ML20073R375

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4734 Re General Emergency - Savannah River Operations & HNP-4527 Re Alert - Security Force
ML20073R375
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/04/1983
From: Nix H, Rogers W
GEORGIA POWER CO.
To:
Shared Package
ML20073R370 List:
References
PROC-830404-01, NUDOCS 8305030690
Download: ML20073R375 (50)


Text

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.-----------------u---a-.in 0108998V PPO^ra PROCEDUGE TITLE

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PHOCFOURE NUMDER

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REEPONSIOLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) r 1

. _ . - - - + _ - - - - - _ - - - - - - - - - - - - - . ---------__-----.----------------;------_-

APPROVEO APPROVED

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REVISICM CHANGEC MODE OF .CPERATICS OR INTENT ( No

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'"( ) An unreviewed S.sfety Guestic.n (See back for Safety Evaluation if required).

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question as exclained _ _ _ _ _ _ below 1 The nrobabili ty of occurrsncq and ths c_o_n.v. o_u_e_n_c_es _o_f__an__a_c_c _i.d_en_t______

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- 1 or malfunction of equipment imoortact to safep are not increased

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the sys_t_e_n_rescends and is ocerated as before t_h_e_ch_a_n.c.e.

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ocerations__to be_ exceeded as stated in' Technical Soecifications. _

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+6 To describe adequate bionssay program for personnel at Plant E.

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l B. R_EFERENCE9 i

1. ANSI,'N343 "M C. LICENIE con'M!WFNT It is intenced that eacn member of tne normai plant operating orgsnt:ation, and any visitors or contract personnel, who may ha es oeen exposeu to airoorne raatation will receive a whole body count each year. Esta person snali receive a baseline count prior to entering bicassay areas ano a rinal count prior to termination. ,

, NOTE '

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Bioassav_ Area - A bicassay area is considered l-i to ce any Airborne Radioactivity Area, and any l

Conteninated Area where unencapsulated radioactive i ma t e r.i a l is present in a fort' and quantity such that the area has a significant potential for becoming an Airborne Radioactivity Area as defined in 10 CFR 20.203 (d). ,

As a minimum, the following areas are considered to be Bicessay Areas.

1. RWCU Pump Rooms
2. Radwaste Drumming Room and Conveyer Aisles
3. Filter Hooms (during filter cnange out) 4 Centrifuge and Hopper Rooms
5. Airborne Areas
6. Contaminated Areas 10,0C0 dpm/100 cm2 7 TIP Rooms All Bioassay Areac are RWP control areas.

O. WHOm- O_ Ony COi.;NT_ PIG. - _

g Whole body counting will be performed on permanent personnel and

/" visitors and contract personnel who may frequent bioassay areas.

(T / Whole oody counting ray also be done off site on special

- occasions using a vendor's whole bocy counter w en deemed .

necessary bv Health Physics.

1. The s chedule fo$ whole body counting of personnel is prepared and distributed by the Training Depagjgggt gg

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2. The Training Ospartment will coordinate the wnole body count witn departmen+ neads to assure an inninterrupted schedule. l
3. When the whole body count is complete, submit the resul'ts to i

a lae foreman for appa6 val.

4 File each per?on's report in his/her exposure file when a lab foreman's review and approval is complete.

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4 i E. URINALYSIS  :

1. Fo r' suspect or known inhalation cases.

NOTE ,

A fission procutt analysis may be performed i by en outsice contractor on personnel suspected of inhair5g airqorne activity. This will be done at the direction of the health physics dept.

a. Have each person collect a minimum of 400 ml of urine.

The label should contain the person's name, social

- ( f. security number, I.D. badge number and cate of collection.

b. Send semple to contractor's laboratory as soon after

. collection as is possible. '

c. File a copy of the analysis in the person's file folder and the original in documentation witn this procadure material.
2. Crosscheck Sample l
a. In conjunction with the analysis, en individual may be asked to p" ovide two specimens, one of which will be used as a crosscheck sample. The other is to be labeled appropriately. See section E.1.a. The crosscheck sample will be spiked using Cobalt 60 or another fission product or may be sent without spiking.
b. A 400 m1 sample will be spiked to produce a minimum concentration of 2E-7 uCi/ml (this is 10 times the LLD t for gross fission products for the vendor), A higher concentration may be used.
c. Log actual uCi/ml and spike source used on Fig. 1. If the semple was not spibed or anotner isotope used O ~

complete, other.

d. The sample will be identified as on Fig. 1.

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e. Upon receipt o' analysis fror, the vendor the results will be logged on Fig. 1. .

4 To determine if .results are acceptable the following f.

method will be u;4d. Divide the results by the error, the quotient is referreo to as the resolution. Next, lI divide the results by the actual uCi/mi and compare tnis number to the range as dictated by the j j 4-- resolution. If it falls within the range the results i

are acceptable. See Table 1. If the ratio falls outside of the limits but falls within the next larger set of limits, check calculations and observe

(

j subsequent results to see if the problem persists.

g. Ch-cH appropriate results and notify a foreman *;F results.
b. Send specemen to contractor's laboratory.

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i. Keep shipping memo until the contractor's analysis

, report has been receivec.

j. File a copy of the contractor's analysis report in O.

documentation.

3. Investigation Levels The " investigation levels for urinalysis results will be 350 pico curies per milliliter (350 pCi/ml) for tritium or 350 dpm/ liter for mixed fission products. If either of these levels are reported a foreman is to ne notified immediately.

The foreman is then to follow up the report with the actions prescribed in AMGI N-343 - 1978.

MANUAL SET -

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TABLE _1_

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RATIO 1-3 0.4-2.5 4-7 0.5-2.0 r i

2-10 O.6-1.66 11-15 0.75-1.33 16-25 O.80--1.25 20-5(i O.85-1.18 51-100 0.90-1.11 100-200 0.93-1.08 O,. -

200 0.95-1.05 EEdTLE._

actual- 1.0 reported - 0.8 0.01 rggorigg =

22 = 80 resolution error 0.01 rggo.r_1gd =

Q.2 = 0.8 range 0.90-1.11 actual 1.0 Thers^ ore 0.0 is unacceptable since it does not fall into the

? pet _-ied range of 0.90 to 1.11.

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PROCEDURC DATA PACHACE I

DOCUMENT to; l*P-9021-1 SERIAL NO: 904-  !

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, RTYPE:__GJ 5.14 XREF:

TOTAL SHEETS: 2 O

  • FRCGUENCY: As Reguire:S COMPLETED Bf:

DATE CCttoLETED:,

I HAVE REVIEWED THIS DATA PACv ACC FOR COMoLETEPESS A O A' w!NST ACCEPTANCE CRITERIA IN AC,COoDANCE WITH HNP-230.

ACCEPTADLE U W L7 TABLE REVIEWED OY:

DATE REVIEkED:

REMARKS:

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Eisutt_1 l EI'1E2.La_Its_2e?_LE Sample ID. - Cross-check sample lf F q

Scurce used: Cobalt CO  !

