ML20126E833

f) v 2 of 13

.. ACCOUNTABILITY OF RADIOACTIVE SOURCES A. PURPOSE To define detailed instructions for the accountability of radioactive sources.

B. FREQUENCY As required C. RE F ERE'; 'ES

1. 10 CFR Parts 20, 30, 70 and 71

2. Reg. Guide 7.3

3. 60AC-HPX-007-0, Control of Radioactive Materials

4. 60AC-HPX-004-0, Radiation and Contamination Control

5. Technical Specifications, Unit 1, 3.8, 4.8, 6.8, 6.10, 6.11

) 6. Technical Specifications, Unit 2, 3.7.5, 4.7.5, 6.8, 6.10, 6.11 D. SAFETY Observe radiation protection procedures.

E. PRECAUTIONS

1. Care should be exercised when handling sources to minimize radiation exposure.

2. H.P. Superintendent's or Department Manager's approval should be obtained prior to use or handling of highly radioactive sources, i.e., those with contact dose rates, calculated or measured, greater than 1 Rem /Hr, beta plus gamma measured with an RO-2A or neutron measured with a PNR-4. In addition, use of such sources should be controlled by issuance of an RWP.

3. Consider the use of shielding and remote handling tools.

4. Sources with 4100 pci beta-gamma activity and 45 pel alpha activity do not require leak test. If a leak test is required and has not been performed within the last six '

() months, a leak test will be performed prior to use.

() 3 of 13 F. RECEIPT OF RADIOACTIVE MATERIAL

1. All receipts of Radioactive material are to be recorded on Data Package 1, Data Sheet 1, Source Receipt and Transfer Log.

2. If the radioactive shipment is a source for chemistry, training department, counting room, or Health Physics use, then refer to Data. Sheet 1 of Data Package 1 for the applicable isotope, determine whether exempt or non-exempt (Refer to 10CFR30 sect. 30.14 and 30.18), and assign the source the next consecutive number. Source Receipt and Transfer Log will be alphabetized to aid in ease of source number assignment.

NOTE If the shipment was CO-60 then look up CO-60 on Data Package 4. If the last CO-60 source entered was CO-60-31, then assign this source the unique number of CO-60-32. Attach this number to the source.

('T Complete Data Package 1. Complete Data Package 2 only for

\> non-exempt. Attach Certificates of Calibration to Data Package 2. Do not make the mistake of attaching Certificates of Calibration to the Receipt Log (Data Package 1).

3. Health Physics and Chemistry personnel will ensure that sources and/or source containers bear labels that indicate the type, quantity, date quantity measurement made, source number, and appropriate radiological postings and symbols.

-4. A complete inventory will be maintained by the Health Physics staff of all non-exempt licensed radioactive sources on-site on Data Package 2, Data Sheet 2. At intervals not to exceed 6 mo., a list of all such sources should be obtained and checked against the source inventory Data Package 2, Data Sheet 2. The Source Continuation Sheet, Data Package 3, Data Sheet 3 should be updated anytime a liqu'id or gas source is diluted, divided, or disposed of.

All nonexempt sources must be accounted for.

5. In cases where physical inventory cannot be performed due to ALARA considerations, inaccessibility, or the source is unsealed, an indirect method may be used such as dose rates, counting, or verification of physical seal (tamper seal) on g3 a housing where tampering could be easily detected as with

(_) faulty or discarded IRMs, LPRMs, SRMs, and TIPS.

f) 4 of 13 v

G. LICENSED _AND NON-LICENSED SOURCES

1. If a li' censed (non-exempt) source is determined to be lost, a Deficiency Report will be prepared in accordance with 10AC-MGR-004-0, Deficiency Control System.

2. Non-licensed sources (exempt) are not required to be inventoried by this procedure.

3. Records will be kept of all receipts, transfer, disposal, leak tests and other information pertinent to byproduct licensed material. Sealed sources shall be leak tested as per 62RP-RAD-007-0.

4. Transfer of radioactive materials (except radioactive materials produced from power plant operation) will be docur.ented on Data Package 1, Data Sheet 1 - Source Receipt and Transfer Log. All radioactive shipments off site will be documented per 62RP-RAD-011-0.

5. In-plant use of sources will be controlled as specified in 60AC-HPX-007-0, 62RP-RAD-010-0. -

H. USE OF SOURCES

(~}

U

l. A Laboratory Foreman or designated alternate will control the use of radioactive sources except as specified in section E.2. ,

2. Sources will be stored in designated, locked storage areas.

3. An "In-Plant Source Sign-Out Register", similiar to that shown in Figure 1, should be used to check sources out of locked storage to the authorized user.

4. The user must acknowledge receipt of the source by signing his name on the In-Plant Source Sign-Out Register.

5. Except as required by a Radiation Work Permit (RWP) and/or work area involved, protective clothing is not required for source handling.

.6. When work is completed, the source user will return the source to the checkout point and notify lab foreman or designated alternate so that the date and time of return can be logged.

I. DILUTION OF RADIOACTIVE LIQUID STANDARDS l

() 1.- Complete accountability of all non-exempt radioactive sources must be maintained at all times.

l

/~' 5 of 13

' V)

2. Calculate the quantity of parent source material required for-the dilution.

3. Pour.this amount plus a small excess of the parent source into a clean container. Never pipet directly out of the parent source container. Never pour any excess back into the parent source.

4. Using Class A Pipets, pipet the exact amount calculated in step I.2 into a clean volumetric flask and dilute to the mark using demin water.

Note The final standard solution may contain a dilute acid to prevent plate out of the standard. Normally, a .1% acid solution is sufficient (ex. nitric acid). l S. Update Data Package 2 for the parent and Data Package 3 for daughter source data. Complete data sheet 2 for daughter source. Assign the daughter source the next consecutive -

number. Prefix this number with the parent number.

() NOTE The fourth standard made from the parent material of CO-60-7 would bear the number

, of C0-60-7-4. A standard with the number of co-60-7-4-1 would indicate that it was the first standard (daughter) made from the parent source of CO-60-7-4 which was a dilution of CO-60-7 which was the primary source.

6. If a dilution is to be made from the daughter source, the l daughter source now becomes the parent source from which subsequent dilutions can be made.

I i

7. If the daughter will be stored in the Radioactive Material Storage Area, then Data Package 2 must be completed and maintained for the life of the standard.

8. Every source from which dilutions are made must be listed on Data Package 3 under the original Source Data before the dilution is made. In this manner, all subsequent dilutions can be accurately tracked.

~^

e ----- - - - -

6 of 13 (a~)

9. Because the chance for errors increases with each dilution,

.the number of dilutions from the parent to the final g daughte'r should be kept to a minimum. All intermediate dilutions that will not be used should be discarded.

10. When sources decay more than four halflives, they should be discarded. The method of disposal is to be approved by a Laboratory Supervisor. When a source is discarded, log the disposal date on Data Package 1, Data Package 2, and Data Package 3. Remove Data Package 2 from the log book and forward to the lab foreman for review.

e O

O

7 of 13 FIGURE 1 IN-PLANT SOURCE SIGN _OUT REGISTER SOURCE SOURCE ACTIVITY DATE & TIME SIGNATURE PURPOSE ISSUED BY DATE 6 TIME f

NUMBER OUT (or USER) RETURNED

______.____._____..____.. . . . . . _ _ _ _ _ _ _ _ _ _ _ __________.______----- =- =====- =___________.________________. _____________

______..___._________.___ - _ _ _ _ . . _ _ _ . _ _ . ....____-_...__== _______._________.__.. ___ _- - _ _ _ _ _ _ _ _ _ . ___.____ __..

___________.___......_____________ ...... .-______________.....____ =___.______________ _ . _ _ _ _ _ _ _ _ _ _ _ _ . ......_______

f4

_.__.....___.... .......___. ___________. _________..__________-___.....==- .======_ .___ _ _ _ _ _ _ _ _ _ _ . . . . . ..._-_...______

._____-.___....____.-eeed........-_______.....____D____________________._g_eee_e_e-e___________..........ee-eee____e.

O _ _ _

(%

8 of 13 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62RP-RAD-035-0 SERIAL NO: ROO-MPL NO:

RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: As Required .

COMPLETED BY:

i t

~

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTANCE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

Page 1 of 2

. 62RP-RAD-035-0 R00

. FIGURE 2 Page 1 of 2

e l

l

[

9 e 3 0 ..

DATA PACKAGE l_

DATA SHEET 1 SOURCE RECEIPT AND TRANSFER LOG i

,..................)

DATE $81PPED SHIPPED SEMARES f SY

,......,.........,...............................q..

SOURCE e SOLID EXEMPT 08 QUANTITY LOGGED SY',REMARES SHIPPED TO DATE/ 150TUPE LIQUID MON *EEERPT TIME ON gam

~_-

..-- J O _ _

..........._~ .

.__ f t........

~

_ --... 1

.......... 4 L........L........JJ t

I

-.........L._ -......._L -

l l.......L.....

ROO 62RP -RAD -0 35 -0 FIGURE 2 Page 2 of 2

62RP-RAD-035-0 0.

10 of 13 PROCEDURE DATA PACKAGE 2 4

DOCUMENT NO: 62RP-RAD-035-0 SERIAL NO: ROO-MPL NO:

RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: 6 Months -

COMPLETED BY:

.O DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTANCE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

Page 1 of 2 62RP-RAD-035-0 R00 FIGURE 3 Page 1 of 2

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

. L 11 of 13 DATA PACKAGE 2 DATA SHEET 2 SOURCE INVENTORY CONTROL LOG SOURCE SOURCE NUMBER SOLID . LIQUID . GAS HALF LIFE ASSAY DATE SOURCE ACTIVITY DATE RECEIVED RECEIVED FROM.

DATE DISCARDED INVENTORY RECORD DATE LOCATION ACTIVITY INVENTORIED BY r

r ............ . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . ..............

1 p-

]

t 4

t A Page 2 of 2

( 62RP. RAD-035 0 ROO FIGURE 3 Page 2 of 2

-b v 12 of 13 PROCEDURE DATA PACKAGE 3 DOCUMENT NO: 62RP-RAD-035-0 SERIAL NO: ROO-MPL NO:

RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: ,

COMPLETED BY:

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKM3 FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIt (N ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTANCE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

l f

i j~ Page 1 of 2 62RP-RAD-035-0 R00 I

I I

FIGURE 4

Page 1 of 2

e 62RP-RAD-035-0 0

/_N 13 of 13 5 /

\.q/

DATA PACKAGE 3 DATA SHEET 3 CONTINUATION SHEET FOR ORIGINAL SOURCE DATA NEW SOURCE DATA DISPOSAL DATE NUMBER ACT AMOUNT NUMSER ACT.* VOLUME INT. TYPE USED mi pct /mi DATE INT.

tall pet /m1

/m s

\v;6 ...... ..... ... .- .....- . . . ......- . _...-

Decay correct activity to date of use.

Page 2 of 2 i

m <

62RP-RAD-035-0 R00

\m/

FIGURE 4 Page 2 of 2 l- _ i

e .. . . ., y 3 l -I s ..

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

'n \

() PROCEDURE Dosimetry Issuance and Trackin.q PROCEDURE TITLE HNP-8004 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

, APPROVED APPROVED REV.' y DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

~

18 Pages 1-13, 1G, 18, ,

22, 8: 31-33 h __..____ .

j ,,

f'_h _ _ . . _2 _f_ f_///d

" DELETED - REPLACE BY &

- _ _18_ _ . _6_2 R_P.re R_A_D_ _00.1_ _ _ _ _ _. _ _

0 . d. .__' . - _ . _ _ _ _ _ _ _ . ._0 #_ ML _ _ _ . .

,3

( 1 v _ _ _ _ .. _ _ _ _ _ - _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ .

___ __p__________________ _t-___________ _..___ ____ ____ _ ..____ ___

HNP-9 L . ~ _ _ , _ . , _ . . _ , .. .._ _ _ . . _ _ _ _ _ _ _ _

/

\

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

/m s PROCEDURE RADIATION OCCURRENCES AND DEFICIENCIES - - - - - .

. PROCEE"JRE TITLE HNP-nOO5 PROCEDURE MUMUER L. a b - -------.

REGPONGIDLE CECTION GAFETY RELATED ( X ) NON-CAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER g..g 4.

16 Pages 1, 7, & al Q,- _.. 4 . y v [ j g..___.-______[._..__

~~~~~~

17 General Revision ~ ~ ~ ~

' ' ~

'% ~~' ' ~~"

440 ~~~

///~/'[

M I84 '

B5[fTEd~~~F5 PEACE I5~~ -

. O, _ _1.7. _ _ _ 6_2_R._P_ _RA_D_ _0_0 2. 0_ _ _ _._ _ _ _ . _ . . - -

( '.

. -/

. - .. . _ _ _ _ _ .r_ . .

s a

___e__ __ ____ ________ ___ __ ________._____ _.____ ________ ___ ___.

4 e om. .e. am em. om 6 .m am. see .us een one se es. m. .es ses een n_ .ee es. .m - es n. .sm. ee e sup een eu. a. .m.mm ese .g.,_em .an. e.no .ses. * +=. ase. mase.a. m__.-__-.e. e es. s. es e., as _ e. e esse em go. esse es. _ _ _ .

. .sAb .g. mas .G. e .e> s. el sa. cit. .S. .G. .es . som *g... ee es. _ .es .sm. use .e. a s. ans..ns. . vs mesu4 des esm.se.s e aein._ -.=.=.. css..=..'e. usa 4..me..,_ a

- B.be. .sgW.f es .e adde eg. .e .es esos me. elkgut. . sum.see see a G.ms.mp.g.am es. .=D.m ma .s se.=aw..il.e.=m .d t e .4. .s . es .se..ma..ium. e G dpcal.est.=.6.uk.m 41s. B.EE88988GM 4e* #

8 w

) ______ .____.. ___ .__..___-___ -_ _ _ . . _ _ _ _ . . _ - . _ . - . _ - _ - _ _ _ - _ . - . _ _ -______.

kb ") R$b

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

. p PROCEDURE Decontaminatinn_____ ______

PROCEDURE TITLE HNP-800G PROCEDURE NUMOER Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-GAFETY RELATED ( )

APPROVED APPROVED REV. DEOCRIPTION DEPT. GENERAL DATE MANAGER MANAG-7 Pages 1 -

5 -g g 8 Page 4 Q,( g_ _ _[_gf._yp.

._____ ______________ _____ ._ _ _ _d_ _ . . __3_ _ __,'_

. _ _ _9_ _..P,, ages 1,2..n._ 4 T.- 5 . ____ f. /_ _ _. McV .Alv ...df__..[__f / #f

.M.

M[

DE[ETED - REPLXCE BY 0, g -

_ _ _9_ _ _ _6_2_RP_ _R_A_D_.0_0_4_ _0_" _ __L_U K_ ____ _ )_ _ _ _ -g-.%____ ___

_ _, _,e ______ _ -

a .

r ._

[

s ... _ _ _ _ ____________________ ________ ______ ________________ ______ .

HNP-9 k _ _.m____ ._ . . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ - _ _ - _ - _ - ___.____.__m__ _ _ . -__. _

r j

\'

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

! /

V PROCEDURE

~~~~

Radiati on Wo rl< Permit PROCEDORE TITLE HNP -8008 PROCEDURE NUMBER Lab RESPONSIBLE FECTION GAFETY REL.ATED I. X) ,

NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MA' NAGER MANAGER 18 Pages 4, G, 8, 12-14 & 21 7 '7

.----- --- --------_-_-_--- _. ---_ . ._ _._--_ _--_-----_ a ._)

/

A z j .----_

19 Page 7, 9 and _21

---_s -------- -------

- g fe.;jf/f-L

.--.)----------- '_

20 Pace 14 ...-- - . -

- t . . . _-- - C 21 Pages 2-3, 5,14_15 & 22

----- _hld'ld&b__t -

- u [ -- f y _8 ,

. #2-- Jencml Cev_islaa--_-_-

6- g n_ M__A/,T4

" DELETED - REPLACE BY n # . _ _ _/ _ _ - . - _ _ .

. 22_. . 02RP-RADa0.0h0-----s . _K--__ ._-

. - _ ___ -- .44//f_

HNP-9

r GEORGIA POWER COMPANY

f. ~

HATCH NUCLEAR PLANT T

c"/ PROCEDURE Airborne Radioactivitv. Concentration Determination sm PROCEDURE TITLE HNP-8013 PROCEDURE NUMDER .

Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

.-____ ____-__----___ -__- ,_._._ _ - - _ _ _ _ - _ _ _ _ _ t __ ._.__-________..________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGE-

.-1_2.- - - Pa. 9e s_ J. 3 ,. .&. 7. -. -. _

- - - - - _4b.. ..8_ N.--. 7 - , _ _ _ _p _ d 13 Pages 1-3 & 5-6 g. g.

f #u f5_.1/Tk d _-._ $.---.__

f-DELETED - REPLACE BY---- ---__---____- /

O, 5.

_.13-- .-.62RP. .RAQt009-0"-_ _ _ --- - .. b_ - . ..... _ . - . - - , _-..-_ - -. - . . . . - _. .. _.

Em Aid.am sSe - um elub em giubsame - men magh egen est sum ett aus. ame esp tm emme eWh 9 D. esse seesages mes.nearumanca.D he.ense sagees. auesage esm..uas .me es=,.ee en e esos neue same s.ie eng. gapp gute ese af5*enum Duksame mas an. eas. asas suan - estsWD Eh

..se De .e em emps -eate.e tuerens emue gap. spa esp set suin . age usan assa sageusesm. esso amme esseg.e us.e.no esse gne ses aume oggo,e .ukame eeneasse eul. ese gumpgues wase-aims amps .es _ see eso esp sum. assa sale diin emps eak emit -adme up ass eum eut dmW 4

=Gk .* eminsist eies .e. eten me dumin tut. euh eineete .m> Bumsgaan same een esat hs. eene 34 sagtsagt ames suas .m. seen.mae ==use.=s-. Weesmonearmete u.atesese 6.mease w. eenomes ease meshesse amen stups mu. Elbe em.gue_em amm age- suae eutsuBB et. dmW 8W .'P *

,*-m

>U/ - - _ . - - __e_____-_______.____._ _.-______.. _.____- _ _ _ - _ - - _ . - _ - _ - - . ._--_---.

HNP-9

--.%._.,.--.- --w._ .., y. ,. . - . , . , . - . . . . _ _ . _ _ -

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

[

n

(._) PROCEDURE Leak __ Testing of Scaled Sources PROCEDURE TITLE HNP-8015 ._

PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . L________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANA g

5 Pages 1-2 & 4 ._f____._g@_________ -

p

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ____ _. __ _ _ ___ __. .__/f'

//f M_

" DELETED - REPLACE BY s .

_ _ _5. _ _ .. _ . 6_2._R_P _R_A_D_ .00_7_ _0_ _ _ _ _ _ _ ..__ _ _ _ _ _ . ________ __ .. _ ___

A _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

f 3 N_J O,

,v

) _ _ _ _ _ _ ..____________________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

HNP-9 k

r sr

[ t t

GEORGIA POWER CPMPANY HATCH NUCLEAR PLANT r

m. i V PROCEDURE

~~ Ghi ~~p, ment and Receint of Radioactive Material PROCEDURE TITLE

~~ ~

HNP-801G ~

PROCEDURE NUMBER Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-GAFETY RELATED ( )

APPROVED APPROVED REV, DESCRIPTION DEPT, GENERAL DATE MANAGER MANAGER 17 General Revision

[

/

_ m

_ _ _ .=_. r .,

),

/ '

m....v. ._ __[f _.5# /6~. h/A

.. 1_8__. P._aSe_s 1 .8.t _10._1.2. t _14. _ SI. C.

. . .a .- . . .

" DELETED -REPLACE BY _ ' . A4 g

e _ ...18. _ . 02RP. RAD.011.0"_______ _ N. ._ _ _ . . _ _ . . _ . _ ' .. . _ _ _ _ . . .. . . . .4/5/4C.

s

. . . . . __.____ _ _ _____ .______________ _ . _ _ _ _ . . _ _ _ _ . _ _ _ - _ _ _ _ . - - . . I s

V HNP -9 -

i i

GEORGIA POWER COMPANY j HATCH NUCLEAR PLANT i m.

(m ) PROCEDURE Plunt Fume Hood Velocity Measurement PROCEDURE TITLE HNP-8020 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

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

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

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 7 " DELETED - REPLACE d@$UEAGI BY 62HI-0CB-001-0" O 4

---..--------------------..--_--- -_ _= } <~

P) i x_- -----__---------_----_______.------------__--..-_-------_----_-..--_----.

_----------------_---- -----------_----+---_-------_----..--------

..-------------------_..--_-----_-------.4 - _ - _ - - _ - - - - - _ _ - - . . ---_----

--____e--------____----_------_---_---------+---------_--------------.

_+- - - - - - - - - - - - - - - - - _ - - -----_-----_----__-_--_---------_------__----

..----------------8 -----_-------------_-----

r

/

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

HNP-9

t GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

m\

U PROCEDURE Bioassay Samgling PROCEDURE TITLE HNP-8021 _.

PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-sal-t..tY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAG

' (.

6 Pages 1-5 & 7 g /

~----- ~ -- ~~ '~~~~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '

7' DELETED ~~lfEE5'CE 57~~ ~ ~~~ e~ M

- _ _ _6 _ _. ._ _0_2_R_P_ _RA_D_ - - - _0_1_3

- - _ _ _ . - 0 - - _', _ _ _W _ _ _ _ e_ _ _ _ .

gp _r5_. -

n f

e _ _ _ - - . .________--_________ .. _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ .. _ _ - _ _ _ - - _ _ _ _ _ _ - - . .-_______

(3 o)

+

HNP-9

-y. . _., ,,_--,...----r--. w

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT b

V PROCEDURE Envirnnmental and Personnel Tl.D Cross Clwr.k Program PROCEDURE TITLE HNP-8022 PROCEDURE NUMOER Lab RESPONSIDLE GECTION GAFETY RELATED ( X ) NON-GAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 8

Pages 1 -3, G QQ j '-

sf s .. .

