ML20076F687

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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8137 Re Portable Ion Chamber Model RO-2A,HNP-8143 Re Low Vol Air Sampler Model H-809 V1 & HNP-4200 Re General Fire Procedure
ML20076F687
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/24/1983
From:
GEORGIA POWER CO.
To:
Shared Package
ML20076F677 List:
References
PROC-830524-01, NUDOCS 8306140254
Download: ML20076F687 (37)
v • d • e


Text

{{#Wiki_filter:m t [k { GEORGIA POWER COMPANY i HATCH NUCLEAR PLANT a PROCEDURE 4 h Portable Ion Chamber _ Model RO-EA O era' bion And Calibration i PROCEDURE TITLE 1, HNP-8137 'i .I ~% PROCEDURE NUMBER l i Lab RESPONSIBLE SECTION I e, l' SAFETY RELATED ( X) NON-SAFETY RELATED ( ) l I APPROVED APPROVED REV. DEECRIPTION DEPT. PLANT DATE HEAD }-..--- MANAGER [ .----------'u 4 .- - L K.d.L g { Pages 1 th 1 g ,/ -? / ~. ( 9 3 ) .----------------l-------------_ HNP-9 8306140254 830606 PDR ADDCK 05000321 PDR F MANUAL SET t

~.. - g Pl.i.O..C F..C. t_u_tE_GU_V._i f _TO_n..t G_FO_t_e..C_T d PROCCCURE rd. 1INP __ Q.:?.__l_ _ _ _. t ,~.* f Revir, ion No. 4 --________1_____.-__-.___. a R FGl': F T.F_D_ O_Y_ _ _ _ .__ __ _ _O_f_P__ A.R T _GI.T. _t_- rF_,' n.._,_a.P_P_: a.~.:W I_. _ __ _. _Datc: Date; Signature: Nm:ve; _//_ - A -//~ 0_..____ O_ f_ _t _- 1 /' m 0 INTENT 'S DEGCRIDEO IN FSAR: l REVISICM CH.2.NGEC McCE OF.CPERATION OR ( ) Yes ( No l i ( ) An unreviewed Safety Guestic.n ( ) Tech. Specs. ( ither l CHANGE INVOLNES: ~~ (See bacl< f or Saf ety Eval uation if required). I i ( Non-Safety einted ( ) g SafetyRe[ated Rafety/Non-safety Status Change ( ) Yes ( No Attach mariced up copy of procedure to thi's form. ul_~ v'4gW_.,xb h, c/'/fgk_.q';/(yyg_. _jf -//f/_ L f,__--. l REASON FOR REGLEST o 'E?L _ 5 YG h 5 k h $?<5lk C hhMb.' E A C$$1_b__5f W b5 .bd"r"N_h]%-.w_emaimda$.bMm A_d'EL - .d 't AS. /mtg_[L&k di'"dla_" aaJaa'Le& _. .L N 2 'aad Aaal bit __bsszeue.i_ k ' /' \\ n 4 ( /)Ye s ( )No re. 3 PRR RECON:C CO,'.PPROV,^.L: Pl<D..6eretary i N 83-G3 -._.__._ __-_-_l4.Lkl l..- L Date PRO Numi,er I tNP '.7 A Al S.ET..

w c . SA..f.*.ETY I.N. A..,.UA..T...T. t t. e e. rocedure does not constitute an unreviewed.:afety----- ---- _ . Q i f thi T.h.o '_r.e.v..i.s o.n..o-s...c. -... - question as explained belcw. -- ---- - - ---- - --- ----- -----------_- --- ------------ f a_n_ _a_c_c.i.d_e_n - ~ he proba.b._ility o..f.._ occur _rsncq.and ths f.o_n.Secu_e_n_c_es _o 1. T -- n.c.-- s e d ti rea f - or ----.n.c.- .o.- equi cme..n..t import. an.t. to s a etJ'.are.n.o malfu tion f ..o.v.- th.e--a on_a.lyzed.i.n thg FS AR dJLe_10..lbf.ic..CbADSES_b.CCAUSE_ -- e ab f ce of _th_ e th_e revi.s.i.on d.o._es not chance th.e our.o.se o..r. 9.er orman - J-t i. sy_ stem.--- _- ----- - - fferent t.vo__e. --- oss.i.b.i.li ty of a..n._ acci dent or ma.l. fun.ctio.n.o..f. a di The p 2. lt from this chance because -e.-.t.h. an anal' zed in the F. SAP, does not r..e..s.u l