Other', specify ( ) ,

Actual uCi/mi = (a)

Contractors results uCt/ml = (b)

! The difference between (a) 8r (b) =

(c)

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'5) = resolution (c) l (b) =

(d)

, j (a)

Compare (d) to resolution on Table 1.

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(s.s ), acceptable unacceptable Foreman notifsed of results.

Completed by:

Reviewed by:

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HATCH NUCLEAR PLANT l

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Gene ra l_ Erne r.n_o.n__cy_

a - Savannah Rive r_ Op.e rat i ons OHi ce PROCEDURE TITLE \

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.- - - - PROCEDURE NUMOER i

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_ 1 RESPONSIDLE SECTION l

NON-CAFETY RELATED ( )

SAFETY RELATED ( X )

APPROVED APPROVED DEPT. PLANT DATE REV. DESCRIPTION HEAD MANAGER

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HNP-9 MANUAL SH

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  • REVIGICN CHANGES MCOE OF GPERATION OR INTENT AS DESCRIBED IN FSAR:
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Safety Related ([) Non; Safety Related (

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                                                                                                                                                                         ) Yes                                               (               ) No Safety /Non-safety Status Change (

Attach marked dp copy of procedure.to this form. . .

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ne revision of this procedure does _ _ _ _ not constituto _ _ _ _ an unreviewed safety

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question as explained beled. __ _ . . __ _ _ _. , I

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The probability of occurrence and the consequences * ..

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y." ~ o'r malfuricticn of equip: ent irportant to safety are not increased

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i . . . above those analyzed in the FSAR due to those changes because _ Q.t.$;.M -1 .. .*- . . . .v .,

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                                                                                                                                                                                                                                                                                                                                                                                                     . .M.'c'2O The possibility *of an accident or malfunction of a di'fferent type i                ' ' (. .                  .              2.                                                                                                                                                                                                                                                                                                    __                                                                    u than analyzed in the FSAR does not result_ _'from this change .because. -                                                                                                      .W .'J..'ite          .:M
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E. l. HATCH NUCLEAR PLANT - ' "P - T2" set. T id e r age -.~..a Ji, q 2 Georeia Power m ~~ e

        ,3ee litle Page                                 v                                                       1 of 1           (   +

9EUE86kEEE@GENCY - SAy6Nd64_@IyEB_QEEB61196@_QEElCE N_O__TE__  ; i This procedure supercedes HNP-4714 Rev. 4 dated'3-7-79. ! i f A. CO.3QI TION i Events are in process or have occurred which involve actual or l imminent s ut.stanti al core degrad-ation or meltiiig with potential ! for. loss of containment integrity. Release can be reasonably l expected to exceed PAG ey.posure levels offsite for more than the immediate site area.

0. BEEEB(MCE l
. HNP-4720.
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                           ' Respond in accordance with the Interage3g _ Radiol'gical, i                 1.                                                                                    o Assistance Plan for' Region 3.                                                1, l                                                                                                           ,,
i 2. Radiological Assistance Team reports in to the Emergency

( Operations Facility specified. I Norma'l Emergency Operations Facil' v - Simulator Building at Pl QE. I. HATCH (Telephone: 9E Alternate Emergency Operations Facility - Appling County ___ Gheriff's office at the courthouse. (Telephone:-  % L ' e 1 l

. i GEORGIA POWER COW ANY HATCH NUCLEAR PLANT PROCEDURE

                                                                                      ---Alert - Securitv Force                                                                                                                     -

iM55E50sE TiYLE-HNP-4527 = PRUCE505E~RORaER Lab RESPCA555LE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER ___-_._____p___.._ _____.

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                                .                                                       PROCCOURE NO. HNP-                                         .[d 7
                                                                                                                                             .8 Revision No._                                                                                          .

PFOU.STFD BY .,,,____DrP AgTMJN T _ H5(.O At3PyO'/At. Name; Date; Signature: Date:

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    .-                      ' REVISICN CHANGES MODE OF CPERATION OR INTENT AS DESCRIGED IN FSAR:

f * ( ) Yes , (X)-No ,

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JGE IhVOLVES:

                             . .' ( ~') An'unreviewed Safety Guestion                                                                (         ) Tech. Specs.                               (N) Neither                                                      ,'
 "E.T'.f~.?? .'f'9 .(See .ba ck f o r Sa f ety Evalbation i f requi red ) .                                                                                                                                                .

Safety Related ([) Non-Safety Related ( ) .- Sdfety/Non-safety Status Change ( ) Yes ( %) No i  ; ., Attach marked up copy of procedure to this form. - REASON FOR REGUEST_ g fgff_ ce rg [7f g,[', __,[g e e., . s** l 'r

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a _ GAFF.T.Y._P. ./._' l_n.' T_T D_._* ! _ _ I 2 e ___ - - - - _ = - -_ .,_.___. _ . t _ __ -. _ _ _'Ihc revision of this procedure does --_ -- _-- -_-._ - ~ not constitute an unreviewed safety _- ( ) question as explained below. . _____' *4 i r

1. The probability of occurrence and t.he (.onsequences of an accident

( - or malfunction of equipment important to safaty are not increased 3 l-

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                                                                                                                                                                                                                                                                                                                                                      =

above these analyzed in the FSAR due to these changes becau'se l.. U ,.'. .

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3. G'.p, t . .. . ..;j e the revision does not change the purpose or performance .of the
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The possibilit 'of an accident or malfunction of a different type .

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change any limited safety system settings which would allow a' _ - u G iC @. ..~

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safety limit to be exceeded or to allow a limiting condition for v ' '#:j3 ., operations to be exceeded as stated "in Technical Specifications. .. __  % ..' y?lq J--'-. .

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E.1. HATCH NUCLEAR PLANT HNP-4527

   < Joe Title Page u.u .

g 4 Georeia Power ch See Title Page o 1 of a #g

                             &ERT - SECURIYY_FCRCE A. CONQlllOd Events are in process or have occurred which involve on 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 (PAG) exposure levels.

D. REFERENCE HNP-4520 C. ACTION

1. Access Control Points:
a. Stop entry into the protected area and past Gate 1, except for G.P.C. perscunel.
b. Standby to receive employee, v sitor, and support group badges and to account for anyone remaining in the protected area if emergency is upgraded to Gite Area Emergency or General Emergency. Report to the Rally Point Leader those persons unaccounted for.'
2. CAS/SAS Operator: ,
a. Establish communications with the control room. *
b. Initiate the call list provided for Alert.

t

3. Shift Supervisor (Security):
a. Direct a security officer to the EOF for Access Control. l
b. Direct a security officer to proceed to the Doy Scout Camp and the public picnic area to instruct all percons to leave the area. The security officer will complete his task and report by radio to CAS/SAS for .turther instructions.
c. Direct a security officer to prohibit any non-Georgio Power personnel except NPC from entering Gate 1 without Plant Management approval. ,

1 f IIANUAl SET  !