" DELETED REPLACE.BY ~/) .

. . _ _ .8._ _ .63RP-RAD. 00L .0" __ _. ._ .

_/._ .. .

. . ._ .4. . _'_ _ _ _ _ _. . _ _ . _'___._ .M_N_ _ _ _

O

i. . . . _ _ . _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ . . _ _ . _ . _ _ _ . . _ _ _ _ . _ . _ _ _ . . _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ . . _ _ _ _ _ _ _ . .

G

_ . . _ a_______.______.__.__ _ . _ . _ _ _ . _ _ _ . _ . _ _ . . . _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ . .

.._.._.e. >.eb e_ .e._ .e. . .m ._ e -..s....-._.g. . . . .._*da _ ._ * *e e -

-.e._.

HNP-9

GEORGIA POWER COMPANY HATCH NUCl. EAR Pl. ANT i

n N

(j PROCEDURE In-Plant Rmliation f.evel MonitorinIl PROCEDURE TITLE HNP-8024 PROCEDURE NUMBER Lab RESPONSIBl.E SECTION sal-1-iY RELATED ( X ) NON-SAFETY RELATED ( )

. . _ _ _ _ .. . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ .. . _ _ _ _ _ _ _ _ _ _ _ _ _ . .____ _-_ _______a._ _____

APPROVED APPROVED REV. DESCRIPTION DEPT, GENERAL DATE MANAGER MANAGER 4 Page 4 -

a .

_. . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ . _ . _ _ %_.___ _ -u _c ._ _ . _ _o ,f . .

F e

./

. _5.. _ _ . ..P..a9 e...s. 1_ .a.. n.d 6. _ _ ... _ . .

.- _ f'_ . . -_ _stk..&-***

- l2 /$ 'NML

" DELETED - REPLACE BY d, .

,O,

\ /

.. _ _5_ _ _ ... 6_2._R_P_ _ RAD _.0.14. .. 0._"_ _ _ _ _ _ _. /._O._ _. .'.- _____.____._'_ _ .

v

>A

() . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . ___ _____ _____ . _ _ . . . _ . _ -

HNP '3

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

,n.

( )

(_/ PROCEDURE Radiation & Contamination Control of on Site Mobile Drveleaning Facility PROCEDURE TITLE HNP-8025 PROCEDURE NUMBER

- Lab RESPONSIBLE SECTION

, SAFETY RELATED (X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 3 " DELETED - REPLACE 47 /GW2~

BY 62RP-RAD-015-0"

..--------------------... ----- ------- . [{}' .

4 AL,JLC.

a

G, ---- --..--------------------------------------..--------------- .---------

LJ (m_-) ------..--------------------...---------------. .---------------- +-------.

MM'M---M--M---M-------- m---------------Mov--------------MM f----M---

HNP-9

r GEORGIA POWER COMPANY HATCH Nt.tCLEAR PLANT n

( v )' PROCEDlJRE Hi_qh Rad.i_alj;nn Area Eni rance Control PROCEDlJRE TITLE 11NP-802G PROCEDlJRE NtJMBER I. a b RESPONSIDLE SECTION GAFETY RELATED ( X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV DESCRIPTION DEPT GENERAL DATE MANAGER MANAGER

~

G Pages 1, 3-5 fx 7-9 f

t. . . . . .G .

. h_ _ _ ._ . /._ _ ._ _dn._ .... s_ .. /._/.a_ /" .

'))lht s.em . . _M f ff

. _7_ _ .. .P_a. g.e._s1.. _2_.and_ 8_.10 _. _

. [..(/_M. .. ..' . . y.e . _ . . __ .

" DELETED - REPLACE BY _f.-.

A n I

.. L _ _ . . 62RP- RAD.-01G-0.,, _ _.. _ .. ..IU^ . . _ _ - _ . _ . . _ _ _ _ . . _ . _ _ . . . $' f.f.-

\

v/ . . _ _ _ . . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ . . . . _ _ . . . _ _ _ _ . _ _ _ _ _ . . _ _ _ _ . _ . _ . _ . . . _ _ _ ...._ ____

+ . ,

L g(D

/

\u!

HNP-9 s

N

GEORGIA pot 4ER COMPANY 11ATCH NtJCLEAR PLANT

/m v) PROCFDl)RE Plant Gite Curve _.v.

PROCEDURE TITIE

._f_INP -8__029 PROCEDURE NtJMl3ER Lab _

REGPONDIl3LE SECTION GAFETY RELATED ( X ) NON-DAFETY RELATED ( )

APPROVED APPROVED REW DESCRIPTION DEPT, GENERAL DATE MANAGER MANAGER 3 "n es e-a n s O g....a. .- ... G. ,g._ .. g.g, e y pg.

.,. .~. ~ .

._._3..... _6. W._ .RA.. D. . 0. 18.. _0_"._ . _ _ _ _ . _ _b. . .

.._.j c_ .. .._.. ...._ _ g/g. ..g..s. .

m

, s . . _ . ___ _ _ . . . _ _ . _ _ _ . _ _ . _ . _ . . _ _ . . . . _ _ . _ . . . _ _ . _ . . _ . _ . _ . _ . _ . . _ _ . . _ . _ . . _ . . _ _ . _ _ _ .

i N. j

.g.._.g..e.g e.eg.m_.. _.e .g .g ... .e..e .e.eg.gm.. .gp.gg. g ..e. . ._.e. . e . . . = . .

.._._.D. _ _ ..._.e.__.e.__.__.-.g.. . .- -s . . . . . ..e...e. ._ . . . . . . _ .s . _ _ . _ .

.._ _.i ..e..__.___.._ .e...p ... e+..-i .* * . = .g... .. .e... .e. ..- .g..e ,_. .e e . . . .

.b . . . ....e.e.a .e..-e._..-..me .e......i.- a.. - . . .. .... . ..

I INP -9

GEORGIA POWER COMPANY

,m HATCH NUCLEAR PLANT

.: 1 L/ PROCEDURE Health Physics Start-Up Surveillance PROCEDURE TITLE HNP-8030 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_ _ _ _ _ _ .._____-_________-____ --_____________-- p________________. . _ _ _ _--.

1 " DELETED _ REPLACE dP <AOW8 BY 62RP-RAD-019-0" h

_ - _ _ _ _ .. _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . _--__ - __ __ _ ___5 _, _ _ _ _ _ _ _ _ _ _ _ _ .

p~s - _ _ _ _ _ .. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . p__-________-____- - - _ _ _ _ - _ .

t i -

ss

- _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ r________________. _______.

______.. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .r________________..____-__.

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r_______-________. _______.

l I

I r

I f~ -____--___________-_-______.- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . .

t

\._

l l

HNP-9 t

\.

GEORGIA POWER CONPANY llATCil NUCLEAR PLANT A

I i v PROCEDURE

_ ___ ________G.u.a.n t i t a t i v e F_ i t T e s t i n <1____________

~ ~~

iNP-nona ~ ~~~~

PROCEDi}RE NUMUER Lab _ ._ __ ____ _

RESPONGIDLE DECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X )

APPROVFD APPROVED REV. DESCRIPTION DEPT. GENERAL DATE M/$ NAGER MANAGER

~ /*' '

U.) g ,.___--_.._p.._

2 General Revisinn .

p,g,.. yA gf

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

/

" DELETED - REPLACE BY h . , . . .d. AQ I 2__

. 6. 2 R..P.. .BA. D. _02.0_-Q"._ _ _ _

_ /.Gl.,. '.

_44/tf q ._ ___ ______ __ . _ _ __ _.. __ __________ ___ __ _______ _ _ _ _ _ _ _ .

b -__ __ . _________ __ ____ ______ ________ ______ ________ _ _ _ _ _ _ _ . .

( .__ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . _ __ _ ._ _ ____ _ _ _ _ - _ _ . _ _ . _ _ _ _ .

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

/_$

I

' ._/ PROCEDURE

--- Contaminated Tool Issuance and ReturD

- - - - - =

PROCEDURE TITLE

~ ~~~~ HNP-8034 ~~~~~~~~~~~~~~~~

PROC 5 DURE NUMBER

~~~~~~~~~~~~ Lab ~~~~ ~~~~~~~~

RESPONSIBLE SECTION

, SAFETY RELATED ( X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAC:R 2

Pages 1 thru 2

. _ - _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ - ... _ _ - _ _ . _ i

q 66.g

_____4____ , jf f_

" DELETED - REPLACE DY A *

- - .2. _ _ . Ji2R2_RAR2 02 L-E_- _ _ _-. .. 6. . . _-__ _ _ .. _ -. .

(<,-)

~- j

. . . - - _ -.__ ___________-____ ___-_-__________ ~________________ .-____...

ns ;

v HNP-9

\

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT 7 ,

m, / PROCEDURE Waste Classification and Manifest Reporting Resin Shigments PROCEDURE TITLE HNP-8036 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANArER O New Procedure -

. . - _ . - _ _ . _ . - _ _ _ _ _ - . - - _ - _ - _ _ _ _ _ . - _- - - _ _ - - _ - . _ _ . . _ _W - . - - _ . . _ _ . / } _ -_

1 Pages 2 3, 6, & 8

, O _ff_g___

g.

(n , ?

(._,) 2 -Pa g e. s..1- .s '3 and 9 /d, ' d,1 - A dh40 4'

" DELETED - REPLACE BY A

bg / '

, '-9 / . f[2%Y i>vik

- - - _2 _ _ . . _ _6 2_R_P --- - RAD _02 3_- 0_"_ _ -- _ _ .

. _ _ _ _ - - - - - - - _ _ _ _M

_ _ _ _ _ ' - - _ - _ _ _ ~ _ .M_ _ . . _//S..

o ___-__ ______-______-__ ___ _ _ _ - _ _ _ . - _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._______.

s

) -

s._ /

. . . = .-be,m.==.=.--==. _ _ . - . - - . .. - - = = = = . = = = . - . - = = . = . - -

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Waste Classification and Manifest Reporting OAW (Comgacted and Non-Comgacted Trashl PROCEDURE TITLE HNP-8037 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

_ _ _ _ - _ . .._.-__.G.-_-__________m-. __-__---____-___.. - . _ _ _ _ - _ _ _ _ _ _ _ - - - ..--___--_.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANA ER 0 New Procedure h '

g /u, , j j (N

__ _1_ _ _ P_a_ge._s._ _1._4 > 6- 10,14-15&l7

" DELETED

- REPLACE BY h -

[ 43*f-

,,,, f

~

/5/7._8.

A 51Mk 4_

~)

i 1 - -62RP-RAD

- .- - - - - .0. 2.4.- .0. . "- - - - - _ - . -. -.--- ----- -.

. .-------------------- . . - - - - - - - - - - - _ - - - . . . - - - - - - - - - - - - - - - .._ - - - - - -o-

_ _ - - - - . ________-.____.___-_- -e____-._____.__--._. . _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ - . , _ _ _ . _ . - _ _ _

\, WGM eh auge GW SWh. . $mh gge g gm egegutgaygm tule op .ge - ene gag gge e $m umb 093eaua...e5 em een ees REDGule embem een es eau cum - - .4page -est esseegD emme timiusuum gambe4IS eSD em Elue - 959- e em . g .ee ge espOWD $9. ens D i

)

1

/

m- aos em ee. e em. .===em esso e- een eeneen een en- em ao suo one em os. een een en esa son - .eene em e- ==am .m* *m .e mee ese == s- == ese ome es. . . eum m esese . same - e- ene een ame ame em= eum em een .em een ee. e- am een mee eu.

HNP-9 1

l l

6 l

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

'.s' PROCEDURE Waste Classification And Manifest Reporting All Tyge Waste PROCEDURE TITLE HNP-8038 PROCEDURE NUMBER Lab RESPONSIBLE SECTION

. SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

,_--- ., - _ _ _ - _ - _ _ _ _ _ - _ - _ - - - - .r_-____----.___-__.. _ - - - _ - _ _ _ _ _ _ _ _ - - . .________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANACER /

y-..--

O New Procedure - 1

%,. ---M ,,- - -

- -- { X -- G ,L

/1 1 Pag I(/ . -

~ ' <f^ #~~~ [#

^ ~ ~ )~ ~

4 #7 5

)M

- ~ ~

5M

~

mrDM_es 1-13 and 16 ~ ~ ~ ~ ME/ 5 ~ ~ ~

ED - RE V ~~~h ~' a/#5-1 62RP-RAD-Q25-D" -

/

I - _ - - - - = ' = 46- - - - - - - - - - - - - - - - - - - =h.- - - - - - - - _ _ - - - - - -.i.---------------_a*-_-----8

.N /

v

-WED- 46--..em - -tm - - - - - -em -gen- - -see- - -.bem egn - - - - em - em am am - em em - $um ='. - m - _ GWe emp_44--gup>-m-_-.h.OED - - WW---#

HNP-9 9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

.f k PROCEDURE Warte CJaniFication And Manifest Reporting Re cir rM ati on Sptem Pini.ng PROCEDURE TITLE HNP-8039 PROCEDURE NUMDER I ab RESPONSIBLE SECTION

, SAFETY REl..ATFD ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER b Si b Pr c d > g

_ _ _ . _ , _...-p.-__-._.__. # .. .. $

" DELETED - REPLACE BY . -

_ _0_ _ _ 62RE RAD-026_.0_"______ _ .___ . _

._.__._ .___._ _. __._ _._.__. //_N_/f.. _r.

\

] ______ ..____________________ ______ ___._____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _

l

__ ._._._._.__._em _m.. _ _ . _ _.qm.g_.u ._.__.el e.u._ eim _ e _ . _ . _ . _ - .___8__EO' HNP-9 h

I g .

-_____-.__._M

C_. e_n_pC

.. . T .A. .An_l.a.ir. p.. e_ n_M. .P.A..hlV.

m HATCH bH 'c' ran PI AhlT P.o.n_c__- ene _ o. .r Maintenance and Operation of Portable High Efficiency p a_ n. +. 4_ r_ s_e l. m_ +

m A. +m. . . n_ e. n. h. . a_ n. of. l.J.r_P A. ).

r. J 1 + p m_ + 4.

n n. . l_in. . J. +_ e_

.P.R. n_ c_ __ e nt_lR..r_ . T. _T Tl r_

u. .n. ip _anA. n_

P.o.n_e_ rni_n. .a_ .hu_iM.n

_ . . _ . . c_o.

Leb

.A.pc_A.

_. n_h. lc_ _T

. __ Al e C_ec_T._ T_n_h.

. l c_arETv.

. o.m__.A.T. _rn r.

y .>

.. bin _w_c_.A.rr_T. v .o._m_.A.T. _rn i.

s

.A.P.. A.p

. n_ U. r_ n_ .A.P. .PR.n_U.

. _ rn p r U. .

.._ ne_c_ c_ o.

_. . ._T p T _i n_h. i. ne_pT.

C_ r_hirpa.i._

_ . . _ . . . n.A.v. r_

M.Ahl.a.C_ r_p..

.. . M A_ht.A.C_

. . e_.n.

'y, p a n e_- e- - 1 . +-h n. .- --tc

./g 1

._a g(gs-c 9pg A.*

L; .

_ f f_.7 M

g " DELETED - REPLACE BY f),,g. / ! '* . .

e q _ _ _L _ _ ..__ M _0.CB_-DQP.R"______.. 5 W_ _ _ _ _ _ _ _ _ , _______ _ __ ___. .f//6./@_~_ .

0 ______ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ .________ _ _-_.

u..w.o - o.

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT n ;

'w./ PROCEDURE Leak Testing of Respirators Using the Dynatech 3G2R Test Syst'em PROCEDURE TITLE HNP-8041 PROCEDURE NUMBER Lab' RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X)

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 0

New Procedure -

./- -. .

, /g.cu <

/ g gg gg

" DELETED - REPLACE BY '

---Q -- . .-

I - l an -------. . ----- - - - - . - - - - .

./ '\

k (n

t w

..w.---.-.--.-----.. ---- . -------..- - ---- --- ..--.---.--e.

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

,n

') PROCEDURE

\/

Radiological Work Practices PROCEDURE TITLE HNP-8042 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) .

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER i ,

/

O New Procedure

" DELETED - REPLACE BY h

/\

i

[- .

g g/

M-. .. .

- _ _ .Q _ _ .. 52.R_P .[taQ _027-Q"__ _____. . _K_ _ _ . _ _ _ _ _ _L- _ .

t

. Q )i ------. .----_-------------- . .----------------. .---_---------------------

t~,

\

HNP-9

GEORGIA POWER COMPANY

. /..

HATCH NUCLEAR PLANT

.n PROCEDURE Process Control Program (PCP) for Liguid Waste Solidification PROCEDURE TITLE HNP-8043 PROCEDURE NUMGER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGE 0 New Procedure ., q gg

~

--~~~~ ~ ~ ~ ~ ^ ~ ' ~ ~

Ntilifo TiifR~Act BY~~ '

~~~~ ~~~~~',~~~~~ -

. _ _0_ _ - .. 6_2_RP-R_AD -- -- _ _028_ _0"

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

_y ~~'~~

,_____._ -_----- . g/g//_ /_ - _~.

/ s t i 4 /

v

<s 1 t e HNP-9

r GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

's

') PROCEDURE s ,

a

_Ogeration of the Bartlett Nuclear Mixing __ Unit PROCEDURE TITLE HNP-8044 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

AFRRQVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANA ER

..--------------------..-------------- /

O New Procedure

-___--..--___-_____-______--.. - _ _ - .hQg -

g g j

" DELETED -REPLACE BY b I

--M/I--

-- D--.. 62RL .0CB 003=0"-------..1---- ------- , -- ---- - - - .

,m i, \, ------..--------------------. .----------------..----------------..--------

v o

ni

(_

\

, = = - - - - ..------------------- d.--------------- d-HNP-9

s, . ._

GEORGIA POWER COMPANY HATCH NUCl.. EAR PLANT

n V') PROCEDURE Protective Clothing Regitirements for Ogeratin_q Machinery in Hot Machine Ghng PROCEDURE TITLE HNP-8045 PROCEDURE NUMBER Lab RESPONSIBLE SECTION GAH: .iY REl.ATED ( X ) NON-SAH- I Y RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT GENERAL DATE g MANAGER, MANAGER O New Proceditre -

_ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _C. ./_

._____._.__.__7.__.V ._./._M._ _ _/_

._ _ 1 ..p. age _3. _ .__._._._. _____ . e'A-!_ _ . . _ '. . _ . . /. . . _ _ _ _ . _ . ._/)f' j'/._

" DELETED - REPLACE BY . 8

,r xi ..__l__. . 62.82_R. AD_-02.9 0..n Q

___J o

V . . _ _ . _ _ . _ . _ _ _ _ _ _ _ . _ _ . - . _ . _ _ _ _ . _ . _ _ . _ . . _ _ . _ _ _ . _ _ . _ . _ _ _ . _ _ _ _ _ . . _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ . .

HNP-9

s GEORGIA POWER CONPANY HATCH NUCLEAR PLANT O

V- PROCEDURE Stirvev u Freguency and Work Scheduling PROCEDURE TITLE HNP-ROSO PROCEDURE NUMDER Lab RESPONSIBLE GECTION SAFETY RELATED ( ) NON-GAFETY RELATED ( X )

APPROVED APPROVED REV, DESCRIPTION DEPT GENERAL DATE MANAGER MANAGER 22 Pages 1 thru la /

,/..___ __

. . . _ . _ _7_7_r _.g_ppy ._

. ._ .13_ ,,, ,_ .

.."PaEes

[M . _ _ _ _.. _ M s _. ._ .1% . _ _ _ _ _ . _t _: /f/ ((__ /;8 DE ETED -1_thru .18. BY . . .__._./

p REPLACE . g '

Q 13

_ . _ _ _ . _ _6 2 R_P._ R.AD 0_3_0_- 0. " ._ ._/..d._-

J

/_._.._._.__. _ _ . _ . _ . _ . . -

%._)

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

(

n ).

\_) PROCEDURE Portable Ion Chamber PIC-6A Operation & Calibration PROCEDURE TITLE HNP-8100 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )

.---------=_ - - - ..-------- =___ .

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 7 " DELETED - REPLACE E 4Ed@'

BY 62HI-0CB-004-O" <Y ~

__ --= ==---___- -

_ _ _ - - .. .2 _-_ _ __--. W t

! ,)

\_/ . _ .

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

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

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

..-. --- -----==___- - _ _ _-- _ _ _ _- _

.---------------------..----------------..-----== . -

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

--_---.. - - - =_____-____-_-_-__-____ -_-_-_-_ --.._------.

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

e

-s g - - - _ _ - ..-------_--_--_------..___--_--___--____.______---------_..--_-____

t s N/

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

.g.

i s x/ PROCEDURE Teletector Model 61129/D Ogeration and Calibration PROCEDURE TITLE HNP-8101 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAG--

7

_...-_e_ne_ral G Revis_ ion------- --------. .-----Od h- ----d,.1 m - - - - M- gr - - - / - -- ---

8 Pages 4-5 & 9 k[0 .- fb ' - '-4 dis- j- .

ff-..