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f th.e. chan.ce. -- - Y.ste.m. res.o.onds and is operated as be ore 1 the s i I i lS ifications-3 _The marcin of safet.y as de.f.ine_d in the Techn ca - oec CD' ' is not reduced due to this revision because the revision does not k'l; ~ 'l chance any limited safety system set _tinas which would allow a 21 l' = = safet1;- l,.i.m.it to be exceeded 'or to allo'.ur a limitino _ condition for Snecifications. operations'to be exceeded as_ stated in. Technical 1 e .umm.*..E. t l .m m..m. e. .mm..m. .s. .e..u u. --.u..u.. m m..e. -~ eu81..uk -- -~..m -.m.- f -.m. -.m. - -- :- I --.m.e..m..su..u.-.* - -.um u.em. gm. .m. .m.eu..um m.um. -".m.-.m..u..u. i

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====~o 4 r ova' my,siou uo Sao Title Pagt GeorgiaPowerd .- ~o 1 of 7 hf> omSee Title Page , PORTABLE ION CHAMBER, t_10 DEL _RO-2A OPERATION _AND CALIBRATION {i A. PURPOSE f To insure instrument is calibrated properly and'to provide guides ~ j for.the user. l B. REFERENCES Portable Ion Chamber Model RO-2A Technical Manual. 1. i .2. Gamma Calibrator Procedure. Eberline Instrument Corporation Check-Out Procedures. 1 3. l~ C. SAFF-TY Observe Radiation Protection Procedures. D. TEST EGUIPMENT {$p 1. Gamma-Calibrator. -2. Calibrated Beta' Source. 3. 92 mci CS-137 Source. E. DESCRIPTION OF INSTRUMENT _. The lon Chamber, Model RO-2A, is a portable air ion chamber instrument used to detect beta, gamma and X-ray radiation. The RD-2A has four linear ranges of operation to measure dose rate. The ion chamber is vented to atmospheric pressure and is specifically designed to have flat energy response into the X-ray l region. F. DESCRIPTION OF CONTROLS __ 1. Function Switch: Eight position rotary switch that turns the instrument OFF, checks the condition of the batteries, checks instrument ZERO, and selects the range of operation to be used. Used to set the meter to zero when ZERO switch 2. ZERO Hnob: position is selected, or when in an insi'gnificant radiation k field. I MANUAL SET L

w r_ h== E. I. Hatch Nuclear Plant "=u== ~o HNP-8137 Geor8 a Power A. umiou no S:e Title.Page l ~m. om 2 of 7 See Title Page-

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Calibration Controls: Four variable resistors, one for each range. G. OPERATION __OF INSTRUMENT '1. 3" urn the function switch to BAT 1, and then to BAT 2 ~ position. The meter should read above the BATT cut-off line in both cases. ~ NOTE If BAT check on any range does not indica te good, tag instrument out with TO SHOP tag. 2. Turn the function switch to ZERO position. Check that the meter reads zero. If not,-set it to zero with the ZERO knob. 6 3. Set the function switch to the desired range of operation. The switch position selected is the full scale reading of that range. NOTE When selecting the most sensitive range 50 mr/hr switching Ocv transient noise may cause a temporary deflection of the needle, This can be avoided by turning the function switch through the ranges slowly stopping at the 300 mr/hr and letting the needle settle, and then switching to the 50 mr/hr range. 4. When measuring beta or low energy gamma or X-ray emissions, open the sliding beta shield on the bottom of the case and face the bottom of the instrument toward the radiation source. To open or close the shield, depress the friction release button on the left~ side of the case and manually move the slide or let it fall due to gravity. When the shield is open, protect the thin face against damage by puncture and radioactive' contamination. NOTE The effective center of the ion chamber is marked by dimples at the front and sides of the instrument case. The zero setting of the instrument may be checked in radiation fields by merely selecting the ZERO position. Since the ion chamber is vented to atmospheric pressure,.it is sensitive to changes in both air pressure and j temperature. Tables 2-1 and 2-2 in the Technical Manual gives correction factors which should be used if the instrument is used in conditions of significant differences from the calibration conditions. MANUAL SET. g.

