET

.. ~ _ -...

m

1 en.uva nu.tuuni 80 E. I. HATCH NUCLEAR PLANT HNP-8016 1

See Title Page ut vi sou r.o uns 13 See Title Page 10 of 48 The radiation measu'rement in the cab shall be surveyed with an E-400 or teletector which reads less than 2 mr/hr and is calibrated at a point less than 2 mr/hr.

The shipment should also be i

surveyed with two different instruments to insure you do not have a low reading instrument.

Final measurements for the truck will be made using instruments assigned solely for radwaste shipments.

{

l 2.

Survey the package for dose rate and contamination to assure acceptability for shipment (Refer to Section M).

j 3.

Label the package as specified in Section J.

4.

Complete the radioactive shipment record (RSR) per

.j Section K or Section L.

[

5.

Placard the vehicle in which the package is to be s'

shipped if a Radioactive Yellow III label is required.

i See Figure 3 for placard details.

l..

NOTE i

i l

For shipping via aircraft see Section P for special l

details.

{

J.

PACKAGE LAGELING NOTE f

Not required for L.S.A.

exclusive use vehicle.

See 49 C.F.R.

173.392 B.

Each package of radioactive material must be labeled, unless exempt, on two opposite sides, with a distinctive warning j

label.

i e

i 1.

Referto.[ Figure 4forlabeldescription.

l 1

2.

Select the appropriate label from Table 4 below using the j

radiation survey.

i 3.

Insert on two labels the applicable information as required by using legible printing with weather resistant marking.

1 4.

Affix the labels to the package on opposite sides.

1 MANUAL SET

g--

t

~

1 l

MtDUHL NO APPHQVAL HNP-8016 E. I. HATCH NUCLEAR PLANT atvoo" ~o See Title Page 13 o.1 11 of 48 See Title Page 1

TABLE 4

(

RADIOACTIVE MATERIAL PACKAGES LABEL CRITERIA

~

(172.403)

DOSE RATE LIMITS AT ANY POINT ON AT THREE FEET FROM

. LABEL ACCESSIBLE SURFACE EXTERNAL SURFACE OF OF PACKAGE PACKAGE (TRANSPORT INDEX)

" RADIOACTIVE-WHITE I" O.5 mR/hr O

" RADIOACTIVE-YELLOW II" 50 mR/hi-1.0 mR/hr

" RADIOACTIVE-YELLOW III"*

200 mR/hr 10 mR/hr Requires Vehicle Placarding (This label mandatory for any fissile Class III (173.389A) or large quantity package (173.3898), regardless of dose rate levels.)

These limits in table come from 173.393 (i).

H.

COMPLETING THE RADIOACTIVE SHIPMENT RECORD (RSR)

NOTE e

An RSR will be completed for every shipment of radioactive material whether it is " exempt" or not.

Refer to HNP-BOl7, Control and Accountability of Radioactive Material.

1.

Non-Fissile Mat'erial Enter the following information on the R.S.R.

Refer to figure 5 and 6.

Bloc #k #1 - Enter name of company, addresses, license a.

number, and individual's name if sent to anyone's attention.

Enter a phone' number if it is known.

Enter name of freight line or truck company as carrier.

b.

Block #2 - Specify type of waste; generally it will be compacted waste and resins.

~

Block #3 - Identify shipment as to whether is is nocmal c.

l form or special form (section R of this procedure).

l Usually it will be normal form.

If'it is normal form then indicate the physical form.

d.

Block #4 - Indicate class of material by checking l

appropriate box.

See block 16 line 6.

MANUAL SET

i nuwum so HNP-8016 E. I. HATCH NUCLEAR PLANT See Title Page

  • v - o 13 om b

12 of 48 See Title Page e.

Block #5 - Indicate the type of quantity by checking l

the appropriate box.

f.

Block #6 - Indicate type of vehicle.

I g.

Block #7 - Indicate if any special instructions are j

included.

h.

Block #8 - Indicate if prior notification of shipment has been given.

f i.

Block #9 - Indicate if placards have been affixed to vehicle.

j.

Block #10 - Indicate if labels are affixed to i

containers.

.a k.

Block #11 - Indicate container specifications (i.e. 7A

^ -

or special permit #,

etc.)

i~

1.

Block #12 - Indicate that we de have a copy of the i

. receivers license and that it does cover this type of material.

Must be signed by shipper.

m.

Block #13 - Have driver read and sign exclusive use statement.

n.

Block #14 - Give driver his copies of the appropriate papers and have sign block #14.

o.

Block #15, line 1 - Indicate transport group number and list all radioisotopes identified.

Line 2 - Use correct section and list the measurements ind(cated.

In section "d"

list the survey instruments used' by model and serial number.

Line 3 - Give the contamination level measurements.

Use the average reading found.

p.

Block #16 - Indicate that the packages have been correctly labeled and marked.

q.

Block #17 - The technician controlling this shipment will verify that the certificate statement is true and then sign the statement.

MANUAL SET

APheQVAL PROCEDUHL NO e.

E. I. HATCH NUCLEAR PLANT HNP-801G j

See Title Page

  • vum uo om 13 See Title Page 13 of 48 l

r.

Block #18 - After the technician is satisfied that the shipment is correct he will sign the first line authorizing the release of the shipment.

Before the final release, an authorized, knowledgeable laboratory foreman or higher supervision must review all aspects of shipment for compliance to applicable regulations and then sign and date the release.

s.

. Block #19 - Indicate that the shipment does not exceed the limit of 10 nanoturies per gram of transuranics.

t.

Figure 11 - List packa,ge numbers as they are loaded.

If this is a drum shipment then list the drum numbers.

y If other items, then list the items sequentially (if they are not already numbered) as they are loaded.

In v

the second column record the contact dose rate as measured directly with an instrument.

The third column 1

is for the dose rate at three feet from the package surface (this is the transport index or T.I.).

Estimate the activity of each dru~m by section N of this procedure using the appropriate formulas, graphs, or s

1 tables and the dose rate at contact.

Record the i

activity in the fourth column.

Perform wipe smears on the drums or packages and record the contamination levels in the fifth column.

List the quantity of the package in the appropriate units (ie. cubic feet, liters, etc.) in the sixth column.

See item 11 on i

figure 9.

Determine the total weight of each package and record the weight in the seventh column.

If the weight is over 110 pounds and the shipment is mixed freight the weight must be labeled on the package (see 172.310 (a).

The right side of figure 7 is a continuation of the left side.

Total columns 4, 6 and 7 and list these totals in the spaces provided.

I 2.

Fissile Material Enter the following information in the appropriate space on the RSR.

Refer to Figures 14, and 15.

Figure 15 is to be used as a continuation sheet along with Figure 14 when shipping large numbers of containers.

a.

Shipped To - receiver's name, address and license number.

See HNP-8017 for instructions on verification of license.

b.

Number, Date - number and date of shipment.

j MANUAL SET

[

.j

AflPRQv4 PH(X;&DUHt NQ HNP-801G E.1. HATCH NUCLEAR PLANT See Title Page aeve> ~o 13 care GeorgiaPower

~ ~o See-Title Page o

14 of 48 c.

Shipped Via - motor freight, air express, etc.

Give name of carrier.

i j

d.

Remarks / Description - describe (i.e. six irradiated fuel bundles, L.P.R.M. assemblies, T.I.P.. drive parts etc.)

Include remarks such as fissile class if needed l

or Type A or B or Large Guantity shipment.

NOTE More than one item or type of material can be shipped on the same RSR.

i i

e.

Physical State - check physical state, identify SN i,

material type and isotope (s).

j h

f.

SNM Net Wt., Enrichment Isotopic Wt., Curies, Specific

. Activity, Concentration - complete if SNM is being

]

shipped.

1 j-g.

Container, No. of Containers, DOT /BE No., Serial No.,

4 Weight, Seal No. - complete for al?. radioactive shipments.

If not applicable put NA.

h.

Transport Group - check appropriate block.

j i.

Radiation Survey Data - enter Jata required.

j.

Surveyed By - signature of surveyor.

1 k.

Radiation Units - complete if shipping fissile material.

1.

Placard Required - Check block if shipping a yellow III label package.

a m.

Shipment Approval - a Laboratory Foreman or a higher classification must sign here.

The person approving the shipment must be knowledgeable in the NRC and DOT regulations, Chem Nuclear requirements and Georgia Power Company Procedures for radioactive shipments.

n.

Method of Shipment - identify carrier.

I o.

Marking and Labeling - record the type of label and marking on the package.

t p.

Shipment Originator - place of origin of the package, normally it will be Plant Hatch.

q.

Date -

MANUAL SET

. ~

~

,,.uaou e

E. l. HATCH NUCLEAR PLANT HNP-8016 4

See Title Page

{

  • nww no om 13 See Title Page 15 of 48 2.

Distribute the RSR copies as f'llows:

o

. ~ ~1r.

Original - to package destination.

b.

Yellow - to driver of vehicle transporting package.

c.

Pink - File in H.P.

office.

3.

If a shipment is not exempt from packaging and labeling, the

(

shipment receiver must be notified by telephone or letter, i

before the shipment arrives.

Some exceptions are, (1) if the shipment receiver expects a shipment at regular time intervals or (2) if he knows it is coming.

L.

RADWASTE SHIPMENTS TO CHEM NUCLEAR l.

When shipping radioactive waste to Chem Nuclear complete an RSR form (Figure S & 6), the Chem-Nuclear Record Form (Figure 8 and 9) and (Figure 10 & 11) and the South Carolina Prior Notification Form and Shipment Certification Form, (Figure 12, 18, and 19).

CAUTION 5

NO LIQUID WASTES ARE TO BE SHIPPED TO BARNWELL.

NOTE It is very important that these forms be complete and instructions for completion followed.

When shipping waste, current copy of these forms supplied by the vendor, shall be used.

Forms in Fig. 8,9,10,11 and 12 are only specimen forms.

2.

Assure that Barnwell Site Disposal / Criteria is complied with.

I DistribuketheChem-NuclearRecordFormasprescribedbelow:

3.

a.

Original - To Chem-Nuclear b.

Yellow - To Chem-Nuclear

~

c.

Pink - File in H.P.

office.

4.

Distribute the RSR as prescribed for other shipments.

l 1

NANUAL SET

[

~

-,x E. l. HATCH NUCLEAR PLANT HP5'-801G See Title Page aenw. eca oara 13 See Title Page 16 of 48 4

!!OTE When shipping radioactive waste to U.S. Ecology, Inc. complete a Radio-active Waste Shipment and Disposal Form (Figure 13).

When shipping waste, current copy of these forms supplied by the vendor, shall be used.

Form in Fig. 13 is only a specimen form.

s M.

HyRVEY FOR CONTAMINATION CONTROL (49 CFR 173.397) 1.

The following are permissib.le levels of removable (non-fixed) radioactive contamination.

t a.

Package for mixed cargo shipments:

A Beta gamma not greater than 2200 dpm/ LOO cm Alpha not greater than 220 dpm/100 cmA b.

Packages for exclusive use shipments:

^

j Beta-gamma not greater than 22,000 dpm 100 cmA f

Alpha not greater than 2200 dpm/100 cm -

8 c.

Transport vehicles - accessible surface (49 CFR 177.843):

Dose Rate not greater than 0.5 mrem /hr Beta gamma not greater than 2200 dpm/100 cmA Alpha not greater than 220 dpm/100 cmA NOTE A vehicle for transporting radioactive material as exclusive use must be surveyed prior to loading of packages for shipment from Plant Hatch and after removal of radioactive packages shipped to Plant Hatch.

d.

Transport vehicle used solely for transporting radioactive materials (49 CFR 177.843):

Dose rate (interior surface) not greater than 10 mrem /hr.

Dose rate (3 ft. from interior surface) not greater than 2 mrem /hr.

These vehicles must be stenciled with the words, "For Radioactive Materials Use Only" in. lettering at least 3 inches high in a conspicuous place on bos;. sides of the exterior of the vehicle.

The vehicle must be closed at all times other than loading and unloading.

~

1 J

NANUAL SET L'

i

i APPngvg PROCtDUht NO E. l. HATCH NUCLEAR PLANT HNP-8016 see Titie Page

..s.o~ ~

GeorgiaPower d

~~

17 of 48 i

See Title Page 2.

Perform smear survey on packages using a sufficient number

-.-of smears to assure a representative assessment.

Refer to HNP-8012.

Results must meet criteria in M.1 before shipment can be made.

3.

Perform a smear and dose rate survey on the transport vehicle (exclusive use) prior to loading package (s).

Use a sufficient number of smears to assure a representative assessment.

Refer to HNP-8012.

Record results on Data Sheet 1 of Data Package 2 or Data Sheet 2 of Data Package 3.

Results must meet criteria in M.1 before packages can be loaded.

Notify Health Physics supervisor if limits are l

exceeded.

N.

ESTIMATING CUR _I_E CONTENT OF PACKAGES 1.

Resin in a 55 gallon drum.

a.

Obtain a grab sample f.'om each batch of resin and I--

perform an isotopic analysis.

b.

Determine the average weight (1bs.) per drum for each I

batch of resin.

le. weight of the resin after subtracting the weight of the empty drum.

c.

Sum the specific activities of all the radionuclides present to obtain the specific activity of the drum contents (uCi/g).

d.

Estimate the activity of the drum contents as follows:

Activity (mci) specific activity of drum contents uCi/g x

=

453.6 g/lb.

x Average drum weight lbs.

x 1 mci 103 uCi e.

To etermine the quantity of Transport Group II j

isotopes normally found in spent resin, a sample of primary coolant shall be sent to an outside vendor (Teledyne) for Strontium analysis once per quarter.

When significant fuel leaks are identified, as specified by the Health Physics Radiochemistry Superintendent or his designated alternate, this analysis will be done more frequently.

The contribution of Transport Group II i39 topes, which is l

determined from the ratio of the Cs activity to the activity of Sr 9#

, must be added to the total l

curie content of the shipment.

l l

l l

(

EMUAL SET

. -. - - - -. O

W VAL PRUCeDWt NO E. l. HATCH NUCLEAR PLANT WP-801G See Title Page aeve ~u cara 13 Geo iaPower l

~ ~o See Title Page 18 of AB The following example calculation illustrates this method:

- Diven:

Total curie content = 150 mci (excluding contribution from Group II isotopes)

Activity of Sr90

= 1.5 E-07 uCi/ml Activity of Cs/37

= 3.0 E-04 uCi/ml 90 Ratio:

Activity of Sr 1.5 E-07 = 5.0 E-02 Activity of Cs 'J7_ = 3.0 E-04 Contribution from Group II Isotopes:

150 mci x 5.0 E-02 = 7.5 mdi f

Total Curie Content:

150 mci + 7.5 mci = 157.5 mci f.

Sum the specific activities of the radionuclides present with half-lives longer than five (5) years j

(uCi/g).

g.

Calculate the volume of the resin accounting for any settling in the container ( an3 ).

h.

Estimate the concentration (uCi/ an3) of the

~

radionuclides present with half-lives longer than five (5) years as follows:

Concentration uCi

=

cm3 (Specific activity of radionuclides x (453.6 g/lb) x (Average drum with T 1/2 5 yrs. uCi/om)

Weicht LBS)

(volume of resin cm

)

2.

Trash inva B-25 box.

l I

a.

Measure the exposure rate at 3 feet from each l

[

accessible side and top of the container in mR/hr.

L e

b.

Average the highest readings collected at each point (mR/hr).

Estimate the Curie content using the formula below:

c.

mci = 2.43 x S.F.

x D.R 0

Where D.R.

is average dose rate in mR/hr i

from step 2.b.

H S.F.

is shielding factor from Table $

r k

MANUAL SET

aremovat Paoctouwt uo E. l. HATCH NUCLEAR PLANT WP-801G See Ts.tle Page aevis.o~ ~o 13 oan GeorgiaPower

~ ~o 19 of 48 l

See Ta.tle Page TABLE 5

- ^

l Density (gm/cc)

Shielding Factor

[

.3 1.37

+

.4 1.76

.s 2.so i'

.6 2.99 l

.7 3.94 i

p ai= =Esm ag= =i=cLs=.s=n=i tgis=i= 9a se

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PMUGtDuHL NO APP M I

HNP-801G E. l. HATCH NUCLEAR PLANT See Title Page ao w.~u 13 can See Title Page 20 of 48 O.

SHIPMENT OF EMPTY CONTAINERS (49 CFR'173.29) l 4

1.