" DELETED - REPLACE BY e -

/_)

n L

=

\j d 4

rr x, L_) ------..--------------------.- - - - - - - - - - - - - - - - - . ---------------- :--------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT g a

.t ,

N/ PROCEDURE Count Rate Meter PRM-4A' Operation and Calibration PROCEDURE TITLE HNP-8102 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

-- -.r-------_-_-----_----.. _ _ - - - - - _ _ _ - - - - - _ . . _ - - - - - _ _ _ - - - - ---

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_a._--------_----__----. .---__-----_---- .. _ _ _ _ _ - - _ - _ _ _ _ - - _ .--_

7 " DELETED - REPLACE udddf_-_.

BY 62HI-0CB-006-O" MO -

- -= +-- _=-------..---- - - -

-, - _---* - M- ..f 5 l

t

,a _--

s v/ - - - - - ..--- -_

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

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

_ _ = = = -

. _ = - _ - -

._--- = ---

=--------..-------.

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

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

= = = = - ------- .------..---------------- -----

-m f

s -----_..-----_-----_______-_.. _ - _ _ _ _ - - _ _ - - _ _ - - .. _ _ _ - - - - - - - - - - _ - _ _ .- - - - _ - - - .

HNP-9

/

c_ r__n_.o.r a I A P. nu. .r.n. _.

e_ n_g.n.. a.ra.y I..IATFH. b!.! frLr_n^ q Pl_Abl.T.

,m

( ) pp.n_e__r_ DUD..F_.

s A. 1 Portable Neutron Rem Counter PNR-4

'Oraration and Calibrati~on P.A.DCE-D.i IRE _ T. ITI _F_

Hb!P-9103 PP.n._CrDLiRr bfi mIMB. r.R Lab p.r._e_:p nn.iq T DI.F_

. . _ _ cEPTIOP4 a -

9AFETY RELATED ( ) BON-SAF Y APPROVED APPROVED p r_ u. .

n e_ g r p T A. T. I O. bf.

. _ .._ . D.P_P. T. GEIsERAL DATE MANAGER MANAGER 7

P g s 1,3 4 & 7

._a__e_________________. ._A_~ () .. . . . _

___ . _ _ _ ../_/ _5 f._f_-;- //;/g1 Pages 1 5 and 7 8 .j/_

8 [ _ _ _ _ _ _ . _gs* . _ .56 _ .. E._z

_ _ _ _ _ _ - _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . __ ., . _ _ _f_5

- " DELETED - REPLACE BY -7 .

's' 8 62HI-0CB-007-0" lO _f/'#/gjs

\s

.____ ~ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ . - - _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . .._---_ __

._____a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ _ _____ _ _________________. _ _ _ _ _ . _ _ _

, _ _ _ _ .a __________________a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . ______.

.____a ________________.; _ _____ ________ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . ._______.

.._-___.: ________________.i _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .. ____ __

'\

\

>.v I

. _ _ _ _ _ _ .___________________q _____._ . __..___ . _ _ _ _ . _ _ _ _ _ _ _ . _ ..________

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

!s\

V PROCEDURE Fast-Slow Neutron Counter Model PNC-4 Operation and Calibration PROCEDURE TITLE HNP-8104 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..___________ __3 _____ _ _ _ .

.________p

__ 6 _ _ Page _ _ ..1, _ _3-5, _ _ _7-8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ [____ _

_ ..jg

_______g _ g, _ _ _y_ - y _/ _J

-~~~~~

7 Pages 1-5 and 7-8

~ ~ ~~

/g ~ -

/gm g- .