l-E.1. Hatch Nuclear Plant "===~o t~m= HNP 0137 i See. Title Page m ys,on oo Georgia Power d 1 mme om See Title Page 3 of.7 H. DOSE' RATE INTERPRETATION 1. Gamma _ radiation. a. When no significant difference is seen in the needle deflection with the beta window open and the beta window closed, the radiation should be reported as gamma only. When high gamma dose rates are present low beta dose rates may go undetected unless a smear is taken and removed from area and surveyed for' beta dose rate. b. When significant differences are seen in the needle deflection with the beta window open and beta window closed, the gamma exposure rate is the meter reading with the beta window shut. The indicated beta exposure is the difference between the reading with the beta window open and closed. NOTE The meter reading above will reflect true dose rate exposure only for true field dose rate. This is when the intensity of the radiation in all parts of the chamber is practically the same. Small beams, point CN i sources, and small line sources will give meter 0-readings less than actual exposure ratesand must be l evaluated on an individual basis. 2. Beta __ radiation. The beta contact dose rate for a source at least as large as the window on the RD-2A is meter reading window open less meter reading window closed times beta correction factor on the side of the instrument. NOTE The beta correction factor is only for a source at least as large as the beta window. Sources smaller will have to be evaluated on individual basis. I. GAMMA CALIBRATION _OF INSTRUMENT (Guarter1rl_ CAUTION The gamma field intensities required for calibration of the RO-2A are potentially hazardous to personnel. Observe precautions to prevent over exposure. 2 l MANUAL SET w

E.1. Hatch Nuclear Plant

== mocwum ~o HNP-8137 See Title Page es os uo Georgia Power A 2 cm ..m ~e e See Title Pace 4 op 7 NOTE lt is very important that the_inside of the chamber assembly be kept dry to avoid leakage currents due to moisture. If the desiccant becomes saturated and the RD-2A becomes .tcratic due to m'oisture, renew the desiccant crystals and cycle the instrument between room temperature (or lower) and + 140' F. three or four times to flush the chamber air across the desiccant. CAUTION Avoid any contact with electrical components with the hands as damage to the amplifier will occur. 1. Turn the function swi.tch to BAT 1, and then BAT 2 positions. The meter should read above the BATT cut-off lines in all cases. NOTE The entire chamber assembly must be in the gamma field. l 2. Turn the function switch to zero, check zero off-set. If not on zero, turn the ZERO knob until the needle comes to 7-the zero position. 3. Turn the function switch to 50 mr/hr, place the instrument in about a 10 mr/hr and 40 mr/hr gamma field respectively, and check the readings. Record the readings on the Instrument Calibration Data Sheet (Figure 1) in the "As Found" column. 4. Turn the function switch to 500 mr/hr. Check zero off-set. 5. Repeat Step I.3 for about 100 mr/hr and 400 mr/hr fields, respectively. 6. Turn the function switch to 5 R/hr. Check zero off-set. 7. Repeat Step I.3 for about 2 R/hn and 4 R/hr gamma field, respectively. S. Turn the function switch to 50 R/hr. Check zero off-set. 9. Repeat Step I.3 for the 10 R/hr and 40 R/hr gamma field, respectively. 10. If the instrument reads within i 20% of the actual dose rhte in Step I.3 thru I.9, write all values recorded in the "As Found" column into the "As Left" column, and proceed to Section J. MANUAL SET f' ,m.,