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   . 41 L                                      [                                  It Georpia Power aA                   ~ > ~

See Title Page o 2 of 2

d. Direct unneeded security officers to report to the Rally Point (Gate 16).
e. Account for all Security Force personnel.
f. Report to the EOF Manager for additional instructions k when all security functions are complete.
g. Place two officers on standby for duty at the News Center.
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             -                                                                                                                                                                                                                                                                                       1 GEORGIA POWER COMPANY                                                                                                                                                                                 I e

HATCH NUCLEAR PLANT PROCEDURE , p t o 0 ___ G i .t .e _A.r._e a. Em e r1 c rm c v. - S_ e c u_.r__i

                                                                      -- -                           .                                                                       _Zt . F_.o..r__c.e.

1 I

                                                                     ~~~~

H! P-4G27 - PROCEDUEE UU5 DER l

                                                              .                                                       _ _ _ _ .          _-LAB RESPON3 IDLE SECTION SAFETY RELATED ( X)                                                                                   NON-SAFETY RELATED (                                                                          )                                                    >

_ _ _ _ . - _ _ _ - _ - _ _ _ - _ _ - _ _ _ . . . - _ _ _ - - _ _ - - _ - . . ._-___ ___-______s__- ____ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE ' HEAD MANAGER .

             .-__ __                   ._-_____ ___--____ -_                                                       ._ .-____ ___ ____                                                      - -_ --_j, -._.                                                                            __

3 Pages 1&2

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E , .,s,- s-n'&n L P_ROQFOt 'RE_RFU T G_f Or_i_P$ty _ I i m . PRnCEOURE NO. HNP _ _. 2_7

                                                                                                                                    - .2
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Revision No. , - --

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l i REVISION CHANGES MODE OF CPERATICM OR INTENT AS DESCRIRED IN FSAR* i . ( ) Yes ( /Q. No

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     . f.8. NA3. CHANGE INVOLVES:
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        . . 3. ;.'.t . -?. ? ( 0) An unreviewed Safety Guestion                                                                  (         ) Tech. Specs.                                                                                  ,

I 7.'p',T.'.C.t'"'41'. ( Se e .ba ck f o r Sa f e ty Eva l uati on i f required). . . l I S.sfety Related 6/-4 Non--Saf ety Related ( ) Sdfety/Non-nafety Status Change ( ) Yes ( d No ,

                                                                                                                                                                                                                                                                     .l' Attach marked up copy of procedure to this form.                                                                                                                                                                              ,
                                                                                                             ,/If f O/ M~.l _ h b 1/
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REASON FOR RECUESThi;&.n...y ,

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                                  '                                                                                                                                                                                               _ - _ =                                        =-_                                 __

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1. The probability of occurrence and the consequences of an accident; l' ,-
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                                                                                                                                                                                                                                                                                                                                   .c or malfunction of equipment important to safety are not increaued                                                                                                                                                                              l-                     .-

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2. The possibility'of an accident or malfunction of a different type $ ." -

t'han analyzed in the FSAR dces not result from this change because .,.

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                                         '                                                   .                                                                                                                                .                                                                                                                 .          . .: ,c tne system responds and is operated as before the change.                                                                                                                                                                                                      t ".9
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3. The marejin of safety as definod in the 'Ibchnical Specifications
                                                                                                                                                                                                                                                                                                                                   . Ib . ,d:':
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ti's not reduccd due to this revision because tho' revision does not T. 7 i:l change any limited safety system settings which Pauld allow a. ., '. i i s.' -

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                                                                                                                                                                                                                                                                                                                                                 , ' ': R operations to be exceeded as stated'in Technical Specifications.                                                                                                                                                                  '
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liNP-4627 dee Title Page E.1. HATCH NUCLEAR PLANT y v,..,

             <au                                                                                         3    g d,ee .fitle Page Georeia o   Power cb                         -

1 of 2 SITij_ AREA @rERGENCY_- GECURITY FORCE A. CONDITION , Events are in process cr have occurred which involve actual or likely major failures of plant functions needed for protection of g the public. Any releases are not expected to exceed PAG exposure U levels, except near the site boundary. ( G. REFEREtlCE HNP-4G20. ( C. ACTION

1. Access Control Points:
7. Stop entry into the protected area and past Gate 1, unless authorized by the Emergency Director.

(

b. Standby to receive employee, visitor, and support group  ;

badges and to accoun+ for anyone remaining in the { protected area. Report to the Rally Point Leader those  ; persons unacccunted for. t 0

2. CAS/SAS Operator:
a. Establish communications with the control room. (
b. Initiate the call list provided for Site Emergencies.

l

3. Nuclear Security Supervisor or designee: i i

a Report to Err.ergency Operations Facility,

b. Dispatch Decurity Vehicles to Roadblocks.
4. Shift Su;,ervisor (Security): l
p. Direct a security officer to the Emerger:y Operations Facili+y for Access Control.

MANUAL SET

m _ _ _ _ . . a._. . _ .. ._ 2 = _ m . .u_ m_ . A_ _ . ._ . a=-c _. ._... _a_ _ _ a - ,- . . . , , . . HNP-4627 aee Title Page E. l. HATCH NUCLEAR PLANT ,,

        ,.u,                                                                                     3 aee Title P. age               GeoroiaO      Power eb                    ~

2 of a

b. Direct a security officer to proceed to the Day Scout Camp and the public picnic area to instruct all persons ,

to leave the area. The security officer will complete his tack and report by radio to CAS/SAS for further instructions.

c. Direct three security officers to attach the boat to a security vehicle. Proceed to river and launch the boat.

Two security officers will man the boat and patrol the river adjacent to the plant. All river traffic will be cleared from the area. The driver of the security vehicle will report by radio to CAS/SAS and proceed to the designated E.O.F. For future instructions.

d. Dispatch a security officer to the warehouse and training building areas South of the Protected Area to assure all persona in those areas have evacuated.
e. Dispatch additional security personnel as necessary to control access to the E.O.F.
f. Dispatch two security officers to the News Center to Control Access.
g. Direct unneeded security officers to report,to the l' Rally Point (Gate 16) or as defined by Rolly Point Leader).
h. Account for all Security Force personnel.
i. Report to the EOF Manager for additional instructions l when all security functions are cornpi c t e.

S. Roving Patrols: Security force roving patrol outside the protected area report to their rally point, the old constr'ection parking lot and the protected a.rea patrols to Gate 16, or as defined by the Hally Point Leader. h { ( ( l i 13NUM SEI

s.- . . . .. .- .~. . - . - - - ~ - . , . . CCORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Site - Apf l i ng~C oun-t v Sheriff ~ ' ~ " ~ ~ ~ ~

                                                                   ~ ~ ' ~

Area Emerg@en -- p @cv5DE TIT [E ~~~~ HND-Ar.,31 ~ ~

                                                            ~

PROCEDUEE~UU55EU Lab RESPONSIBLE $ECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) 1

                     .            _-        -----------_---- -                                                        c.---            --             --. --- .                    .. -- - ---- - --.\                               - - - _ - - - ..