g 7y g fg

~~~~~[~~7~ ~M

~

(")

7'i){((TED$~~REEECE hE~~~ /

'~~[~03[ _M_ _ a__

V ..gd8_

_ _1_ _ _ _._62til-OfB _nos-aa _ y _ ____ _ _ _ _ _ _ -

.________________+ ________________-.________

.________________( _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _.________

t l

. i n. ______-. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

!V l

HNP-9 l

r i

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

-s

( )

C/ PROCEDURE Gas Proportional Alpha Counter PAC-4G Operation And Calibration PROCEDURE TITLE HNP-8105 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

,7;(

5 Pages 1-4, G&9 g/.

,t ._ . ._

g- 7_g . g- 'g

_T _ _f_ _ _ . M

" DELETED - REPLACE BY / /

I

- - _5_ _ _ . . 6_2_H_I _0_C..B_- 0 0_9_-p_" ~ _ _ _ _ _.

_ _ (M __' . ...- _ - _ - _ _ _ _ _ . # _#_ -

j

,~

\

(G --____ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..______ -

(3v)

HNP-9

GEORGIA POWER COMPANY m

HATCH NUCLEAR PLANT

[V \

PROCEDURE Mini-Scaler Model MS-2 PROCEDURE TITLE HNP-8106 PROCEDURE NUMBER Lab-RESPONSI LE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- _ _ _ _ - .u__--------______-___.. - - _ _ _ _ _ _ - _ - - - _ - _ .._____----_----_-..-__--_-

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 6 ,Pages 1-5 and 7 g-/g

& A _5 7 fl

. . - - - _ - - - _ _ _ _ - _ _ _ - - - - - . t_ _

-_@ _ . d _u_ _ _gvf_. _

" DELETED - REPLACE BY 6

- - - - - - . . --62H - - _I--- 0C.B - Q1.Q .0 " ------ .. _ _N- W---_'/' ,. - ----- ------_.

[- dif ///_#T-O (v s - _ - - - _ ..--------------_-----. .---_------------. ..---------------. .-------.

A, ----__. .__----_-_-__---_--_-..-__-------__--_-..--__-----_-_----..------__

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

./ PROCEDURE Geiger Counter E-400 Ogeration and Calibration PROCEDURE TITLE HNP-8107 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________.p________.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 9

6 Pages 1-4-& 6 y

_ _ _ _ _ _ .. _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _7 g.,_ _

g.

" DELETED - REPLACE BY .- . ,

___f__.. _ $ 2ill .0f B-D11_-Q"_ _ _ _ _ _ _ ..ttM_ _ _ _ _ _,._______ _ _ _ _ _ ..6./_# W- __

,.s_

/

n r l.u_./>

HNP-9

y.

T GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

,~

/\

U PROCEDURE Pocket Dosimeter Use and Performance Test PROCEDURE TITLE HNP-8108 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

______..____________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ .._______e.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._____________ _..____ __________..________ PA'c 8 Pages 1-4 and 8

/ /- J6

- _ _ _ - _ _ _ _d_19 / _. . _// /

"D2LETED - REPLACE BY

_ It g .

___ E_ _ _._ .

. n.

g. .

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______________.e- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

_ _ _ _ _ _ ..____________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..ae_______________..________

p _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

y _ _ e.m aus aus _ .. en eso _ es aus am _ en _ an em _ == em me amm _ ao _ _ .._____umeinen==_====.m_e.m_.. em a.o _ _ ano _ sus ao se == an en _ an em _ ..____me__am l

HNP-9 l

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

, j PROCEDURE Victoreen Condenser R-Meter Model 570 Operation & Calibration PROCEDURE TITLE HNP-8110 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

--____.- . . - _ _ - - _ - _ - _ _ _ - - _ _ _ - _ .. _ _ _ _ - _ _ - - _ _ _ _ _ _ - + _ - _ _ - - - - - --__ __-.. _ - - _ _ _ _ .

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

-__-_---_--_--__--_-______-.____-_____--_-__-+ - _ - _ _ _ - - _ - _ _ _ _ - - . . _ _ - _ - _

5 DELETED - REPLACE #-

BY 62HI-OCB-014-0"

/]

t m- _-- _ _ _ - - _ _ _ _

~

7 ff j p____

m N'w)/

--- _ _ ..=_

__.-__--_-____-__-_-+_-_---__--_---__..-_-_----

___ _ _ _ ..______- _ _ _ .._----__--_=-

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

-_--_-.----_-_-___-=

/ \ g

( s/

_-..--_-_--___-=__-_---_.--___-____-__-___-- - - - _ _ - _ _ _ - _ _ = _ _ _ --_____---

-_---_dP-_-_-_-----_-__---__ m______m-_-------->-_----_---____--->_-___--m' HNP-9

GEORGI A pot 4ER COMPANY HATCH NtJCLEAR PLANT im

\. PROCEDlJRE ARM Portable Calibration IJnit PROCEDlJRE TITLE HNP-Rill PROCEDtJRE NUMDER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV, DESCRIPTION DEPT. . GENERAL DATE MANAGER MANAGER vg .

5 Pages 1 and 72 y /y .

- j g f,.y 4 g.

- - - - - - - - - _ - - - -- ,g- v wggg g3-- gg g g 93----

.__5..._._. . 6.2. .H.. .I _0_C._B_- _- ._0_"._ 01_5 _ _ _ _ _ _.

-{. . _W" '-- --- _-

' . ./._ _ _ _ _ _ . _ _ . _ - . 6*//.</FJ

( .

s _ _ _ . _ . .______.__________ __ . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ . _ _ _ _ . . ._._ _ _ _ _ _

v)

HNP-9

_ , , - - , - _,_- y_,_ _ - - - ,, -

GEORGIA POWER. COMPANY HATCH NUCLEAR PLANT (v ) PROCEDURE Radiation Monitor RM-14 Operation and Calibration PROCEDURE TITLE HNP-8114 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAM:.1Y RELATED ( )

______+____________ ___ _.._ ____ _______ _.. __.________ ____..________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 11 Pages 1-5 & 7 g-g~ f f

~~ j ~~ 2fgg i g, . .

,g,g[

~~ ~~ ~ ~- ~ ~ ~

irDELifED~E~liEPLACEBY'~~ /" .

_ _ 11_ _ ..6.2131._0fB-016.0_"_ __ __-.A_d__ j _ _ _ _ _ _ . _ _ _ _ _ _ _ . 4 #_ M___ _

, s _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._______

t i

%.J

[ %g

/

{ 'I. - . ._ ___ .. _ . , . _ _ .._

%J HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT (a ,/\

s PROCEDURE Gamma Calibrator Op_eration And Calibration PROCEDLIRE TITLE HNP-8115-PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFFTY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT., GENERAL DATE MANAGER MANAGER RG 5

General Revision

" DELETED - REPLACE BY

[Q g/ - ..-.---

.-y ff g g 5

- - - - - - . . -62HI-0C

- - - - - -. B 01. 7. 0. "- - .- - -- - ..-b

. --- ------ g # ff---

~.s

/

4 f,

V e- --------------. .----------------..--------

HNP-9

GEORGIA POWER COMPANY m

HATCH NUCLEAR PLANT

/ \

(_) PROCEDURE Mini Pulser M0 del MP-1 Operation & Calibration PROCEDURE TITLE HNP-8116 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )

e-m---<

m-m-mm--m---m-ihmm---------mm----' ------m-m----m---* = m--m m m m e .

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

+- __ _ _

h---------

+----------------r----------------..--m----.

4 DELETED - REPLACE fj$'sG27 BY 62HI-0CB-018-0" b -df -

V#fS .

, N

^

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

, ---- - --m. --

O _ -- W M s -m-----m----MM-mmMMW4 MM----m-mm---Wm-+5mm-- _--MM--M-e - e m - M - M.

/%

\

=

-+--m-- -

+--m---------..---+---- - --

___-__. - - - - __--_---_____ + _ _ _ _ _ _ - - - _ _ _ _ - - - . -_-______--____--..__---__.

e.. - - - - . _ - _ - - - m__e- e

.Hm -G-- _

.s- -e_ G.msh_ --m m m m m..

.------- - - - - - - - - - - - - - - - - - - - - -r--== ___ _r = = - m - - ------------m--m---.m-------.'

6m-mM-d> = - - - - ' -_ _ _ _ ----W-_____-' sk-m---m- _

H-m-r--_-- _

-_--.-.-_ mMM-mM-m.p 4

% em.e ese-em -=em.___ - -- : _ maue.m - en e.m en a.m .me um em .nm .e == .m = une em e.e e e en e. mam = e e e m e.a n--> e- een em se - ums - e.m me = - ann en am m.m amm --me_-_- - ---

6*e-M-=p-" ' - - - - - __ __ em W - - M M M -M *>* M M m M - M M ---- em W - M - ahe.Se----_--------- ___

M em-

===----. - - - - - - - - - - - - - - - - - - - - .=---------m-m----.-= _ _ _

. -= - - - - - - - - .= - - -

emmmmmmmmm-- --m- - m- mem m mm-mmu m-mmm- __ _ _nn_mme-->mmeggememgemmmm-mm-M-hM-->

4-m--- --

=-MM--W-WW---*=h---mm----MMM---am--mm---mm-----m-.m--mmM-Mm' W--MM-am-_ _-_N___-- - - -_u m----hh---MMM--m-** M W M m m M--m m h m W M M M - *--M-MMMm

'4---Mm-m-m-M-----M-M--------mmm--mm--m------- wh-m-mm-m-----@+m- ==-MM--MM 6- _-eaM----- _.- - - - = = = - M GS M - M M-'=- m M - M M - - M M M - em - - -am-G.e-------- _ ___--- - - - -

_ T -""'Sh m m W - G.# - .'

o r----------====. - ---. .--= _ = - - - - - - ...---------------- --------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE f)')

s.

Geiger Counter Model E-120 Operation and Calibration PROCEDURE TITLE HNP-8120 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 5 Pages 1-4 and 6 A pf I ~

g,__

.y.22 _ _i _-

__g. _ _ _ _ _ _ . ._ W/4%

_ _ _ _ _ _ ..yDE E__ -

- _ _ _5_ _ . . _ _6_2_H I _0_C_B_- 0_1_9_- 0_" _ _ _ _ __ __..___[_d__'

______ _ _ _ ' _g/g_/_rf__ ___.

C

( -_____.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________

l P

i r

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . L________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .________

f L

\

O I \

1 - _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

i l

t HNP-9 1

i

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

(_) PROCEDURE Portable Scaler Model PS-1 PROCEDURE TITLE a-s HNP_8121 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- _ _ + _ _ - - - _ - _ _ _ _ _ _ _ _ _ -. - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ + - _ _ _ _ _ _ -

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

-________________--___-____ p_________________ ___--___________ +_

3 DELETED - REPLACE k ' W__

f BY 62HI-OCB-020-O" IA f // /g f

-_____.-_________________---.p_ , W O_L_ _ _ _ _ _ _4 ,-

, -_____.- _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ . p-____---________. . _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ .-_ _ _ _ _ _ _ _

/ h i I kJ ______.._________-___-______ p_________________ .__________-_____ p________

____--..____________________ p___________-____.. _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ .p_____-_.

-_____..--_- _ _ _ = =- -__________ _

p_________ ____.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________

___ . - ______ p______- -______________________. p_______.

--____.._______________ ___ p_____-___-_______ . _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ .---_____.

______..______-__=__________ p__________________ _ _ _ _ _ _ _ _ _ - _ - - _ _ .-________

--___-8"-_____--6______6__-- f__M_M-_____-____..--______W_______"-______MS O___M_88_=- _-___________

-Z_.

______________-_mm________ __-__ -_______m

- - - - - _ ..____________________+ - _ - _ - _ _ _ _ _ = _ _ _ _ _ .- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -_______.

--- _ _ _ .._______--___________ h_-_-___-________.. - _ _ _ _ - _ _ _ _ _ - - _ _ _ .-_-_____-

-___ _ _ .-__-____-___-________ -_-_______-__-_-- .- - _ _ _ _ ~ _ _ _ _ _ - - _ _ .- _ _ - _ _ - _ .

4

[ '%.

j % -_m__m.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -_-_______-____-_.._ _ _ _ - _ _ _ _ _ _ _ _ - _ -w___---_m

( i

'.s/

-__ _ _ _ -.___m_____=___--__-__. .w_______-____-_u._-____--_______m.--_____m.

HNP-9

j.

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

( PROCEDURE G)

Regulated Air Sampler Model RAS-1 Operation and Calibration PROCEDURE TITLE HNP-8128 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY HELATED ( X)

F________________. .________________..________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER g

_ _ ' _ g_- [

2 Pages 1 and 2 ;

_g_ /p ,y//

..,,DEEETED__TEPEKCrBY__. p --

_ _ _ _2_ _ .. _ _6_2 H_I_ _0_C_B _0_2_4_ _0 "_ _ _ _ _ /JA _ _ .. _ _ ,__=_=:__

/~

( _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .________________q .________

_ _ _ _ _ _ -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________. .________________a .________

______a. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

______- .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________a . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________s. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.________

f. ~'\ . . _

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT (j PROCEDURE Portable Ion Chamber Model RO-3A Operation & Calibration PROCEDURE TITLE HNP_8129 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X)

APPROUED APPROUED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

- _ _ - - - -- - - =

1 " DELETED - REPLACE BY 62HI-OCB-025-O"

-_____ / f_ff..

=- _ - - - _ _ - - - _ _ _ ..____--

______--4

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

- - - - = - _ .. - _ _ _ _ _ _ _ - _ _ _ - _ _ _ .. _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ ._ _.,

f 1

= - - _ _ _ _ _ ..-___-----_-----_.. _ _ _ _ _ _ _ - - _ _ _ _ _ - - .. - - _ _ _ _ _ -

= - - - -

m.

\,

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

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

HNP-9

GEORGIA POWER COMPANY e HATCH NUCLEAR PLANT

/ \i l

V PROCEDURE Robbins Air Purification System PROCEDURE TITLE HNP-8130 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED (X)

-_---_-----------___.- - - _ - - - - - _ _ _ _ _ _ _ _ = .=- . _ _ _ _--..-_=

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 1 " DELETED - REPLACE ' M----

BY 62HI-OCB-026-O" -

'(

s v)'. -- .---__-

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

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

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

- - - - - _ .. - - - -- =-___ = = = - - -- - - - - - - - . _-_____ .---- -_ .

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

--- .---=-

- - - - _ _ - =

w----------------.-------..

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

---__-..=

- - - _ _ - ..-- ----___ . = = _ - -

- - _ _ - .._=____- --___--_---_-.. _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ ..-_-_--_--___-____ .--_-_-_ .

- - - = = _ - - _ - _ - _ _ _ _ ..-________---____. _-_----- --

(R) v HNP-9 e- -,.-w-y-

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT (ss-) PROCEDURE Underwater Hi Range Survey Meter Operation & Calibration PROCEDURE TITLE HNP-8132 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X)

APPROUED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_ = _ _

_ - .s _ _

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

~2 " DELETED - REPLACE T/ -N

I BY 62HI-0CB-027-0" -

jf g M---.------ ------ , __ _

n

.; y ------..---M---------_------.._-------------- ..-MM __ -._ _ _ _ _ - - .

u)

-- =. . - - _ _ _-- ____---- --

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

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

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

=__.

_ =-.- -- -

.M------=-- _M-..__------

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

--M--- _ - _ _ _

==- _ - - -

-M---- ----

=-- _=---. _

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

-MM--M.--MMM-W---em--' - - - -.____M.. - - - ----

m-M- __ _ - - - ..-_-mm---mm .--- ._e.

---MM-= WM-M-M __--M-M---mM--eaM-- _---------____zm_m.e---2-- _ - _ - - -

__-mMM--e =--M-M-Mp 6-MMM- --

M-M---- =6 M- =_ _

-- m m- M -- ---mhW--M-h-M.---M--mmp

-MM--M* --- ---M--

-..-6------_M---MM-d e--M-----MM-MMM-M.=-WM----W

-hM--M.--M-W=^ ==---__W--MMMmme ___=_-=C- -

WW-.--mmh _-MM-h-N-M--..M_M--mmm

---M-- __

---W-MM-MM--MMMm.W--M--WW--m--_mme em-_---6---m--m--em---M-mme

, ------. . - - - - - - - = -- - ._M------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT i

im t

w PROCEDURE Whole Body Counter Systems PROCEDURE TITLE HNP-8134 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

.---___3____________________..________________..________________..____--__

APPROVED APPROVED REV. I DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 5 Pages 1-10 and 12 PR&

- _ _ - _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . y ,qv , ,

/y_..g_ g '_g 4.g

" DELETED - REPLACE BY A - M_

___ 5. _ _ .. _62RI __ QCB -D2& .0."_ _ _ _ _ _ _ .. N_ _ _ . _____ __ /__ _.__. /_/dff_

O v

- _ _ _ _ _ ..____________. ..___--_e. _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ .. _ _ _ - - - _ _ _ _ _ _ _ _ _ _ .._--_____

i e eAD euk EMD _ _ *= WEB _ se me eup sup GID WIB em gun app - emp qump _ esp gum en en em .. em - gas emy e e_ es _ - en emmy en emp en _ - .. _ gun esp enk e. amo em e em Gmb - _ _ _ en EuS ** eED _ - _ en _ _ S'

{V \

HNP-9 L_

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT (h

- (_) PROCEDURE Hand & Foot Monitor HFM-4A Operation & Calibration PROCEDURE TITLE HNP-8135 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

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

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

.-----------------..----------------.+- -

3 " DELETED - REPLACE BY 62HI-OCB-029-0" f'

_-- - _ _ - - - - _ _ _ _ - _ _ -.. - _ _ _ _ - - - ---j .--_--__

-_______.s - _

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

A _ _ _ _ _ _ _ _

i G') ------.-------------_ .

_ _ - - - ==.----- ---------+-

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

= _-

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

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

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

4

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

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

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

_=.. - - - - -

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

=..-----------= _ ____..----------------.-----------------.-------.

s HNP-9

F-GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

,O t t PROCEDURE a

Beta Counter Model BC-4 PROCEDURE TITLE HNP-8136 PROCEDURE NUMBER Lab RESPONSIBLE SECTION sat-t . i Y RELATED ( X) NON-SAFETY RELATED ( )

______.p________.-___________..____________-____._________________.________.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 3

Pages 1

_____--__-3

& 5 g_ /

jJI'd _ Q_ - _ _ _ _ j _ - ..F y ,gg [,RL0 -- D.

DELETED - REPLACE BY ~ __ M_ _.

3 6 2 H_I_- 0_C_.B_ _0_3 0 _0_"_ _ _ _ @

-- _ _ _ __'_t____e___r_

.. _ _[d_ _ _ _ _ .. _/f_S_ _

/m' 4

\

l

____-_.. _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . .--______________, ________________z ________

__el.__E..= e. Ga. GI.G. - - - _ m. _ e. . WeGu.Gu.m. _ _ mi.M._eu._e__e.ep._._dah_____ealb.4. sWD dump _ _ qu. ap. m g. _ _ - emp gue _ _ et. m. ga. _ _ quus .at _ _ _

?

I

\ /

%/

__--__,._____-______________q._______________.

HNP-9

GEORGIA POWER COMPANY

/

HATCH NUCLEAR PLANT

/ r\

k

\_/ PROCEDURE .

Portable Ion Chamber Model R0-2A Operation & Calibration PROCEDURE TITLE HNP-8137 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

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

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

- - _ - _ - .- - _ = _ - - _ _ _ - - =... - _ _ - - - - - - - - _ +_-___---_-______+_ _ _ _ - .

2 " DELETED - REPLACE 'M E BY 62HI-0CB-031-0"

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

h --___--__qs

- - -_.$ A $f . -

,/ ,Ti m

--_-____-__-___----_.._________--_---_+_______---_ .

, i

%/

______--__--__--_--+_--__ -

--__--+-__-__--

-_+--_-----_-----_---__.._--__- ._--__+---__--_______--.-_---_

- _ _ _ _ _ - _ _ _ - _ _ _ - ._-_____----_== - - -+-_- __ +-_---_-.

+ _ _ - _ - - _ _ - - _ - - --- -- -

_--___________-_-+__-_-_--_____---. - _ - - _ _ - _ .

_+ - - - - =--_--_--__--._________--___---+_____- -__--__m-______.

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

---_-- +--_ = - - _ - - - - -__________--__-__--____ _ _ - - - - - --

- =- - - - - _ - -

= ----_-__._---______--_____.--_-______ __ _____.__---_-_.

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

( , ---_--

--_--_+--__---_---_-___-__ a-_--_-________-_. .-__--__--__-----m.__-_---.

HNP-9

F-GEORGIA POWER COMPANY HATCH NUCLEAR PLANT t /

im j s r k> PROCEDURE Use and Operation of the Drager Multi Gas Detector PROCEDURE TITLE HNP-8140 PROCEDURE NUMBER Lab RESPONSIBLE SECTION e

SAFETY RELATED ( ) NON-SAFETY RELATED (X )

J

--.._--_--- ____ =-.----_-- _ _ _ _ ---

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER O " DELETED - REPLACE .-

j@kbE2E BY 62HI-OCB-033-O" ,

]' Y -

g

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

--- f_.

f

/^s l

\ _-

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

- - - - - - - - - - - - _ _ = = = .._-_______--____-. -

= _ . . - . -

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

r% --_--_.. - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ____

- _ _ _ _ _ _ _ _ ___--_--------___-+--____--

' tv)

-_-_--..__------------------n-_---_----------..----_----------- .--------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

(/ PROCEDURE MSA Combustible Gas and Oxygen Indicator Model 250 Operation and Calibration PROCEDURE TITLE HNP-8141 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY-RELATED ( ) NON-SAFETY RELATED ( X)

p-_--_==. . _ _ _ _ _ _ _ - - .-_-

3_---__-

_==-- _ ___ . ==

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

.p-_------__--_---__-- -

0 " DELETED - REPLACE p_ db SI_

A $h BY 62HI-0CB-034-0" g[h 9j '

~

--- +-_ _ ==--__--__--.-_---_ ----_-_---. --__-- - -_ _-- p _k W --_--

p J

- . _ _ - - p-__--- _

- - - . _ _ - - = - - _ - _ - - - - - = ._ - = - - - - = - = - - - _ - - .__--__---_--___-- p-_----__

.. - - - - _ - - = = - - - - ___-- -- _ _ - - _ - - _ _ - - - ..________---_---- p__----_.

._- - - - _ _ - - - - - - - - __ - = - - - ..----_--_________ - = _ - _--- p-------_

= = - _ - _ - _ - - - ._--_---------_---._ - _ _ - - - - - - ---- p_-------

- - - - - - .. - - _ - - _ _ - - _ _ _ - - _ _ .--------_--___--- p_--__--.

__.._--_----_-----------._ - _ - - _ - - - - _ - - _ - - - .._--_______------.+---_--_.

.. ----__- ___=-. _ _ _ _ - - - - .. - _ _ - - _ - _ - - _ - - _ _ ______-- -

. -------=== ___ ==.___---_---_---_--..-_----_-----_--_.- - - - - - - - -

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

Q -----_..--------_----_------.-----_-----------.-----------------..--------

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

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT em i r

(_) PROCEDURE Stabilized Assay Meter SAM-2 Operation and Calibration PROCEDURE TITLE HNP-8142 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )

p________- --- - - - - .s________.

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_ _ _ _ _ _ .______________ -+ _ _ _ _ _ _ _ _ - _ - - - p________________

3 " DELETED - REPLACE =_f 4___bE6E____

ghM BY 62HI-OCB-035-0" -

pg

_ _ _ _ _ _ .-_____- _=.

_.s h _ _ _ _ _ _ _ _ _'

=

________ __ ___ +_ ______

em 4

tv ) - =- -- -

___+________________. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _.

___-__.. = - - =- -===-

.r________________+____________ r________

_-..____________________ . - - - - -=- ---____ r________________. - _ _ _ _ _ _ _ _.

_ _ _ _ _ _ .. _ _ - - - ___=== -

==- - - - - . _=_____ r_- ____________4- _____

_ _ _ _ _ _ .._______ ___________.________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._-- = = _ _

______..___- - - = _ _ _ _ _ p-_=-. - - - _ = _ _ _ . ________________.________

_=-

f

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ = = - = _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ = = - - - _ _

______.. _ _ _ _ = = - - - _ _ _ - - - - _ .-________________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ _ - __

______..____________________+________________ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _-___--.

_ _ _ _ _ _ ._____________________ p________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ r________

J (Q,_ ______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._________________________

________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -________________a________________. _ _ _ _ _ _ _ _ _

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

/

(m) v PROCEDURE l.ow Volume Air Samaler Model H-809 V1 PROCEDURE TITLE HNP-R143 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

. - - - - - . --------------------. .------------ ^ ---- - - - - - . . - - . .---- ---

4 Page' P" - -

,rDRETED- E-BY---- -A- -

dLL

- - - - - - # 7 ff_.

4 62HI-0CB-036-0" REPl'hC

.'g- ---- -

~ ' - - - - fM g/g-

,m, ------. . - - - - - - - - - - - - - - - - - - - - . .----------------. . - - - - - - - - - - - - - - - - . .--------

t x_-)

N

, v,t - . - - - - - . ------.-------------- - - - - - . . - - - - - - - - - - . .----------------. .-------- .

HNP-9

GEORGIA POWER. COMPANY HATCH NUCLEAR PLANT r^si i

(_/ PROCEDURE Geiger Counter Model E530N Operation / Calibration PROCEDURE TITLE

= HNP-8144 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X)

-q__-==- -

==-

- - _ + _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ - - - - = - - - - - - = _ _ + _ _ _ _ _ _ ,

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

=__-

_________+_______________ - _ _ _ _ _ _ = - =____4___ _ _ _ ..

O " DELETED - REPLACE af "E64E BY 62HI-OCB-037-0" C. ,

g

+____________________+_____ _ _ _ _ _ _ _ _ _ _ . _______ __ --+ _____..

_ _ _ _ _ _ .-____=--

_________+________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _______..

(D) v _ _ _ _ _ _ .

____________________+______= _____ +________________4_______.

_ _ _ _ _ _ .-____________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ .

_ _ _ _ _ _ _.____________________+ _ _ _ _ _ _ _ = = = - +-_______________. -_______.

_ _ _ _ _ _ .._______= - _ _ _ _ _ _ _ _ . ________________+________________. . _ _ _ _ _ _ _ .

_ _ _ _ _ _ .. _ _ _ _ = = - __________

+________________+_______-- -

______..____________________+________________+________________.._______.

______..____________________+________________ r____________- -

________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ .

______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________________ r_________________ .________.

_ _ _ _ _ _ ..____________________n________________.- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________ p_____________ . _ _ _ _ _ _ _ .

r- _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

.t s_

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

,s

\

(_/ PROCEDURE Portable Ion Chamber Model RO-4A operation / Calibration PROCEDURE TITLE HNP-8145 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X ) NON-SAFETY RELATED ( )

p______ _ _ _ . __= - --- - _ _ _ _ _ . -________________.p________

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

_ _ _ _ _ _ . p__- = _ _ _ _ _ _ _ _ _ _ _ _ _ . _=__ _ - ______

_ - - - ___________ p_

1 " DELETED - REPLACE *M_ _ _ _ _

BY 62HI-OCB-038-0" ~

fg

_ _ _ _ _ _ . p__==------ 1 s

49

%.J

______ +____= - - = = _ _ _ _ _ _ _ _ _ .-________________ _________________+ - _ _ _ _ _ _ _.

_ _ _ _ _ _ . $_______= _ _ _ _ _ _ _ _ _ ._ = = - - =__ -= - _ _ .______=__ - = = _ _ _ _ . p________.

______ +_______-____-= ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._________________+ _ _ _ _ _ _ _ _

______4-_-_- - - - - - - = = = .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-__________--

+_-______

_ _ _ _ _ _ .-____== = = _ - - = = .. _ _ _ _ _ _ _ _ _ = - - - _ ___________- -_. ________,

______m___________________________- __________________=- -.-_-______

______. _ _ _ _ = - - - - - - - - _ _____..-- _ _ = - _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-_______.

____-_n____________________. . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -_-_____-

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

O

(_j - _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________..________

HNP-9

1 l

l GEORGIA POWER COMPANY l HATCH NUCLEAR PLANT i

m\ i KJ PROCEDURE Ludlum Micro R Meter /Model 12S PROCEDURE TITLE HNP-8147 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.p________________.-________

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER l

- _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______________ p________________.-__ __ _

2 " DELETED - REPLACE g BY 62HI-OCB-040-O" ),)b() u

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ . _____ _________y _____ _ _ _ _ _ _ _ _ _ .-

p gj.

_ _ _ _ _ _ .- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ .

i

,m2

-_____.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________________. -_______..

_ _ _ _ _ _ .._________- _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________________. ._______..

_______ ____________________ s________________. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _______.

_ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________________.- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s_______..

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .H________________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. . _ _ _ _ _ _ _ .

_ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .h________________. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________.

______- -____________________ s________________ .________________+_______.

l

______-.____________________ F________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .i._______.

s

______..____________________ s________________..________________ ._______.

HNP-9

GEORGIA POWER COMPANY w

HATCH NUCLEAR PLANT

(' _)\ PROCEDURE Beta Continuous Air Monitor Model AMS-3 Operation and Calibration PROCEDURE TITLE HNP_8148 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

_ _ _ _ _ _ + _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________.p________________.-________

APPROVED APPROVED REV, DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

._____ p____________________.s_______________ r________________ m__

O " DELETED _ REPLACE /_

fab.

BY 62HI_OCB_041_O" C f-

______,____________________4_____

g

(~'

._____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________ p________________. - _ _ _ _ _ _ _ .

L.

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________ p________________. -_______.

______. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . -________________ p________________ _______.

______4____________________.- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .,________________.s________

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________________ . - _ - - = _ _ _ _ _ _ _ _ _ _ .s________

- _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s_______.

-_____- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________+_______.

O, .

_ _ _ _ _ _.____________________ u________________--________________ f._______e.

I HNP-9 1.

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT i

A <

K/ PROCEDURE High Range Survey Meter Extended Chamber Cutie Pie Model CP-TP-5B Operation and Calibration PROCEDURE TITLE HNP-8149 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X_ ) NON-SAFETY RELATED ( )

- _ _ _ _ _ .L________-- _ _ _ _ _ _ _ _ _______- - - - _ _ _ . -

__________p________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

______4_____________________ ________________ ________________ p__ ___. .

2 " DELETED - REPLACE "#'2I BY 62HI-0CB-042-0" b)

_______ ________ / /_S_r__

)

,. i m

s,

'd _ _ _ _ _ _ .- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r_______.

- _ _ _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._________________ s_______.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . r________.

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,r_______.

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._________________ r________,

--____4____________________. _________________- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r________

______ s____________________ --_______________ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________

_____ h____________________ -________________ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ -H________'

(_,) ______ s____________________ s________________- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .________.

- _ _ _ _ _ + _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________.________________ - _ _ _ _ _ _ _ .

HNP-9

GEORGIA POWER COMPANY i

HATCH NUCLEAR PLANT m

/

(_ PROCEDURE

o Xetex Digital Dosimeter Model 415A

Operation and Calibration PROCEDURE TITLE HNP-8150 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- _ - - - - ._ _ - - - - _ - _ _ _ _ _ - - _ _ - - - - . p-----__ _------ --.-_----- - - - - - - - - _ . _--_--_-

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

__. -_--_------_-------_+_---____----_-- -----------------+-_ - -

0 " DELETED - REPLACE

BY 62HI-OCB-043-0"

--_---.-_-----____---------+----_

h _-------- ,

6d 1 ' f g- g ----

n (v) - - _ - _ - _ _ _ - _ _ _ _ - _ _ .. _ _ _ _ _ - _ - - - _ - _ - - _ .-_____-_.

- _ - - - - .- - _ _ - - - - _ _ _ - - - - _ _ - - - - .n-___-----__----_.. _ _ _ _ _ _ - - - - - _ _ _ _ - .---_---_.

-_--__4-_--_-_------_____--. ._____--_-_-_--___----_____--_____...---_--_.

i L

. (~,h

,_ ---_--+-----------___------. .--_--_----------.-----------------. ...----_-

s-------__-----___--_. .-_------_-_--_-_m-_--__--___---__ --------

- HNP-9 i

i L-

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Panasonic UD-702 TLD Reader Operation and Calibration PROCEDURE TITLE HNP-8151 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

5-------___----_-_----------_-__----_-+_--_--__--__-___ ________.

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER O " DELETED - REPLACE 6f ,

BY 62HI-0CB-044-0" ,hh '

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

/

AS_..

) - - - - - - ..-_---------_--------.. - - _ - - - - - _ - _ - - - - - ._ _ _ _ _ - - - _ - _ - - _ _ - - ..__-___-.

~ -

- - - - - _ . ----_-------_-__----...- - _ _ _ _ _ - - - - - - _ - -+-----___--___---..----___..

..---------_--_------_.._--------__-----m----_--_______--..-__-_---

\ ------..----_---------------.----------_--__-_-----------_--------------

Y I

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

'm)

(/ PROCEDURE Instrument Calibration Intervals PROCEDURE TITLE HNP-8152 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- - - - - _ .. _ - - _ _ _ _ _ _ _ - _ - - - - _ _ _ - ..-_-_--_-________..--_____---_-____a.________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER O " DELETED - REPLACE g 5 JI BY 62HI-OCB-045-O" ' LJ

---___+ - _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - - .._-__- _ - _ - - - - _ _ ,:-______

__ =- CA S_.

ib k' - _ _ - - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ .. - _ - - - _ _ _ _ - - _ _ _ _ _ .._____--_-_-___________--_.

- _ _ _ _ _ ..___________________--__----______--_-~._ _ - - - _ _ - - - - _ _ _ _ _.. . - - _ - _ - - ..

_ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ __.-________-___-__4______---_-_____.._______.

- _ _ - - .. - - _ _ _ _ - - _ _ _ _ _ - _ _ _ _ _ - ..________________ n_-______________. ._______.,

p- -_--__ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ ..________________ >.-__-___---______. . - - _ _ _ _ _ .

,V

--_-__ -___________-----_-____-_-______--___ r__-______--_____. .-______.

HNP-9

GEORGIA POWER COMPANY

,x HATCH NUCLEAR PLANT

, i

, i.

K/ PROCEDURE Dositec Digital Alarm Dosimeter Model DOS 501 Operation and Calibration PROCEDURE TITLE HNP-8153 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

- - _ _ _ _ .s__-_.._____._______. ________________.p_______= = _ _ _ _ _ .s________.

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

- _ _ . . _ . s___________________. -____ _.________ +____________= .

0 " DELETED - REPLACE r__ M__.-

g BY 62HI-0CB-046-O"

r. _________.._______ +______

hb C -

_, g

_______.7s______ _. _ _ _ _ . _ _ _ . .

O +__. ________________

g%.,j

.s_______.__._____.s_______.

WM___.- _ - _ _ _ _ _ _ . _ _ _ . . M W _ _ _'h______._______._' ____M__.._____.1 m______.h

---__. h_-_..___ ..---- ____ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r_____...________, _ _ _ _ _ _ _ ..

- - _ _ _ . .F_____.._--________. _ _ . _ _ _ _ . . _ _ - - . . . . p________..___....p_______.,

..____ h___-.__---__.---._-- -.._____________ H_.____________..w-_____...

= = . . _ = . F --=_--=__.__.. ___--H___=_____.____.h_=___..___..___..F._ .___.,

- - _ _ . . .w__.--__..___________. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r.._-..__._____.r______..,

-_-_-_ h_..-___..-_-.__-_. _ _ _ _ _ _ _ . _ . _ - _ - . _ .p....-_._________.p.___....

- _ _ . - . . F.______________...__. -..__._. ..-..... _ _ _ . . _ _ _ _ _ . . . . . . . . _ _ _ _ . . ..

-____. F______._-_-___.-----. - - - - _ _ _ _ _ _ _ _ _ _ _ _ .5--______________.p_______..

-_-___ F__________.._-_-____ __...______..___ h____________.._. ___.-__..

---___ F_-_-____..___ __..__+_-____..... _... p___....._-_-_-__ p._--....

+__--= r_-___..____ _--__ _. p ___.._.--._-___ p..________...... . . . . . _ _ . . .

(

O) s_ ___ __ r______.___._________ -_ __-_______.._ ,._ _ ___________o..___.__.

W._wm_ h.___.m__.m.__.m_..mm. -_m__m.m.____..m..h-m..___m___ _.._ H_.m__...

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT I

/~%

-( .

PROCEDURE HP Well Counter System PROCEDURE TITLE HNP-8154 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

.em.-_m __

_-------_-=ausunase-_______me.

m=- aus _*em _ _ em bio _ ee _ -. - _ ' - - __ _-_ _ _ _ em egen .. eup e.B een ese samp - _ a APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

______ p____________________ p___= ===______ .________________.

1 " DELETED - REPLACE .___bN_UE__.

6P !

BY 62HI-OCB-047-O" h) t'

._________s ___'__.

r____________________.r__=_- =________. .

______ r____________________p________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _

s a b/ ______ p____________________.p________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______.

.__.-_ F_______------_---___ F________________. . _ - _ _ _ _ _ - - _ _ _ _ - _ _ .. _ . _ _ _ . .

e___m_ ___mm-w__m_m_______m _____m______m___..____mmm_________e ._____m_..

. _ - _H.-----______.---____p_._____________..________---_____.. _ _ _ _ _ _ .,

.___-_H-_______--______..=_F._-__.-_-______-.. _ _ _ - - - - _ _ . _ _ _ _ _ .. - _ _ _ _ _ .,

.___ _ _ .r==__ -_-___.....m___H_.__=____=____m.. _ _ _ _ _ _ . = _ _ _ _ . . .. _ _ _ _ _ _ _ ..

-_-___ -- ___.._____..=_ =_H______..__=_____.. _ _ _ . . . - _ _ _ . _ - _ . .._______..

l I

4 e__m__a>__m.______M___mmm_me. h_m____mmmm_mm__m. ._m___m_____m__M_..___M___.i

-_____. - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .H__-____________. . _ _ . _ _ _ _ _ _ _ _ _ _ - - . . . . - - _ - - ..

=____m. .mm______=____=_=_mm_ Hw_m==_m_____mmm_. .m____mm==mm==__m. . = = = _ = _ _ .

_ = _ - _ < >_m_m_-m_____. F_m__-_-___mm.m_-- . m m m m . _ _ m - _ _ _ m _ -- .._______

.--___...--______________.__ H________.__.--__.. _ _ _ _ . _ _ . - _ _ _ _ _ _ _ .- _ . . _ _ _ - -

(~g _m____..____________________ r________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.________

1

. k %J I

===___. =__w=__-____________ H-_====___-__---_~m___-==_-__=___m- -__=__=_.

HNP-9

GEORGIA POWER COMPANY HATCH NtJCLEAR PLANT

-m k)s PROCEDlJRE Airborne Contamination Monitor Model RAl(-PR Ogeration and Calibration PROCEDlJRE TITLE HNP-8155 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X J) NON-SAFETY RELATED ( )

.....__.__________4.___....____.__.._._____..

APPROVED APPROVED REV, DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 1 Pages 1, 3, 5-6, 9 and 11 ' 7 -' *

~ ~ - - - ' - ~ ~~

p [J,) ~~ g g? g~ ~ ~

a E6dtfE6 -7 [p~ LAC'5 5V~~~

~ ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ '

~~~~"~~T~

~

.l_. _6 2.HJ.-QC.B_ 9@-Q"_,_ _. . _ . .