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== raxtw ~ HNP8137 }. Sro Titic Pcg2 oom,o,,,,o Georgia Power n l' k -,,o See Title Page 5 of 7 j 11. If the instrument does not read within i 20% of the actual dose rates in each field, continue with Step I.12. 12. Turn the function switch to 50 mr/hr. Check zero off-set. Place instrument in about-10 mr/hr and adjust the 50 mr/hr 'E6ntrol resistor until the meter indicates the field reading or i 20% of this value, also check the-40 mr/br dose rate using a field of about 40 mr/hr. Record meter values in the "As Left" column. 13. Turn the function switch to 500 mr/hr. Check zero off-set. Place instrument in about 100 mr/hr field and adjust the 500 mr/hr control resistor until the meter indicates the field . reading i 20% of-this value, also check the 400 mr/hr dose rate. Record meter value in the "As Left" column. i 14. Turn the function switch to 5 R/hr. Check zero off-set. Place instrument in about 2 R/hr and adjust the 5 R/hr control resistor until the meter indicates the field reading or i 20% of this value, also check the 4 R/hr dose rate. Record meter values in the "As Left" column. 15. Turn the function switch to 50 R/hr, check zero off-set. Place instrument in about 10 R/hr and adjust the 50 R/hr control resistor until the meter indicates the' field reading y'.. ~ or i 20% of this value, also check the 40 R/hr dose rate. 1 Record meter values in the "As Left" column. " J. BETA CALIBRATION OF INSTRUMENT (Guarterly) 1. Zero RO-2A, place instrument on center of the beta source l slab (beta window closed) and measure gamma radiation, } record in the "As Found" column. Open beta window (as in G.4) and measure radiation level, record in the "As Found" column. Subtract the gamma reading from the beta, gamma reading. This is the beta indication. l Determine a beta multiplication factor by dividing 230 (Beta slab reads 230 Mrad beta) by the indicated beta dose rate. Record this value on Figure 1. After calibration is complete, replace calibration sticker-and beta multiplication factor on instrument. CAUTION When RD-2A needs.to be removed from its can, use caution when replacing can, beta window on detector can be punctu' red by the bolt on the tension bar in the can. 4 = MANUAL SET j g

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atvisio o Sao Tit 1e Paga Georgia Power n e.m ~o 6 of 7 See Title Page NOTE When adjusting control resistors is complete, replace caps }. I. on resistors while in field so if resistor turns while caps l it can ~~hre being replaced causing meter reading to change, j be determined. NOTE ~ be sure to check If changing mylar is necessary on RO-2A, mylar with a ohm meter and put conductive side to the inside of the detector. r 1 e a s 4 J k MANUAL SET 0 v

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. =. e L GEORGIA POWER COMPANY-g HATCH NUCLEAR PLANT PROCEDURE Low Volume Air Samp_ler Model H-809 V1 PROCEDURE TI.TLE HNP-8143 '^ PROCEDURE NUMBER Lab RESPONSIBLE SECTION l . { SAFETY RELATED ( X) NON-SAFETY RELATED ( ) } s ,.________________e_______. APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE i l HEAD .___ /_ MANAGER e _ _ _7 _ _ _ _ '...___ ____ N I / (W_..__,_+__ C. iW_ J_. .o , b_. 1 Pages 2 & 4 9 ..u .__ y_ __ __ / l %[j - _ _2 _ _ _.. _P_a_g e_s _2_ _&_ _5_ _ _ _ _ _ _ _ _ _.._ _ $30_7 %u 2_. _,. _ _ fh_ _ _ _ u, _//,/__../Q#/_#3 l' 6 I m.,, v i 1, I l 4__ t i< i t c 1 i I i u w 'i - d I, MANilAL SET j 1

(U* - P R o..c r nttG E nt:.V T G t Ost Grot : GT It..:P.,,__ [ / M _ PROCCCURE t!O'. ./ Revision No. ,/ i - ---- ---- --- e.t-tFi.'.O AP P : < O'.' A.I. Of P.'.R T M 9 1T ._-.___-- - Fe.U::F.T.FD_DY + R -- D M e * -- Signature: Date: ru.me; ..----- p-- N.j------- 3.y r3 - w------ a a 9M REVISICt! ,M.'st:0p.. MODE OF.CPERATICM OR INTENT .S DEGCRIDED IN FSAR: ( ) Yes ( No CHANGE INV0l.VES: ( ) An unreviewed Safety Guest' ion (- ) Tech. Specs. ( l-VTInithe r (See back for Safety Evaluation if required). SafetyRe[ated ( Non-Sofety Related ( ) Safety /Non-safety Status Change ( ) Yes (Mo G =. Attach mark:ed up copy of procedure to thi's form. ~ f / ' fg__ REASON FdR REGUEST o_ J,lO N y & l s _ _ f 2 ff f _/ $ ? Q } - - } Q a# Y .-.... H n_A Utg' e r - p,.:- m y -: y m ~n,, M.. "g.c f,C_k2?f9 P -/e- -