Containers originally used to ship radioactive material may y

be shipped as Empty containers if the following requirements l

are met:

a.

Containers must be securely closed so that no residual E

material can leak out.

E b.

Radiation level must not exceed 0.5 mrem /hr at any point on the external surface of the package.

c.

Contamination on the surface of the package must not exceed values as specified in Section M.

d.

All shipping labels and all stenciled, painted, or F

engraved markings showing original contents must be removed, obliterated, or covered.

A e.

An " Empty" label must be placed on the outside of the g

package.

This label must be a square 6 inches on a side with the word " Empty" printed in black letters at s

least 1 inch high on a white background.

h f.

The Bill of Lading must be marked " Empty Container, which originally contained radioactive material" immediately following the description.

P.

SHIPMENT BY AIRPLANE Packages to be shipped by airline must meet the following DOT regulations:

49 CFR 175.75 (a) (3) 49 CFR 175.85,(b) 49 CFR 175.85 (d) 49 CFR 175.700 49 CFR 175.710 49 CFR 173.393 (n) (7) 49 CFR 173.393 (p)

G.

INCOMING EMPTY VEHICLES (49 CFR 177.843) 1.

Once a vehicle used for carrying Low Specific Activity radioactive material in truckload lots arrives, the vehicle must be surveyed.

The vehicle cannot be loaded for normal use until:

a.

I'n the ca'se of a comm'o'n ~chrri~er, I

~

l l

l MANUAL SET

j APPHQv&L PHOC&DUML NO E.1. HATCH NUCLEAR PLANT HNP-BOl6 See Title Page

  • vwa ao 13 an See Title Page 21 of 48 (1)

Radiation levels at any accessible surface must

~

not be more than 0.5 mrem /hr.

(2)

Contamination on any accessible surface must not exceed:

A Beta-gamma-2200 d/m per 100 cm 3

Alpha - 220 d/m per 100 cm b.

In the case of a vehicle which is used only for the transportation of radioactive material and is marked For Radioactive Materials Only.

(1)

Radiation levels must not exceed 10 mrem /hr at any 3

accessible interior surface and 2 mrem /hr at 3 feet from any interior surface (2)

There are no smearable contaminatien limits.

R.

DEFINITION (49 CFR 173.389)

}'

1.

Fissile Material Fissionable material, typically U-235 and Pu 239.

(U-233, Pu-238 and Pu-241 are other less f requently encountered i,

fissionable material).

Less than 15 grams U-235 is considered non-fissile.

2.

Normal Form Radioactive material not in Special Form.

Normal Form radioactive materials are groeped into Transport Groups.

Normal form materials are typically liquids and powders.

3.

Radioactive Material Any material which spontaneously emits ionizing radiation.

Materials in which the radioactivity is uniformly distributed and which has a specific activity less than 0.002 uCi per gram are not considered to be radioactive materials.

4.

Special Form Radioactive material in a form which if released from the package might present some direct radiation hazard but would present little hazard due to radiotoxicity and little possibility of contamination.

To be classified as Special Form material, the material must meet the following requirements:

l e

MANUAL SET

~~~

-a m -

E. l. HATCH NUCLEAR PLANT HNP-8016 See Title Page

= v w. -

wra 13 See Title Page 22 of 48 1

a.

Must be in massive solid form or encapsulated.

-,_ (.

Must have no overall dimension less than 0.5 mm or have at least one dimension greater than 5.0 mm.

c.

Each item must not dissolve or convert into dispersible form to the extent of more than 0.005% by weight when:

f (1)

Immersed for 1 week in water at pH 6-8, 68*

F, and a maximum conductivity of 10 umho/cm.

(2)

Immersed for 1 week in air at 86*

F.

d.

Each item must not break, crumble or shatter if a steel rod 1 inch in diameter, weighing 3 pounds, and having a m

flat end is dropped from a distance of 40 inches into I

the item.

e.

Each item must not melt, sublime or ignite at temperatures below 1000*

F.

l..

f.

If the material is encapsulated, it must also withstand i

a free drop thru 30 feet on to an unyielding surface and it must withstand heating to 1475* F for 10 minutes.

5.

Transport Group:

One of seven groups into which Normal Form radionuclides are I

classified according to their radiotoxicity and their relative potential hazard in transportation.

6.

Transport Index:

'I The number placed on a package to designate the degree of control required for transportation.

This number is the d

larger o's the following:

l a.

The highest radiation level in mrem /hr at 3 feet from any accessible externa 1 surface of the package.

3 1

b.

For Fissile Class II packages only, the number obtained by dividing 50 by the maximum number of packages that f

may be transported together.

7.

Type A Guantity:

l That quantity of radioactive material which requires Type A l

'or general packaging requirem'ents.

g MANUAL SET

  • i Mh A PROCtL)ut*t WJ E. l. HATCH NUCLEAR PLANT HNP-8010 See Title Page aave w ura 13 l,

Georgia Power ll

~~

See Title Page o

23 of 48 8.

Type B Guantity:

-That quantity of radioactive material which requires Type B packaging.

Type O packaging must meet all the requirements that Type A packaging does plus it must meet the standards for hypothetical accident conditions in transportation (see 49 CFR 173.398c).

S.

Semi-Annual Report of Solid Waste and Irradiated Fuel Shipments.

Record, every semi-annual period on, Figure 20 of Data Package 5, the following information.

1.

Cubic meters and 'cotal curies of spent resins, filter sludges, evaporator bottoms, etc. for 6 month period.

2.

Cubic meters and total curies of dry compressible waste, contaminated equipment etc. for 6 month period.

3.

Cubic meters and total curies of irradiated components, j

control rods, fuel channels, etc. for 6 month period.

4.

Other items that contain licensable amounts of radioactive materials not covered above for 6 month period.

5.

Breakdown of percent and curies of major nuclides for each of the four categories above.

6.

Number of solid waste shipments, mode of transportation and destination of the shipments.

7.

Number of irradiated fuel shipments, mode of transportation and the destination of the shipments.

o i

n I

11 t

u 9

NANUAL SET

e O

j E. l. HATCH NUCLEAR PLANT HNP-801G See Title Page

=

OM S e Title Page L. _.24 As FIGURE 1

" NORMAL. FORM" R.A. f.i. (173.339(D[

f.

.R AD'OACTi'M i.: ATERI AL - II.0.S.'

u.....

IliCLUDES A!!Y !.1ATERIAL W!!!Cil DOES liOT QUAllFY AS "SPECIAL FORfil".

ff 0RI.iAL FORL! fiiATERIAl.S ARE CLASSIFIED liiTO EITl!ER OF SEVEll TRA?iSPORT GROUPS.

l i

I m

lASTE M ATERIAL l't (CUC l's E!.TTLE WITFl'1

,f PLASilC BAG l',' N vtist C0 hit.txta H3 TIAL Rts:ST A.*t t'

% 7 LOW. melit?iC. COMEU$ilStt j' '

8 POWDER IN CLASS AkD.C2 IRANCISLE SOLIG

, t. A On

t?

va, N)

PLASTIC EDITLE

[

0 I

I t

0 1

O l

"SPECIAL FORH" R.A.M. (173.389(G) AND 173.398(A))

i

, MAY PRESENT A DIRECT RADIAT10t{ HAZARD IF RELEASED FR0 2 l

' PACKAGE, Bi)T LliTLE HAZARD DUE TO C0liTAMl!!AilGli

{

i "SPECIAL FURM" R.A.f,1. MAY BE "t! ATURAL" Cl!ARACTERISTIO, j

l.E., MASSIVE SOLID !.*ETAL, OR " ACQUIRED" THROUGli lilGH lliTEGRITY EHCAPSULAT10;l j

l MAssr.'E 00T SFEC. 2R*

HlCH INTEGRITY SOLID !.tEIAI.

(178.341 ENCAP58.'tATIO.'i AS A SCALED SOURCE

.s

}>io a: tun enn

-,v u=y i

p..b..mn,p ping c

N l

  • SPIC.2R CONTA!!NE'if C0ts NOT AUIC'.'AT;CALLY GLIALIFY As
  • 0FECLAt.

FORI.!" SPEC! TIC EVALUATION is P.ICEssArsy AGAINST 173 333;Al NANSAL SET

l 1""

muum u E.1. HATCH NUCLEAR PLANT HNP-801C.

See Title Page n,s,o,,,,o Geo iaPowerd

~~

See Title Page 25 of 48 FIGURE 2

~

TYPICAL TYPE A PACKAGING 1

s PACKAGE MUST WITilSTAi!D !!GRMAL C0i!0! TID'lS 1173.393lB})

0F TRAllSPORT O':LY WITliO'JT LOSS OR DISPERSAL OF TiiE

.RADIDACTiVE CO:! TROL C0'tTEilTS.

dm

N~ &';

D

t.. '

t; N f, r l Ia

.NE2

.9-w.c

~-

0 i

(

FIDERBOARD BOX WOODEN B0X STEEL DRUM TYP! cal. SCHEMES 00T SPEClf! CATION 7A TYPE "A" PACKAGE t

TYPICAL TYPE D PACKAGING SCHEMES PACKAGE MUST STAND SOTH NORMAL (173.393'Bil AND' i

A'CCIDENT [173.393,Cll TEST CONDITIONS WITHOUT LOSS OF CONTENTS.

TITERIOR CRatt N*

COUGLAS fia Ptin003 18 C AUCE Sit [L tt"M 04 CUTtt t0VtR gh'"

.. ' I '..-

LAe scttws

.m,

N-g1"N, ' -)

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(,

t utent nsttina Dl,fx /

gg,.,

p ettettu cc=u.sts 6

rum att ac:::s3_.[ to.us to rtrue's,

%=

MANUAL SET

[

ten nenea

I, PRCELDUHt NO WP-8016 E. l. HATCH NUCLEAR PLANT see. ritie page GeorgiaPower A

~o s e ritle Page FIGURE 3 i'

Il 4

VElllCLE PLACARD FOR RAD!0 ACTIVE f.i ATEi'lALS 9

$t

-[a2.as uhe.)]

j 0

k,,

%q%

3 7

I PLACARD IS TO CE DISPLAYED 03 TRONT. REAR, A!!D El.r;N SIDE OF TRANSPORT YEi!!CLE 1

e 6

ANUAL SEI i

~.

l LD E in 4

g.

j

.L**N g

g

'. g, "i

Color' Scherne

~

\\.

w s

All three tabels:

~""

/

yellow g

y tower Mctf is White

~ '

o e

Vertical Bors are Red.

m o

j Print is in E, lock

/

s..

o f._ e 1

' HANDLE CAREFULLY Q

'p f if,3 Whigg J b el O

h **"' ' 'i"",'",.'o'C**

Yd!w C

I

~

Ccif evt Pet %ChiS80 d

M Q

P t escans t O

CONTENTS:

~~ "

/

NO. OF CU~ RIES.

I l

h

[

q 18 ANS P001 It.a g

C tasaxist:m t.

O i

\\

'O

tm O ".

t. !!!@

re vs 3

I!

z 1

--i

@ qfp py 1 j" HANDLE CAREFULLY

\\

HANDLE CAREFULLY N,E N k) e !'$ 7,#".' " '

.i 1

1 EHiv is.6;g asig g q m

ii

,' ! !, i, ld

,$,[,(h 3 j g-[ ]

]

h(

NO. OF CURIE:[,

l

' 8

  • 5 0"' '

CONTENTS.

1 l

{

J e

'E e

E M

TRANSPORT INDEX:

8 l

'f 5

E

>f E

CONTENTS:

(MAXIMUM Of 50 g

OR AREA)

< - + -,,,..

m

{ gA e

rta ViluCLE I

NO. OF CURIE S:

6 g

l m

E s

j U

% =.4

=

l

-=->.u e

  • we asesames-amma o.

+ a amm. ammames w

=,

t

. mu,,,e APPRQVAL HNP-801G E. l. HATCH NUCLEAR PLANT D

s. Titi pag.

GeorgiaPower A QATE 28 of 48 s.

1111 e.g.

FIGURE 5 otosotA pown CoveaNv t=*iderest wPeru_O Fril v tt.71 S*pt F naC;'*&f flW M tT*kt AL 1

914tPe**40 N %faF_

N* #' ****'* D

Ga. Power CoiP act L L Haten Und I utense WM D

CR&dosctive Davees n.o.s.

Un6 a License e W.5 0

Onsdaachv Lta* erie.s. LSA, n.c.s.

onae,oa:tive uariais. Limned Otr a.o.s.

DHassachve MM alk g,g,g, g

to Case of Emerge 3cy CaJ Q12) 307.T761 ORaseachve usteria#s. Soss.ee Form n,o.s.

TCt _

- L4erme e HAIARD CLASS: Radioactive Matertal Tysy.etner ae==ccmTs textssi 8-cLs4 oTyce A OvanntyiConta.nor

^$,,

CLSA-8ULK*

CType 8 Ousnt.ty iContainw CLSA ucuto CLe<ce Quanaty esam&T e o..ceeed aepwetatt ent: n CDEVICE Qumited Quentity CEvaporator Conctnvases CResme 2.

OCempestee waste CCiudge 8F THESE ARE CHEC<ED. TYPE A 9. OR LARGE CUANnTY MUST ALSO BE CHECKED.

Ca#'s as VEMICLE INFOHfAATiot4-Cr*ECK APPROPPIATEf e

CCIf4 j

Fo't'i f.D -fM?cT ****O*n'tT!r 't 3r'?S1__

S.

DPerra:e kletor Carrier l

Dsormal Form

  • CPPytical Form 3.

DRad Sote Use DRa4 Nat So e use g

)

D5pecial Ferra Oso d Q Leew.d DPasse ost Carryvig Transport Vehicle u

n

'g 00se OChomic 1 Forse CN:trates CClosed Transport 03utte'es CPhosphates Coa & des CU S Mad 4

DCarticestes Omer DTrurm Van. Car Sole use j

  • *ONLY REQUIRED IF MATERIAL IS IN NORMAL DTrue., Van. Car Not Scie Use o,

FORM y,

j*ff t AL f*8 %TM*f*0HS-Ct!!Cfr **eFOSM4To 1904

. Amy special instrucuocs ter se'esy openano thisitne pacLage, is/are sitaened to inse Dyes CNet Anpuca21e shippang form.

4.

Notrac 4 TMH +.e*'!t 7 9ter'**'t tg

-s.- -.d as t...

s-e-.n. s-.,e-.

  • RTOtA"4E0 FCs4 TYF E 8 OR LARGE QUANTITY Oves CNot Anos.caela IL PL &Ca 40$* 0 Hic.( g***)* et t tY 4Q b

'Racisaceve' placards are s*ftsed to com s. des and bo a ends of transport venscle.

' Cyes CNot App;ec@e eyggmyn gF VMcLE HAG MtLOW 1:a OR SOLE USE LSA 10.

L A*2LS cPC'r t haN S'It eTT f$

Redpdred lebe6s (white L yeaoW E. YeMow Orl) ere altsed to opposele sWies of each pechage.

Oves DNat Aapescatpe 33.

COtfTet"* tt Sr f Ctr c aYmat 4

i 007 dpect. cation No, epecial Petre *.c 'USNFC

  • RioutnED FOR 1VPE 8 Of t L ARGE OTy. P ACKAGES t3, 10CP9 'te+!!M'dMf_
  1. 8 There to e sepy of the beense or cert.ficate on rJe weabeg sna: sne sonsgr ee es outworites le rece. e ines snesertas.

Segaature gg

{TQLUttvM til? STAT *WNT 3 sus Dansoort verJoe is deslanesed as *$0LE U$r. e as uncernined anas d w.a tie sopaed ty the cons.gner.

Unioeded ey the eenswice and eo e:f ee snateetes em es e,rned anecess se=e carso caerywiel D00, one inns the mates se es not se ne ymast eed to econnor Sargo to,0v iness e act se ehresbon of tre ser signer, consignee.er ecorisse n

seeni.

J Oyes CNot AppbceD8e tvwFn S siGNAfunE te.

rs,-.me l

The art =ur must have a copy of rus asocument se ins passesssen.

t DRIVERTSIGN a FURE I

8 IIANUAL SET

ePPHQvA1 PHULADUHL Peu j

E. l. HATCH NUCLEAR PLANT WP-8016 See Title Page men.v o g

13 oAtt Georpia Power s1 See Title Page O

29 of 48 l

FIGURE 6 SAD 10t.OCTCA!. f3mRNATI'Wf

1. TRANSPORT C20CFs 1

11 LII IV V

V1 Q EEFJtFT FR0rt DOT FACKACIEC SPEC 3 Sedlenua11 des-Abbreviatices Anathertsed:

e.

b.

a.

4.

a.

f.

g.

h.

1.

J.

k.

1.

e.

e.

e.

p.

2.

StRVEY EATA-USE ArrtoPRIATE SECTION. St:RVIT WITS TO BE totnt/ut. NUMBEas 13 PARENTHE3t$ ARE THE L12 TIT 3 FDL THQ38 MEASURIENT3.

f t

e. Sete Use-C1ssid Transport b.

Sale Use-opee Transport l

3' Ext serface rks (1000)

Centact Eat rks (200)

Est Surface Vaatele/ car (200) l 6' Outer Laterat surf aces. Vehicle (10) 6' Outer Edges Vehicle (10) e Normally Occupied Posittee (2)

Normally Occupied Posittee (2)_

g

e. Eco Sala Use4 pee er Clemed Transport d.. Survey Instruneste l

Centact Ext Surface Pks (230) feet.

Ser. No.

I 3' Ear Surface Pkg (10) test.

ser. No.

t 3.

CthiTAMDIATIC3 CATA Bete-Causs (22.00%F:t/1000,2)

DFM/1000t2 l

2 2

g atlpha (2.200DPN/1000t )

DFM/1000g I

ac2LEss MATE 11AL ts ALFaA E:!!TTEL CE FACEACE EAS REEN SUBJECT TO ALPHA CCt:TAMINATION, INSERT NA CW ALFMA LINE.

s K w L: u,'i G APPESPRIAiE E00.5 16

5. Usighte O Tee O set Applicab).

6

2. Consignee Name 6 Address **

O Tee O Not Applicable

3. Type Packattat Marking (Type A or Type B) O Tee O mot Applicable
6. LSA Packages tierked " Radioactive 13A" O Tee O mot A ticable
5. Limited Quanttry raet ases. Interior t

Fackage Marked " Radioactive" O Yes O wet Applicable

6. Shipping same Hasking ***

O Tee Q Not Applicable -

h e

REQUIRED ON EAQt PAGACE OVER 110 LBS., f*:7.FT IF LSA SOLE USE ee REQUIIID 12 LE55 VEXICLE IS SOLE USE ese sEE atocx f6 I

CE nTIF ts. ATE i

thie la to certify that the above eased e.atestals are properly classified. described, k

packaged, marked. and labeled, and ar la proper condisson for transportation according to the applicable regulations of the Lepartneat of Trenagertation.

h hhipper's Signature i

9

'r,

nTuon t 7 Ar tcM 88 i

this record toepleted by LAIL Servey data. packaging. labe11ag and marking checked for esepliance with applicable regulations forman j

&asseture DALE TFA%s8 An t es 19 Ewetear pouer Eemerattas f acilities de not anceed transuranice liette of $ NANO 5

C1/ CRAM.

le thle stateneet applicablel C Tee Q Me

. tf.n.e thee sive the as.w t of uA30 Curtee per arme 6

NANHL SET

~

61 m

AHH(fjAL HNP-801G E.1. HATCH NUCLEAR PLANT i f See Title Page 13 L 1; o.re GeorgiaPower 30 g 43 J

See Title Page FIGURE 7

,)

DATA UNITfs TYPE WASTE UNITl UPE WASTE

]

O Centamdu Pounds c

Pkg. J Contact. TI ACT. Contam-Qty PoundsIPkg.#

Contact TY ACT.

a n

c o

a 1

(mr/hr)

(r,rf t,r' (rCi) i n a t i o.-

tJ (mr/hr) (c.r/hr)

(mCl) 19a tiori]ty

'I I

i 5

, 'i i

5 l

I i

}

8 l

.l; i

g

' i i

k 2

i-

'k O

3 P

+9 r

t a

h i

i 8

i, i

b j

e I

d I

i i

I 9

s t

I e

i l

i a

6 G

i TOTALS TOTALS GRAND TOTAL.S Shipment-Millicuries (Do not use scient'ific notation)

POUNDS.

QUANTITY l

NOTES a.

Contact reading for billing purposes.

b.= TI to be filled out if packaqes ber.r Yellow !! or Yellow III labels.

c.

Contamination levels in DPM/100 ord. See section H.

d.

Qty-Enter quantity used in cubic feet. gallon-i. milliliters as gppropriate.

For mixed freiqht shipmnts TI cannot excei>d 50.

MANUAL SET e.

f Uhen n<im wilin-, t il Dahsh vehicit. nust be rglacarded.

1

tn 9

tn '

a e,

e,

-1

-4 CHEM-NUCLEAR _ SYSTEMS IN_C_..

te.

RADI0 ACTIVE SitiPilEllT RECORD FORM 4

4 FIGURE 8 T

T mou Can,.y sense BARHWELt. WASTE MAtlAGEMENT F/sCILITY suppasone cuss usa ontv as as O,

O Ccruact Cpirated by: CHEF.5 NUCLEAR SYSTEMS.INC.

g, g

P. O. Dos 726. 03 nacM. South Caroi u 29312 Adcress' (80'l) 259 1781 Customer Survey Cate Swed By

$. RADICACitvE $4PMENT FIECORO FORM M

Rad.at. ort Reading Vie @ -

Pago of (16)

Trenc.h No.

V.CC Tewphones Carr.er Narne Type of Ca*

LOC Cooe aerns TO m w S.gnau e Trailer s Total PEP.S EXF Date & Twee Roc'd h

til r?)

On (4)

(5)

(6)

(7)

(8)

(9)

(10)

  • (II)

(12.

(13)

(fdl (155 ct 7,

1-c c m,

n..

in..

(um.

..e cm O

r.

o~

e u

__ws~ n.._. gg,;.;;.

O 3

n.

m

.s

==

_q r Q

s' g-n

=

z

r. -m.

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O g

r A

O m

m F

i Z

4 l

s 5

5 i

t e

707EL h'

N M

c id<a..= e **e,.m=i.e.se c an.ocomme een..m..a ra. acumc em e i e s w. w

4.us..... w Esamer: %....

.~. m.. = we.3.e m t...w a

._e e.v.rw.,w.., c.im. *.*-ee.cr.eur c.m.,e.

.CJr%$9.r.m s tre

.m 45 I B16 f.l AS,WMr*.h d.nc.m.g e.tMbv RW"e s.h D..s s'.m.Ca l M,,a @'

- c

.~, =.4 1

h

.,V.g.4,le.npee

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, m...

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%%,oN No See Title Page 13 N

~ ~o oAn GeorgiaPower 32 of 48 j

O See Title Page FIGURE _9 I

CHDI-NUCLEWW$iEMS INC.

j RADY0Kdr!VE SHIP:r4T RECdlli FORM

' F CHEfJ-HUCLEAft SYSTCt.tS,INC.

j P

SNSTRUCTIONS FOR COMPLETING RADICACTIVC SHIPMENT RECORD FOW t

K (IftFOtuRfvENTS NOTE. ! Ire 81.*ENT Vav PE PEFL AED IF CONYCNTS SUPeORTW100CUVENiaffriN A EOLRAL UCENSES, THE AAE NOT are CO*.tAirJdCE elm ChE8.t-rwCLEAR S(S7fvS nC'S ST Att AND FCABLC SAMPtWELL Edit CtaTD16A AND AlF6 Cusiumer er sheper must prownse (preited or typed) mtormation m as numtered column headegs.

GENERAL D m tenanarid me.cantact address asto plione numoer.Co'ri;t.anynavneof carnerwhoestransportng e a Di$ca'e comoany na We Cate of the shspmer:f a spJces provisad.

dDOTCorWestonstatements.

An sishorned represeraanve oc we correany must sen arid dateme State of South Carosma an Cahamn headmg erees are to be made as tonows:

norn er comener number - est eacn contener separasely. tderescrion as pacsage itss2 shat me:ch fur D p)

,(

The terms MFP and M& ore met exsumrt auc'de til eacn radosotope contemed m each ceramner (See Nace #3) 91 Psdao' ped.Use as many nnes as are requue<L peanu (3) Physcal Sale swhcane state. schd. gas, tuoegcat (4) Chanucal Fame. setorence secton 172.203 of 49 CFR I

chesolusi forse weste wea Myde(ur)(solencatan media) l 1.

sendthed scauld statalic esado depooned on reca 7

2.

ress Na er Kl.SrCla,etc i

Iseorasory resh f

l Waste desenplen exavroles-fevaporator bastomsk (fear enaterialsk (schered teamsk (irradeted enesaisk (a (5) cercassesk et catera d

2 SNu(Spcoaf NLeber Marenorams wehtmOramsalmatenalasdefeudn10CF Part2tL3(SC.TBe A12 4)

(6) cannot exceerd JD grams pee 4 0 cutsc leet or idagar contamer.

p) Cource Pounns - wegM ti pounos of material as conned n 10 CFR Part 203 (SC. Tale A 1224)

Ikcord we scavery (endbcise)Guanley at each inixope a each contamer(sicluen0 the acewey of De $NM a (B) -

Gross vbegM. we sht c counde of I'ta eksposntse centamer (mclueng conterest As packagesm ancess d (9) inues have segni anc>cated (see a9 CFR t T2 310k See Seebon173330 of 49 CFft Recerd enternas volume of contacer p 5 R* tot a 55 gason drutn. 4.0 n' tar a 30 gason drum, and 0.85IP (10)

(11) t Ped >

Inecate DOT /tJtC contamer speedicaban il appisatde. such as spec FA, Type 8 package, spongight cort p2)

Rected ye hirihrsi ereamJred ratsation lev #s tot ear n thrposaDie cantamor at l'io speedied c> stances.T cetert (13) tioca Nunitwe (I 4 )egu.w niIhnt Icaeng at 3 80-c.

7 (a)of 43 CIE able COMammahan ODects On certadiefs shat rH3 eaCeed towels se torth kl Secton f 73 403 and 171397 al 49 C#R.

Re p 4)

(tSI' Packages s ias te tacepid as scepared ey Sections s72 tot. I12 300.172 400,17 a

Record cash centilicaban numtier torn name pione on cast.

06)

Record the taaer idensicates numeer a space provated.