.h_ . dgf

+._______.

s p . . . _ _ . . . _ _ . . . _ _ _ . . _ . . . . _ _ ____.___ ___ __ . _ _ _ _ . _ . . . . . _ _ _ . . . . _ _ . .

d .._ _ _ . . . _ _ . _ _ . . . . . _ _ . . . . . . _ _ . . . . . _ _ _ _ _ . _ _.____ . ____ _ _ . . . _ .

r HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT t

A 1

(/ PROCEDURE Gamma 10 Portal Monitor Operation & Functional Test PROCEDURE TITLE HNP-8156 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED (X) NON-SAFETY RELATED ( )

+--_-_------_----_-_-3---____--- __.p-_-_-_____----___.--__--__

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

--_-_-_-__---_-___--_--_--- p_-____________ p-__----_-____----__-- - - _ .

O " DELETED - REPLACE @P'JE2C BY 62HI-OCB-049-O" (k) LJ

_-----_--_-_-__--_-_-. p=== a <

7

\

s~J

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

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

---_--..- ----------------+----------------.+------_-------- ----------

r3 ----_- -------_-----_------ ---------------------------------. --------

m.si t

_- F --------_----------. -------__--_--_-- -------_--_------ -_-_---I HNP-9

GEORGIA POWER COMPANY

\

HATCH NUCLEAR PLANT PROCEDURE Use and Calibration of the Lab Dwyer Magnehelic Gage PROCEDURE TITLE HNP-8157 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

-_-_- -p_---_-_--_-----___--__---__-----_--__.p--__----__---_---_-___---_

APPROVED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

__ p---_------__---__--__ _-----_----____. p----_--------__- --_ __

0 " DELETED - REPLACE .

BY 62HI-OCB-050-0" C ,----__

g

__---_ p----_-_--__--------_..-____ ----__---- __- -_---- -__

,, -_---- p--_-----------_--_--. ._----------_-___ ,. - _ _ - _ - - - _ _ - - - _ - -._ - _ - - _ - - _

-_--_- p---_----------___---- ---__--------_----_----___-------- _-__--_-_

-_---_.s---_---__-----------._----__-------_-- _ _ _ - - _ _ _ - - - - - _ - - - ._-_-----_

_.p------__----_---__--. _-__----_----_-------_------__----.__--_---_

_ s___----------_--_-_-. _ - - - - - - - - - - _ _ - - - - ___--______-------._--_----.

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

m

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

r-----------------._-------_-------.---------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

. /T

(_J PROCEDURE Eberline Model PM_6 Portal Monitor PROCEDURE TITLE HNP-8158 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . s________________.s________________.________.

APPROUED APPROVED REU. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

______+ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _4________= -__ p________________+ _ _ _ _ _ _ _ _

0 " DELETED - REPLACE A dr ,4k3r BY 62HI_OCB-051-0" C h) '

+-___________________+_____ _ _ _ _ _ _ _ _ _ _ . ' _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .S, 65_.

s________________+_..______.

f

\-/ _ _ = _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________________.p________________ r________

- _ _ _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ________________+________

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________+________________+_______.

________________+ _ _ _ _ _ _ _ _

-________________a_______.

.______. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________m. _ _ _ _ _ _ _ _

_ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .s________

r- ._____-____________________-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ +_______..

(v)<

._____.____________________ ________________..________________ p_______.

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

- j \

( ) PROCEDURE

. <J Victoreen Electrometer Model 500 PROCEDURE TITLE HNP-8159 PROCEDURE NUMDER Lab RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-GAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAG-O

~ ~ ~ ~ - - - -

New Procedure p~ ~ ~ ~ , ; g %(

~ ~ ' ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ "

j

~~~M

~

~ 3 g g 3 ,- Ri M ~ E ~ ~ ~~'[

r

_ _ _ .0_ _ . 62til 0CB.0a2 0"_______

.t_

(q s

,Ch . __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

'u/

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

(~N. PROCEDURE s ,i

%d

- Teledose Model 503A TelemetrZ__SXstem _--

PROCEDURE TITLE HNP-8160 _ _ _ _

PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )

\--------------------.. ------------- ,----------------.. -------

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGE y-- - .-- ----- ------. .-- -----

0

~~----

New Procedure

~ - ~ ~ ~ ~~ ~~~

g) , ,/gg ,, ,

~~~~ ~~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ~

%dETE6~~hER~ACEBY s

_/h 0 62HI-QC.B-953 0" _@ .

s/e/EE i

/m i i, *

~- ------ --------------------. .---------------- .---------------- .--------

W----- .-------------------- ---------------- ---------------- ------->

---_-- p----------_----_-_-- --_-----____----. --------_----_-- . _ - - - - - - .

---_-- p-------------_------ -_-----_-_------ ---_---_------__ --_----.

(\ ------

r--------------------. .---------------- .----------------.---------

V HNP-9

i~,

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

/m i

'w/ PROCEDURE Eberline Itodel PCit-1 Portal Monitor

.0pera tion _anrLEa.l.11ntina______

PROCEDURE TITLE HNP-8161 - ___.

PROCEDURE NUMBER Lab RESPONSIBLE SECTION

, SAFETY RELATED ( X) NON-SAFETY RELATED ( )

_ _ _ _ _ _ . p_-_ __-___--__-__--__.--_-___________-_._____-____-___--..___ _-_.

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

.___--+ _ _ _ _ - - _ _ _ _ - - _ _ _ _ _ _ _ - ..__--___ _ _ _ _ - _ -

. - - .y - _ _ _ _ _ . .. _

O New Procedure V -

- - - - _ _ -. _ - - - - _ _ _ _ - - _ - _ _ _ _ _ _ _ . /

-- __J /n- . _ _!* - ya _ _ _ _ _Y$--. '- - .

1 Pa g_e_s _1_ t_h.r.u_ 2_2_ - _ _ _ _ - ..__h_-_1-__'____. _ ,g qu . "_7J A

()

[ gf m_[_ _( . [-_cga.M' 2

Pages 8,11 _13,15,19&21

._____..,__---_-_ __---_____. . _ _M_ _ _ _ . . __

3 Pages 1, 4-6, 9-15, 1a.2a_g_22.

wry]

, fj 3,

[__ g.f[_%%

g

" DELETED - REPLA,,CE BY M

l j ._--__. . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ .._________---___. ...___.__.___.___.__-___ .

q v

e--4.-_=

- _ _ _ _ _ _ - - _ _ - _ - _ _ _ _ - _ --_-______----_-__ .__-_m___m_______ .--____--

HNP ')

L

GEORGIA POWER COMPANY

/_\

HATCH NUCLEAR PLANT t \

\ /

PROCEDURE ENMET WOA-20 Portable Oxygen Monitor O pration E and Calibration PROCEDURE TITLE HNP-81E2 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 0 New Procedure / / -

-------------------- - - -- i+

/.

CC 3fM

" DELETED - REPLACE BY '

M

' A 62HI-(') 0 -f/M_

- - - - - - . ----- _0C B- 0 5 5 _0"

--, / GAPS.

-- - - - - 3'7a - - - - - .

,O

~ - - - - - - -------------------- --__------------ ---------------- --------

HNP-9

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT

) . PROCEDURE EC4-8 Portable Area Monitor PROCEDURE TITLE HNP-8163 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER

'q..

O New Procedure g g -

f6 -& *

- - .s' ;.thn g

,'DEEETED - REPEACFBY- . . - - - - . , - - , .

/

+ g 0 62HI-HPL-001-0"

. /d g-

\v /

HNP-9 f

\

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Multi-Scale Check Source PROCEDURE TITLE HNP-81G4 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

_ - - _ - - . ____ _ -_ __- -_____2________________. ___-____________.p_---____,

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER O New Procedure gg

.. p_ - _ __ _ tr g_ .. . . ' _ g

.__ 7 -

m g- g gg gg g my

_---__..,DEEETED _.REPEACE BY _. -

n f g_ _ _ / _ -_ X_

- _ _ _0_ _ .- _ _62H I -HP L _002-0"_ _ _ -.K__l()__

g '

gy s

i -

HNP-9

P <

GEORGIA POWER COMPANY HATCll NUCLEAR PLANT s

Lv / PROCEDtJRE Operation of Waste Separa' tion & Temanrary Giora.ge Facility PROCEDijRE TITLE l_ _INP -8430 l PROCEDt.tRE NtJMDER Lab RESPONGIDI..E SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT, GENERA!_ DATE MANAGER MANAGER 4 Pages 1, 5-G &. 10 12 Am (jt ,

_l _/ . .. . . .

[ M A'6 S

. . _ _ . _ . .Pg._a..e.s _1 _t.h ru 1. _1._ - . . ._ _/._pg. .. . .. . . ... .i. /. A/ .

-- ._.,dM/_ w&m p,

(.J ._ 5 . .

" DELETED - REPLACE BY 62RI-0C8-056-0" g /

e._-.__._.---_.__.__

/K

._ _ ._ _ _ -. _ 7

~~

( )

v 1iNP-9

k GEORGIA POWER C MPANY HATCH NUCLEAR PLANT i

J PROCEDURE Ogeration of the Model B-100 Comgactor PROCEDURE TITLE HNP-8431 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( ) NON-SAFETY RELATED ( X) q________________..________

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAGER 2 Pages 1 -u - -

/g '7

/b

, gf y y

" DELETED - REPLACE BY h / [ 7 .

Y

_ _ .2_ _ _ .. .fi2D L._0CB_. Q51 0_" _ _ _ _ _ _ _ .. _K_ . _ _

_ _ _ . _ _ _ _ _ _ _ .._ _d

> I i !

't.J k / -

%J HNP-9 1

l

)

e .

l GEORGIA POWER COMPANY l 1

HATCH NUCLEAR PLAN 1 l l

l

(] PROCEDURE '

V ,

Decontamination of Protective Clothin_q and Hard Hats PROCEDURE TITLE 1

HNP-8007 '

PROCEDURE NUMBER Lab RESPONSIBLE SECTIOA

, SAFETY RELATED ( X) NON-SAFETY RELATED ( )

APPROVED APPROVED REV. DESCRIPTION DEPT. GENERAL DATE MANAGER MANAG-

. . _ _ _ _ _ . .____________________ .____________ _ ___ _____ '__-___.L_____ ._

9 Page a M '

c DELETED - Replaced by [ N

.__9___ ._--.-32RPd AD_-005.0 ____. .;.___ . . _ _ _ _ _ _ _', _ _4_ _'N_ _ _y' _ _h.___.. 1 . #4

- - _6_

Q . _ _ _ _ _ _ . .____________________ .___~_____________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________

J _ _ _ _ _ _ . ____________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .-________________ ._______l HNP-9 m,

~JM N

GEORGIA POWER COMPANY

-s (u.i l HATCH NUCLEAR PLANT

.. PROCEDURE Control And Accountability Of Radioactive Sources _

PROCEDURE TITLE HNP-8017 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X )

NON-SAFETY RELATED ( )

-__ __..____________ _____. _.r__. _____ _ _ ____

REU. APPROUED APPRCUED DESCRIPTION DEPT. GENERAL , DATE MANAGER MANAGER -

t 10 .. ___.__ ' _______ . . _ _

" DELETED _ REPLACED />M_ 3_

t, BY 62RP-RAD-035-O" ' ' -

___y ._ _ 8_ _ _ _ y_ .,_ _'/ ' _ _ _ _. '?_S. .gs*ff p ______..____________________ ..___________

\ _ _ _ _ _ .

s ..____.___________ .._______.

__ __.=_ ______._______._ ____ ..__________ _ _ _ _ _ _ _ ..____ ___ ___ _ _ . . _ _ _ . .

_ _ _ _ _ _ _ _ _ _ _ _ . =___________ _ _ _ _ _ .

l _

_ _ _ . ._______==- = _ _ _ ..______ .

6_ _ _ _ _ .

._-_4_.h.__g._______.m_.. _...W.W.'.__8 W___..-_ _ .b..E. _.I. _ _ _ _ _ _ _ _ * *_ WW___W l

l ". _ _ _ _

% =.___.I..____gm.______..___W___.I._.i.gy__gu....u.__g.eg.-____W___8>816_____.8 l

5 g a. .m...

% _.m._.m._.m..= __.=.m*** * . *

_

-_.s._.

is..m..m.* ._.m.e._.u..m..m. .m. _.u. _ _ _.. _ _ es. .m.en.

9 a._ _ _.. .u. g _ .m. _ _.e_.. ____.E HNP-9

I i

I O _______-_____--__________________________-__-______________-_______ ________

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PAGE 1 OF 6 DOCUMENT TYPE: DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION 62HI-HPL-001-0 DOCUMENT TITLE:

EC4-8 PORTABLE AREA MONITOR X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE: d REV. APPROVED APPROVED NO.

EFFECTIVE DESCRIPTION DEPT. MGR. DATE GENERAL MGR. DATE DATE

__________----_-_______-_______ .____-_ ____-____ r____ _ _ _ _ _ _ , ___________

3 0 Replaces HNP-8163

(

_ _/ &_ __ _____ _____ _6_ _/_g

__ __ 6_#__#_____

4

____________________________________________________1________________

MGR-0002 Rev. 1 e

m -- ,

I I-62hI-HPL-001-0

(_) 0 2 of 6 EC4-8 PORTABLE AREA MONITOR A. PURPOSE To provide an operation and calibration procedure for the EC4-8, Portable Area Monitor.

B. FREQUENCY

1. Operation: as needed

2. Calibration: semi annual C. REFERENCES

1. Radiation Monitoring System II Technical Manual, TDC# 6040M.

D. SAFETY

1. Georgia Power Safety, Section "O" r

1, 2. Follow all Radiation Protection Procedures E. TEST EQUIPMENT N/A

~

F. DESCRIPTION OF INSTRUMENT The EC4-8 Portable Area onitor is designed for the detection of gamma radiation and ind. cates radiation dose rates in mr/hr. It can be used locally or remotely as an Area Radiation Monitor.

G. DESCRIPTION OF CONTROLS

1. External

a. Meter; a five decade vertical scale ranging from 0.1 mr/hr to 10,000 mr/hr.

b. -High Alarm Light and Reset; lights when the high alarm limit has been exceeded, depressing the light resets t the alarm,

c. Alert Alarm Light and Reset; lights when the alert limit has been exceeded, depressing the light resets the alarm.

\]-

d. Normal Light and Source Check; lights during normal operation and activates the source check if so equipped.

l-w -

rg 62HI-HPL-001-0 h.)

0 3 of 6

e. Alarm Acknowledge; resets the alarm buzzer.

f. Alarm Buzzer; sounds when the high alarm limit is exceeded.

g. Alarm Beacon Light; lights when the high alarm limit has been exceeded.

h. Remote Detection; side mounted detachable GM Detector (DAl-6).

2. Internal

a. Power on; provides on - off capability for AC power.

b. R-15, Rec Cal; remote recorder voltage calibration adjustment.

c. R-20, Span; Mid Range Calibration pot.

. g-) d. R-13, Zero; Low Range Calibration pot.

y

e. R-24, High Alarm Set; sets high alarm limit.

f. R-23, Alert Alarm Set; sets alert alarm limit.

9 R-18, Rec Adjust; provides voltage adjustment for remote recorders,

h. S-5, Time; Response time selection fast or slow,

i. S-6, Alarm Set; causes meter to read the high or alert alarm setting which ever is chosen,

j. S-7, Alarm lock; causes alarms to " Lock In" or reset automaticaly if the radiation field drops below the alarm set points,

k. S-8, Alarm Logic; provides for a positive (+) or negative (-) alarm voltage logic.

1. R-57, Linearization Control; provides calibration compensation in the upper decade of the meter display.

m. R-4, Pulse width; adjusts the pulse width output of Ol.

H. OPERATION OF INSTRUMENT

-p l \ 1.

Be sure instrument bears a current calibration sticker.

L_

1 3

62HI-HPL-001-0

%-) 0 4 of 6

2. Plug instrument into 110 volt AC outlet.

3. Connect detector and place it in the desired location.

4. Open case and turn instrument on.

5. Switch S-6 to.the Alert position, the meter will read the Alarm Setpoint - adjust R-23 to set the Alert Alarm Point.

6. Switch S-6 to the Alarm position, the meter will reaa the alarm set point, adjust R-24 to set the High Alarm Point.

7. The instrument is ready for use.

I. SEMI ANNUAL CALIBRATION (DAl-6 DETECTOR)

1. Expose the detector to a radiation field of .5 mr/hr.

2. Adjust the zero until the meter is reading correctly.

3. Expose the detector to a radiation field of 100 mr/hr.

(~T

4. Adjust the span control until the meter is reading correctly.

5. Expose the detector to a radiation field of 8000 mr/hr.

6. Adjust R-57 (Lin) until the meter reacing agrees with the field intensity at the detector.

7. Repeat steps 1-6 until no further adjustment is necessary.

Enter all of the original readings in_the As Found column on Data Package 1 and all of the final readings in the As Left column.

8. Place a sticker on the Instrument and the detector bearing the required calibration information. Be sure to indicate which instrument and detector are matched.

9. Complete Data Package 1.

-O

7.

,-.\ 62HI-HPL-001-0 0

5 of 6 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62HI.HPL-001-0 SERIAL NO: R00-MPL NO:

RTYPE: G15.14 XREF: N/A TOTAL SHEETS: 2 FREQUENCY: Semi Annual COMPLETED BY:

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

62HI-HPL-001-0 R00

[}

FIGURE 1 Page 1 of 2 i

l

)

62HI-HPL'-001-0 0

6 of 6 DATA PACKAGE 1 PORTABLE AREA MONITOR'EC4-8 Sn8 MPLt Location Field Found (mr/hr) Left (mr/hr)

.5 mr/hr 100 mr/hr 8000 mg/hr Maintenance w

Remarks By Date Next Cal Due 4

5 4

f~ Page 2 of 2

( 62HI.HPL.001-0 R00 i

FIGURE 1 Page 2 of 2

3 GEORGIA POWER. COMPANY s ,) HATCH NUCLEAR PLANT PAGE 1 OF 9 DOCUMENT TYPE: DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION 62HI-HPL_002-0 DOCUMENT TITLE:

MULTI-SCALE CHECK SOURCE X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE: //

REV. APPROVED APPROVED EFFECTIVE NO. DESCRIPTION DEPT. MGR. DATE GENERAL GR, DATE DATE

______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .__________o_ ________ _____ ______ _ _ _ _ _ ..___ ______

0 Replaces HNP-8164 MO g g, y j g jj g'

________--___--__________~__-__--___--_--__--_------_-------____...-___-----

__________-__--_-_-____--~___--_-_______--_____-__--__---__ - - - - _ .._____-___-

s MGR-0002 Rev. 1 O

- 62HI-HPL-002-0 0

2 of 9 MULTI-SCALE CHECK SOURCE A' . PURPOSE To provide an operating guide for the use of the multi-scale check source.

B. FREQUENCY

1. - Use - as required

2. Calibration - annual C. REFERENCES ANSI N323 - 1978, Radiation Protection Instrumentation Test and Calibration D. SAFETY

(} Observe Radiation Protection Procedures.

E. TEST EQUIPMENT Test equipment consists of a check of the check source reading compared to a set of calibrated instruments.

F. DESCRIPTION OF INSTRUMENT

'The multi-scale check source is designed for source checking RO-2A's, RO-3A's, RO-4A's, and E-400's on all scales.

Teletectors can also be checked on the 50 mR/hr and 2 R/hr scales. All instruments require the use of a special jig that assures exact placement of the detector.

G. DESCRIPTION OF CONTROLS

1. . Locking Bar: a safety mechanism that provides a means of locking the check source with all attenuators inserted when not is Lse.

2. Shielded Cover: a lead chield designed to maintain a <2 mR/hr dose rate above the source with the shield cover closed.

3. Attenuator Rods: three rods on the front of the check

() source that control the placement of the attenuators within the check source. These provide a means of varying the dose rate thus providing the ability to source check instruments on various scales.

l

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

62HI-HPL-002-0

() 0 3 of 9 H. OPERATION

1. The individual who is to be operating the check source is required to be on an RWP and use a finger ring.

2. Obtain the key to the check source from the HP key cabinet.

3. Unlock the locking bar and remove it. The shielded cover can then be raised.

4. Do not pull any of the attenuator rods at this time.

5. Obtain the proper jig or spacer, depending on the instrument to be used. Place it in the check source well. It will provide the proper geometry for the desired instrument.

6. Turn the instrument on, check the battery, zero the instrument (if applicable). The beta shield is to be open on ion chambers.

7. Using Data Sheet 1 as a guide, begin.by turning instrument f to lowest scale and pulling the corresponding attenuator

\ rod. Push rod back in, turn instrument to next highest scale and pull the appropriate rod (s). Continue until all scales have been source checked on that instrument.

.8. Fill in the required information for each instrument on Data i Sheet 2. Indicate if the instrument passes or fails the source check.

9. Each instrument must fall between the high and low readings listed on Data Sheet 1. If the instrument fails the source check, it must be removed from service and tagged with a TC!

SHOP tag. Indicate the results of the source check on the tag along with any other problems or malfunctions encount-ered.

10. Insert all attenuator rods when the source check is complete.

i

11. Repeat steps H.5 through H.10 for each instrument.

12. When source checking is complete, insert all attenuator rods. Close the shielded cover and insert the locking bar through the rings on the attenuator rods. Secure the locking bar with the padlock and return the key to the HP key cabinet.

I. ANNUAL CALIBRATION OF CHECK SOURCE +

O

1. Obtain 3 instuments of each type, RO-2A's, RO-3A's, RO-4A's, E-400's and teletectors calibrated within the last 7 days but not used.