APPROVED APPPOVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER

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PROCEOURE NO. I IMP _

                                                                                                                                                                    /_             ?._(_[__

.h . Revision No.______/_________ OFott.:STrn n'/ n:- p ar< T m M..T._H'_r, . _ _. n._vf_.P.: O*./. Ar .__ ._ _ re.:ee ; Date; Si gririt u r e : . _Dato: S s a.

                                                                            )     . _( f {                             s q/                               _
                  < REVISICN CHAMCES MODE OF OPERATION OR INT                                                                                                                           .       AS DESCR.T.DED IN FSAR:
              *- .                                                                                     (            ) Yes                                                    (                  No                                           '
     .,...                                      v ..- .                                                                                                         .
  %...*        .. CHANGE INVOLVES; .
 $;.'1.'. '( -)' An unreviem d Safety.Guestion ( ) Tech. Specs.                                                                                                                                                                       .(              ) Neither -                                        ,                 .

~?tT.**..'":' '.(Se e la ck f o r Saf ety Evalisati on if requirc-d) . Non-Safety Related ( ) -

                , Safety Related

( ) ( kNo Safety /Non-nafety Status' Change (

                                                                                                                                                          ) Yes                                                                                                                                                       ,
                                                                                                                                                                                                                                                                          .                                                    e Attach markad up copy of procedure to this form.                                                                                                                                                                   .

REASON FOR RECUEST g/h4/6g ,f h4 z2'j' f ~ /,.rg . /[d6 r I r - w h Msce41h / ' ~ - 4_m. au _ G.i.. .AE EM_l> di s_ 'nikcs (%wM. ; .. W....S'_?. . .- , ...:

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PRD RECDTUNDO APPROVAL; ( HYbn ( )No - a,_.._. )w ( I. .a -> Pi<O- Gi t relary - p,w, , - g > .. .

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                                                                                                                                       ..       _P.../. " 1 U. ..' T.T.t e t 6                                                     l i
                                                                                                                                                                    .         __-                - - - = _                 _ _ _ _ _                                  ________-                                                                                  1 ne revision of this precedure does -not                                                                                 constitute an unreviewed                                                                  safety                                                      ! ~ (~ M O                            _ _ _ _ _ _ _ - _                                         _ - _ _ -=                                          - - - - - - - _ - - -                                                                - - - - _ _ _ - _ - _ -                                                                           . ..

questien as explained belen. l __ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ =

                                                                                                                                                                                                                                                              .                                               b'
1. The probability of occurrence and the ccusequences of an accident - . - = _ -_

l: '.

                                                                                                                                                                   .-=                                                          _

Ir o'r nalfunction of equipment important to safet./ are not increased

          -                                                     above those analyzed in the FSAR due to these changes because
                                                                                                                                                                                                                                                                                      ~
                                                                                                                                                                                                                                                                                                                                        ,'.                  j
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the revision does not change the purpose or perfor=ance of the g.

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The possibility of an accident or nalfunction of a different type-

2. -
                            . - _ -                                                                                                                                                                                                                                                                                 .                  . :.tr "c-t'han analyzed in the FSAR decs not result frem this change .because                                                                                                                                                      - - - _ _
                                                                                                                                                                                                                                                                     ~                                      .            7,..                g;-
                       '                                         the systen recpends and is operated as before the change.
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The narejin of safety as defined in the Technical Specifications -

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                        . .                                                                                                                                                                            .           .                                                                                         .        y_,. . " . . ,..

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                                                                .i's not reduced due to this revisicn because the revision doep not
                                                                                                                                                                                                                 .              ..                                         .-                             w             ' .>C'.
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change any linited safety system settings which would allow a- .-

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  '~        -            .                                        safety limit to be exceeded or to allow a limiting condition for                                                                                                                                                         .

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                                                                 . operations to be excociled as stated "in Technical Spec'ifications..                                                                                                                                                                            .
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See Title Pagt E. l. HATCH NUCLEAR PLANT .....r..... m 1 See Title Page Georoia D Power a\:.s - 1 of 1 < g 511E_68g6_EUgGQEUCy_;_6E861NQ_qgyNIy_QUEGIEE NgIE , This procedure supercedes HNP-4G11 Revision 5 dated 8-31-79. A. CQNQITIgN Notification has been received from the Plant Hatch Security Force (or as'an alternate from the Emergency Director or other representatives) of an emergency condition involving the release. or potential release of radioactive materials at Plant E. I. Hatch. Person matting notification will specify that Normal or Alternate. Emergency Operations Facility is to be used. B. ACTION

1. Sheriff (or delegate) report by radio or phone to:

Normal Emergency Operations Facility - Simulator Building at / l Plant-E.I. Hatch / (Tel. No. ~m l or Alternate Emergency Operations Facility - Appling County Sheriff's Office in-the Courthouse.

2. Cooperate with the S'r gency Director in:
a. Controllird ce cit.

, b. Expediti..,nm, c ent of emergency vehicles.

c. Providing security for the Emergency Operations Facility.

m G MMiU.11 'iE T

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   . _ _ ._. _ .. _ u ._ _ __.- _ ~ w ;......                    .                                                                                                     __. -. _ _~ - _                           . . _ _ _ _ _ _ ~ ~ . . . . _ _ ,

GEORGIA POWER CCMPANY HATCH NUCLEAR PLANT PROCEDURE S__i._t _e.A r e a - - - - - Em_._e..r 9 o n t v - To omb c C o_un..t L.S__h.e_.r_i .f__f. , HNP-4G32 - PROCE50iic RURoER Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-GAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER

           ._____2                                                                                                                                                                                                                      m____.__

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           ._-___;                  _ _ _ _ . _ _ . _ _ - _ _ _ _ _ _ _ . _ _ _                           ___._.____.______a                                                             ___ _ -__._____________ ___
           ._____                    . . _ _ _ _ _ _ _ _ _ . . - - _ - _ _ - _ .                           ____________-._.i                                                             _ _ - . _ . - _ . - _ _ _ _ _ _ . _ -            __- - _-

__________4 _ _ . . - - . _ .

            . _ _ _ _ _ . .          _.. ______ _ _ _ _ _ . _ . _ . _                                      ____._.__________3                                                            _____--_______._s                                 _ _ _                  _ .