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The possibilit1 of an accident or malfunction of-a different tvoe ? 2. v u th_an ana_l,yzed_in the FSAR does not result from this chanae because s_t.e._m r_e_sponds and is ' operated a.s.=before t.h..e. c_h_a.n.ce. _. the sy --_ _h__e maroin_of safe _ty a_s defined in the Technical Suecifications' 3. T - -- -= is not reduced due to__this_ revision becau_se the_.r.e_vi_s. ion _do g.y ~ i a_ -- _ c_liance anv li.mited.s.afetL' s_ ystem settinos wh_ic_h wo_u_ld _all_o_w a i for --.f.e.t'Y._l,imit to be exceeded' or to al.l.ow a.l.imitina condit on sa. ooerations to be exceeded as stat _ed in Technical Snecifications t r. --I 4 e' t .u e h i [ 'i 1 I - - =. - - - - ~ i z -_.u..u..h.e-.u.-l._4.B._.u..mu.M.mu..u.--gg.hg..W*-_--.'- HNP-9 ii g ilAHAL SET 9 ! L. 4. _.- -.,. _,-, _,_.,. ,-m ,..._.~~...~-._--...M,#

L =w m E..l. Hatch Nucinar Plant - . nouwac ~o ^"av^v HNP-gi43 atmios uo Georgia Power d S:o Title Pcgo { o.u ~ , np q Ron' T4+1r. Ungn LOW VOLUME AIR SAMPLER _MODEL H-809 V1 A; .P_U_R_P_OS_E 7 i m To establish a standard technique for the operation and calibration of RADeCO Low Volume Air Samplers. [ B. EAFEly f 1. Observe radiation protection procedures. i 2. Observe safety rules outlined in Georgia Power Company, SAFETY, Section "O". v e' C. REFERENCE @ HNP-8013 Airborne Radioactivity Concentration Determination 1. 2. RADeCO Model H-SO9 V1 Low Volume Air Sampler Operation and e Maintenance Manual P 3. RADeCD Air Flow Calibrator Instruction Sheet, Model C-828 M. D. TEST EGUIPMENT 1. RADeCO Air Flow Calibrator, Model C-828 2. RADeCD Venturi Tube, Air Flow Calibrator Adaptor E. DESCRIPTION OF INSTRUMENT 4 The RADeCO Low Volume Air Sampler is a compact unit used for obtaining a grap sample of a large volume of air which is monitored for particulate.and radiciodine airborne The model H809V1 may be operated at a fixed flow radioactivity. rate or variable flow adjustable between zero and approximately 90% of maximum. F. OPERATION OF INSTRUMENT 'Remrve the outer ring on the sampler head by turning it 1. counter clockwise and install a 47mm glass fiber filter into Be sure the filter paper seats properly at all the holder. points or it may tear the paper. Replace the outer ring by turning it clockwise. i f MANUAL SET

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~~ ~~ No 9 E..l. H;tch Nucinar Plant %v:t HNP-8143' t uvisioN NO O, -See1 Title Pega Georgia Power m- - No om 2 of 5 Sep Titio Paoc 2. -Open the charcoal cartridge holder by turning the inner ring. counterclockwise, and place a charcoal cartridge into the holder, noting the direction of flow through_the cartridge. Replace the inner ring ~by turning clockwise, and make sure l l ~~ihat both rings are securely together and tight. l Turn the VAR-OFF-HI switch to the VAR position and' adjust 3. the flow rate by rotating the control knob labeled FLOW ADJ. to 3 CFM and note the TIME ON. p e 4. Allow the sampler to run a minimum of 35 minutes at 3 CFM to achieve a volume of RI 100 cubic feet, then turn sampler off and note TIME OFF. /. 5. Take the sample collected back to the H.P. office for counting as soon as possible. Place the glass fiber filter in the holder of the counting scaler and count it for 5 minutes. 6. Remove the charcoal cartridge and wrap it in plastic wrap, and label both the filter and the charcoal for counting room j

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Follow instructions as found in HNP-8013 and complete Figure 2 of HNP-8013 using the appropriate formulas given on the