, r-,+1 v-wm

62HI-HPL-002-0 0

4 of 9

2. Follow steps H.l.through H.6 and take dose rate readings on each scale as stated on Data Sheet 1.

3. Average the readings of-the three instruments-for each scale indicated on Data Shee.t 1. To determine the low reading, take -20% of'the average reading. To determine the high reading, take +20% of the average reading. Record the low and high reading for_each scale and instrument indicated on Data Sheet 1.

4.. Af ter completion of Data Sheet 1, place a copy in a clear acetate folder and post in an area visible from the multi-scale source.

O

62HI-HPL-002-0 f(

O 5 of 9 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62HI-HPL-002-0

~

SERIAL NO: ROO.

MPL NO: N/A RTYPE: Gl$,14 XREF: N/A TOTAL SHEETS: 3 FREQUENCY: Annual

() COMPLETED BY:

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

() 62HI-HPL-002-0 R00 FIGURE 1 Page 1 of 3

- 62HI-HPL-002-0

(. .

0 6 of 9

-DATA PACKAGE 1 Data sneet 1 ANNUAL CALIBRATION OF MULTI. SCALE SOURCE RO-2A SCALE LOW READING HIGH READING ATTENUATOR ROD # PULLE 10 mR/hr

.... .. ......_w..___.........__ ..........__._...........D.

None

.500 mR/hr. 1 5 R/hr 1-2 50 R/hr 2

.... _.....J...._____......______ _....._..........__.1 .._._..._ 3 RO.3A SCALE LOW READI,N,G HIGH READING ATTENUATOR ROD f PULLED 50 mR/hr None 500 mR/hr 1

,("% 5 R/hr 12 50 R/hr 1 2-3 RO.4A SCALE LOW READING HIGH READING ATTENUATOR ROD PULLED

........__....... __........................ ....__......... ..t ........

mR/hr Hone i

, mR/hr 1

[" R/hr l

12 l R/hr 1 2 3 I

i TELETECTOR SCALE l LOW READING

........... ..........._.. fHIGHREADING ATTENUATOR ROD # PUL

............____ . . . . _ _ _ . . . . . . .. . . . . __.. _ _ L( E D 50 mR/hr l 3

2 .R/hr 1-2 Page 2 of 3 62HI-HPL.002 0 R00 FIGURE 1 Page 2 of 3

62HI-HPL-002-0 r3 U 0 7 of 9 DATA PACKAGE 1 (CONT)

Data Sheet 1 (cont)

ANNUAL CALIBRATION OF MULTI. SCALE SOURCE E-400 Low scale response- High scale

. place detector on response - use mark on backside of E-400 jig and shield pull attenuator rod 8 two DATE PERFORMED PERFORMED BY O

Page 3 of 3 62HI-HPL-002-0 R00 FIGURE 1 Page 3,of 3

62HI-HPL-002-0

)- 0 8 of 9

....--.....--............. - ___==-....--............--.......-------.

PROCEDURE DATA PACKAGE 2 DOCUMENT NO: 62HI-HPL.002-0 SERIAL NO: ROO-MPL NO: N/A RTYPE: G15.14 XREF: N/A TOTAL SHEETS: 2 FREQUENCY: Daily

- , COMPLETED BY:

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

Page 1 of 2 62HI-HPL-002-0 R00 r\

U FIGURE 2 Page 1 of 2

62HI-HPL-002-0

/-s \.

-V 0 9 of 9 DATA PACKAGE 2 Data Sheet 2 DAILY SOURCE CHECK LOG INSTRUMENT SERIAL NO. PASS / FAIL DATE CALIBRATION RE MARKS INIT.

DUE DATE l

.......... ........ .. ..._...__........ .............l........ ......

.._....._.__.._.._.._________-..___......_I_._....__I_.....

..._..__....._.......__....____....__. .. ..___....... ,I.........I . .__..

.....__.__ ..._....._.._ ._....._.._.._____.........._.l......_l.._... -

..________........... ....__....... ....__-..__......._l........_.....

...._____.._-_..._...___...._...___....__ _._.....__.._l_........___...

(

...... ......___....._......______..____. .. ...._....l..._. .. .__...

.. .......__..... ...... ......_.._____. ......._...._l___........__..

..............__._....__.............__._ _.._.__...._-l.__...... . . _ . . . .

......_....................... .......__. .._....__._--l._....... ...._..

.................__............ ....._... .............l.. ..... ..___.

......_..........._.....-.......... ..._..__...______..l... .._. ____ .

................._... ... . _ _ . . . . . ....... ..........__l......__ . .....

l

...........................__....._ ___....__... I l

.................._............_... ......n__......._. ....._..i_ _....

........___............. . .........i...........__... . . ...... .......

.__ ...............__.. . ....._.. ..... .......__.. ........l.......

.......__........_........______....__... ..........__l_...............

Page 2 of 2 62HI-NPL-002-0 R00 s

\

FIGURE 2 Page 2 of 2

GEORGIA POWER COMPANY _ _ _ _ _ _ _ _ - - _ _ - _ _ - _ _ _ _ _ - _ - _ _ _ _,

.~

t s

< HATCH NUCLEAR PLANT

%.s

_____-_-_______________________________________ __PAGE 1 OF B DOCUMENT TYPE: _-______-_____-____-______

HEALTH PHYSICS INSTRUMENTATION DOCUMENT NUMBER:

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ -__-____61 _ _ _H_I_- _O_ C B - 0 01 - 0 DOCUMENT TITLE: ___________-___________ _ ,

PLANT FUME HOOD VELOCITY MEASUREMENT X SAFETY RELATED _________-____

NON-SAFETY RELATED EXPIRATION DATE: . /

REV. ___________-__

APPROVED APPROVED NO. DESCRIPTION EFFECTIVE DEPT. MGR. DATE GENERAL MGR.

_____________-_____- __-______ 7 DATE 0 Replaces HNP-8020

_____f______DATE h / _-__ ____________

_______--________-__ _ _K_l_ - ,

___-_ _S_N _St_.

/

_____-_____-_ _ _6 _i - __6_tjL__--.

_f m

e C

si --___ _____---_________--__

Q/ ______

_____ a

-___________________--_-__ ___-__-_ _ g (x- ) MGR-0002 Rev. 1 ________------____-_________--__

I e

62HI-OCB-001-0 (N 0 2 of 8 PLANT FUME HOOD VELOCITY MEASUREMENT A. PURPOSE To describe a procedure for measuring the face velocity of the fume hoods in the plant and to assure that a minimum of 100 ft/ min. is maintained.

B. SAFETY

1. Observe safety rules as described in the G.P.C. Laboratory Safety Manual.

2. Observe Radiation Protection procedures.

C. FREQUENCY

1. Following maintenance on motor or belts

2. Once per year ,,

() 3. As prescribed by a Lab Foreman

E. PROCEDURE

1. Fume Hoods

a. Remove the velometer from the carrying case. Place on level surface and check the zero adjustment. This is done with both ports closed.

NOTE In case the pointer does not indicate zero, the zero adjustment screw on the front of the case should be turned slowly.until the pointer indicates zero.

b. Remove the port caps and attach the Lo-Flow probe (Type 6050-P). Measurements with this probe will be made on the 0-300 FPM (feet per minute) scale. The probe should be attached so that the arrow on the probe points to the left when viewed from the front of the instrument.

c. Place the velometer at one of the positions in the face of the hood. See Data Package 1 (Data Sheet 1).

O

62HI-OCB-001-0

(:)

3 of 8 NOTE Refer to Figure 1 for location of all fume hoods to be checked.

d. Move aside from the hood face and note the average velocity'over a period of one to three minutes. Record the value on Data Package 1 (Data Sheet 1).

e. Repeat E.d for the second & third positions in the hood.

f. Average the three velocity readings and record the results on Data Package 1 (Data Sheet 1).

g. If the average velocity for each hood is less than 100 F.P.M., initiate corrective action.

NOTE If hood sashes have to be lowered to meet 100 F.P.M. velocity, measures should be taken to assure that the sashes are not raised above this ~

] level,

h. Repeat section E for all hoods.

2. A. A. Fume Hood

a. Follow sections E.1.a and b.

b. Place the velometer at one of the four positions on the underside of the hood, see Data Package 2 (Data Sheet 2).

c. Place the velometer into one of the four sections and note the average velocity over a period of one to two minutes. Record the value on Data Package 2 (Data Sheet 2).

d. Repeat section E.2.c until all four sections have been measured and recorded on Data Package 2 (Data Sheet 2).

62HI-OCB-001-0 0 4 of 8 FIGURE 1 UNIT ONE MPL LOCATION MPL LOCATION 1P33-P204 WATER ANALYSIS ROOM, 112' T.B. IP33-P102 RWCU, 158' RX BUILDING 1P33-P103 RAD WASTE, 108' R.W. IP33-P105A LAB, 130 CONTROL BUILDING IP33-P104 RAD WASTE ADDITION, 180' R.W.A. IP33-P105B LAB, 130' CONTROL BUILDING 1P33-P101. RCIC DIAGONAL, 106 RX BLDG. IP33-P105C LAB, 130' CONTROL BUILDING IP33-P209 CONDENSATE DEMIN HOOD, 112 T.B. 1P33-P105D LAB, COLD LAB, CONTROL BLDG.

UNIT TWO MPL LOCATION MPL LOCATION 2P33-P209 CONDENSATE DEMIN HOOD, 112' T.B. 2P33-P204 WATER ANALYSIS ROOM, LEFT HOOD 2P33-P101 RCIC DIAGONAL, 106' RX BLDG 2P33-P204 WATER ANALYSIS ROOM, RIGHT HOOD 2P33-P103 R.W.,'112, R.W. BLDG. LEFT HOOD 2P33-P102 RWCU, RX BUILDING 185 2P33-P103 R.W., 112, R.W. BLDG. RIGHT HOOD O

UNIT ONE MPL LOCATION NA Lab, 130' control Bldg., Atomic Absorption Hood (Perkin-Elme r A. A. )

SIMULATOR / TRAINING BLDG.

MPL LOCATION NA Chemistry Training Lab, Left Hood NA Chemistry Training Lab, Right Hood O

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

62HI-OCB-001-0

.h 0 5 of 8 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62HI-OCB-001-0 SERIAL NO: ROO-MPL NO: N/A RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: As Required r

. COMPLETED BY:

i DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

6 2 HI-OCB-0 01 -0 Roo

!]

FIGURE 2 Page 1 of 2 -

1

l 62HI-OCB-001-0 i ym

'y 0 l

6 of 8 DATA PACKAGE 1 (Data Sheet 1)

PLANT FUME BOOD VELOCITY MEASUREMENT UNIT NO.

TEST EQUIPMENT HOOD LOCATION REASON FOR TEST HOOD MPL NO.

SURV., MR NO. , OTHER 4W O O O ,

M N

s,

%L h hL- I

%L L

V (LOCITY WELOCITY (FT/ MIN) (FT./ MIN)

O

. \j P0$fTION U POSITION X PO$! TION Y POSIT!0N Y POSITION W P03! TION Z 50M ALL-POSITION!

SUM 4LL 80$ttf M1 6

MUST BE GREATER THAN OR EQUAL TO 100 FT/ MIN TO BE ACCEPTABLE.

TEST RESULTS

( ) ACCEPTABLE, ( ) NON-ACCEPTABLE, LAB FOREMAN NOTIFIED REASON FOR NON-ACCEPTANCE / CORRECTIVE ACTION TAKEN:

COMPLETED BY DATE f.__.__......__...... . . . _ _ . . . . ..

O " " ' - c"- '- "

FIGURE 2 Page 2 of 2

62HI-OCB-001-0 0 0 7 of 8 PROCEDURE DATA PACKAGE 2 DOCUMENT NO: 6 2HI-OCB -0 01 -0 SERIAL NO: ROO-MPL NO: N/A RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: As Required

. COMPLETED BY:

DATE COMPLETED:

~

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

Page 1 of 2 6 2HI -OCB-001 -0 R00

.O FIGURE 3 Page 1 of 2 '

e ..

62HI-OCB-001-0

,m, 0 V

8 of 8 DATA PACKAGE 2 (Data Sheet 4J A.A. FUME HOOD SURVELLANCE TEST EQUIPMENT HOOD LOCATION: HOT LAB REASON FOR TEST: SURV , M.R. NO , OTHER VEI.ocITY (FTALIM) POSITION A POSITION 3 POSITIONS A

a POSZZZON C P08171086 D C

D Torn O TOT u + 4 FT/ MIN'

Must Dt 1 100 FT/xzu TEST RESULTS '

( ) ACCEPTABLE, ( ) NON ACCEPTABLE, ( ) NOTIFY LAB FOREMAN NOTE THE DAMPER MUST BE OPENED ON THE HOOD PRIOR TO BEING CHECKED.

j COMPLETED BY DATE Page 2 of 2 62HI-OCB-001-0 R00 O

FIGURE 3 i Page 2 Of 2

GEORGIA POWER COMPANY HATCH NUCLEAR PLANT. PAGE 1 OF 16 DOCUMENT TYPE: DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION 62HI-OCB-002-0 DOCUMENT TITLE:

MAINTENANCE & OPERATION OF PORTABLE HIGH EFFICIENCY PARTICULATE ATMOSPHERE (HEPA) FILTRATION UNITS X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE: d /b REV. APPROVED APPROVED EFFECTIVE NO. DESCRIPTION DEPT. MGR. DATE GENERAL MGR. DATE DATE

____________________________________ _ ______ __ ____,/_____ _________________

0 Replaces HNP-8040 g h________ _ _ _j

____ Q" g yf j gj

/

- _ ___________________ ______f_____

1.

. s

_________________n_________________________. _______________________________

l

_____ _______________________________________ ____________________ ____J_______

I i

s 1 . ____________________________________________ ______________________ _______.

i

~;

4 r.

f F MGR-0002 Rev. 1

I #

I r,.m---._,y-w_ y , or - - ,- .-. - e,--- ,m~,- - -,.-----w.,,,r--

~

5 2 of 16 MAINTENANCE AND OPERATION OF PORTABLE HIGH EFFICIENCY-PARTICULATE ATMOSPHERE (HEPA) FILTRATION UNITS A. PURPOSE

1. To outline the requirements for filter change and general maintenance of the HEPA filtration units.

2. To define operational surveillance of the HEPA filtration units.

3. To provide a system of HEPA filtration unit readiness confirmation.

4. To provide a system of HEPA filtration unit inventory and control.

B. FREQUENCY

1. D.O.P. leakage test of HEPA filters should be performed after any HEPA filter change-out and at least annually.

rg 2. Pre-filter and HEPA filters will be changed out as required tsj by differential pressure.

3.. Spark arrestors should be thoroughly cleaned during each pre-filter change-out.

C. REFERENCES

1. NPO Ventilation / Filtration User's Manual and Log

2. ANSI-N510 Testing of Nuclear Air Cleaning Systems

3. ANSI-101.1 Efficiency Testing of Air Cleaning Systems Containing Devices for Removal of Particulates

4. Regulatory Guide 3.2 Efficiency Testing of Air Cleaning System Containing Devices for Removal of Particles D. SAFETY

1. Observe safety rules outlined in Georgia Power Company, SAFETY, Section "O".

2. Observe radiation protection procedures to limit personnel exposure ALARA and to prevent the spread of contamination.

3. Be alert for conditional changes that might affect the

() requirements for additional radiation protection.

62HI-OCB-002-0

, 0

. T.

3 of 16 E. TEST EQUIPMENT

1. Air Techniques Inc. Model TDA-2E Particulate Detection Apparatus

2. Air Techniques Inc. Model TDA-5A DOP Aerosol Generator F. PRECAUTIONS / LIMITATIONS

1. Contact the electrical maintenance shop for instructions on electrically connecting and disconnecting HEPA units.

2. When using Charcoal Absorber Carts connect both 1000 CFM Charcoal Absorber Carts to a E2000 "2000 cfm" Portable Ventilation System to allow an adequate residence time of approximately 8 seconds.

G. EQUIPMENT USES

1. The portable HEPA filtration units are designed for a variety of uses within the nuclear industry.

The unit may be utilized to provide exhaust ventilation for

/"S containment tents or structures when unfiltered release of m) atmospheric contaminants could inadvertently expose personnel.

2. The unit may also be utilized to provide filtered exhaust ventilation with a corresponding air circulation for void spaces and tanks with oxygen deficient atmospheres where airborne radioactive contaminants may be present.

H. ISSUANCE AND INVENTORY

1. Portable Ventilation Units will be issued from the Respirator Office and recorded on a Portable Ventilation Unit Control Record similar to the one shown in Form 2 (Figure 3).

2. A monthly inventory of the units should be performed by a Health Physics Technician assigned to the Respirator Office. The location of the units should be recorded on the Portable Ventilation Unit Control Record.

I. OPERATING PROCEDURE

1. Review section "D", Safety, and section "F",

Precautions / Limitations.

, 2. Ensure all openings into the containment structure / tent are securely sealed.

( })

.()

s- 4 of 16

3. After starting unit log:

a. Date and time started.

b. Differential pressure across pre-filters,

c. Differential pressure across HEPA filters.

d. Dif f erential pressure across Charcoal Absorber, if in use.

4. Ensure inward ventilation flow through the tent / structure inner air lock door.

~

5. The readings in step I.3 should be logged after approximately every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of continuous operation and just prior to shutdown.

6. When using the Charcoal Absorber Cart an air sample should be drawn on the outlet of the unit approximately every 8

' hours and prior to shutdown.

J. MAINTENANCE PROCEDURE

() 1. Pre-filters should be changed out when the differential pressure across the pre-filters increases by 1.25" WG, Water Gage, above the initial, clean, pre-filter DP reading.

2. Spark arrestors should always be tho, roughly cleaned when changing pre-filters.

NOTE Always replace pre-filters prior to determining that differential pressure across the HEPA filter warrants HEPA filter replacement.

3. HEPA filters should be changed out when the differential pressure across the HEPA filter increases by 1.25" WG above the initial, clean, HEPA filter DP reading.

4. If documentation of the initial, clean, filter DPs is lost the following parameters should be assumed for clean filter readings.

Elwood NPO Pre-filter .25" WG Pre-filter 2.25" WG HEPA filter 1.0" WG HEPA filter 2.75" WG i

n s-

5. Initiate a Radiation Work Permit (RWP) for Portable Ventilation System filter change-out.

y-_m.- - - . , - - - -

-.--,--,,,.--,-----e m,,-m ,-- - ,- - - . .~, , ,-, ,,., *'m.. _ , . . , _ , , -

'O

'- 5 of 16

6. Initiate a Portable Ventilation System Maintenance Check Off List similar to the one shown in-Form 1 (Figure 2).

7. -Establish a Contamination Area / Airborne Radioactivity Area for filtration unit maintenance.

CAUTION If radiation levels on contact with the filtration unit housing are > 10 MR/HR in the vicinity of either filter element, initial opening and filter element removal should be accomplished inside a containment tent.

8.- NPO Fortable Ventilation System filter change-out:

a. Unlatch and open the door for the filters to be removed,

b. If removing the HEPA filter loosen both the top and bottom clamping mechanisms by using a heavy duty screwdriver to turn the threaded rods counterclockwise. The slotted threaded rods are located behind the rubber plugs on the opposite side of g3 the unit from the filter doors.

~

c. Unfold the installed PVC bag but do not remove it from the unit.

d. Using the PVC bag as a containment remove the pre-filters and spark arrestor or HEPA filter from the unit.

e. Visually inspect inlet and outlet surfaces of the new filters for any irregularities. Enter the inspection results on the Portable Ventilation System Maintenance Check Off List.

f. Place the new HEPA filter or new pre-filter and clean spark-arrestor into a new PVC bag.

g. Stretch the new bag over the units filter doorway.

Ensure the air flow markings on filters are pointing in the right direction and that the spark arrestor is placed upstream of the pre-filters,

h. Install the new HEPA filter or pre-filters and clean spark arrestor.

i. If the HEPA filter was replaced tighten both the upper and lower clamping mechanisms to snug tight. Install

(~},

s-the rubber access plugs, o

-h 6 of 16

j. Fold the PVC bag to fit inside the door and latch the door shut.

9. Elwood Portable Ventilation System filter change-out:

a. Reinove both the f ront and rear HEPA filter access panels for HEPA filter replacement. Only the front pre-filter access panel need be removed for pre-filter replacement.

b. If changing out the HEPA filter, relax the tension on the HEPA filter support frame by utilizing the hand crank (s) and removing any wooden wedges.

c. Using a yellow poly bag as a containment carefully remove the HEPA filter or pre-filters and spark arrestor.

d. Visually inspect inlet and outlet surfaces of the new filters for any irregularities. Enter the ihspection results on the Portable Ventilation System Maintenance Check Off List.

e. Install the new HEPA filter or new pre-filters and s clean spark arrestor. Ensure the air flow markings are pointing in the right direction and that the spark arrestor is placed upstream of the pre-filters,

f. If the HEPA filter was changed out raise the HEPA filter support frame by utilizing the hand cranks.

Raise the frame evenly until the outlet side gasket is compressed. Avoid overtorquing the frame which could result in stripping the gears and rendering the unit inoperable.

NOTE If the HEPA filter lifting support frame is inoperable, gasket compression may be achieved by utilizing wooden wedges between the filter support frame and the lifting platform.

Ensure even filter gasket compression.

g. Install all removed filter access panels. Ensure the hand cranks are installed in the clips provided inside the panels.

10. Ensure the differential pressure sensing lines are properly connected.

() 11. Decontaminat? the outside of the unit.

m 1 i

62HI-OCB-002-0 I l

~ 0 l

) :

7 of 16

12. Complete post filter change-out test:

a. Record new DPs across pre-filters and HEPA filters.

b. If HEPA filter was changed out or removed and re-installed a DOP leakage test should be performed.