I!NP-9 MANUAL SET

                                                                                                                   . _ _ . . _       _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                                                                           s
o. - . - ... . _ _ _ ... _ _ . .. _... _ . _ _ .
                                            .                                                                                       /ffi-                                                                                                                                                                            -

R..F'._,'_T.D_T.CN - - -PFo_i tr ST Pn..OC.O! DE PROCCOURE NO. I lNP __ ; V, _'(OK h . Revision Mo.__.__ 2

                                                          ~

p 3[i'T-E' ff n nV Of7P , .0 T.C NT Iran AP P:. OVAt. Dale; .~~~5Ih3hiure: Date: reme;

                                                                                                                                                                                                                                                                         'O
                                          ,      f})lf)$ _ hj - fh                                                    '

WW767Y ,- ._. - IN FSAR:

                 ' REVISION CHANGES MODE OF CPERATION OR INTQt'T                                                                                               j AS DESCRIBED

( ) Yes (A)' No -

                                                                                                                                                                                                                                                                                                     '                        ,     s l, .

A - r-

 .$..'5' CHANGE INVOLVES: -

(K) Neither. .

                                                                                                                                                   ) Tech. Specs.
  '.f.e ,';( ') An unreviewed Safety Guestion

( ' ^ -

  • f'. 'l.~.T . ' 3 '. ( 5e e .i,o c k 'or Cafetf Evr.limtion if required).

( ) Non-Safety Related ( ) . Efety Related . . . .. . S$fety/Non-safety Status Change ( ) Yes . ( N No e. Attach marked up copy of procedure to thi s f orm. , REASON FOR REGUEST__ /. hap, _ b / k f_ 5 8 __ f/ 2Md6

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PRD RECOMMFNDO /.r>PROV/.L; (.<d'b s ( )No - t _ . .t._, mu.___._._____.-- I-PRU. bperetary ,

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Sf_t_FT 1. FV,'.4_.U_AT_T ON I i -

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

The revision of this procedure does not constitute an unreviewed safety

                                                                                                                                                                                                                                                                                               !          '[' ]       .

question as explained belcw. l ..,' _ -=- - The probability of occurrence and the consequences of an accident

1. --
                                                                                                                                                                                                                                                                                                                      +
                   ,                                            or malfuncticn of equipment important to safety are not increased                                                                                                                                                               l' s
      .                                                         above those analyzed in the FSAR due to these changes because                                                                                                                                                                                                    .
  , : '. c.f 4                      ;              ,            the revision does not chance the purpose or performance.of the                                                                                                                                                                       y.                   U. . . .'.
 '.l.
                                                                                                                                                                                                                                                                                                        . ' . ~ ' .: ,.
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                                                                                                                                                                                                                                                                                                               . .a.:-..:,. . ,
                                                                                                                                                                                                                                                                                                              < . ,' 7.~.i:,
2. The possibility'of an accident or malfunction of a different type
                                                                                                                                                                                                                                                                                                      .                 . a ,1c than analyzed in the FSAR dces not result 'frem this change because _-                                                                                                                                                                  ..                   ....4
                                                                                                                                                                                                                                                          ~
                                                                                                                                                                                                                                                                                             .        . . ,                   ..r: .

the system responds and is operated as before the change. -'.\ 'N.6

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The margin of safety. as defined in the Technical Spacifications.

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                                                          ' :ib not reduced due to this revision because the revision docs 'not                                                                                                                           .,
                                                                                                                                                                                                                                                                                                  ",y                          ,:
       -                                                                                                                                                                             .                                                                                                                                 .. i
                                                                                                                                                                                                                                                                                                            ' rY e.;- ?lT.*,
          '.                                .                   change any limited safety system settings uhich would allow 'a                                                                                                                         e
                                                                                                                                                                                                                                                              #        .r
                                                                                                                                                                                                                                                                                                            * 'i
                                                                                                                                                                                                                                                                                                        ..                         -e ,
                                                               ' safe'ty limit tio be exct.:ded or to allow a limitin'g condition for                                                                                                                                                                         :                         j;
                                                                                                                                                                                                                                                                                               ..,.,.,'[.....

operatidns to be exceeded as stated'in Technical Specifications.. _ k.'iD ~l

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limp -4632 E. I. HATCH NUCLEAR PLANT ~o-Geo Title Page "'-

 .*u                                                    A                                      2 See Title Pagc Georgia Power t.d                  "~

1 of 1 l SIIE 68[6_EUgf_lQgbCY_;_.ICO[Q2 _ COUNTY _O!jgP IFij NQIE This procedure supe r cedes HNP--4Gla, Revi s ion 5 da te d 8-31-7 3. A. CONDITION Notification has been received from the Plant Hatch Security Force (or as an alternate from the Emergency Director or other representatives) of an emergency condition involving the release or potential release of radioactive materials at Plant E. I. Hatch. Person mat <ing notification will specify that Normal or Alternate Emergency Operations Facility is to be used. D- 6CIID3

1. Contact Appling County Sheiff's Department for any instructions relayed by:

Normal Emergency Operations Facility - Simulatsr Building at l Plant E.I. H=+ch (Tel. No. Alternate Emergency Operations Facility - Appling County Sheriff's Office in the Courthouse. ,

2. Dispatch deputy to patrol the highway North of Plant E. I.

itatch on US #1 to prevent traffic from stopping. e 9

                                                                 !? ill SEI

N rL _. _ . --_ . . . - . - - - - - -_.~.m_-- . ~.~ .- _m_ ~ ..,___ -

       . s GEOF{.1 A POWER CG;'.PANY HATCH NUCLEAR PLANT PROCEDURE                                                                                        -

General Emnranncy - Encuritv "Fo -- rce

                                                                               ~~~~~~~~- RiUE E50iiE- TITLE HNP-4727     ~

PRUCEOUiiE UU55ER Lab ~ REEPON55 ELE EECTION SAFETY RELATED ( ': ) NDN-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER _____.s _ . . _ _ _ . _ . _ . _ - _ _ _ . _ _ _ _ . .___ _.__--_- _ _ . _ _ . . . _ __ ____._.__- _____-__ A / f 3 P*@ 2 _ _ . - - _ _ _ _ _ _ _ _ _ _ - _ _ - . } .) f'? _ N _- ;_., J- _ _ ,/_ _j,d.m. _ ._ _ *f. f.- . <F_ ly-.f_g_3- . (

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                                                                                                                                                                                                                                                                                                                                                                                                .I PROCEOURE Nn. I!!'P __                                                                         .

7s , (v.3.. Revision No. ____._..._____ . rFPM1m2NT I F,10 rf PPOUAt. pr.U:sTFo ny '~~

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                                   '.REVISICN CHANGES                 .