(17) 3 The kwas nne as Pe conom et cacn page ausst be comsicted for coeurres 1.8. 7.8 and al by Eacn seem s*wnwvil mu.st tm accompww d Dv anisolcose anaars's represcru*0 IF's Denne 2) ce eacn ana sie au w.e core.re nouve.ne uunen:

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I isympfi til 20 Addda ui stkpgww) papers may flP tequetW e edef $$ a$ (Ffl 172 201 4) w l

i m

4 IIANUAL SET

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PMLUuHt NO E. l. HATCH NUCLEAR PLANT WP-8016 I

See Title Page at e o~ ~o 13 I

oara Georgia Power

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See Title Page o

33 of 48 FIGURE 10 CHEM-NUCLE AR SYSTEMS. INC.

P.O.3QX 726 PNP FORM BARNWELL. 5.C. 29812

'il Telephone (803) 259 3577 or 259 3578 2.

Date:

1.

Category ot Shipment:

Revised Date:

(

3.

Shipper's Mme:

Street Address:

~

City:

State:

Zip:

4.

Emerg ncy Contact Person:

Emergency Telephone No.

S.

Carrier's Name:

Street Address:

City:

State:

Zip:

f 6.

Emergency Contact Person Emergency Telephone No.

7.

Volume of Shipment: Cubic Feet:

8.

Estimated Total Activity (for Iype B

& Large Quantity) 9.

Estimated Date of Shipment:

i

~

o 10.

Estim.sted Date of Attival of Shipment:

r o

\\

11.

Routes Shipment Uill Follow In State Of South Carolina (Be Specific):

1 12.

Signaturs/::ano of Person Completing Form 13.

Copy #1: Cbem-Nuclear System 9, Inc.

Tc1cphonc Number C.irolina. DPl.C Copy #2: St.ite of Sout h, form Attach to HSH Co,5y #3 Copy e4: shipper's cory MANUAL SET

o l

s PHOCLDUWt NQ W HOSAL MP-8016 j

E.1. HATCH NUCLEAR PLANT me no See Title Page f

13 o re g

GeorgiaPower sA

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34 of 48 FIGURE 11

^

DEFINIT 10"5 fte Prior Eotification Plan (PSP) is required by the State of So.uth Carolina. Prior notification is required for shipments falling into the following categories:

Category of Shipments:

Category I:

Shipeents containing Type B er 1.arger Qaantity Packages (cuelve days notice requircd).

Category II:

All Cosk Ship ents (Five day s notice required).

Category III: Non-Cask ship =cnts greatcr than 75 cubic feet (ten SS-gallon drums)

(Five days notice requir.ed).

Specific itecs as per front of form:

Item (1) Category of shipment (see above).

(2) Date: the date this form is filled out or revised.

(3) Shipper's name: Specific company and plant na:e, location b/ name af l

street, city, state, and zip code.

(4) Name of person to be contacted in case of an caergency with the shipment, with the appropriate EMET.GE';CY telephone number.

(5) Name of transportation coc:pany picking up this shipment for delivery with street address, city, state, and zip code of major home office.

(6) Name of the person to be contacted in case of an emergency with the shipment, with the appropriate EMERGE %CY telephone number.

(7) External volusa of the liner, box, container used to* contain the radio-active material during ship =cnt.

(The actual volume of the package to be disposed of).

{

(8) The esti=at'ed total activity for Category I (Type B or Larger-Quantity packages). The actual co puted activity must be telephoned to Chem-Nuclear Syste=s, Inc. on the day of actual shipment.

(9) The " estimated date of shipment". The actual date will be provided by telephone on the date of -hipcie nt.

(10) The " estimated date of shipr:ent ARRIVAI.".

This date will be revised when the " actual shipment date" is determined and telephoned to Chem-Nuclear Systens, Inc. Additionally, if the shipment is delaved enroute and will not arrive on the estimated date, CNSI will be advised by the shipper of the " revised estimated arrival date".

.(11) Specify the route that the shipment will follow during its travel in the State of South Carolina.

(12) Signature and nace (printed) of the person coepleting tilis form with office telephone nur.ber.

SPECIAL NOTE:

geecipt of mail. ram or letter must be twelvo (12) business days prior to t

l Tshipnent of Catepry I, and five (5) business days prior to shipment of i

Category II and III shipcents. Send to:

CHEM NUCiEAR SYSTtMS. INC.

Post Of fice Bow 776

.Bornwell. South Carolino 29812 Telephon~e No: (803) 259-3577 or 259-3578 9

IIAHAL SET

PHOCtpyML ~o

,2 ePHowAt HNP-BOl6 E. l. HATCH NUCLEAR PLANT

. L os.o~ ~o See Title Page 13

'[

DATE GeorgiaPower 35 of 48 See Title Page 4

FIGURE 12 1

.x j

l' Caneral Instr::tions and infer.ation I

4 f

This form is to be used to provife the Department with prier notification of rafloact ve This notificatten j

1.

wasta shi;=ents trans;c ted into or within the State of South Carolina.

(

All written 3

is to be made 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before tas expected date of arrival in the State.

t notices shculd be railed to l

Bureau of Radiological Health Radioactive Waste 2'anage=ent Section S.C. Ccpt. of Health and Envi cr:= ental control

)'

2600 Bull Street Columbia, South Carolina 29201 I

A separate form shall be submitted for each radioective waste shipment.

4 2.

Prior notification is required cf all radioactive waste shi;=ents as defined in 3.

parag:aph 2 of Interna Requiaticas for the Transporation of padioactivs Wasce ist:

or within South Carolina except as provided in paragraph 4.1.2 of the Zeiulati:n.

The " Manifest st==ary" portien of this fors will satisfy riaire= ants of providiv 4.

the Depart =ent with a shipping =anifest, h:vever, it does not satisfy the requirements Regulations of shi; ping dccusents which shall accompaay the shi;=ents as required bf cc j

and the dis;csal facility's license and criteria.

I ll dEivers of the

. A copy of this cc4 sted form shall be provided to the carrier and a 1

i

5.. radioactive wasta shi;=ent.

Upon delivery of the shiptent to the consienee,, acknowledgement of receipt shall be obtained, and a copy of this form and the shipper / carrier's certification form shall 6.

' be returned to the Department.

Specific Instructions

, ' Item Nurber

'1.

Self Explanatory Self Explanatory This ites applies to all ship =ents of radioactive waste transported to and within j

j 2.

3.

the State of South Carolina.

i Each ship:ent cf radioactive wasts shall be identified in sc=e e.anner by the shi;;er.

This number can be a radioactive shipment =ccord number, bill of lading nu-ter, allo-4.

The identification nurbar shall only be used once to identify the cation m: ster, etc.

one shi;=ent for which notification is being rade.

Self Explanatory Indicste in this ites the disposal facility, corsany, organi:stica, etc., to which this 5.

6.

shi; cent has been consigned.

1 Self Explanatory 7.

For through snirnents, indicate in this item estirated date shi; rant will pass 8.

through the state.

9.

Self Explanatory 10.s 11. Applies only to exclusive use, sole use, and full load shi;.ents.

insu:s You should check w: tis carrier t:

12. All routing infer-ation must be specifi:.The carrier is rescensibic to info.~ tno routes you prescribe are acpropriate.

departure.

Cepart:-ont of any c.anges cf suces in South Caro 1Las alts:

a 13 th:1 21.

Self 2xplanatory To be signed only by an authorized representative er acent of the sh:pper Cercaficaticn 0

MANUAL SET d

RAD 10ACilVE WASTE SHIPT.1ENT ft DISPOSAL FORM O P. O. Bot 578 Beatty. NV 89CC3 US ECOLOGY, INC.

(7o2)553-22o3 m

! m

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N EXCCUTIVE 07FICE: (502) 423 71G0 state P.O. BOX 7243 e

LOUISVILLE, KETJTUrttY 40207 Permit Number m

0 y

Illinois Ollicc:(015) 454 2376 O P.O. Box 038 j

j Richtand.WA 99352

.+

,+

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sierve'ev mo.

(309)377-2411 7

y NO. 01525

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PROPER SHIPPING NAME & HAZARD CLASS sotwrw cAteas l TOTAL WEGHT o

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Nu'.ista i

IN POUNDS e

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tl We.t t at.<1ioactive M3terial. Fissile. N.O.S. - Radioactive Material UNOD13 I.

UNM12 hl p Wa,:c Ra Mactive Materict, Lewv Specific Activity. N.O.S. - Radioactive Material j

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2 2rficactive Material, N.O.S.

- Rac!ioactive Material l

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ll We<.te Ra icac:ive Material, Larr.ited Guantity N.O.S. - Radioactive Material

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. RADIOACTIVE Silll5 TENT RECORD NO.

FISS10M MATERIitL_

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f SHIPPED TO:

SM6PPED FROM: GEORGIA POWT.R COMPANY PLANT E.8. HATCH BAXLEY. GEORGIA 31513 LICENSE NO.

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uRfMR, MR8HR. AT 3 FEET MAXIMUM RADIATION AT SURFACE CONTACT PRtfectPAL EMtSSION:

Da>MMA ONEuraON C A'P A O= Era 2

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SMEAR RESULb-9' DATE SU,RVEYED S'/t TRANSPORTATION PEGJSHIPMENT

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OP'AcAao aEou'aio SHIPMENT APPROVAL TRANSPORTATION AND SHIPPING RELEASE l

THis 13 TO CERTIFY THAT THE A80VE NAMEO ARTLCLES ARE PROPERLY C ANO ARE IN PROPER CONDITION FOR TRANSPORTATIOrd. ACCORDING PACKAC10, MARKED ANO LA8ELEO

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- DATE _

SNepesENT ORIGINATOR 1

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shipper is te ec-slete h6s scruen of the farm aed Frasent it to the carrier as part of the the carrier small erreple:e has nortsen of ce form. C;en

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ekippisg deessents. Epon receapt.

delle'ery of O* sea. wet to the censkenee, a espy of ess certif tasties form. and a espy of the Prior Not&ficataen ame raa& fast form wath the consignee acknowledgement. saall Se returned to l

the o*ta *::= cat.

P et ti s a:ecer's ce-t s ficate a: ;c-et:a-ee

2. Enahment idenuncataen me.

L. Same ed snapper and addresse

3. Transport perust ue.

totewee fae. (

)

aadseactave easte Transpectataes ar.4

$m semptsasco wata act i.e. ast of 17ec. the eeuta Caratar.4 I hereby certify en benalf of the above-named shipper to the South Caro 1&P4 Departe Stepenal Act.

emet of Sealth and Envirensental Centrol that the ageve-named s'stpper has cer@lled wath all tre=

e&atens of Act so. 499 of 1980 and all applacable laws and admin &strative rules and regulattens.

t.ranspasstataea, storage, disposal ard delivery hoek State and Faderal, regardaag the pacmagsag.

I further certify that taas shappest of rasamact&ve waste has been Laspected of such eastes.

withia 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the t&se of departure and tAat no itsas of mon =cespliamse w&ta appliceske 1mse ruiu se regulauene were found.

' hoe i

sag::arure TFped aimme amt Tule et Agaat of saa;;er Part !!: Carr.er's Cere s !: cat ;os

2. Saapoea6 Adeat&t&Casses Juan

- s. Name of Carraer and Addresse

3. Tranapest Traaler me.

Dele +eae 7e. f

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S. Letaatted Date of Asr6 val ei 34a;ments

4. ScheduleJ Date of Departwre et Shapnents of realta one Imysterseental Cor.trea

, Certaf testsen as aersey made to tse souta caretsaa sepermer.

ee certati=

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  • proptrly placarted for tranaisrt acrord;rg to arpttes.ste U.d. Petartment of Transportatase Fagua c

all san;parst pepers orig &c.ated or reprehsed by the carr&er have been preferif in ee naurert vemte has nee taspecus aenrnng se as,tiessie state ar.s reeerst g Lationas I:)

. emented.

segulations watt.13 the presstabed intervats and that all safet/ eM operattenal cr.mponesta are na fe) all drtvers wens wt11 eeerste the good wertist.orier and meet ce reeairenents of reeskataertsgehicle =& thin the state of soun Carolana are gaala l

(f) speat!1ed by a;pticaele U.d. Ceparment of *ransportuace regaistecaos be Ameediately neutted of any wortance. escurtag after departure, fram the supper's nettfisataan (gl all a;ptaeasle laws acd of prLary routes an south Carelt..a ar4 estimated date of arrivalsadministrathwe rules and regwaattsas, beth St radioective toastes walk be semp%hed wath.

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U See Title Page 48 of 48 IMTA PACNACE e

~ ' EFFLUENT AND WA:TE DISPOSAL SEMIANNUAL REPORT (YEAR)

WLIDWA3TE AND1RRADIATED FUEL $HIPMLNTS FOR UNIT l

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CEORGIA POWER COMPANY e ~.. -

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HATCH NUCLEAR PLANT f,.

PROCEDURE s

.S.ITE AREA EMERGENC_Y - CONTROL ROOM OPERATOR.S PROCEDURE TITLE HNP-46.22 PROCEDURE NUMBER l

~

1 LAB 1

RESPONSIBLE SECTION

.I SAFETY RELATED ( X)

NON-SAFETY RELATED (

)

e APPROVED APPROVED REV.

DESCRIPTION DEPT.

PLANT DATE HEAD MANAGER 1

,Page 2 y

/

7_ _ _ _ _.._yLf p, A

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2 Page 2

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._- -_ _D_F_P_.".R_ _Tt_G. _._! T :#_,10_ _._*,P_P_: < 0_' '._:.: : ___ __

. Naine ;

_Date:

m Dute; Signature:

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REVISICM CHANCES MOCE OF.CPERATIO.l OR INTENT AS DESCRIDED.IN FSAR:

(}C) No

(

) '<us

. *

  • CHANGE IM/OlNES:-

(

) An unreview d Safety Guestion

(

) Tech. Specs.

$X ) Neither (See back. for Saf ety Evaluation if required).

s j,,

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s Saf ety Related

(

)

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. :. +. _ w.w.a.. ::.., w.a.a.:...... -: _ v-w. +.: --- ::-.:.... r,..

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(

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Attach marked up copy of proced6re to this form.

~

..,.,..,..n REASON FOR REGUEST

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que I

- _._ Th e g_re_b.. i l_i_f.9_o..f.._o_c c_u_r_e_=._- w.a. n d__ tag e n n.s.o.c u_e_n_c_e s__.o f__a n _a c_c_i d_e_n t____--.__

1 s

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-- _.a. - _- ----.c. -- - _e d_ --__ ____

re not in reas -

a_b.o'n_th;ig_a_thz_e.j_h'__tii_ J33_d.u_e_1Q._thss.e.gbao.caS_b.c.ary.-

-- e_rev _s_on does_ n.o.t ch'ar.:e t_he our_cose or oerformance of the th ii

- _s]_s_t em_._-.*. -.

- = - _ -

2.

The cossibility of an iccids t or malfunction o.f._a differen.t tyce *

.:..~

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-.a

.z than an_a_lyzed in the FS.a?. d:ss__not resul_t _f_ rom this chance because the sys_t_s_:_resconds. and is ::srated as before the cha_n.oe.

u

-T....

3.

The marcin of safety as de"__.e_d in the T_echnical_Scecific_a_t.i.o_n_s e

~G.... -

is_ n'ot reduced due to thi_s r_a_v_i_sion because the revision does not

,J t

chan.ce _a_n.y. limited safety sys_t_s_i settines whi_c_h_would allow a _

_ _ _ =.. - -

safety l,.i_n_it to be exce=ded or t'o allow a limit _i_nc condit_i_on for_

m co_e_r_atio_n_s_t_o.b._e_ exceeded as stated in' Technic _a_l_.Soecificat_i_on_s_.

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1 of 2 SITE AREA EMERGENCY - CONTROL ROOM OPERATORS,

" NOTE l

l This procedure supercedet HNP-4601 Revision 5 da+,ed B-1-80.

A.

CONOITION

~

s Events are in process or have' occurred which involve actual or likely m'jor failures of plant functions needed for protection of a

the public.

Any releases are not expected to exceed PAG exposure levels, except near the site boundary.

B.

REFERENCES HNP-4620

..[

1 C.

ACTION'

~ ~ ~ ~

y.,

i f.

l 'w 1.

Take appropriate action to place the plant in a safe condition in accordance with emergency operating procedures,

+_4'___?

Tech. Specs., and annunciator response procedures.

2.

Check wind dire.ction and saeed on panel H11-P658.

Determine evac,uation route, based on wind direction as follows:

_.. ROUTE WIND DIRECTION 315*

- 90*

North on U.S.

1 91*

- 525*

South on U.S.

1 226*

- 314*

Either' direction on U.S.

1 3.

'Make the following announcement over the PA:

]

ATTENTION, ATTENTION:

A SITE AREA EMERGENCY EXISTS.

INITIATE SITE AREA EMERGENCY PROCEDURES.

REPORT TO GATE 16 TO EXIT THE PLANT AND RECEIVE FURTHER INSTRUCTIONS.

EVACUATION ROUTE WILL BE (NORTH / SOUTH /EITHER DIRECTION) ON U.S.

1 HIGHWAY.

l, Sound the Gai-Troni cs tone for Site Area Emergency end i

repeat announcement.

8 4.

Chsck Control Room instrumentation to determine status of l

~'

plant as to whe ther or not a General Emergency should be

, declared.

Notify Shift Supervisor of findings from l

~

performance of HNP-4853.

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IF Shift Supervisor has not reported in to the Cqntrol Room,

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s. ~.'.,,c. h-n.

snitiate his actions as per HNP-4623.

3f:

t.e. :.

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E..

Announterent of the " Site Area Emergency" status should be 2

. '. '1,. '..... c -

repeated periodically (approximately every 30 minutes) c. ;..

.E.'..Q...*7..'C.,

throughout the duration of the event.

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PR65500RE TITLE HNP-4FP4