NOTE If a DOP leakage test cannot be performed after a HEPA filter change-out the unit can only be used with an HP supervisor's permission. Filter efficiency must periodically be checked by comparing up-stream and downstream air samples.

13. Attach a Unit Readiness Sticker, similar to the one shown in Figure 1, across pre-filter and HEPA filter accesses in such a way that the sticker would be destroyed if either access were opened. Ensure the appropriate use area is indicated on the sticker.

14. Complete the Portable Ventilation System Maintenance Check r~ Off List and submit it to the Respiratory HP Foreman for

(_}/ review and filing.

K. DIOCTYLPHALATE (DOP) TESTING OF PORTABLE HEPA FILTRATION UNITS FOR LEAK RESISTANCE

1. Disconnect Intake Duct.

2. Establish air flow.

3. Warm-up instructions for aerosol generator,

a. Unscrew reservoir closure on top of unit and fill to approximately top of sight gauge on reservoir with dioctylphthalate (DOP). Replace cap when filled,

b. With power and aerosol off, attach line cord to 110 volt supply.

c. Attach line from compressed nitrogen supply to inlet at top of unit. Keep nitrogen supply regulator closed.

d. Turn power on and fully open metering valve on back of unit (full CCW).

e. When ready light goes on after approximately 30

,_ minutes, unit is ready to produce aerosol.

v)

'r.

~\

8 of 16 NOTE After initial startup, the ready light will cycle on and off as heater cools and reheats.

This will not affect testing,

f. Turn aerosol switch on.

g. Adjust nitrogen supply line regulator to 50 pounds.

NOTE The metering valve located in back of the aerosol generator is used to adjust the aerosol output. The concentration will vary by opening and closing the valve. The aerosol will be-emitted from the nozzle on the front of the cabinet in a steady stream of blu'ish white smoke. Once the

. heat has reached the level at which the ready light goes on, the unit will continue to produce aerosol for approxi-mately one half hour.

-O

(,j 4 .- Warm-up instructions for particulate detection apparatus.

a. Set all switches to off position.

b. Plug line cord into a 110 volt power source.

c. Remove caps from the test connections of the HEPA unit.

NOTE When testing filtration units not having test connections:- disconnect lines from pressure taps for magnehelic gauges and delete step d.

d. Insert upstream and downstream probes into test connections and tighten fittings to ensure leak tightness,

e. Attach a 3/8" poly-flow sampling tube from the upstream probe to the upstream fitting on the particulate detection apparatus. Repeat for downstream connections,

f. Set selector switch to zero position; this will protect the electronics during the warm-up period.

6211I-0CB-002-0 O

r

(- 9 of 16

g. Set selector valve to clear position; this permits air to be drawn through the filter and provides clean air for the scattering chamber.

h. Turn power switch to on position; this activates the unit.

i.. Allow five minutes warm-up time,

j. Adjust meter zero control until meter reads zero; electronic-balance is established by this procedure.

5. 100% and Straylight Adjustments

a. Turn selector switch on the particulate detection apparatus to the 100% position; the least sensitive,

b. Set selector valve to upstream position; this diverts the air route from the filter in the unit to the sampling inlet of the probe. For downstream sampling, set selector valve to downstream position.

c. Adjust gain control until a reading of 100 is obtained on the meter; this establishes the upper limit of

' () measurement and provides a direct read-out for the lower scales,

d. Set valve to clear position; thus providing clean air for the light cell.

e. Set selector switch to 0.1% position; the most sensitive. The .01% position may be used if extreme sensitivity is required.

f. Adjust straylight control to obtain reading of 0 on the meter. This adjustment compensates for any incidental light in the system or stray electronic signal which might cause an undesired signal to be relayed to the 2 phototube.

NOTE An ideal setting for the gain control is one in which the control is advanced approx-imately four to six turns clockwise from the full off position. This is usually an indi-cation of an adequate amount of aerosol con-centration for testing. Occasionally the situation occurs when the system being tested uses large volumes of air, causing dilution of the DOP aerosol. Should this be the case

~

}

("T

(_/ 10 of 16 and a problem arises with respect to obtain-ing a 100 reading, then every effort should be made to introduce additional aerosol so -

that the 100 reading may be obtained. If this is not possible, then common practice is to adjust the gain control until the reading on the meter is 50. Testing may be performed, and penetration readings obtained should then by multiplied by 2 for relating the reading to a 100 base. It is possible that a setting of 50 may still be out of range, so a base of 40 or 30 may be used. In each case, the penetra-tion readings should be multiplied by the pro-per factor to bring the reading to a 100 base.

Readings made in this manner are possible be-cause the instrument is linear. In all in-stances, proceed to paragraph I.4 aforementioned after base-line has been established.

6. DOP Test of HEPA Unit After the 100% base-line.is established the unit is ready for use.

() a. Set selector switch on 0.1%.

b. Set selector valve to downstream position to permit sampling through the downstream probe.

c. Read the percent penetration meter and record percent penetration.

d. Record results on Data Package 1.

NOTE A meter reading of 100 corresponds to 100%

of the selected value on the selector switch.

If the penetration is too high to be read on the 0.1% scale, then the selector switch should be set to one of the other scales as required to make the readings.

7. Shutdown of Aerosol Generator

a. When testing is complete, close metering valve.

b. Wait until stream of white smoke ceases.

[ c. Turn aerosol switch off.

()

l s

e 62HI-OCB-002-0 0

11 of 16

d. Turn power switch off.

e. Disconnect-from power supply.

f. Turn nitrogen supply off and allow line to bleed down.

g. Disconnect from nitrogen supply.

8. Shutdown of Particulate Detection Apparatus

a. Turn cal switch to off position,

b. Turn power switch to off position.

c. Disconnect from power supply.

9. Completion of In-Place Leak Test

a. Restore the system for normal operation, disconnect all sample lines, remove upstream and downstream probes, and replace caps on test connections.

b. Notify the HP Foreman that the test is completed.

() NOTE The system shall not be returned to oper-able status if'the results of the In-Place Leakage Tests are unacceptable.

c. Cor)pletetheIn-PlaceLeakTestReport, Data Package 1.

10. Acceptance criteria:

a. Units with leakage of .05% or less have no restrictions.

b. Units with leakage of more than .05% but less than .1%

may be used only with a Health Physics supervisor's permission. Downstream air samples should be taken to ensure adequate filtration.

c. Units with leakage of .1% or more should not be used.

l

(_)

I ,

l

62HI-OCB-002-0 12 of 16 FIGURE 1 UNIT READINESS STICKER-THIS UNIT'HAS BEEN SERVICED AND IS READY FOR USE IN AN UNCONTAMINATED /

CONTAMINATED AREA ONLY. (CIRCLE ONE)

/ H.P. TECH.

Date t

O-O

62HI-OCB-002-0

~(::) 13 of 16 FIGURE 2 PORTABLE VENTILATION UNIT MAINTENANCE CHECK OFF LIST FORM 1 PORTABLE VENTILATION UNIT MAINTENANCE CHECK OFF LIST 1.. Pre-maintenance test operation data for HEPA filtration unit NO. .

a. Spark arrestor / coughing pre-filter differential pressure

H20.

b. HEPA filter differential pressure

H20.

2. HEPA filtration unit maintenance RWP NO. .

3. HEPA filter visual inspection results.

satisfactory / unsatisfactory /N/A (circle one)

4. Spark arrestor screen cleaned .

5. .HEPA filtration unit decontaminated.

bA ,/

s a. Available for use in uncontaminated areas.

yes/no- (circle one)

b. Available for use in contaminated' areas only, yes/no (circle one)

6. Unit Readiness Stickers, Figure 1, installed on unit.

yes/no (circle one)

7. HEPA filtration unit NO. _ available for use.

8. Post-maintenance test operation data

a. spark arrestor / coughing pre-filter differential pressure

H20.

b. HEPA filter differential pressure

H20.

Completed By H.P. Tecnnician/Dare Reviewed H.P.. Foreman O

62HI-OCB-002-0 R00 Figure 2 ,

( 14 of 16 FIGURE 3 FORM 2 a..

HEPA FILTRATION UNIT CONTROL RECORD

. TYPE SERIAL, AREA PERSON DATE ASSIGNED RETURNED / BY EQUIPMENT NO. ASS IGNED ASSIGNED BY AVAI LABLE

............................r..............__......................... ..____. ..

I .....___ _ . . . . . . . . . . ____. ... . . _I - ..

I I ..........._........ .... ____... ..

I

........._....... ........ I............. ...___ ............ ............_ ..

I I

. . . . . . _ . . . . . . . . . . . . ..... . . . . ..i_ ..

l I

I .......I...............

l I

I l ........................ ....... ..

I I ..... ......_ __

..................l- I n....._._.n_............ .................... .... ....... ..

.................................................................. ._ ..._.y ..g 62HI-OcB-002-0 R00 N.gure 3

62HI-OCB-002-0 o 0 L

v!

15 of 16 PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62HI-OCB-002 0 SERIAL NO: R00 MPL NO:

RTYPE: C1b.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: As Needed COMPLETED BY DATE CCMPLETED:

V I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCCRDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

Page 1 of 2 6 2HI-OCB-002-0 R00 FIGURE 4 Page 1 of 2

62HI-0CB-002-0 0

/ \

! J

\/ 16 of 16 DATA PACKAGE 1 IN. PLACE LEAK TES*ING REASON FOR TEST:

( ) NORMAL SURV. ( ) FILTER REPLACEMENT ( ) OTHER TEST PEPPOPMANCE TEST BY Serial number of unit being tested:

Pre-filter differential pressure

H20.

HEPA filter differential pressure

H20.

STEP ACTION TESTED BY 5.a-f Calibrate penettometer. Start DCP injection.

6.a --......

HEPA filters:

K.4 Percent Penetration Gauge s Readings: 1st ----------------- --------

(\' )

2nd ----------------- --------

K.4 Leakage = ------------------------------t --.-----

Type of aerosol generator used Type cf particulate detection apparatus used All test port caps have been replaced securely Test equipment has been removed from test site Sample lines decontaminated as necessary COMPLETED BY DATE Page 2 of 2 6 2H1-CCB-002-0 R00 O FIGURE 4 V Page 2 of 2 l

l

t v .

GEORGIA POWER COMPANY '

(G

,jx t

HATCH NUCLEAR PLANT PAGE 1 OF 3 DOCUMENT TYPE: DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION 62HI-0CB-003-0 DOCUMENT TITLE:

OPERATION OF THE BARTLETT NUCLEAR MIXING UNIT X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE: MN REV. APPROVED APPROVED EFFECTIVE NC. DESCRIPTION DEPT. MGR. DATE GENERAL .G R . DATE DATE 0 Replaces HNP-8044 gg , . . ____

g _.--_ -_--__.-

g _4 .p g._gg - .a _-.

/

r c ..._______________________ ____________ ______ _____________. ._____ ___________

\

i m MGR-0002 Rev. 1

62HI-OCB-003-0 O o 2 of 3 OPERATION OF THE BARTLETT NUCLEAR MIXING UNIT A.- PURPOSE To provide instructions for the safe operation of the mixing station.

B. REFERENCES Bartlett Nuclear Inc. Process Control Program Procedure C. SAFETY Care must be taken to avoid contact with the mixing blades curing operation.. Never place hands or arms into the mixing container while unit is on.

D. DESCRIPTION OF UNIT

1. The Bartlett mixing unit is a portable self-contained hydraulic mixing unit, allowing personnel to simply and O efficiently operate the equipment necessary for waste solidification.

2. Bartlett mixing station consists of the following:

a. Caster mounted thick wall tube 4" steel frame,

b. Removable top plate to facilitate movement or transporting.

c. Removable cylinder motor and swivel lock hoses,

d. 5 gallon reservoir hydraulic system with sight glass filter and exposed valves.

e. Portable control panel for remote operation.

f. 115 volt explosion-proof electric motor.

g. 600 psi pump with gauge and relief valve,

h. Drum stop with lock-down apparatus.

1. Removable mixing blade.

3 Flow control valve for controlling RPM's of mixing

{ blade, i

1 J

62HI-OCB-003-0 g

.\ /

0 3 of 3 E. OPERATION

1. This system is designed to be used with a 55 gallon D.O.T.

specification 17 H drums.

2. Hydraulic system is incorporated for raising and lowering the mixing blade and is operated from the control panel.

3. Switch on power at the control panel (indication light should be on).

4. Engage electric motor switch (indication light should be on).

5. To raise mixing blade, engage "up" switch.

6. To lower mixing blade, engage "down" switch.

7. To turn mixing blade, engage "forwarc" awitch

a. Blade should turn freely.

(]) b. Psi gauge should read approx. 350 psi and flow control meter set at 3.

NOTE Unit is not electrically designed to mix in the reverse mode.

8. Oil line on sight glass should be in line with black indicator line or within 2 inches for operation,

9. During operation, the speed of the mixing blade may be increased by unlocking the flow control meter knob and rod moved up scale. The vortex in the liquid waste should be maintained as long as possible to give a good homogeneous mixture.

O

,s GEORGIA POWER COMPA!1Y

( HATCH NUCLEAR PLAtlT PAGE 1 OF 7 r -__________._______________________.._________. ._ ________________________

DOCUMENT TYPE: DOCUMENT NUMBER:

HEALTH PHYSICS It3STRUME!3TATIOt3 62HI-OCB-004-0 1

DOCUMENT TITLE:

PORTABLE IOtl CHAMBER PIC 6A OPERATIO!! & CALIBRATIOli X SAFETY RELATED

!!Oli-SAFETY RELATED EXPIRATIOtt DATE: / df /

REV. APPROVED APPROVED EFFECTIVE 11 0 . DESCRIPTION DEPT. MGR. DATE GENERAL MGR. DATE DATE O Replaces HtJP-8100 gd u.

/

gfg [

_ _ - - _ a . _ _ _ _ .q.. .46 ,a0. _4_ _ -__._. _g g A

e

,s s

v fem, a

MGR-0002 Rev. 1

62HI-OCB-004-0 0

2 of 7 PORTABLE ION CHAMBER PIC-6A OPERATION At3D CALIBRATION A. PURPOSE To establish standard operation guides and calibration technique of the Portable Ion Chamber, Model PIC-6A.

B. SAFETY

1. Observe safety rules outlined in Georgia Power Company, SAFETY, Section "0".

2. Radiation protection procedures will be observed when calibrating the instrument with radioactive sources.

C. REFERENCES

1. Portable Ion Chamber Model PIC-6A Technical Manual.

2. Gamma Calibrator Procedure 62HI-OCB-017-0.

3. Eberline Instrument Checkout Procedures.

D. TEST EQUIPMENT

1. Electrostatic Voltmeter.

2. Gamma Calibrator.

E. DESCRIPTION OF INSTRUMENT The PIC-6A is a small lightweight portable instrument which measures the dose rate from gamma radiation. The detecting element is a gas filled ionization chamber. Dose rates from 1 mr/hr to 1000 R/hr are measured in two ranges of three decades each. A single rotary switch turns the instrument off, provides a battery check and selects the range. A beta window in the bottom of the instrument provides for the detection of energetic beta particles.

F. DESCRIPTION OF CONTROLS

1. External control O

m____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ . . _ _ . _ _

>,_1 62HI-OCB-004-0

's /

0 3 of 7 Four (4) position switch -

OFF - turns instrument off BATT - the meter should indicate above the BATT cut-off line.

R/hr - instrument will indicate from 1-1000 R/hr mR/hr - instrument will indicate from 1-1000 mR/hr

2. Internal controls

a. H.V. Limit - adjusts the maximum high voltage (up to 3600V) when the instrument is in a radiation field less than the lowest readable.

b. Zero - an adjustable fraction of the reference voltage which is set to yield zero current through the meter with a radiation field equal to the low end meter reading. One control for each scale,

c. Span - An adjustable series resistance uhich is set to yield a meter deflection equal to the radiation field when in a higher field. One control for each scale.

G. OPERATION OF INSTRUMENT

1. Turn position switch to BATT position. Check meter to see if it is within BATT OK limit. If not, tag instrument out with a TO SHOP tag and affix tag to instrument.

2. Turn switch to range desired.

NOTE The meter reading is a direct readout of the radiation intensity in either mR/hr or R/hr, depending on the range.

Fluctuation of the meter is normal and is caused by the random nature of radioactive decay. If measuring radiation below 100 KEV, the most accurate reading is obtained with the bottom of the instrument pointed at the source.

3. Beta Radiation Detection:

With the beta window open, place the bottom of the instrument in close proximity (1/4") with the source to be measured, and note the reading. Close the beta window and measure the source again. If no difference is seen between the open window and the closed window then report the

, radiation as gamma only. If the open window reading is

(-)

'x_/

higher than the closed window reading then beta radiation is present. To determine True Beta Radiation Dose Rate obtain a RO-2A or RO-3A. Measure radiation with window open and window closed. Multiply the difference by the beta correction factor located on the side of the instrument (RO-2A, R0-3A) used.

h 62HI-OCB-004-0 0

4 of 7 H. CALIBRATION OF INSTRUMENT CAUTION Do not touch electrical components with the hands as damage to the instrument may result as well as electrical shock to the operator.

1. Remove cover and silica gel packets.

2. Turn position switch to BATT and verify battery is above BATT cut-off line on meter, if not replace batteries and repeat this step.

3. Turn position switch to Mr/hr range and place instrument in about a 2, 10, 100 and 1000 mr/hr fields respectively, and check the readings. Record readings in the AS FOUND COLUMN of Figure 2.

4. Turn position switch to R/hr range and place instrument in about 2,10, 100 and 200 R/hr fields respectively, and check

(]) the readings.

Figure 2.

Record readings in the AS FOUND COLUMN of

5. If the instrument does not read within + 20% of the true dose rate in each field continue with step H.7.

6. If the instrument checks out properly, record readings in AS LEFT COLUMN of Figure 2, turn position switch OFF, replace silica gel packets with 2 new ones or dried packets, replace cover, complete Figure 2, replace the calibration sticker with a new one bearing this' test date and when the instrument is due for its next routine quarterly calibration.

7. Turn position switch to mr/hr range.

8. Place instrument in about a 2 mr/hr field.

9. Adjust "ZERO" (mr/hr) pot to correct meter reading.

10. ' Place instrument in about a 1000 mr/hr field.

11. Adjust " SPAN" (mr/hr) pot to correct meter reading.

12. Repeat steps H.7 through H.11 until no adjustment is necessary.

13. Repeat steps H.7 through H.11 for the r/hr range using 2 O r/hr and 200 r/hr as the fields and the r/hr "ZERO" and

" SPAN" pots.

62HI-OCB-004-0 0

5 of 7

14. If the instrument does not respond properly in steps H.7 through H.11 perform the following: .

a. Turn position switch to r/hr.

b. Adjust H.V. pot (R16) for 3100 volts. Denote in the remarks section of Figure 2 the M.P.L. number of the voltmeter used to check H.V. if H.V. is checked.

CAUTION Do not short the high voltage. Damage to the transistors will result,

c. Repeat steps H.7 through H.11.

15. If the instrument responds within + 20%, perform step H.6 and record readings in the AS LEFT COLUMN, of Figure 2. If the instrument cannot be calibrated, tag the instrument out with a TO SHOP tag stating the reason (s) it was tagged out.

O O

I .' _U

, . j '-~

r f

I l 62HI-OCB-004-0 0

6 of 7 FIGURE 1 HIGH VOLTAGE ADJUSTMENT Electrostatic Volt Meter l

l l

l

, O.

. 4 GWD-cearen p a t r__ ,rg cH wN cMnetafi "- Hy D w,,.,

(RI&

1 t k=4 y

3 C / Rc c/t 7' 00 Ann

i. FOR P/C- 6 /3

}

9

, N <

00 00 l sf>1YRERO 5FA!/ U2[0 l

\ '% ","In c

O

. - . . . - , , < _ . - . . - . - - - , , . . _ , _ , , . . , _ _ . _ -_r. .._.,_m., _..,ym, .myo,_ _ , . , __,,- , _ , , , . ...y..y,, . . _ , . , , , , . . , . . .

,- (. ,.

V C' 's,_/

l Tr;3TRifta:T PIC-6A LOCATIOrt NPL tio.

S .!!.

Ii!STRU:*.E:iT REASIT:CS ACTL;;. A;T:;AL %:E: DATE: CATE: DATE:

". t'_ : ? . COG:T COSE Cr.!S. 07: LAllt. SY: CAllB. Cf: CAi.la. SY: =

5 '; .R'.E : ATE RATE AS FC*2ia AS LEFT AS FCUND AS LEFT AS F0UiO AS LEFT AS FCC D AS LEFT ,$

- :o

!!/A 2 c:r/hr mr/hr mr/hr f$

'i/A 10 r.ir/t.r mr/hr mr/hr !!3

FA 100 cr/hr mr/hr mr/hr o

>n"

/A 7003 cr/hr mr/hr mr/hr '

lC i m e

_ i:/A 2 r/hr r/hr r/hr $y

!!/A 10 r/hr r/h r r/hr y

!;/A 100 r/hr r/hr r/hr :

I:/A WO r/hr r/hr r/hr o

H in m

in tn e

m fl.7. her St. poly, Scns. Set (Circl e) !L V. . P.S. , Sens. (Circi c) H X , P.S. , Sens . (Circlcl i4X .P.S., Sens. (Circic) H.V. P.1, Sens. $

s n!*:T. FE:FOR:/.EE- "

o' E{ 1 '.3 0 o 0 i

4 o o

b o

t GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PA 1 OF 12

.______________________________________________-__GE ___________-____________ _

DOCUMENT TYPE:

DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION 62

---_________________________________________________HI-OCB-005-0 ____-_-_______________

DOCUMENT TITLE: _

TELETECTOR MODEL 6112B/D OPERATION AND CALIBR

-______________________________________________ATION ____________________________

X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE:

.REV APPROVED APPROVED NO. DESCRIPTION DEPT. MGR. EFFECTIVE

.___ DATE DATE DATE

____________-_______- _ GENERAL ____ ____ MGR.

0 Replaces HNP-8101

_.____-____________-- h _) gg _ - _

/ -

_f_, ___. ____ __

j jg

^

C\

\_j MGR-0002 Rev. 1 ---_______

e A

62HI-OCB-005-0

, s_- 0 2 of 12 TELETECTOR MODEL 6112B/D OPERATION AhD CALIBRATION A. PURPOSE To establish standard operation guides and calibration technique of the Teletector Model 6112B and 6112D.