( ) Yes MODE (OF . 7% No OPERATION OR INTEtjT AS s . - - o -

                                                                                                                                                                                                                                                                          .if 2; .' , :N.. CHANGE INVOLVES: .                 .
                                                                                                                                                                                                              ) Toch. Specs,                                              ( N Naither
       .j"5M;T.R-)-!(An unreviwed Saf ety Guestion
                                        .                                                                                                                                                         (                                                                                                                                                   '

w w p ' ys . .(See back f or Saf ety Evalimtion if required). . (, ) Non-Safety Related ( ) ' O.afety Relt,ted . . . ( ) Yes ( ) No , 9 SEfety/Non-nafety Statuc Changa e. Attach marked up copy of procedure to this form. I !_c' _ '-_ u__ 2 v .. REASON FOR REGUEST_ T4 c #m_ _ uE 4 - f /_/_//h_t%'z.__ _=?. _a. 2 qn w s! Os,. a--- r g.,. y_- .i k_._ r. a_ _ s - - LA -a~ ... r

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i- _ _ _ _ - . PRO RECCT.INOG APPRO'//L; (/) Yen( )No __

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t The revision of thia procedure doca not constitute an Unreviewed safety (' d',i. quantien as explained helc.i. - l .., (-

1. The probability of occurrence and the censequences of an accident fl . - .__

o'r malfuncticn of equip:.cnt important to safety are not increaned

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abovt those analyned in the FSAR due to these changes becau$;e T ,- fi

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The possibility of an accident or nalfunction of a different type

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                                                                                                                                                                                                                                                                                                                                                                                                                               ,te than analy cd in the FS,3 dces not result frcm this change because
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, ,                                                                                   the system responds and is operat d as before the change.                                                                                                                                                                                                                                                    .. .. . Z.'
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3. The marcjin of safety as defined in the Technical Specificatiens
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i's not reduced due to this revisien because the'_ revision does not _
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ch'ange any limited safety system settings which would allow a l f;,/ t/c,W , t . l

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                                                                                    .cperations to be exceeded as stated in Technical Specifications.                                                                                                                                                                                                                                       - -                             U l_             .
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HNP-4727 E.1. HATCH NUCLEAR PLANT w ~9 '.o See Title Page 3

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Georoia D Power na 1 of 2 e( Geo Title Page EEEEBe'=_EUERGEMCY_:_ggCyg1Iy FORCE P NQIE This procedure supercedes HNP-4706 Revision 5 dated 12-8-30. A. CQNDITION Events are in process or have occurred which involve actual or imminent substantial core dagradation or melting with potential , Release can be reasonably for loss of containment integrity. expected to exceed PAG axposure levels offsite for more than the  ; immediate site area. , B. ggEgRENCE . HNP-4720. C. ACTION _

1. Access Control Point.

1,

a. Stop entry into the protected area and past C te unless authorized by the Emergency Director. .
b. Standby to receive employee, visitor and construction worl<er badges and to account for anyone remaining in the protected area. Report to the Rally Point Leader those persons unaccounted for.

E. CAS/SAS Operators *

a. Establish communications with the Control Rtom.
b. Initiate the Call List provided for General Emergency.
3. Nuclear Security Supervisor or designee:
a. Report to Emergency Operations Facility.
b. Dispatch Security vehicles to roadblocks.

MANU,11 SET

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Gee Title Page x & 3

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Georoia D Power /'A 2 of 2 Gne Title Pagt

4. Security Shift Supervisor *
a. Direct a Security Officer to the designated Emergency Opera tions Facility for Access Control.
b. Direct three Cecurity Officers to attach the boat to a security vehicle and proceed to the boat ramp and launch the boat. Two Security Officers will man the boat and patrol the river adjacent +o the plant. All river traffic will be cleared from the area. The driver of the security vehicle will report by radio to the CAS/SAS and proceed to the designated Emergency Operations Facility for further instructions.
c. Direct a Security Officer to proceed to the Doy Scout Area and the public picnic area to instruct all persons to leave the area. The Security Officer will complete his task and report by radio to the CAS/ GAS for further instructions,
d. Dispatch a security officer to the warehouse and training building areas South of the Protected Area to 7I assure all persons in those areas have evacuated.
e. Dispatch additional security personnel as necessary to control access to the EOF.
f. Direct unneeded secutity officers to report to Rally Point (Gate 16 or as defined by Rally Point Leader).
g. Account for all Security Force personnel.
h. Report to the EOF Manager for additional instructions when all security functions c>e complete.
5. Roving Patrols:

Security force roving patrol outside tne protected area report to their rally point, the old ct struction parking lot, and the protected area patrols to date 16 or as defined by the Rally Point Lea'Jer. MMiUAl SET

     - - - - - - . - - - - - - - - - - - - - - - - -                                                                                                         a

4 O GEORGIA POWER COMPANY IIATCH NUCLEAR PLANT PROCEDt GE General Emergency - Applirm County Sheriff

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                                                                                                 ~ EiiU~EUUEM          C                                      TITLE-~
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MNP-4731 PROCEDURE NU55ii' _ _ . --. . L.a o RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-GAPETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER

             . _ _ . _ _ _ .          _.____..________a__.__                                                                         _ __                     ____a                  ____                      . _ _ _ _ _ _ _ _ ...___                                          ___

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PnOCrnt 13E. R..P_,'.!.D.T ON. Fat tFST P.'lOCEDURE NO. HNP-i n/<>, J / ._ b , Revision No. _  ! .

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RFOUf'STFD DY Di Pe-RTt49!T M9D APPNG'/At. ~ SignaIUr3i~ , Dat3:

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                           ' REVISION CH.^.MGES MODE OF CPERATION OR INTEt.!T                                                                                                        a                    AS DESCRJ.DED IN FSAR:

( ) Yes ( fN). No ,

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A

.faM;TCHANGE INVOLVES:
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                                             '               An unreviewed Safety Guestion (                                                                                   ) Tech. Specs.                                               '( k Neither                                                             1.               ,1 Wi . '!( .)          .

( ': T.l.117 9 '.(See..back for Safety Evaluation if required). f- .- .

                ~ , Safety Related (k                                                                                                   Non-Safety                       Related                              (              )               .                                                                                     ..

t S$fety/Non-safety Status Change ( ) Yes (

                                                                                                                                                                                                                . k No                                                                                   . ' . .,,' ,.
  • p Attach marked dp copy of procedure to this form.

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T..T.0 .! , I i - s p/ _ __'Ihe revinion of this prcceduro does not constitute an unreviewed safety

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questica as explained below. - - - - l .., __ m .

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1. The probability of cecurrence and the consequences of an accident -- I l

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             - .                                                  or malfunction of equipment important to safety are not increased lr..                    -

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                                                                                                                                                                                                                                                                                                                                       .                    s above those analyzed in the FSAR due to these changes because
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t. the revision does not change the purpose or performance.of the
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2. The possibilitj'of an accident or malfunction of a different type l
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than analyzed in the FSAR dcca not result frcm this change because .- .: . i  ! _ . . . . c .,;: . the system responds and is operated as befc re the change. ' V. '.T

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3. The mar (jin of safety as defined in the Technical Specifications. G-  ; .;-
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is not reduc 2d due to this revisica because the revisien does not
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change any limited safety system settings which would allow'a'- U .;,f f.t;, . ;.} .?~ ,

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safety limit to be exceeded or to all'ou a limitin'g condition for ': M(.5..f.J.;

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                                                                 . operations to Fc exceeded as stated ~in Technical Specifications..