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Lab RESP 655I5LE SE6TI6N s

SAFETY RELATED ( X)

NON-S/EETY REL ATED (

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E.1. HATCH NUCLEAR PLANT HNP-4004 4

See Title Page

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3 See Title Page 1 of 2 1

SITE _ AREA EMERCENCY - INTERNAL _ SURVEY _ TEAM,

NOTE 1

This procedure supercedes l-iNP-4GO3 Revision 4 dated 1-2-81.

A.

C.ONDITION Events are in process or have occurred which involve actudl or likely major failures of plant functions needed for protection of the public.

Any releases are not expected to exceed PAG expostire levels, except near the site boundary.

I O.

BEEERENCES HNP-4620.

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C.

ACTION' r-s.

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NgTE_,

. g, ' j This' action is to be taken by the H.P. Supervisor J

and* technicians.whenever possible, or by other traj.ned personnel.

1 1.

OSC' Manager or his designee will form the Internal Survey Team.,,.The survey team will consist of H.P.

technicians or Other trained RET members.

The minimum number of Internal Survey Team members will' be two.

The OSC Manager or designee may increase the number of survey team members if the conditions warrant.

2.-

Obtain the following equipment from the OSC emergency kit:

a.

High Range Dose Rate Meter b

b.

Shears c.

MSA Air Pack 4

d.

Protective Clothing e.,, ' Air Sampler (load with silver zeolite cartridge and glass fiber filter) 7

, f.

Radio

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High Range Dosimeter (self-reading) g.

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See Title Page 2 of 2 3.

Turn survey instruments on to allow for warm-up.. Check battery of survey ins.trument.

Check operation of air sampler and radio's.

4.

Don protective clothin.g and the SCGA.

5.

. As directed by the OSC Manager or desigriee, procSed toward area where the emergency exists making a survey as you go.

NOTE At all times follow limits and guidelines in HNP-4866.

6.

Notify Control Room and/or OSC Manager of any unusua'l conditions such as high dose rates, high contamination levels, damaged equipment, etc.

Retreat if dose rates are significantly higher than expected.

-[

,e Ih conditions permit survey -fo'r ' habitability of H.P.

lab and 7.

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counting room.

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5 8.

Rope off and post areas of high radiation as conditions

-. q; permit.

, L40TE The' primary means of communication with the OSC,

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Control Room, EOF and.TSC will be through the use of the plant telephone system.

If this system should become inoperable or an alternate system is preferred, then the plant radio and/or page will provide alternate means of communication.

j 9.

Survey area outside Unit 2 truck door.

Post area and control access as appropriate.

l 10.

When requested, assist the Control Room, TSC and/or EOF in evaluating the extent of radioactive material released, the potential for release and offsite doses.

11.

Document survey findings on standard Health Physics Survey forms; present findings and present survey forms to H.P.

I Supervision for approval and filing (see HNP-8012).

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Re,t' urn to the OSC when released by the Shift Supervisor or p

12.

H.P. Supervisor.

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$'...' I GEORGIA POWER COMPANY

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HATCH NUCLEAR PLANT uJ FROCEDURE 5

Site Area Emergency - Rer, cue Team

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PR CEDORE TITLE HNP-4E.28 PROCEDURE NU5GER l

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Lab RESPONSIBLE SECTION s

SAFETY RELATED ( X)

NON-SAFETY RELATED (

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amNw t m % 1DV84 W E. l. HATCH NUCLEAR PLANT HNP-4E.28

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See Title Page "tvva w h

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3 Georgia Power.

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See Title Page 1 of a j

SITE _ AREA EMERGENCY - RESCUE TEAM NOTE

~

1 This procedure supercedes HNP-4GO7 Revision G dated 8-31-79.

A., CONDITION

~

Events are in process or have occurred which involve actual or likely maj'or failures of plant functions needed for protection of the public.

Any releases are not expected to exceed PAG ex*posure levels, except near the site boundary.

B.

REFERENCE HNP-4620 C.

ACTION

~

2f3 - i 1.

The OSC manager or ' designee appoints members of the RET to V.. ?-

3 also appoint a member of the Rescue Team to act as the serve as the Rescue Team.

The O'SC manager or designee shall En. g,

i Rescue Team Captain.

=

2.

The Rescue Team Captain should designate members of the Rescue Team to fill the following positions:

~

'a.

First Aid Leader b.

Survey Man l

c.'

Rescu'e Team Assistant

~

d.

Rescue Team Assistant 1

i 3.

The responsibilities of'the Rescue Team members are as follows:

a.

Rescue Team Captain: ': Lead team in rescue effort; maintain communication with the OSC and/or the Control Room; assist, if necessary, in first aid as directed by the First Aid Leader; assure an ambulance has been called if needed; carry radio.

b.,* First Aid Leader:

Lead Rescue Team in first aid

' measures; inform Team Captain of condition of

(

' victim (s); assist with stretcher and rescue equipment

__c If needed; carry first aid kit.

e g,

e,_

c..

gurvey Man:

Perform an immediate survey of area (s);

1 update the Rescue Team with respect to radiological

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'conditiong throughout the rescue effort; assist First

/V*i.

s-Aid Leadeb if requested; carry dose rate instrument.

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E. l. HATCH. NUCLEAR PLANT HNP-4G23

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See Title Page na mo. w u

vait Georgia Power d 3

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See Title Page 2 of 2 d.

Regue_,Tenm Assistants;,

Participate in the. rescue effort as directed by the Rescue Team' Captain.

4.

Use protective clothing only when the time and the situation permit.

Respirators may, also be needed depending on the 1

nature of the situation.

All team members should be

. equipped with a High Range Self-Reading Dosimeter in addition to their TLD and 200 MR Dosimeter.

5.

Obtain the following equipment:

a.

First-Aid Kit b.

Stretcher High Range Dose'itrte Meter c.

d.

. g --

kalkie-Talkie y,;.,.,

[

e.'

Pinch Bar (if required for rescue) 5 f.

Rope and Tackle (if required for rescue)

~p'J.

t 6.

Retreat if dosimeter reaches 2R and victim has not been located.

t

'k.

Limit dose to members of Rescue Team in accordance with

~

HNP-4812 during rescue.'

B.

Refer to HNP-4801, HNP-4802, HNP-4803 and HNP-4810 for additional instructions concerning first aid, decontamination, handling and transport of exposed and/or contaminated injured individuals.

9.

Report condition of victim to the Control Room, specify whether or not the victim is contaminated.

Assure that the Shift Supervisor relays thi.s information to the hospital.

10.

Contact Emergency Operations Facility or Control Room by

(

radio or phone for ambulance pickup of victim in the upwind i

direction of victim's location.

11.

Move victim to ambulance.

12.

Arrange (or radiation technician to accompany victim to l(

(,

hos*pital in ambulance.

l _.'

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Update the Technical Support Center as soon as possible.

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Take necessary measures to limit spread of contamination and l,/;gg h.l i, repor't to the DGC when rescue effort is completed.

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HATCH NUCLEAR PLANT f~. 't PROCEDURE Act i on s* f o r Al l P e r.c..o.nn e l i n G_ en e ra l E_m_.e r.g_en_.c. i e s PROCEDURE TITLE HNP_4721 PROCEDURE NUMBER Lab RESPO.NSIBLE SECTION SAFET,Y RELATED ( X'i NON-SAFETY RELATED (

)

a______________a______.

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nw m.m E. l. HATCH NUCLEAR PLANT HNP-4721

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See Title Page mim o Georb aPower nk

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i ho 1 of 4 See Title Page ACTIONS FOR ALL PERSONNEL IN GENERAL _ EMERGENCIES,

} @TE

  • This procedure supercedes HNP-4,700, Revision G dated 9-5-79.

A.* CONDITION Events are in process or.have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

Release can be reasonably expected to exceed PAG exposure levels offsite for more than the immediate site area.

I B.

REFERENCE HNP-4720.

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ACTION

.. ~ ~

v.;.

1.

Persons discovering an emergency condition shall immediately

>- y l

notify the Control Room by the most expeditious means avail-A

-F able.

2.

Control Room ope,cators shall announce the nature of the emerg,ency on the public address system and specify that personnel initiate general emergency procedures.

3'.

ControlRoomokeratorssha.11placetheplant'inasafe l

con-dition as the emergency warrants.

4.

If possible, person (s) in immediate area take appropriate, i

rapid action to limit the extent of the incident with avail-able means, and then retreat to the rally point.

(

5.

Persons involved in the incident report to Health Physics at the Emergency Operations Facility as soon as possible after decontamination for further evaluation of dose received.

6.

Persons called in from offsite should report to the Emer-gency Operations Facility unless specifically directed otherwise.

~

7.

Staffing of the Emergency Operations Facility (EOF) shall begi'n immediately.

The normal EOF is in the Simulator Building and the alternate EOF is the Appling County Sheriff's Office in the courthouse.

The OSC (Operations

~~

Support Center) should be located in the Unit 1 Service

, '('

Duilding, with the headquarters / reporting area being the

., f, yi North end of the break room.

The alternate OSC is the

i Simulator Traini.ng Building.
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See Title Page o

2 of 4 8.

If the emergency occurs during a regular day shift members y

of the plant operating

  • organization on site will report as follows:

a.

Control Room Operations Supc'r' visors, all on shift Operators, Shift Supervisor, Operations Supervisors, Shift Technical l

Advisor, Shift. Clerk, (Communicator / recorders as needed)*

8 b..

Emergency Operations Facility (EOF)

~

The following personnel will report to the EOF afher checking through the rally point:

Manager Engineering, Health Physics Supt., Health Physicists, Manager Administrati.on, Finance and Human

.gff. ;"

Manager, RET members assigned to Field Monitoring

' Resources, Supt. of Regulatory Compliance, Security y,,,

teams.

(Communicator / recorders as needed)*

3,'.

c.

Technical Support Center'(TSC)

Thefollowinhpersonswill report directly to the TSC

,following notification of a General Emergency.

f Deputy General Manager, Superintendent of Engineering l

l Services, Superintendent of Maintenance, Superintendent of Ope. rations, Reactor Engineer, Engineering Supervisors, Laboratory Supervisor (Health Physics),

Document Control Supervisor, (Communicator / recorders as needed)*

Security Representative.

.l d.

Operations Support Center (OSC)

The following persons will report directly to the OSC

)

(

following notification of a General Emergency.

1 1 Maintenance Supervisor, (OSC Manager), 1 crew instrument technican w/ foreman (pre-designated), 1 crew l

electrician w/ foreman (pre-designated), 1 crew mechanic w/ foreman (pre-designated), all R.E.T. members, Plant L

Equipment Operators.

(Communicator / recorders as "needed).*

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,* Communicators / recorders are members of the Plant Engineering and Regulatory Compliance, staffs, and will be dispatched as required.

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See Title Page Ha vie,.o j

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Georgia Power "-

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Gee Title Page 3 of 4 9.

All personnel who have not been assigned to the control room, TSC, OSC or EOF will evacuate the site per' step 12 or

~~

~

13.

10.

Members of the plant organization will comply with appli-cable procedures to effe'ct orderly coordinated actions in

.the emergency.

11.

Members of the Radiological Emergency Team (RET) report to the.OSC immediately if on site when the emergency begins.

If team members are called in, they will report,to the EOF for assignment.

12.

Evacuation Erocedure for personnel inside the Primari Protected Area.

n.

Every Ef f ort shall be.Inade to minimize personnel exposure to radiation.

Ig.

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b.

All personnel shall stop work, turn off po$entially hazardous equipment such as cutting torches, and leave the work area by the same route taken to enter the area.

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NOTE Personne1' working in contaminated areas should remove

~

" rubber gloves and booties prior to crossing the first step-off' pad to exit the work area.

Remaining protective clothing should be removed before leaving the radiation contro.11ed area, i. e.

exiting through C52,'T-16, T-17, Railroad Airlock etc.

In general, i

protective clothing should be removed as soon as practical, depending on the nature of the situation.

c.

Proceed to Gate 16 via the most direct route, unless an alternate route is specified by the Control Room.

d.

Proceed to drop-off indentification badges at the Security post and continue to the area immediately outside Gate 16, the Environmental Building, or the Skills Training Building as directed by the Rally Point Leader for personnel monitoring.

NOTE i

~

Personnel who have been in the area of the emergency should remain in a group and should not mix with other j

personnel at the Rally Point until monitored for T

possible contamination.

The same holds true for

l. hl,]i personnel who have been working in contaminated areas

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E. I. HATCH NUCLEAR PLANT HNP-4721 See Tit 1e Page

.sva.u o

4 Georoia Power A um See Title Page o

4 of 4 e.

Once personnel monitoring is completed, RET members will direct personnel to leave the plant site.

f.

Personnel should leave the plant site on personal vehicles using U.G. 1-twy.

1.

The direction of travel (North, South, either direction) wil-1 be announced by the Control Room and will be based on wind direction.

g.

If required, company vehicles will be used to

. supplement transportation needs.

8 13.

Evacuation procedure for personnel outside the primary

~

protected area:

l a.

All personnel shall stop work, turn off potentially hazardous equipment, and leave the work area.

b.

Proceed to Cate 1, via the most. direct route, unless an

[.... ;.

alternate route is speciFied'by the Control Room.

n.

c.

Personnel monitoring will be performed at Gate 1, the

  • =

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Environmental Building or the Skills Training Building M

as determined by the RET members present.

co[npl et e d, RET personnel d.

Once perso.nel monitoring is will direct all personnel'to leave the plant site.

e.

Personnel'should leave the plant site in personal vehicles using U.S. Hwy.

1.

The direction of travel will be.' announced by.the Control Room and will be based o.n wi6d direction.

f.

If required, company vehicles will be used to supplement transportation needs.

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PROCEDURE 1

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Cennen! Eme_rgency - Control Room Og~erators

~-~

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PRUCEDUR5 TITLE HNP-4722 PROCEDURE NUMBER

~

Lab RESPON555LE~SECTION 8

SAFE.TY RELATED ( X)

NON-SAFETY RELATED (

)

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1 of a CENERAL EMERCENCY - CONTROL _ ROOM OPERATORS NOTg This procedure supercedes,HNP-4701 Rev. 4 dated 5-13-78.

A.

QONDITION Events are in process or.have occurred which involve actual or imminent substantial core degradation or melting with poteritial for loss of containment integrity.

Release can be reasonably expected to exceed PAG exposure levels offsite for more than the-immediate site area.

~

B.

REFERENCE I

HNP-4720 g -.

C.

ACTION

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1.

Take appropriate action to place the plant in a safe

_3 condition in accordance with operating emergency procedures, 8

Tech. Specs., and annunciator response procedures.

2.