B. REFERENCE

1. Teletector Model 6112 Technical Manual. TDC-0541M

2. Gamma Calibrator Procedure 62HI-OCB-017-0.

C. SAFETY Observe radiation protection procedures.

D. TEST EQUIPMENT

, 1. Gamma calibrator.

{} 2. Beta source.

E. DESCRIPTION OF INSTRUMENT

1. The teletector Model 61123 is a portable battery operated instrument for measuring gamma radiation, for detecting beta radiation and for tracing radioactive materials or contaminations. The fully transistorized printed circuit is contained in a waterproof case. Four 1.5 V batteries in the handle of the instrument serve as the power supply. The teletector 6112B, has a wide measuring range from 0.1 mR/hr to 1000 R/hr in five switch controlled scales, simple operation by a single switch for all functions, and a self contained telescopic probe extendable to a maximum length of 13 feet.

2. The model 6112D is the digital equivalent of the model 6112B with the exception of an integration function and time constant feature added in.

F.- DESCRIPTION OF CONTROLS

1. Model 6112B I

a. External controls, g~ Switch Turns instrument OFF, B (Battery check), 1000

(_) R/hr, 50 R/hr, 2 R/hr, 50 mR/hr, or 2 mR/hr.

b. Internal controls.

62HI-OCB-005-0

(~3

.V 0 3 of 12 (1) P1 potentiometer Adjusts high voltage current (2) P2 and P7 Calibrate 0-1000 R/hr potentiometers range (3) P3 potentiometer Calibrates 0-2 R/hr range (4) P4 potentiometer Calibrates 0-50 mR/hr range (5) P5 potentiometer Calibrates 0-2 mR/hr range (6) P6 potentiometer Calibrates 0-50 R/hr range

2. Model 6112D

a. External Controls (1) Function Switch; turns instrument off, B (Battery Check), R/hr, mR/hr and mR (integrate).

(2) Time constant switch; adjusts. response time on the mR/hr scale in 1, 4, and 16 second intervals.

I)

NOTE The time constant switch is operational in the mR/hr range only. The R/hr range is automatically set at 1 second,

b. Internal Controls (1) P1 potentiometer Adjusts high voltage current.

(2) P2 potentiometer Adjusts the upper range at the R/hr scale.

(3) P3 potentiometer Adjusts the lower range of the mR/hr scale.

(4) P4 potentiometer Adjusts the battery voltage indicated on the LCD.

(5) P5 potentiometer Adjusts the lower range of the R/hr scale.

(6) P6 potentiometer Adjusts the lower mid range of the R/hr scale.

-\~t

(') (7) P7 potentiometer . Adjusts the upper range of the mR/hr scale.

, . . ~ , ,- ,, ,v n-. w-. -+ .- , , . , - - - -,

gy 62HI-OCB-005-0

.V 0 4 of 12 (8) P8 potentiometer Adjusts the time base oscillator.

(9) P9 potentiometer Adjusts the upper mid range of the R/hr scale.

G. OPERATION OF INSTRUMENT

1. Turn switch to B. Check meter to see if indicator is within black area on the scale (6112B), or LCD indication is greater than 4 volts (6112D). If not, tag the instrument out using a TO SHOP tag stating the reason (s) it was tagged out.

2. Dose rate measurement

a. To carry out dose rate measurement, place the main-switch into one of the five measuring ranges. Select the measuring range ir. accordance with the dose rate present.

f-)s

(_ b. If full scale deflection is obtained as you approach a source of radiation, switch over to a less sensitive range.

3. Detection of Beta Radiation Detection of beta radiation becomes possible after removal of the cap from the beta window. First, read dose rate with cap in position. If deflection increases after removal of the cap, beta radiation is present. The increase in deflection provides no information about the additional dose rate of beta radiation. If beta radiation is detected with a teletector obtain a RO-2A or RO-3A to determine Beta dose rate.

4. Use of telescopic probe First extend the telescopic probe to the desired length. If sources of (presumed) high activity are to be traced, extend the probe to its maximum length where possible.

CAUTION The telescopic probe must be extended and retracted slowly.

Also avoid rotation of the probe. This prevents damage to the cable inside the probe, n

62HI-OCB-005-0 (s

\.]) O 5 of 12

5. Use of the earphone.

If only a small deflection of the pointer is obtained in the least sensitive range (2 mR/hr) it is advised to connect the earphone to the earphone connection. This produces the G.M.

tube impulses in the form of clicking sounds. At higher dose rates the clicking sound becomes a hissing noise so that the deflection of the meter must be used for orientation.

H. CALIBRATION OF INSTRUMENT

1. Model 6112B CAUTION Do not touch electrical components with the hands as damage to the instrument may result,

a. Check batteries by placing the switch to B. The meter should read in the black area, if not, replace

(^)

N_/

batteries and repeat this step.

b. Turn switch to 2 mR/hr.

c. Place probe.in about a 0.5 mR/hr and 1.5 mR/hr gamma field respectively and check the readings. Record the readings on the Instrument Calibration Data Sheet in the As Found column,

d. Turn switch to 50 mR/hr.

e. Repeat step H.l.c. for about 10 mR/hr and 35 mR/hr field respectively.

f. Turn switch to 2 R/hr.

g. Repeat step H.1.c. for about a 0.5 R/hr and 1.5 R/hr field respectively.

h. Turn switch to 50 R/hr.

i. Repeat step H.1.c. for about a 10 R/hr and 35 R/hr field respectively.

j. Turn switch to 1000 R/hr.

k. Repeat step H.l.c. for a 50 R/hr and 200 R/hr field respectively.

62HI-OCB-005-0 0

6 of 12

1. If the instrument reads within + 20% of the actual dose rates in steps H.l.c. thru H.l.k., proceed to step H.l.aa.

m. If the instrument does not read within + 20% of the actual dose rates in each field continue with step H.l.n.

n. Turn switch to 2 mR/hr.

o. Place probe in about a 1.5 mR/hr field and adjust potentiometer P5 until instrument reading equals the actual dose rate i 20%.

p. Turn switch to 50 mR/hr.

q. Repeat step H.1.o. for about a 35 mR/hr field and using potentiometer P4.

r. Turn switch to 2 R/hr.

s. Repeat step H.l.o. for about a 1.5 R/hr field and using

() potentiometer P3.

t. Turn switch to 50 R/hr.

u. Repeat step H.l.o. for about a 35 R/hr field and using potentiometer P6.

.v. Turn switch to 1000 R/hr.

W. Repeat step H.l.o. for about a 50 R/hr field and using potentiometer P2.

x. Repeat step H.l.o. for about a 200 R/hr field and using potentiometer P7.

y. Repeat steps H.l.w. and H.l.x. alternately until instrument reads i 20% at both dose rates.

z. Go to step H.l.b. and repeat the step through H.l'.l.

recording the results in the As Left column.

NOTE Even though the instrument is 1 20% of calibration points every effort should be made to make it read as close as possible to the calibration points.

-n v

c 62HI-OCB-005-0

% ,/

0 7 of 12 aa. If the instrument checks out properly, complete instrument Calibration Data Sheet turn switch OFF, replace the calibration data sticker with a new one bearing this test date on it and when the instrument is due for its next routine quarterly calibration.

bb. If the instrument cannot be calibrated initiate repairs.

cc. Repeat Section H.1. when instrument is repaired.

2. Model 6112D

a. Turn function switch.to B and make sure the battery voltage is over 4 volts. If less than 4 volts, replace batteries before calibration.

b. Turn the function switch to the R/hr position,

c. Place the instrument in the following fields 10 R/hr, 1.50 R/hr, 200 R/hr, and 750 R/hr. Note the readings on Data Sheet 2. If the readings are within + 10% of the

() -

required reading go to step H.2.j., if not continue.

d. Set P9 on its right mechanical stop.

'e. Place instrument in a 10 R/hr field and adjust P5 until 10 R/hr is indicated,

f. Place instrument in a 150 R/hr field and adjust P6 until 150 R/hr is indicated.

g. Place instrument in a 750 R/hr field and adjust P2 until 750 R/hr is indicated,

h. Place instrument in a 200 R/hr field and adjust P9 until 200 R/hr is indicated.

i. Indicate on Data Sheet 2 all readings As Left and which pots were adjusted if any.

j. Switch the function switch to the mR/hr range.

k. Place the instrument in the following fields 10 mR/hr and 750 mR/hr. Note the readings on Data Sheet 2. If the readings are within + 10% of the required value go to step H.2.n., if not continue.

(~s 1. Place the instrument in a 10 mR/hr field and adjust P3

(_ until 10 mR/hr is indicated.

62HI-OCB-005-0 i( 'g

'pf 0

8 of 12

m. Place the instrument in a 750 mR/hr field and adjust P7 until 750 mR/hr is indicated.

n. Indicate on Data Sheet 2 all readings As Left and which pots were adjusted if any,

o. Switch the function switch to mR and place the instrument in a 10 R/hr field for 36 seconds. The instrument should indicate 100 mR + 10 mR.

~

Record the results on Data Sheet 2.

p. If the instrument checks out properly complete the calibration Data Sheet 2. Replace the calibration sticker with a new one bearing the next quarterly calibration due date.

q. If the instrument will not check out properly and falls out of tolerance repairs must be initiated.

m

5 l

1 62HI-OCB-005-0 j

(D

.%).

0 9 of 12 l 1

PROCEDURE DATA PACKAGE 1 DOCUMENT NO: 62HI-OCB-005-0 SERIAL NO: ROO-MPL h0:

RTYPE: G15.14 XREF:

i TOTAL SHEETS: 2 i

FREQUENCY: Quarterly COMPLETED BY:

O V

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30AC-OPS-003-0.

ACCEPTABLE UNACCEPTABLE REVIEWED BY:

DATE REVIEWED:

REMARKS:

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

Page 1 of 2 62HI-OCB-005-0 R00 I A FIGURE 1 Page 1 of 2 e r,,,- , , --- ,-,r- - , , - - , - m,--,nn--------,r-------n-- ~-r -,n,,-,-cn.. en ,-,r>--v,,~-,,-,,v , - - - , wr-- -- , - -

62HI-OCB-005-0

- q v 0 1

10 of 12 DATA PACKAGE 1 TELETECTOR MODEL 6112B CALIBRATION DATA SHEET Serial No. MPL No.

Location INSTRUMENT READINGS CALIBRATION ACTUAL AS FOUND AS LEFT SOURCES EXPOSURE RATE 0.5 mR/hr mR/hr mR

. . . . . . . _ _ _ . .. . . _ _ . . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .....___.._____.. . ....._.___/hr _...

1.5 mR/hr mR/hr mR/hr 10 mR/hr mR/hr mR

. . . . . . _ . _ _ _ _ _ . . . . . . _ _ _ _ . _ _ . . . _ _ . _ _ _ _ _ _ _ . ., _ _ _ _ _ . . _ _ . _ _ _ _ _ . ,_.__..___/hr .___

35 mR/hr mR/hr mR/hr 0.5 R/hr R/hr R

. . . . . . _ _ _ _ _ . . . ., _ . . . _ _ . . _ . . . . . . . _ _ _ . . . . . . . . . _ _ _ _ . . _ . . _ . _ . . ..._____.../hr ....

. s 1.5 R/hr R/hr R/hr

\

. (V . _ - _ . . _ . . . . . . . .,_..__-_-._..

10 R/hr R/hr R/hr 35 R/hr R/hr R/hr 50 R/hr R/hr R/hr 200 R/hr R/hr R/hr

-Maintenance Remarks Next cal due date Cal by Date Page 2 of 2 62HI-OCB-005-0 R00 i

FIGURE 1 Page 2 of 2

62HI-OCB-005-0 O

V O 11 of 12 PROCEDURE DATA PACKAGE 2 DOCUMENT NO: 62HI-OCB-005-0 SERIAL NO: ROO-MPL NO:

RTYPE: G15.14 XREF:

TOTAL SHEETS: 2 FREQUENCY: Cuarterly COMPLETED BY:

DATE COMPLETED:

I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH 10AC-MGR-003-0, 30AC-OPS-001-0, 30RC-OPS-003-0.

s:

ACCEPTABLE d hNACCEPTABLE a

REVIEWED BY:

DATE REVIEWED:

REMARKS:

i

- =_______.__....___.___________________..___=--- _ _.___________

Page 1 of 2

!. 62HI-OCB-005-0 R00 FIGURE 2 Page 1 of 2

62HI-OCB-005-0 e

0 12 of 12 DATA PACKAGE 2 TELETECTOR MODEL 6112D i

CALIBRATION DATA SHEET Serial No. MPL No. -

Location INSTRUMENT READINGS

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

CALIBRATION ACTUAL AS FOUND AS LEFT SOURCES EXPOSURE RATE

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

10 mR/hr

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

750 mR/hr 10 R/hr 150 R/hr 200 R/hr

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

750 R/hr

-es 10 R/hr for 36 seconds = 100 mr Q ......--...--...--...---........---- __ ==---.........------- -_..

n Maintenance i

Remarks i

Next cal due date l

i Cal by Date I

i

+

l I

1.

Page 2 of 2 62HI-OCB-005-0 R00 r

l I

J FIGURE 2 Page 2 of 2 I

Y ry, -- - - - r.-~y ,r. ,- - _

e GEORGIA POWER COMPANY

.( HATCH NUCLEAR PLANT 1 OF 14

' .________________________________--__-___-__-_-__PAGE __-__--_--___--____-______

DOCUMENT TYPE:

DOCUMENT NUMBER:

HEALTH PHYSICS INSTRUMENTATION

.__________________________________________________62HI-OCB_006-0 _______________________

DOCUMENT TITLE: _

COUNT RATE METER PRM-4A OPERATION AND CALIBRA

.______________________________---_____________ TION ____________________________

X SAFETY RELATED NON-SAFETY RELATED EXPIRATION DATE: st/ /9 REV .

APPROVED APPROVED NO. DESCRIPTION DEPT. MGR. EFFECTIVE DATE GENERAL MGR. DATE DATE 0 Replaces HNP-8102 __________f_

g

_____________________ _ __ _g)

_f f .g /

g, q ___gf_ __g g.

y _____

( ______________ ______ ___________

1 i-i i' _____________ _______ __________

\

i _____________________ ____________ ______

e s

i s __________________ _____________ _______ __________

(

I.

i l _____________________ ____________ ______

s MGR-0002 Rev. 1 r

l l

L

() 0 2 of 14 COUNT RATE METER PRM-4A OPERATION AND CALIBRATION A. PURPOSE To establish a standard technique for operation and calibration of the model PRM-4A rate meter with Geiger-Muller and scintillation type detectors.

B. SAFETY Observe radiation protection procedures. Observe safety rules outlined in Georgia Power Company, SAFETY, Section "O".

C. REFERENCES

1. Count Rate Meter Model PRM-4 Technical Manual.

2. Mini-pulser Procedure 62HI-OCB-018-0.

3. Eberline Checkout Procedures.

D. TEST EQUIPMENT

1. Mini-Pulser with coaxial cable.

2. Gamma Field

3. Electrostatic Voltmeter.

E. DESCRIPTION OF INSTRUMENT

1. The PRM-4A is a portable, battery-operated pulse rate meter which may be used with a wide variety of detectors for measurement of alpha, beta, gamma or neutron radiation.

Normally the HP-177C geiger detector-is used with the instrument, for measurement of gamma radiation and detection of beta radiation. The count rate is read out by the Eberline Lin-Log presentation.

2. This presentation eliminates all scale switching and multiplying factors, yet retains linear increments within each decade. Four decades are covered using two meter movements to yield a scale length of about 1.5 inches per decade, which gives maximum readability and ease of interpretation. Full scale readings for the four decades are 200, 2K, and 20K and 200K counts per minute (CPM) f respectively, calibrated to read the true pulse frequency.

(

' ("T

\~) 0 3 of 14 F. DESCRIPTION OF CONTROLS

1. External Controls,

a. Switch-three position switch-turns instrument OFF, ON or BATT. Spring return from battery check position to ON.

'b. High Voltage Adjustment - controls magnitude of high voltage applied to the detector. Clockwise rotation increases voltage.

2. Internal Contrcls.

a. Calibration Controls - four controls to adjust the meter reading to agree with pulser frequency.

b. Sensitivity Controls - 20 turn variable resistor (R207) mounted on card P202 adjusts sensitivity of detector.

G. OPERATION OF INSTRUMENT

' l. To operate instrument turn the switch to the BATT position.

The left pointer (Black) should read in the green area. If the black pointer does not read in the green area, tag instrument out with a TO SHOP tag stating the reason (s) it was tagged out.

2. Read the Pointer that is on scale. The Black pointer is read up to 2K CPM then it disappears from view and the Red pointer is read. Fluctuation of the pointer is normal and is caused by the random nature of radioactive emissions.

3. When using the earphone a click will be heard for each event counted. Using an SK-1 speaker, only one-half the number of clicks will be heard.

1

4. .When surveying a general area for gamma radiation with the HP-177C Geiger-Muller Detector, the probe should be held i

perpendicular to the source of radiation and at waist level. For beta detection, open the beta window and hold the detector as close as possible to the surface being

surveyed. Now close the beta window and monitor the surface again. When no significant difference is seen in the needle deflection with the beta window open and the beta window I

closed, the radiation should be reported as gamma only.

When significant differences are seen in the needle S deflection with the beta window open and the beta window

(~/

x_ closed, beta radiation is present. For true beta dose rate, obtain an R0-2A or R0-3A.

i i

L.

~

(~T

%-) o 4 of 14

5. Daily Calibration with Scintillation Detector.

a. Turn switch to the BATT position. The left pointer (Black) should read in the green area. Check BATT Ck.

column of Data Sheet 3 if pointer is in green area.

b. Release switch and it will return to the ON position.

c. Obtain an average background count and record on Data Sheet 3 in counts per minute (C.P.M.).

d. Place a radioactive standard (Cs-137-4) in the center of the bottom detector surface and obtain an average source count. Record on Data Sheet 3 in C.P.M.

e. Subtract the background counts from the source counts and record this source not counts on Data Sheet 3.

f. CalcElate the detector efficiency using the following formula and record on Data Sheet 3, ensuring that the efficiency is greater than or equal to 5%.

O Source Detector Efficiency = Net C.P.M. X 100 Source D.P.M.

H. CALIBRATION OF INSTRUMENT WITH HP-177C HAND PROBE

1. Remove the instrument from the case and silica gel.

2. Remove the High Voltage Supply from instrument. (P-201A).

3. Turn the control switch to BATT position and check battery condition. Black pointer must be in green area, if not replace batteries.

4. Connect Mini-pulser at spring connector (Junction R8 and C2-marked on the instrument). See Figure 1.

5. Set Mini-pulser for negative pulses at' 10 millivolt amplitude and adjust sensitivity control pot (located on P-202) for optimum setting of 10 millivolts.

6. Set the Mini-pulser frequency to 160 cpm, 1,600 cpm, 16,000 cpm, and 160,000 cpm successively and check and record readings on Instrument Calibration Data Sheet 1 in the As Found column.

/)

\/ 0 5 of 14 NOTE Even though the instrument is 1 20% of calibration points every effort should be made to make it read as close as possible to the calibration points.

7. If readings are within i 20% of the Mini-pulser frequency, turn instrument OFF, remove Mini-pulser cable, replace High Voltage supply card and silica gel, place instrument in case and proceed to step H.15.

NOTE Check crossover points on the LIN-LOG scale by using 1,000 CPM and 100,000 CPM input frequencies respectively. Readings.should be 1,000 1 400 CPM and 100,000 + 40,000 CPM. Do not record these results, but if instrument is not within these limits proceed to step H.8.

8. If readings are not within s 20% turn R3 and R5 to maximum clockwise position.

I(_)

9. Adjust High Voltage to 900 valts, see Figure 1, and record the MPL number of the electrostatic voltmeter used in the REMARKS section o,f the Instrument Calibration Data Sheet 1.

10. Set the Mini-pulser frequency to 160 cpm and adjust R2 for proper meter reading. Record reading on Instrument Calibration Data Sheet 1 in the As Left column.

11. Set the Mini-pulser frequency to 1,600 cpm and adjust R3 for proper meter reading. Record reading on Instrument Calibration Data Sheet 1 in the As Left column.

12. Set the Mini-pulser frequency to 16,000 cpm and adjust R4 for proper meter reading. Record reading on Instrument Calibration Data Sheet 1 in the As Left column.

13. Set the Mini-pulser frequency to 160,000 cpm and adjust R5 for. proper meter reading. Record reading on Instrument Calibration Data Sheet 1 in the As Left column.

NOTE Check crossover points on the LIN-LOG scale by using 1,000 CPM and 100,000 CPM input frequencies respectively. Readings should be 1,000 + 400 CPM and

(( s) 100,000 1 40,000 CPM. Do not record these results, but if instrument'i,s not within these limits proceed to step H.8.