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                                                                                               "" " 73 E. I. HATCH NUCLEAR PLANT                      m .n,   .a Gi ia Title Pam 1 ,,

A a Georoia Power ch - s L.er Title Paqi D 1 o

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r geggrj AkhMg]gCUC L;gP Ligg_COUMILSUE31EE NOIE This procedure supercedes HNP-4711, Rev 4 dated 9-7-79. A. COLCIIION Notification has been received from the Plant Hatch Security Force (or as an alternate from the Emergency Director, State of Georgia Department of Natural Resources-(E.P.D.) or their representatives or Civil Defense of an emergency condition involving .the release of radioactive materials at Plant E.I. Hatch. Residents near the plan t may require evacuation. Person making notification will specify whether the Normal or Alternate Emergency Operations Facility Center is to be used. D. ACI1ON

1. Sheriff (or delegate) report by radio or phone to: -

Normal Eme gency Optrations Facility - Simulator Duilding at Plant E.I. Hatch (Te1. No. or Alternate Emergency Operations Facility - Appling County Sheriff's office at the courthouse.

2. Dispatch deputies to establish and man barricadet touth of Plant E. I. Hatch and west of the plant on the county road to Deen's Landing. Both deputies are to remain in radio contact with the Emergency Operations Facility and the Cherift (or his delegate).

! 3. Limit traffic into or out of the plant t c. persons displaying the Georgia Power Compan-f Power Generation Department identification badge. Power Generation Department employees can vouch for other persons or groups to exit the plant area when an rvacuation is in progress. A%u lan c e s are allowed to enter with permission of the Emergency Operations Facility. Other persons wishing to enter the plant area must be authorized by the Emergency Director.

4. Nutify the Georgia Otate Patrol to initiate IW m /JS CENERAL t h _1 L ' ?f - G m 4Gtn CJi/,lL PAlHUL. bpe:tfy .Ict m l ar Al t e r n a i.e
        !      . ; i. h t ; t  s ' ,' o i i c n 2 Caci 1Lty.

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HNP- M See Tit 1e Pagt E. I. HATCH NUCLEAR PLANT .u ,s a.., , ca , . 2 Sen Title Pagt Georgia Power c1 ~~ g ,, a

5. Cooperate with the Emergency Director, Georgia Dept. of- Natural Resources and GEMA in:
a. Assessing extent of emergency and evacuating trea residents when required.
b. Controlling traffic.
c. Expediting movement of emergency vehicles.
d. Providing security for the Emergency Operations Facility.

l

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_ . __ .;- a- ,,___e.. _,_ _3 GEORGIA POWER COMPANY HAICH NUCLEAR PLANT PROCEDURE G e.n.e r.a.l- - .Em.e.r3so n c v. - To.o.mbo Cnu.nty

                                                                                         -- ----                                                                                                                                          - - - - - -           ..-..m.-.----.e. Cheriff NNP-4792               -

PRUCEDUIIE UUABER Lab RESPON5IDL5 SECT 50N SAFETY RELATED ( X ) NON-GAFETY RELATED ( ) W_ _ _ _ .

                                           .__4____________m._._q                                                                                                            .

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                                                                                                                                                                                       /1-$t?,) o PR..O.-.FOt       . -- '.:E C. r. V.T D1 DN.- PFol1:79.T n
   . ~ - ,                         .

PROCEOURE M7 I INP - - 4' -

                                                                                                                                                                                                       ')   _2 _-

Revision No. __ _ _ - .

rOU::STFn ny f F-PMit re:n i 1.rr, o ,M:.ow.t.

t u.u.s ; . o...t e ; signatur<-: Date: n I,0 kJi1keJ a?. 3 7.3 42 4 6 fe) w / _p e .cs u--__ .

     -.                           <REVIGICN CPANGEO MODE OF CPERATIDM DR INTEL'T AS DEGCR.T.GED IN FSAR:

( ) Ves ( No . x . . -

    ;N.,*
  ~ . ,         e..   .......

2 CHANGE INVOLVES:

                                                                                                                                                                                                                                                                                                                                                          ~
                                                                                                                                                                                                                                                      '(                    Neither. .

25['?-' M." -)- l An ( unrevicued Safety Guestion ( ) Tech. Specs.

 ~
      " ? fT. .L ' " - '.(See.back for Safety Evaluation if required).                                                                                                                            .                .

( k) Non-Safety Related ) . SMety Related ( . S$fety/Non-nafety Status Change ( ) Yes ( No . Attach marked up copy oF procedure to this form. REASON FOR REGUEST__ 2hy ,__ 2)__j] fhhdk_' ye (d'( -

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                                      'Ihc revinica of this procedure does not constitute an unreviewed safety - - - -

__ -._ _ - - _.- - - = _ _ - - - - _ . - - - - - - -

                                                                                                                                                                                                                                                                                                                                                                         ![
                                                                                                                                                                                                                                                                                                                 .                                                                                               ../ -
                                      <1ucstican as exn. lained below.                                                                                                 --                                                                                                   - -_                                    _ - _ _ - _. __

[ _= - . _ , _ _ - - _ _ _ _ . - t,  ;

1. '1he probability of occurrence and the censequences of an accident --

l- .

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o'r malfunction of equipment irpbrt ant to nafety are not increased *

  • above thcce analyzed in the FSAR due to these changes because
                                                                                                                                                                                                                                                                                                                                                                                            'f-.
                                                                                                                                                                                                                                                                                                                                                                                           . 4. Q
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                                                                    , the revision does not change the purpose or performance of the                                                                                                                     _ _ _ _ - -
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                                                                                                                                                                                                                                                                                                                                                                                     .t The possibility 'of an accident or malfunction of a different type
                  I                                  2.                                                                                                                                                                                                                                                                                                                                                              ..
                                                                                                                                                                                                                                                                                                                                                                                                                         .c
                                                                                                                                                                                                                                                                                                                                                                                                     . .;. ,v-than analyzed in the FSAR does not result from this chango because                                                                                                                                                                                                                                      .
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                             .'                                             the systen recponds and is operated as bef$re the change.                                                                                                                                                                                                                     _ , _ __
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s The nar<jin of safety as defined in the Technical Specifications -. ';"...,'.',

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                                                               ' . :ib not reduced due to this revision because the revision doon not                                                                                                                                                                                                                                                    ...,o
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                                                                                                                                                                                                                                                                                                                                                                                        .* . V, st .i.-           .. , b ch'ange any limited safety sycten settings which'woul'd aliow'a l

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                  .              .                                          safety limit to be exceeded or to all'ou a lir.itin.g condition'for
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                                                                            .cperations to be exceeded as stated 'in Technical Specifications.-