Check wind dire,ction and speed on panel Hil-PG58.

Determine evac.uation route - base bn wind direction as follows:

WINDDIRNCTION ROUTE j

315'-90 North on U.S.

1 91* -225 South on U.S.

1 226*-314' Either direction on U.S.

1 l

3.

Make the following announcement over the PA:

l ATTENTION, ATTENTION:

A GENERAL EMERGENCY EXISTS.

INITIATE GENERAL EMERGENCY PROCEDURES.

REPORT TO CATE 16 TO

~

EXIT THE PLANT AND RECEIVE FURTHER INSTRUCTIONS.

EVACUATION ROUTE WILL DE (NORTH / SOUTH /EITHER DIRECTION) ON US. 1 HIGHWAY.

g Sound the general emergency tone on the gal-tronics system.

Then repeat announcement.

~~

4.

Using HNP-4853 perform Dose Assessment Calculations, until

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the dose assessment team, at the EOF is activated.

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If Shift Supervisor has not reported in to the control room,

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Announcement of the " General Emergency" status should be f

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RESPU. 55YiiLE~55CTION SAFET.Y RELATED ( X)

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PLANT DATE HEAD MAb,ER 1

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See Title Page

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See Title Page 1 of 2 CENERAL EMERCENCY - INTERNAL SURVEY TEAM

, blOIE_

This procedure superced's HNP-4703 Rev. 4 dated 5-13-78.

e A.

CONDITION Events are in process or have occurred which involve actual or imminent substantial core degradation or molting with potential for loss of containment integrity.

Release can be rebsonably expected to exceed PAG exposure levels offsite for more than the immediate site area.

I

'B.

REFERENCE HNP-4720 C.

ACTION v

y NOTE "To This action,is to be taken by.the H.P.

Supervisor

~

and technicians whenever possible, or by other irained personnel.

1.

OSC t4anager or.his designee will form the Internal Survey Team.

The survey team will consist of H.P.

technicians or other trained RET members.

The minimum number of Internal Survey Team members will'be two.

The OSC Manager or designee may increase the number of survey team members if the conditions warrant.

2.

Obtain the following equipme.nt from the OSC emergency kit:

a.

High Range Dose Rate Meter b.

Shears c.

MSA Air Pack d.

Protective Clothing e.

Air Sampler (load with silver zeolite cartridge and glass fiber filter) f.

Radio e

g.

High Range Dosimeter (self-reading) s

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3 Georgia Power al van

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Turn survey instruments on to allow for warm-up.. Check 3.

battery of survey instrument.

Check operation of air.

sampler and radio's.

4.

Don protective clothing and the SCOA.

^

~

As directed by the OSC Manager or designee, proceed toward 5.

area where the emergency exists making a survey as you co.

L40TE At all times. follow limits and guidelines in HNP-4866.

I Notify control Room and/or OSC Manager of any unusual 6.

conditions such as high dose rates, high contamination levels, damaged equipment, etc.

Retreat if dose rates are significantly higher than expected.

lab and If conditions permit survey far' habitability of H.P.

M'i 7.

F counting room.'

g-Rope off and post areas.of high radiation as conditions 8.

'., ~Ti permit.

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NOTE,

.s Control

'The primary means of communication with the OSC, EOF and TSC will be through the use of the plant

Room, telephone system.

If this system should become inoperable

~

or an alternate system is preferred, then the plant radio and/or page will provide alternate means of communication.

i Post area and 9.

Survey area outside Unit 2 truck door.

control access as appropriate.

assist the Control Room, TSC and/or EOF in When requested, 10.

the evaluating the extent of radioactive material released, potential for release and offsite doses.

Document survey findings on standard Health Physics Survey 11.

findings and present survey forms to H.P.

forms; present (see HNP-BOl2).

Supervision for approval and filing Return to the OSC when released by the Shift Supervisor or 5

12.

H.P. Supervisor.

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HATCH NUCLEAR PLANT PROCEDURE Cenpen! Fmorgoney - Rescue Team PR6CEDURE TITLE HNP-47PR PROC 660RE UO58ER

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See Title Page

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1 of 3 CENERAL EMERCCNCY - RgGCUE TEAM N._O_T.E This procedure supercedes HNP-4707 Rev.

3 dated 5-13-78.

A.

CONDITION Events are imminent substantialin process or have occurred which involve actual or for loss of containment integrity. core degradation or melting with potential Release expected'to exceed PAG exposure can be reasonably immediate site area.

levels offsite for more than the l

.B.

_ REFERENCE HNP-4720

. d..

C.

ACTION My

1.

.The OSC manager or designee appoints members of the RET to 5

serve as the Rescue Team.

also appoint a member of the Rescue Team to act as theThe OS Rescue Tearn, Captain.

RJ The Rescue Team -Captain should designate members of the Rescue Team to fill the following positions:

FirstAidkeader

~

a.

b.

Survey. Man Rescue Team Assistant c.

d.

Rescue Team Assistant

.3.

The responsibilities of the Rescue Team members are as follows:

Rescue Team Cagtain:

Lead team in rescue effort; a.

i maintain communication with the OSC and/or the Control I

Room; cssist, if nacessary, in first aid as directed by the First Aid Leader; assure an ambulance has been called if needed; carry radio.

b.

'Fi r s t_A i d_Le n d e r:

Lead Rescue Team in first. aid measures; inform Team Captain of condition of victim (s);

assist with stretcher and rescue equipment 3

..:if' needed; carry first aid kit.

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Georoia Power cb cart

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D 2 of 3 See Title Page Perform an immediate survey of area (s)*

Survey._tian;.

c.

update the Rescue Team with respect to radiological conditions throughout the rescue effort; assist First Aid Leader if requested; carry dose rate instrument.

d.

, Rescue Team Assie.tunts:

Participate in the rescue effort as directed by the Rescue Team Captain.

Use protective clothing only when the time and the situation 4.

permit.

Respirators may also be needed depending on the natui e of the situation.

All team members should be e, quipped with a High Range Self-Reading Dosimeter' in addition to their TLD and 200 MR Dosimeter.

I 5.

Obtain the following. equipment:

a.

First-Aid Kit

,.g b.,

Stretcher y

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High Range Dose Rate Meter C(.

c.

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d.

Walkie-Talkie Pinch Bar (l'f required for rescue) e.

f.

Rope and, Tackle (if required for rescue) 6.

Retreat if dosimeter reaches 2R and victim has not been located.

i 7.

Limit

  • dose to members of Rescue Team in 'accordance with HNP-4812 during rescue.

8.

Refer to HNP-4801, HNP-4802, HNP-4803 and HNP-4810 for additional instructions concerning first aid, decontamination, handling and transport of exposed and/or contaminated injured individuals.

9.

Report condition of victim to the Control Room, specify whether or not the victim is contaminated.

Assure that the Shift Gupervisor relays this information to the hospital.

e Contact Emergency Operations Facility or Control Room by 10.

radio or phone and arrange for ambulance pickup of victim in the upwind direction of victim's location.

11.

Move victim to ambulance.

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3 op 3 12.

Arrange for a radiation technician to accompany yictim to hospital in ambulance.

13.

Update Technical Support Center as soon as possible.

14.

Take necessary measures to limit spread of contamination and report to t,he OSC ;ianager when rescue effort is cornplete d.

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'., I HATCH NUCLEAR PLANT PROCEDURE Review and Revision of Emergency Plan and Im l ement.i ng P rn rorfie res

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H N P. 4.R. 9. 1.=

PROCEDURE NUMBER

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RESPONSIBLE SECTION SAFETY RELATED ( X

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NON-SAFETY RELATED (

)

,____.,_______________.,_____________3_____________._,_____.__.m i

APPROVED APPROVED REV.

DESCRIPTIDN DEPT.

PLANT DATE HEAD MANAGER 1

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1 of 4 See Titic Page bey]EW AN9_RgylSig3_gE_EMEBEEUCY PLAN j

i ANg_IM.PLEMENTING PROCEQUHES A.

PURPOSE

~

To describe generally the methods for review of emergency plans, agreements, and procedures.' '

D'.

EREQUENCY (MINIMUM)

~

I 1.

Emergency Planni_nd' Coordinator Resgonsibility Eme'rgency Plan - Update as necessary; review and certify to b'e current annually.

g Agreements - Update as needed; review and certify to be 4

current annually.

Procedures - Review annually and rev.ise as needed.

d Emergency Call List - Update q'uarterly.

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2.

Indogendent Review Group Responsibility

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Emergency plan, procedures, practices, training, readiness testing, equipment, and interfaces with State and local governments -re9iew nominally every twelve months, the interval from the previous review may be shortened, -but may not be extended beyond 15 months.

The review may include the emergency plan, its implementing procedures and practices', training, readiness testing, equipment and interfaces with offiste agencies.

The results of the review, along with its recommendations for improvements, shall be documented and reported to licensee management and to appropriate offsite agencies.

Management controls shall be implemented for evaluation and correction l

of review findings.

Records of the results of these reviews and any recommendations shall be retained for a minimum of five years.

C.

EMERGENCY PLANNING _ COORDINATOR (EPC)

The EPC will be responsibie for reviewing and revising where l

necessary; the emergency plan, procedures, agreements, and call lists at the frequency in Section B.

Documentation and scheduling of the procedure reviews will be through the use of the normal plant procedure review process.

Certzfication that the plan and agreements are current will be stated in Data Pa citage 1 (Data Sheet 1).

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.I_NDEFENOrtjT REVigtiGROUP The onsite GA organization shall conducttherebiewdescribed in Section B.

Documentation for this review will be by report to-the SRO and Plant Manager and to offsite agencies as appropriate.

E.

gVALUATION OF REVIEWS AND REC'OMMENDED CHANGES The PRD and SRO will review recommended changes to the emergency plan, and agreements.

The PRD will review recommended changes to emergency procedures and call lists.

I The PRD and SRO will evaluate the report on the independent review and will assume implementation of the corrections which they deem appropriate.

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Georgia Power a 3 of 4 i

See Title Page I

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I PROCEDLXIC DATA PACKACE DOCW to: HPP-4121 -1 y

SERIAL NO:_ _ _RO2-PPL po:_tuA i

RTYPE: C15.03 XREF:___N/A

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.s I HAVE REVIEWCD Tif1S DATA PACHACC FOR COMPLETDESS Ap AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH MP-830.

ACCEPTEDLE LNACCEPTADLE REVIEWED BY:

DATE REVIEWED:

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g The Emergency Plan and Agreements have been reviewed and are tertified to be current.

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PROCEDURE Securitv Alert _- Security Forte u

PROCEDURE TITLE HNP-4902

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PROCEDURE NUMDER I

Lab

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RF.SPONSIDLE SECTION i

SAFETY RELATED ( X)

NON-SAFETY RELATED (

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s APPROVED APPROVED REV.

. DESCRIPTION DEPT.

PLANT DATE i

HEAD MANAGER 4

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REVISICM CHANGCC MCC E O.7.CPERATIDM 03 INTENT AS DEGCRIDED IN FSA

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T_h a..oroS 35 f li_t t o f occurr.=._- a.su_a.n d__t_h.e. c_o_ny a u_e_n.c_e s__. o_f__a n_ a_c_

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SECU.,ITY ALERT - SECUnTTY FORCC

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CO'IDITIO!!

', Notification has been roccived of a security alert involving:

A bomb, other overt threat, or a civil disturb'ance.

B.

ACTION 1.

Security Post 200 Delta (Monitor / Communications Operator).

a."

Notify the Appling

County, and/or Toombs County

. Sheriff's Department, and/or the Georgia' State Patrol (depending on the nature of the cause for the aler t) giving them the conditions causing the alert.

b.

Initiate provided up to date call list for security alerts giving to the persons on the list the conditions

,jfI for the security alert.."

d,..

c.

Notify Gate 1 (Construction) that a security alert has been called and to admit no persons or vehicles until

,the alert has been. terminated or access granted by

.3, plant management.

.j d.

.If the security officer on 200 Charlie (Access) has been committed to the Response F.o r c e, admit no persons 2......

or vehicles to the protected area until the security alert has been terminated or access is granted plant management.

e.

Verify communication radio and telephone communication with the control Room.

2.

Shift Supervisor (Security) a.

Have all non designate'd vehicles removed from the 7

protected area, t.

b.

Recall all visitors 'and, have them leave the protected 1

area.

l c.

If unauthorized entry or intrusion is discovered or J

]

. suspected, notify the Shift Foreman, and begin a scarch i s

for the intruder.

If necessary, activate the Response l 1

, Force and call in additional cocurity personnel.,

Search the exterior of all buildings and structures.

l The Shift Foreman vill conduct the necessary interior a.

cearches,

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2 of 2 Soo Pann 1 If a bomb is suspected or discovered, r ef er to !!NP-302, Bomb and Other Over t Threats.

Orced tus d.

Assist -shif d Supervisor.(operations)- in determining if further emergency actions are required.

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RESPOMSlBLE GECTIGN GAFETY RELATED ( X) l'ON-SAFETY RELATED (

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APPRO'/EO APPROVED

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con Title Page Isil

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1 of 2 Cne Title Pnge E69196991c66_ M UI A.

GL650_935LB.ICI190 One or more of the following conditions are satified:

1.

An ARM alarms upscale; or 2.

Local dose rates as indicated by other instruments are about 10 times higher than expected; or 3.

Air activity is greater than 1 MPC (particulates and lodines).

and 1.

Control Room has not been notified p'rior to event; or 2.

Access is not controlled; or 3.

Event is not preplanned.

D.

PURPOSE To assure that personnel are promptly notified and that adequate protective and corrective measures are undertaken to mitigate the consequences of a radiological event within the operating buildings.

C.

REFERENCES HNP-4321

" Actions For All Personnel In A Radiological Event" HNP-4322

" Radiological Event - Control Room Operator" HNP-4323

" Radiological Event - Shift Supervisor" HNP-4324

" Radiological Event Gurvey Team" HNP-4420

" Notification Of An Unusual Event" UNP-4520

" Alert" HNP-4G20

" Site Area Emergency" i

l HNP-4720

" General Emergency" nunm sn L

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CL69I 69Il003 f.3915 The Shift Supervisor, Operations Supervisor (or higher ranking licensed or certified person present) in consultation with the Health Physics staff, when applicable, recognizes and declares that the plant (or area within the plant)is in a class of a Radiological Event.

1.

The Control Room staff will announce the Radiological Event

_ per their applicable procedure (HNP-4322).

2.

All plant personnel should follow the actions described in HNP-4321.

3.

Augment,on-shift resources as needed.

4.

. Assess and respond as outlined in'HNP-4323 & HNP-4324.

5.

Escalate to a more severe class, ie, " Notification Of An Unusual Event", " Alert", " Site Area Emergency" or " General Emergency", if appropriate.

The criteria describing these classes are specified in HNP-4420, HNP-4520, HNP-4620 and HNP-4720 respectively.

6.

Close out with an announcement over the P.A.

system when the event has ended.

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HNP-4?ai

~~~~

PROC 5i3Uiif~iiU55ER

~~~~

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2 1 of 2 Gee Title Paria.

ACTIONG FOR ALL._ PERCON!jEL IN:A RADI_OLOGICAL_ EVENT NOTE This procedure supercedes HNP-4 GOO Revision 7 dated ' 81.

A.

COUDITIOU.

One or more of the following conklitions are satisfied:

1.

An ARM alarms upscale; or 2.

Local dose rates as indicated by other instruments are about 10 times higher than expected; or 3.

Air activity is greater than 1 MPC (particulates and iodines).

and 1.

Control Room has not been notified prior to event; or 2'

Access is not-controlled; or 3.

Event is not preplanned.

D.

6CIlON 1.

For personnel involved in incident:

a.

Retreat to safe room and contact Control Room.

Give location, nature, and extent of incident.

Request assistante if required.

b.

Eliminate or limit extent of incident if possible.

Do not stay in high radiation or airborne contamination area.

c.

Evacuate non-essential persons from adjacent areas.

d.

For liquid spill:

(1)

Avoid contact with liquid.

-(2)

Contain with plastic sheets, if available.

i (3). Absorb with cloth or paper, e.

Assist injured.

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Stand by for further instructions from Shift Supt /rvitor.

Submit to radiological survey.

Verify not contaminn t e d,e g.

GouIlgt!

t Do not enter Control Rocm until veiified not contaminated.

Remain segregated until decontaminated.

2.

Person (s) not involved in incident.

Observe public address announcement and radiation aldrm..

a.

b.

Evacuate and stay clear of radiafion area specified by PA announcement-and Control Room unless requested otherwise.

De ' prepared. to implement f10TIFICATION - OF UNUSUAL EVENT, c.

. ALERT, SITE AREA or GENERAL EMERGENCY procedures,.if the emergency-is reclassified.

i

~d.

Continue normal work activity.

3.

Visitors' escorts direct visitors to stay with you.

Avoid radiation area.

Escort visitors, if not involved with-radiation area, to Service Guilding until emergency is eliminated or-further instructions given.

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A-S00011100 One or more of the following conditions are satisfied:

1.

An ARM alarms upscale; or 2.

Local dose rates as indicated by other instruments are about 10 times higher than expected; or 3.

Air activity is greater than 1 MPC (particulates and lodines).

and 1.

Control Room has not been notified prior to event; or 2.

Access is not controlled; or 3.

Event is not preplanned.

D.

6CTION 1.

Announce over the public address system:

A RADIOLOGICAL EVENT IS OCCURRING.

AGOVE NORMAL RADIATION (OR AIRDORNE RADIOACTIVITY) EXISTS IN THE __(location) __

AREA.

EVACUATE AND STAY CLEAR OF THE ___1195g11g91___

AREA.

FOLLOW ACTIONS FOR ALL PERSONNEL IN RADIOLOGICAL EVENTS.

Repeat Announcement.

2.

Contact the Health Physics office to assist in mitigating this condition.

3.

Checl< status of ARM's and ' effluent monitors near incident a r c a r..

Notify Ghift Supervisor of abnormal indication er sudden thange.

Attempt to verify accuracy of alarmed Al(M's and eIfluent monitors.

4.

Observe control room instrumrntatir.n and' controls.

Implement corrective action to elsminate'cause of this

(

abnormal condition, if possible to do no from the.contr61 room.

46 4

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SAIL Georc>ia Power em

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If requtisted by the person discovering the incident, shutdown equipment to limit the spread of contamination.

E.. ' Che cit habitat >ility of control room by observing radiation monitors, or possible isolation of control room ventilation system.

7.

When this abnormal condition no longer exists, announce an all clear over the public address system.

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GEORGI A PO'..jE.R COMP ANY I!ATCll UUCLEAH PLANT PROCEDURE

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SAFETY RELATED ( X)

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PLANT DATE HEAD MANAGER

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A.

CQU21IIQU One or more of the following conditions are satified:

1.

An /5RM alarms upscale; or 2.

Local dose rates as indicated by other instruments are about 10 times higher than expected; or 3.

Air activity is greater than 1 MPC (particulates and iodines).

and 1 '.

Control Room has not been notified prior to event; or 2.

Access is not controlled; o r.*

3.

Event is not prep 1'anned.

D.

69I100 1.

Contact Control Room.

Request location and nature of incident and dose rate of areas involved.

2.

Go to Control Room.

3.

Confirm incident announced over public address system.

4.

Contact person who discovered this abnormal. condition, if possible, and evaluate situation.

5.

If necessary, and if laboratory personnel are on site,

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Co-ordinate corrective action'as required.

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Determine cause of-incident, limit extent of incident, 'and bring the abnormal condition under control.

B.

Evaluate incident with lit:alth Physics staf f assistance to determine if an emergency exists.

Upgrade to the.pr'per o

emergency classification.

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=- i ...n...,.. I M ' -'i n E. I. HATCH NUCLEAR PLANT "" wa '~ one Title Pap-3 /} ; ~ '~ Georeia Power em 0 1 of 2 e,ee Title Page 860196921EoL_EYEST - D"BYEY._IEot! NOTE This procedure supercedes HNP-4503 Revision E. dated a-23-81. A. G0b'91IIOU One or more of the following conditions are satified: 1. An ARM alarms upscale; or Local dose rates as indicated by other instruments are about 2. 10 times higher than expected; or 3. Air activity is greater than 1 MPC (particulates and iodines). and 1. Control Room has not been notified prior to event; or Access is not uncontrolled; or 2. 3. Event is not preplanned. O. ACTION NOTE This action is to be taken by Health Physics (HP) personnel whenever possible or by other trained personnel when HP is not available. 1. Obtain the following equipment as necessary: ? High range dose rate meter High range dosimeter GM survey instrument Full face respirator Protective clothing Air sampler Wipes 2. Turn instruments on and allow them to warm up. 3. I'roceed toward area where the Radiologi cal Event exists indicates the need to do mal:ing survey as you 90. IF survey so, don the protective clothing and the respirator if .necessary. !.in UAL SET

m.....,..... 2. E. l. HATCH NUCLEAR PLANT t iNP - 4 N!4 ""'d '* o Gee Title Pane p 3 un Georeia Power aA ~~ V 2 o f i! Gr.n Tii1 e Pnqr. UDE - At all times adhere to the limits and guidelines in liNP-4865. Notify the Control Room if any of t;he following a. readings are observed: Beta, Gamma - Any reading above 5 r/hr. Contamination - 10,000 cpm above bacl< ground on a wipe. 4. Talce samples with an air sampler if conditions permit. 5. Determine cause of high local activity and notify Control Room. If conditions indicate that a higher emergency classification exists notify the Shift Supervisor and discuss declaring the upgraded emergency Rope off and post areas.of high air activity or radiation as 6. conditions permit and cicar area of personnel where necessary. 7. Using HNP-8005 and HNP-SOOG procedures to control local contamination and radiation when returning to normal. 8. Assist, when requested, the Shift Supervisor in evaluating incident to determine if.,any radioactive material released from the plant will cause the action levels in HNP-4853 to. be exceeded. E 9 %e i en f.1ANIML SE T

GEU!tGI A PUNEl< COM!8ANY HA'ICil I.'UCl. Call PLAtJT PilOCEDURE 1 .o. _i.F..i _c_a_t..i.._o_n_ o.f U.n u m. a _l F..v. e n t -l? n <. c u e Tenm N+ HNP_44Pn PROCEI.iURE N!.I5[5i5R ~ ~ ~ ~ ~~ l.a.b --. - =- RESPONSIULE SECTION SAFETY RELATEO ( X) NON-SAFETY RELATED ( ) _--_.---_s. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANyER .. v'I,4. _Q a/ _s_ _ _t _. / :/) ) / E' Page 2 2 . n_ _ _e.. _ _n. u df n_: / 3 Pages 1 and 2 // ___t~..<.- .. _ p__<.c_.a. _./._ y. I _. ..c. - i ~. l t I INP-9 l.W UM S t I

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........,.t., ...........s..... s __._.._..__:The revision o f this cro d.a.r.e_. d.M-__.::_ c_en.s.t. i.t.u t_e a.n_ un_rev i_ cue d s a f e.tJ.... O _mest_io.n_a_s__c a..ir.ed.h._a m_._- l .a..n. d t h.o...c o n.i.n o_u_e_n_c s_ _o f_ _a n _a.c. _c _i @._r._t 1 T h e o r M.. i.l i_t.y o..f.. o.r c u r e.. - a a. or m1fu.:tien of ecuir s-t i rortant to safety are not increased _ _ h..o_v.a._t P.:...'._a n_e l_v.7 a d_.i.n " _= 2 0 du.a.__r 9. tah..n. c a chuy.n e.b.aAm " a. r a - _ -__ - e.r.e v_ _s_ o_n_-.n. --- _od es n t chir._:s the_.our.n._ose _or nerfo.r.ranc.e of the_ th - i i - y_s_t_c m_. _ *- ___ - - -- s - of an if s t _or mal function _of a di f fer_e_n_t_tvoe ~ ___ 2._ The_.o.os s.n.._i l_i ty.....,_.. -.~; s. .._ _a c - .,- :.. e ' th_an an_a.l.w:sd in the FS.2?. c:ss not resul t f_re n th_is.c. hance _b_ecause '~ v - - = - --- e svs_t_s_ r_escon. ds_ and is ::erated as. before _t.h e_chan.ce. th -_ .--_h_e_ra rc in o_f__s.a.fe_ty as de'insd in t_h.e. Technical _Scecific_at. ions 3 T / .___ i_s__n_ot__r_e_d_uc_e_d__du e__t_o_t_h_i_s_r_s_v_i_s _i o_n_.b e ca us e th e re_v_i_s_i o n do e s -=- -- -- = -- _ - 4 cha n.ce _a_nv l i_m_i_t ed s. a_f s_t_v s y s te 1 s e t ti n e s wh i ch woul_d__a l l o.w.-.a.'._-_--_.-- - = - - safet*v l_init_'to be_ ex. css d_s.f. or to allos. a l. imi tinc c_on_d.i.t_i_on for_- _- _o.c_e.r_a t i_e.n._s to__b.e_ ex c.e e de_f _a s s t. a.t.e d i n _Te chn i_c_a.l.- S oe_ci f.i.c a t.i.on_s. ..,....r.. z. - - - - _ _ _ _. _ - - - _ _ - - - - - - _ _ _ _ _. - _ - - - ~ _ _ - - - _ - - _ _ _ - - i s lw-Q tif.NUM Sf T _

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7 cee Title pam. a f):j g au -~ Georm,a Power zn.. 1 of d 0 _.ee Title Page S UDI1Elc6IlC0_GE_UUU3966_. web 1_GEEGUE_IE6t! A. EDU21Il00's indicate a events are in process or have occurred which Unusual of safety.of the plant, such potential degradation of the level No releases of radioactive as those noted in HNP-4420, Table 1. material requiring offsite response or monitoring are expected ,unless further degradation of safety systems occurs. D. REFERENCE HNP-4420 c. ogI193 of the RET to The OSC manager or designee appoints membere, 1. serve as the Rescue Team. The OSC manager or designee shall also appoint a member of the Rescue Team to act as the Rescue Team Captain. The Rescue Team Captain should designate members of the 2. Rescue Team to fill the following positions: a. First Aid Leader t-b. Survey Man Rescue Team Assistorit c. d. Rescue Team Assistant 3. The responsibilities of the Rescue Team members are as follows: Rescue Team Captain _ Lead team in rescue effort; a. maintain communication with the OSC and/or the Control Room; assist, if necessary, in first aid.as directed by the First Aid Leader; assure an ambulance has been called if needed; carry radio, b. Eir21._61LLggdgri Lead Rescue Team in first aid measures; inform Team Captain of condition of victim (s); assist with stretcher and rescue equipment if needed; carry first aid hit. 4 imnediate survey of area (c); c. Ot3ry,gy_ Man: Perform an update.tho itescue Team with rer.pect to radiological condstiont, throughnut the rescue offort; assist First. Aid Leader if requested; carry dose rate instrument. ^ RURUI.L SII

w-_, .m.. E. l. HATCH NUCLEAR PLANT hup -6 6.m Geo Title P;gi.. 3, .m 2 of a See Title f'aqe d. ggggyo_Tggg_6sp is_tp,9121 Participate in the. rescue effort as directed by the Rescue Team Captain. 4. Use protective clothing only when the time and the situation permit. Respirators may also be needed depending on the nature of the situation. All team members should be equipped with a High Range 'Blf-Reading,' Dosimeter in addition to their TLD and 200 MR Dosimeter. 5. Obtain the following equipment: a. First-Aid Kit b. Stretcher c. High Range Dose Rate Meter d. Walkie-Talkie / e. Pinch Bar (if required for rescue) F. Rope and Tackle (if required for rescue) 6. Retreat if dosimeter reaches ER and victim has not been located. 7. Limit dose to members of Rescue Team in accordance with HNP-4812 during rescue. 8. Refer to llNP-4801, HNP-4DO2, HNP-4803 and HNP-4810 for additional instructions concerning first aid, decontamination, handling and transport of exposed and/or contaminated injured individuals. 9. Report condition of victim to the Control Room, specify Whether or not the victim is contaminated. Assure that the Shift Supervisor relays this information to the hospital. 10. Move victim to ambulance. 11. Arrange for radiation technician to accompany victim to hospital in ambulance. 12. Notify a laboratory supervisor as soon as possible. 13. Take necessary measures-to limit r.prrad o'f contamination and report to the Laboratory-Foreman or Supervisor and Shift' Gupervisor when completed. i ) . l.1/@ U.R S f I

y w --e - _ + u (,L 03C 1 A l'( M, ~R CM;PANY l lAl Cl I Ni Cl..! AR Pl. AN T ' PROCEDI13C _._- __._ A_ c t..i.n.n r __f o_ r.._ A.. l.l. P.. o r.n o n. n. o.. l _.i..n_A__l o r t PROCEDt!RE TITt.E I!NP-4_521 l_ a...b. RESPONGJf;LE SECTION SAFETY REl.ATED ( X ) NON-SAFETY Ri~ LATED ( ) 3_____________a____.____________..________, ~____ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 3 Paoes 1 & 2 I M 0# N-MA Dalel. ion on Page 2 _/__f____s %.._W W,. _ en n7 _. t_..,. _.._b..[.. '_a lu_Il.uJ !! Ml22 .- 9' -__0D___ s va.?s _n 1. _7_ s_ _3_ _ _ _ _ _ _ . _7[_ _., _ lt.' %. _ _/[5_O_rn_s_/h__.a y. '. S rages 1, 2 & 3 7 .s p. -__c or.e i-L

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'_' t_: T :..G_,- i..P_ r : e n_... ..u.. t.:.<.::_:_ c.'I.r_n_._f_w _.._2__.. oc, t e : N..:.e ; Date* G2 gn.. t or. : \\b. ^- 3 'f f.? ! } j? 3 j J3 l /\\ q _ _ _ _ a _._ _, REV15!C ! Cl U,t:GEC M M CF.CPERr,T I Oil DR J NTENT ,',S DEGCRIGEO.IN FSAR: * ( ),Yes ( ')( ) No ~~ CHANCF. INVC!NES*- '"( ) An unr ev i ewr.d Sr.f oty Gue st i c.n ( ) Tech Spots. (K) Neither (Gen back for Safetv Evaluatic.n i f rc. qui r c.d ). ... :. u.... ~.,..y. ~. ( 'K ) Non ) 8 ._...Sa f e t y R e l a t e d....( ~ ~ ,..... Safr.ty Related . :...a. :-..a.......,.n. :.::.m.:...._.. 2... .:....c. -~ . ( K....). N o . ". '.. Safety /Non-safety Status Change ( -) Yes v.

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. _ ~ _ _ - - _ - d,,, =;n:m:. ' " ' - 'E E. l. IIATCH NUCLEAR PLANT Ge e T i t i r, Page .u...... G-van 6 Georeia Power.cA '4 000 Tstle Page 0 1 of 3 L 6CIloggf og_6L6 PEREOUMELJ N ALEGI A. f00D1IIOUS Events are in process or have occurred which involve actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions.of the EPA Protective Action Guideline (P.A.G.) exposure levels. D. BEEEBEUCEG HNP-4520 C. 6CTION 1. Persons discovering an emergency condition shall immediately notify the Control Room by the most expeditious means available. 2. As soon as an emergency condition of the Alert Class is confirmed, Control Room. Operators shall announce the nature of the emergency on the public address system and specify that personnel initiate Alert procedures. 3. Control Room Operators shall place the plant in a safe condition as the emergency warrants. 4. If possible, person (s) in immediate area take appropriate rapid action to limit the" extent of the incident with available means and then retreat to their report area (see C.10). S. Persons involved in radiation incidents report to the Health Physics Office f or decon tamination, if necessary, and further instructions concerning evaluation of dose received.- Personnel decontamination should be documented as described in HNP-8009, " Personnel Contamination Gurvey". E.. Persons called in from_offuite should report to their assigned locations and, if unassigned, to the Operations Support Center for assignments.

  • /.

'Gtaffing of the Operations Support Center (OGC) and the Emergr ncy Opera tions Facility (COI) shoul,d begin immediately. The OGC should be l e t.a t e d in the Un21 1 Gervice Duilding, wi th the hradqu.ir ters/ reporting area being North end of the breahroom. Thr alternate OGC is the ~Dimula t or Training tiu s 1 ding. 'Ihe normal EO;? is in the Giinula tor Tra tning Duil dinij wi th the alterna te t-eing the Appling County Dheriff'<, offtcu in the courthour.o. L1Tatifil SEI

""P - 'C E. I.1lATCl1 NUCLEAR PLANT Cee 1 1 lie Page C /g san Geon>ia Power ca ~"> P. o f 3 ,,ue.(1tle Pun *: O 8. If the emergency occurs during a r.egular day shif.t, members l of the pinnt operating organization,on site will report as follows: a. Control Room Operations Supervisor - All onshift' operators, Shift Supervisor, Operations Supervisor, Shift Technical l Advisor, Shift Clerks, (Communicator / Recorders as needed) *. b. Emergency Operations Facility (EDF) Manager Engineering l HP Supt. Health Physicists Manager of Administration, Finance and Human Resources j' Supt. of Regulatory Compliance Security Manager RET Members on Field Monitoring Teams (Communicator / Recorders as.needed) Technical Support Cc'wter (TSC) c. Deputy General Manager [ Superintendent of Plant Engineering and Services Supe'rintendent_of M'intenance a Superintendent of Operations Reactor Engineer Engineering Supervisors Laboratory Supervisor (Health Physics) Document Control Gupervisor 1 Gucurity representative ~(Communicator /Recorderc as needed) Nas Nt\\(. {k

1. ~~ .a --=- '""'-k =.m E.1. HATCH NUCLEAN PLANT 3u0 Title t'ny. 5 4 n Georgia Power,ma 3 of 1 c ee.fitle Page a (OSC) d. Operations Gupport Center 1 Maintenance Supervisor (UGC Manager) instrument technicians w/ foreman 1/2 crew (pre-designated) 1/2 crew electricians w/ foreman (pre-designated) 1/2 trew mechanicu w/ foreman (pre-designated) All RET members Plant Equipment Operators (Communicator / Recorders as needed) Communicator / Recorders are members of the Plant and Engineuring and Regulatory Compliance Staffs, will be dispatched as required. l o c at i or.s outside the protected l Personnel assigned to work area and who have not been assigned to the Control Room, 9. TSC, 000 or EOF will remain at their work location and await further instructions. l Members of the Radiological Emergency Team report to the OGC 10. emergency begins. If team members are if on site when the they report to,the OGC for assignments. called in, inside the [ Members of the plant organization and contractors 11. protected area and who do not have specific emergency locations, go immediately to your report area, assignment Maintenance Department to Maintenance Shop or i.e. Instrument Chep, Administration Departmont to Service Duilding offices, contract workers to contract office areas, etc. Remain in these Warehouse workers to Warehouse area, areas until further instructions are given. Members of the plant organization will. comply with orderly coordinated actions 12. applicable procedures to effec-L in the emergency. 13. Department heads should consider the d2smissal of l nonessential perconnel, throu;;h norual exiting procedures, based on the nature of the emergency, j [ L IWlU.'il Sf T