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  • 8% %E l hb*t 'ed E. I. HATCH NUCLEAR PLANT HNP-4732 See Title Page e we. w 2, u 2 3c.e Title Pag, Georgia Power A ~~

1 ,, g CENEGAL EMERGENCY - TQQMOS_ COUNTY _SUERIEF NQIE This procedure supercedes HNP-4712 3 Rev. 4 dated 9-7-79. A. CQNQITIQM 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. Notification has been received from the Plant Hatch Security Force (or as an alternate from Civil Defense leaders, Georgia , Dept. of Natural Resources or the Emergency Director or other i representatives) of an emergency condition involving the release , of radioactive materials at Plant E. I. Hatch. Residents near the plant may require evacuation. Person making notification will specify whether the Normal or Alternate Emergency. Operations Facility is to be used. ,- l B. ACTIQN . l

1. Sheriff (or delegate) contact the Appling County Sheriff's Department for any instructions relayed by: NorAal Emergency Operations Facility Simulatnn noildinn at Plant E.I. Hatch. (Tel. No. ~

i EE Alternate Emergency Operations Facility-Appling County Sheriff's office at the courthouse.

2. Dispatch deputy to establich and man barricade north of Plant E.I. Hatch at the bridge. Deputy is to remain in radio contact with the sheriff or his Jelegate.

l 3. Limit traffic across the bridge to persons displaying the l Georgia Power Company Power Generation Department t identification badge. Power Generation Department employees can vouch for other persons or groups when an evacuation is in progress. Ambulances are allowed to enter with i permittion of the Emergency Operations Facility. Othrr persons wishing to enter the plant area must be authm .:od by the Emergency Director. fMiul SEI

L.. m ...~__ _ ...- ,_ _ ........- _ _ _ _ ..- _ ~ _ _ _ _ . - - __- -- liNP-4730 l see Title page E. I. HATCH NUCLEAR PLANT ,,,..e..~

                                                                                                    .                   j 2
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3ee Title Page Georgia Power asa 2 of a

                                                                                                                        }

l

4. Coopercte with the Emergency Director, Georgia Dept. of Natural Resources and GEMA in:
a. Assessing extent of emergency and evacuating area residents when required.
b. Controlling traffic.
c. Expediting movement of emergency vehicles.

e e t d e a S 8 e MAHilAl SET

m;,_ _ : : . . u.- . c . ..w.  ;-..-.-..---.-.-.--n-~~~..u.s=,- GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDLIRE General

                                                                      -------------                   Emer    3 e     n c v - Gear 3 a State Patrol- - - - - -      i 7gg                 g 77
                                                                            ~

1IN3-4739 ~~ - PR55E50RE- EOR 5ER L.a t> RESP 5N55ULU~5ECTIQU~~~ SAFETY RELATED ( X ) NON-CAIETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 Page 1

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i:NP-9 MANUAL SET

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REVISION CHANCES MODE OF CPERATICM OR INTEt'T AS DESCRIDED IN FSAR: ( ) Yes . (' No i

      ~
              . ... ' CHANGE INVOLVES: .
   ' f "2').t',,'

s P. .' ( ') An unreviewed Sa:Fety-Guestion ( ) Tech. Specs. .( ). Naither

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               -';'..             J"1 '.(See.back for Safety Evalbation if required).                                                                                                                         .                                                                     ..

( Non-Safety Related ( ) .

                            . S.afety Related                                                                    )
                                                                                                                                                                                                                                                                                                                                     .                             ~
                                    - Safety /Non-safety Status Change (                                                                                                        ) Yes                                  (
                                                                                                                                                                                                                                     ) No                                                                           ,

attacn merked un cony or Procedure to tais #orm. . REAsCN eCR REauEsr___ r/irai;,. . .c>i ,i&:-}-re- _ sMo o - ~l

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i t. GA__r_:FT_Y . P.._/.'.1 U...?.T_.T.O.'.t l i f The revision of this procedure does not constitute an unrevie.ied safety __ _ _ , _ _ . ~ __ ___

                                                                                                                                                                                                                                                                                                                                                              ! '( '

queatica as axplained belc.i. - l _ l. r

1. The prehability of occurrence and the consequences of an accident lI ~.

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                                       .                                                  o'r nalfunctica of equipmnt trnortant to safety are not increased                                                                                                                                                                                                        .--

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                                                                                                                                                                                                                                                                                                            .                                                   l' . . ,

above those analyzed in the t'SAR due to these changes because - 1, : ,W

     }i , . .'.'/.s '; ,. .; , . '
                                                                             .         . the revision docs not change the purpose or perforraance .of the                                                                                                                                                                                                            . .                 9.
        '..'~..,'........-                                                       -

2 .-

        . . ....a ;. .. 3 c .. , . : .,                                               . system.                                                                                                                                                                                                  .
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                                                                                                                                                                                                                                                                                                                                                                                 - ~
2. The possibility ~et an accident or malfunction of a different type j ".

than analyzed in the FSAR does not result 'frca this change because

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                                                                                      - _ - -- the system responds and is operated as before the char)ge.
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e. . 3. Tha cargin of safety as defined in the Technical Specifications ' -

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                    .                                                                    .cperations to be exceeded an stated "in Technical Specifications.                                                                                                                                                                                                             .-                       ,*

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     .  ,.-                                                                                                   4 At 6 % 'W A1                                                              s IA A & [0 fit Ps0 HNP-4735 See T.itle Page E. l. HATCH NUCLEAR PLANT                   _

l m . a See Title Page Georgia Power en -- 1 of 1 e i e , l I GENERAL EMERGENCY - GEORGIA GTATE PATROL I NOTE. . 4 This procedure supercedes HNP-4715, Rev. 4 dated 9-7-79. r l 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. Notification has been received from the Appling County Sheriffs i Department or Plant Hatch Security Force or Ga. Dept. of Natural Resources or Civil Defense of an emergency condition involving the release or potential release of radioactive materials at Plant E.1. tOtch. Notification will specify the Normal n  ! Alternate Emergency Operations Facility to be used. Radioactive materials released is likely to affect the public and m,ay require evacuation of persons living downwind of the plant. l i l D. ACTION -

1. Officer reports to.  ;

1 Normal Emergency Operations Facility - Simulator Guilding at l Plant E.I. Hatch. or Alternate Emergency Operationd Facility - Appling County Cheriff's office at *he courthouse. Officer contacts the Emergency Director upon his arrival.

2. Patrolmen assist Toombs.and Appling County Sheriffs to set up road blochs along highways to the plant and generally establish police control over area imnediately surrounding the plant.
3. Institute protective measures for the public au deemed necessary by the Emergency Director, ieorgia Dept. of Natural Resources, or Civil DeFonse evacuation of residents in affected areas may be required. -

l MANUAL SET l k j}}