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I -i [ - ""u"""" I"'" C E.1. HATCH NUCLEAR PLANT -s ~ ~ s t aru-T:tto P:,ne_ 6 3 Gh u* cs Georm,a Power a ~~ ~ 0 1 of 1 Sne Till o Pn'n-66EBI_:_CONIO26._UD0tL9;GEoI909 cou21Inuii'[ c, A. s or have occurred which involve an actual or Ev[nts are idIp'rocer pot'ential substantia 1'edegradntiQn of the level of safety of the ~ plqnt. Any releaces are expected tp be limited to small (P.A.G.) f ractiorpLof the E.PA Protective Action Guideline ei' osure levels. j-p D. GElgBGb'gG r HNP-4530 't .' l C. ACTION r + 1. Take appropriate action to place the plant in a safe condition in accordance with emergency operating procedures, Tech. Spect;.,7'and annunciator recponse procedures. i 5. Make t'he f.ollo, ring announcement over the PA: ..ATTENT, ION, ATTENTION: A STATE OF EMERGENCY OF THE ALERT CLASS EXISTG. INITIATE ALERT PROCEDURES. Sound the Gai-tronicsttone for an Alert and repeat announcement. 3. Check control room. instrumentation to determine status of ~ plant _as to whether or not'a Site or General Emergency should be declared. Notify Shift Supervisor of findings from performance of HNP-4853. - 4. If St)ift Supervisor has not, reported to the control room, ' init'inte his actirtns as per HNP-4523. 7 ,e 5. fAnnouncement of the " ALERT" s'tatus should be repeated periodicalJy (approximately every 30 minutes) throughout the / duration 'of thh/ event.

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CCORCI A l'OUT R Cf MP/.f tY. HATClIi!UCIEAR PtAMT PROCCDORE _ -.. _ A..l..F.R. T. _.. R.. r.. R. C._l.G....1.F. A. M_- ---- - _ l'ROCl.Ut WE TI'lLE 10 !P -4 '3P...G -LAB


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- ~~~~- GN~ETY RELATFD ( X ) NON-SAFETY RELATED ( ) ___.._______________________________a.____.__.____..______._. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER . ~__ _ __ ________._ _____. 2 Pagen 1 and 2 ,.g /.?fh [ cmf,j 3 i g,3 _ LL,. d.a ~,.c,c. _ _ _. _ _ _ '_ _ _3_ _ _.. _ P_a.h.e_s _1_a_n_d_ _2. .)_/.a'_"'%g.,..:.._/_.M,. f,2s_ _. _WJ..,I.,_ N,, _ (.d$ d'T.. k-h_ ad.4.. r_.7_d_ _ 3,_ ecfd / i 4 Dmp.s. 1_a.n_d_1_ _ _ _ sn__ / s e

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__.y . P_!.q ' l. i.f...i t..: _ M.. _ /.t..'.1... c.i... i. : :-__.....l.' r s PROCECt'3E Edl. Il?'P - l-b2O Revir. Ion !!o._ ____..._ 't.) _ 2 . _ _ __.--- '!< c.:. re.:' D n / I YT /.! / T:'.',- M :-C,-i-f,p p:. i :.j,.. Date: (>a 1 - S i g n c ti.i r o : N,w ; ,l '7 [:-T ) lDbkt U i j ,I .c-,./ REVISICM CHAT:GCO MT.F. OF.CPER AT J DM DR INTENT AG DF.GCRIDEO.IN F3AR ( ).Yes ( x) No CHANGF. INVCtNFS-( ) Ar. unreview d Safety Gtmrtic.n ( ) Tech. Specs. (f) Neither (See back for Safety Evaluation if requirc.d). ( ) Non-Sofe-ty R. elated ( ) Safety Related m- ~.._.s. ......w.__.,..... ..-.....+..,.:........-:. (X) No. Safety /Non-safety Status Change. ( -) Yes e. Attach marked up copy of procedure to this form. ~ J. ~. t) 73 REA5ON FOR RECL',ST ' OH _ _n o t//4__jy WM _

== Jn ts,.1 ! Tt o .T ' ) (_, f_ $ (1_. b_ _ t.____b_ - (, b.b 0 11' J_. 0_4_t,L LJ ! S._.._ _/l1 M_ ___--( 6 p. . c.1 _ __._a s_ __ _ dux. I m,__7 : _ _ _r n w ol o- -.s_. - - C[ sat.___h_b_i_~,i.._."a dcb< ? ~ - - 4. ' .%_._r.c.7.__: _ C l '5 - ( 'I f p u,5, ia in,s huu__u_,._L, &c ,s_4___k_- n c Uv Y Ytr N_L__d;._v._M _l_lwc < ____n__I_wuh_?_o$___il__bl.7.0m, _%__ht c(t l f!I (t h .N e __-___=--__ =_ =-- - e,7 w__.___ i m enn ucces..e.w unnv. n w.s ( )Nm , u _._.. litU DicrG1Ory j'-> t. t 03-4G .,. 3..,.p,i. 3.,_._ _.._ D.i t e pHil Num! e p.) s o m m [.1,*.NiiM. 5 I I

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ca_rc_i_n_o f.s..a.fe t.y--.-.a s.d. e_# i n e_d i n t he T e chn i c e..l. S c e c.i..f.i c.a t i o n s.--

The - 3 /- _---__n_ot r_e_d_uce_d due.t.o._thi_s r_ev._i s i on b_eca_u. s e the_.r.e_vi_s.i._on d. o_e_s n_ .i s --.-- st.s., s etti.ne.s '.:hi ch woul d all o.w--a - --- - cha nce__any l i.-.i t e d.s. a f e t.y sy safet'v l,imit to be excesd?f or.to allow a limitine con.di. tion fo_r f i -- ---- o e.r. a.t.i on.s..to _b e e x c e ed e_d i s s_t.a..t.e_d i n T e chn i c a o =. - - - - - _ 4 g 3 3 lp.o 3 Ilf.!!!!M. SI1 n

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== 7 m;a ....n.,. HNP -'M E. I. HATCH NUCLEAR PLANT - A ~ " " " nee Title P;qe g 4

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" ~ ~ Geomia Power d Gee Title Pv;e U 1 o f-2 i l ALERT _.. REOct E TEAM A. CO32ITIO'l Events are in process or have occurred which' involve an actual or potential substantial degradation of the level of safety of the plant. Any relcares are expected to be limited to small frac-tions of the EPA Protective Action Guideline (PAG) exposure levels. D. REFEfjENCE HNP-4520 C. ACTION 1. The OSC manager or designee appoints members of the RET to serve as the Rescue Team. The OSC manager or designee-shall also appoint a member of the Rescue Team to act as the Rescue Team Captain. 2. The Rescue Team Captain should designate members of the Rescue Team to fill the following positions: a. First Aid Leader b. Survey Man c. Rescue Team Assistant d. Rescue Team Assistant 3. The responsibilities of the Rescue Team members are as follows: a. Rencue. Team _ Cap,igini Lead team in res cue.. e f f o rt; maintain communication with the OSC and/or the Con trol Room; assist, if necessary, in first aid as directed by I the First Aid Leader; assure an ambulance.has been ~ called if needed; carry radio. l. b. Eizpt_ Aid _ta nderi Lead Reecue Team in first aid l l mrasure'; inf orm Team Captain of-conditien of- . victim (s); assist with stretcher and rescue equipment l .if needed; carry first aid kit, t - C. OU PXP y...bhm :_ Perform an iwnediate survey o f; area ( s )

  • update the Retcue Team onth respect.t o radin1092 rat cond 1i onu. throughou t. t ho' rt":. cue ' e f f o ri; a to r 2 ': t. F t e r t Aid Leader if r e qutui t e d; carry dono rate s u'm. t rumen t.

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Georgia Power /.n - ~ " g,, g see Title Poor., S ants), ' Participate in the rescue d, Oncup_Tggm_A;r.i t effort as directed by the Rescue Team Captain. 4. Use protective clothing only when the time and the situation permit. Respirators may also be needed, depending on the nature of the situation. All team members should be in equipped with a liigh Range Self-Reading Dosimeter addition to their TLD and 200 MR Dosimeter.

5. -

Obtain the following equipment: a. First-Aid Kit b. Stretcher liigh Range Dose Rate Meter c. d. Walkie-Talkie e. Pinch Dar (if required for rescue) f. Rope and Tackle (if required for rescue) 6. Retreat if dosimeter reaches 2R and victim has not been ~ located. 7. ' Limit dose to members of Rescue Team in accordance with HNP-4812 during rescue. 8. ~ Refer to HNP-4C01, HNP-4802, HNP-4803 and HNP-4810 for additional instructions concerning first aid, decontamination, handling and transport of exposed and/or contaminated injured individuals. 9. Report condition of victim to the Control Room, specify whether or not the victim is contaminated. Assure that the Shift Supervisor relays this information to the hospital. 10. Contact Technical Gupport Center or Control Room by radio or phone for ambulance pickup of victim in the upwind direction of victim's location. 11. Move. victim to ambulance.

12. ~ Arrange for radia tion technician to accompany victim to,.

A i hospital in ambulance. I 13. Update the TGC as soon as possible. 14. Take necousary meacuroc to limit spread of cont 3mination nnd j report.to ttio DOC Mutnger when roucue elIort i t, completed. L

CI ( n<G J A 11r.X H COM:'/.MY llM Cil f1:1Cl FAR PLAH f PROCl Dt 1RE _..G._ i..1,. A.. r o i Iw e..r.Ir.re.rX_ ._ _ f..!? ?.>....A r.P. O. _. -_. ic t,...a..,. b 1 f.c C,., t: m....-. c. e s. I ab REGPONSIDLE LECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPRO'E D APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 1 Page 2 '} [, p,q c[f[g, ~ 4./h_.f. ,g v . Y.i_M _N 'e r'2 2. f_. ,..... - /_.. o./.[. r_/. _. _?./. _L. _ 2_ _ _. _P_a_n.c. _s _1_ _&_ _3_th_r.u. 7 _ _ _. 1_ . __ /,--- ~ o 'c Q ' .,9_f*k_'f_.[ f_ _g g,. :5 9 3 Pages 1, 4_7 .. _ _ _',r[//_ _q..y;,,4_ _ _, Q

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- -w. s_.. g- ._,_,,.,,s..- m / 't. h . pp:1.. 'l..O! r ?C Rf_t. f.G b..: i_: e it_: ~:~.T. e panecot ac do. n.-r J/Ro \\' f... - ) Rovinion ?!u. .O- _ _ _ _ _ _ _P_. i_. d Y. :_"."_._T.." D_T_W . _ _ _ _ f_:'.~. f_'.. R.. _T ".~.;_: _1 _1_. I'_','. L.. _.' P f,: n_' ', r _ _ ~ ~~~ p,,iu, . a {.._- --Dole. -Lignatore:_ .. _ m _ _ _ _ _, pate. lll f.\\<.'.ha nt b 'l N 'h<" ]f m,~~ . 3 ')' D = gEVISICM CH. NGCC MOCE C:~.CPERATION 03.. J NTENT AS DEGCRIDED IN FSAR: I (._ _.) _y e.. . - - -( %.) N o-- ~ --- l CHANGE INVC'ViS: ~

  • (

) An unrevi.ned Sr-f ety Gue stic.n ( . )..Te ch.Gp e c s. - (I ) Neither (See b4ck for Safety EvaJuation if requirc.d). cy, f e t y R e l a t. e_ d. _.(.K ) Non-Sa f et y._R e.l a.t o.d. '.(_ _ _).,_'.. ....-....s.......... .... _....... ~. ~...,e. .-....:. :.... -. a. _...r a... .:... w. s ..n..... .. '..'..'sc.fety/Non-safety Status Change ( )..Yos-( ) No ~' .. ~..., /,tta ch ma rke d up copy o f _ p r o c e dur e. to.~.t.hi's. _f.o.rm.. _ _ ....... ~ ~. ~~ --' REASON FOR REGUEST (ffN$e-Y h 0 'nw n 'Outh re9ffW 0@h Yuh.

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= GTTr_AprA Ptjrg,cFt!q A. fAAgg,1,'Z2;gI,PT T 09 Events are in progress or have occurred which involve actual or likely c.ajor failures of plant functions needed for protection of the public. Refer to Table 1. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. O. Pl.lRPO?E Purpose of the site area emergency declaration.is' to (1) assure that response centers are manned, (2) assure that monitoring teams are dispatched, (3) assure that personnel required for evacuation of near site areas are at duty stations if situation becomes more serious, (4) provide consultation with offsite authorities, and (5) provide updates for the public through offsite authorities. C. PLANT ACTION 3 NOTE Supvw 0%u The Shif t. Foreman or -Shift Supe rvisor (or higher ranking I licensed or certified person present) in consultation with the STA, if feasible, recogni.7es and declares that the plant 7 is in a state of emergency of the site area class. The O udtr5 Ghift Supervisor assumes the role of emergency director l f until relieved by the-Plan;t Manager or his designee, l q< w~ i 1. Promptly inform State and/or local offsite authories of site art.a emergency status and reasons for emergency. 2. Augment resources by activating TSC, operations support center and EOF. 3. Assess and respond. 4. Dispatch onsite and offsite monitoring teams with associated communications. 5. Dedicate an individual for plant status updates to offsite authorities.1ud periodic press briefings (perhaps in ~ conjunction with offsite authorities). G. Make senior technicial and managotnent staf f onsite availabic f or cone.ul la lion wi th NHC and G tu te on 'a iperi odi e bas a s. En e e ~

= i. l. I Lil a,s i i fi u m.it I l.!Ill " ~ ' ' ~ l u p.. 4r.%Y -~~ m. o.. ' Lee I i 1.1.f I '. <;.. b s e-f..UCOl!'lil,)OWCI' EJ.s iW.D.o ~~ ~~ i ~ ~ ~ - ,;i( * '-~~ o 2 of 7 Ge e...T, i i 1 e l'. i q o 7. Provido metsorological dain.ind dnc.e er,timates to of f.,i le aut.horities for aclual rele.v.es via a dedicated i ndi v i.lua l or au toma ted da ta t ransmi ssion. 13. Provi<ld releane and done projections based on available plant. condition information and foreseeable contingencies. 9. Escalate to general emonggnry class, if appropriate. OB 10. Close out or reduce emergency class by briefing of offsite authorities followed by written summary within 8 hours of closecut or class reduction. D. STATE AND/OR LOCAL O':FBITF (4UTl40RTTY ACTTONS 1. Provide any assistance requested. t 2. If sheltering near the site is desirable, activate public notification system within at least two miles of the plant. 3. Provide.public within at least abcut 10 miles per' iodic updates on emergency status. 4. Augment resources by activating primary response centers. 5. Dispatch key emergency personnel including monitoring teams ~ with associated communications. 6. Alert to standby status.other energen'cy personnel (e.g., those needed for evacuat* ion) and dispatch personnel to near site duty stations. ~ 7. Provide offsite monitoring results to GPC, DOE and others and jointly asse<s them. 11. Continuously assess information from GPC and offsite monitoring termis with regard to changes to protective actions aircady initiated for public and mobilizing evacua tion resources. 9. . Consider placinq mill < animals within 2 miles on stored feed and assess need t.o extend distancts. 10. Provide press briefings, perhaps with GPC. 11. Escalate to ennt. ten _i _ emenqnnev-class, if' appropriate. lie. Maintain site area emorgency <.tatus'until closeout or reduction of emergency clans. ^

r. ~ f TtGLF. 1 SITE ADEA EMERGENGY /.r:..- r.r. t T ;f34 Em it PMU4T STATUS P..7AM.II g vt.: tj? '1. ~ I l li I l'. F.cwn loe.s c coolant accident greated Drywell High pressure Greater than 1.8 psig '7 9 i tr an r a'.< cup pu ps capacity. Initiation alarm, and increasing j Reactor Low icvel Initiation Less than -23 in and alarm decreasing Hi Flow Drywell Drain Sump alarm o Drywell High Temperature alarm Greater than 14S F and Increasing l'.n I-* A j2. Oegraded core with possible loss of Some combination of the lM d' c :lant get etry (e.g. massive cladding following: ailure or 1 css of core flow) Containment High Radiation l,,, O s py_4 c ;'~. = alarm ..N.G. Fission Product monitor 17;> O .2 2 Hi Hi Radiation alarm and N.G. 12 9 I - , Fission Product monitor in-

-:q dicator off scale on high end,

[-y *. C Reactor Low Level In-itiation j d'- E ~~~ in C alarm ~. 1_-. N 2. Gteca line break outside containment Some combination of the follow-l,9 wit.'.eut isciation ing: Turbine Bldg ARM Hi alarm Greater than 15 mc/hr l< A MSL Hi Flow alarm Greater.than 120% and increastng ~ MSL Low Pressure alarm Less than 855 psig and decreasing A. Less of effsite power and loss of onsite Undervoltage alarms on all 4.16 Zero voltage indicated p:wer for more than 15 minutes kV: buses for more than 15 min-on'all 4.16 kV buses utes and loss of control ecom I- ; e E; normal lighting or more than 15

e" -

minutes gcd inability to energize 3lE Q 4.16 kV buses from Diesel Generat-j j,7 : .3. ors for more than 15 minutes, t.:J d i ~t l' ~ ,. _' i s.* 'o O 6't.'

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  • 7 TABLE 1

~ e- ~ ~~ T .I SITE A,EA EMERGENCY (CCNTINUED) R INIT;ATir:C CC miT CN EGUIPM NT STATliS FAC.Axt. cs Vat,13:: cil vital onsite DC power Loss of CC Busses for more ?. 'L:ss 08 f:r :.:re'tban 15 minutes than 15 minutes 1,. C 31ete loss of all function needed Inability to Shutdown with ,g Control Rods y r 4:e picnt het chutdewn i f n P. Trc.cient re ;uiring cperation of Scram. signal present and power ~ not decreasing, Standby Liquid 1,2 stu-::~n syste.s with failure to 4 Control initiated. Scro- (ccntir.ued pcwer generation l3 v f*A but no core da nage i:r.r.ediately evident).

1. -. H s-

~ 3 ~

i. @. r-5.
'.ic-da.see to spent fuel in Reactor
  • 0bservation Cu s '. f ir ; fe.g. large cbject damages Spent Fuel Storage Pool Low Less than 8 f t above fuel !I:C r

and d.e p : Gy. u a. creasing 4.el Or water icst belcw fuci (level) Level alarm m j y-~ ~ t~ : .d Fire alarm and observation Shift Supervisor's 9. Fire cc pecnising the functions of ,1udgement x 1 N safety systces typ : s

10. M.st c. all alarms (annunciators)

One or more of the following: Shift Supervisor's {. 3 j,8p '

  • judgement g

e

1.,t a.d plant transient initiated a.

loss of feed water 4 c: in progress 1,., b. turbine trip c. loss of offsite power .d. los's of reactor coolant pump

5..,

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  • 1a. Radiological-gatec :t effluent monitors Main Stack and Reactor Bldg.

j y ce'act levels c rrespending to Vent monitors Hi Hi alarm

E E4 grecter than EO ne/hr for 1/2 hour plus monitor readings plus I*

{2 t. er ;reater tha-500 er/hr W.O. for doe.e projection calculations } j t.. . i n u t. e s (cr f:ve tiras these. plus field measuremente. Icvt-15 to the thyroid) at.the site a bcontar/ for adverse meteorology i!b. C-.ta:r ent post LCCA radiation Containment Post LOCA O i 7 am:t:r rc di gt indicating a Radiation alarm plus .E I.i 4ittier.'pr: duct inventory equivalent monitor readings plus 3 ? to

  1. fsite dose rates as described dose projection cal-in lla.

culations 11:. FaOs projected to be exceeded Effluent monitor cutside site Scundary readings plus dose I projection calculations Cp<-mW 1:t2 1 -* 12. Irmir.cnt less'of physical control Loss of control of vital Shif t. Supervisor's judge-hd ( -cf the plant areas ment based en advice of j O Security Shif t Su ervisor:> v: C

v..

s..- } I;) e . Shift-Supervisor's t 3. Scvere r.ctural phencmena being Observation f,f_d_. l 3 -! erperior.:cd er projected with plant judgement

1. _r.,l >

net in cold shutdexn; g c. %.:, ; =: I a. Earthquake greater than CBE 1. "Seis'mic Instrumentation CSE level is 0.15 g [%[9 eM 3 level Triggered" alarm 2. Units I and II recorders .)r p start I i.~~ t' s 3. "Eelsmic Switch Tripped" !3 I >' r clarm which i's set at DBE GI. level (Unit II) j.; 4. or Unit I Seismic Peak Shock Recorder h2,gh g level alarms ~ 5. or Unit II Seismic Peak ? [):, 50 Shock Recor ier high 9 M icvel alarms 3 .a e-6. Peak Shock Annunciators i $2 se t at 100% OBE have been 3 3; -4 actuated .i - ~: j 7. The maximum 9 Icvel 6 measured by the Time /

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