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U bottom for calculations. G. CALIBRATION The sampler is calibrated once every (3) three months or as often as needed using the RADeCO Air Flow Calibrator, model C-828. 1. Place a charcoal cartridge in the sampler as though preparing to take a sample. Remove outer ring and place a 47mm glass fiber filter into 2. holder. In place of outer ring, screw the RADeCO Venturi Tube into it's place. Plug sampler in and turn VAR-OFF-HI switch to HIGH and allow 3. a warm-up time of 2 minutes. Connect the Venturi Tube to the VAC outlet of the Air F1'ow 4. Calibrator, making certain the INTAKE on the calibrator is r open. Adjust the screw at the top of the air sample rotameter - 5. until the rotameter float indicates the flow rate shownkby j the Air Flow Calibrator. Record this value on Data Package 4 1. i A, e MANUAL SET J'

~ ~ E. l. Hatch Nuclear Plant "==ac ao r~om HNP-8143 ' Sse-Titic Paga Georgia Power d-mm ~o 2 of 5 p _Sen T!+1e Pagn i 6. Turn the VAR-OFF-HI switch to VAR and then adjust the control knob labeled Flow ADJ. until a rotameter reading of I 3 CFM is observed. Take a reading from the Air Flow Calibrator meter pointer and record on Data Package 1.. 1 7. I);the. observed reading'is 3 CFM i .3, lock the retainin_g nut on_the rotameter screw down and place a drop of " correction fluid" gr similiar substance on the threads. This creates a seal to prevent further adjustment from being i made without detection. If readings are not 3 CFM i .3, repeat steps G.5 and G.6. 3 l Remove the charcoal cartridge from its holder and place the 8. sample head back together. Repeat steps G.3 through G.7 for l the glass fiber filter only and record results on Data Package 1. + 9. Remove Venturi Tube and replace outer ring on sample head. Record any adjustments made in the MAINTENANCE PERFORMED section of Data Package 1 and replace the calibration sticker with a new one bearing this test date and the next routine quarterly i 14 day calibration date.

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.i I i l I i i k MANUAL SET

g;,,, E. l. Hatch Nuclear Plant raouwn ~o p.ca-. HNP-8143 3 uvision o See Tit 1e Page GeorgiaPower d 2 um,.o 4 of 5 -Goo Tiile Pao" er .w a n.o 4 PROCEDlFE DATA PACKACE DOCtkOJT NO: H P-8143-1 SERIAL. PO: R02-PPL ND: R M E: C15.14 LW: r TOTAL SFEETS: 2 FREGLENCY: CurPLETED BY: ' W. 's oATE CcrPam: I HAW RE.VIEbED THIS DATA PACKACE FCR CorPLETDESS i NO AGAINST ACCEPTANCE CRITENIA IN ACCCRD44CE WITH HP-830. 4-LNACCEPTABLE ACCEPTABLE REVIEWED BY: DATE REVIEWED: i REMARKS: i i I i Page 1 of 2 HP-8143 RO2 t 9 FIGURE 1_ Page 1 of 2 s i MANUAL SET 9

- ~., E. l. Hatch Nuclear Plant-raocewao.o H ' '+-o - [ HNP-8143 nevisio= ~o See Title Paga 2 Georgia Power a- .. m. r.m _f.fi. Titla Paan g op g l f DATA PACKA0E_1 (Data Sheet 13 I R_ADgCD H-Sp}_y1_C&lPRAT10N SHEET 4 i-h I M.P.L. t& EER SERIM. NJMBER l l, ,/s {; s AS FOUPO s i CFM WITH GLASS M O CHARCOAL t CFM WIIH CLASS M D CHARCOAL (AT 3 CFM) i f~ CFM WITH CLASS FILTER OFLY s> _s i CFM WITH CLASS FILTER OtLY (AT 3 CFN) n AS LEFT f CFN WITH GLASS MD CHARCOAL CFM WITH CLASS NO CHARCOAL (AT 3 CFM) J ~ CFM WITH CLASS FILTER CrLY CFM WITH CLASS FILTER OrLY (AT 3 CFM)

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TEST EGUIPPENT USED: _MPL (FLOW PETER) } MAINTENANCE PERFORPED: t I N t \\ LOCATION: CALIBRATED BY: s DATE: 4' + l i g l' i i i l I P r s. ,\\ s i Page 2 of 2 HP-8143 R02 l 1 i. i. . I' l FIGURE 1 l-Page 2 of 2 ?^ i s, MANUAL-SET i'. ( - - - = -- * -...w S

.z s. A ...._.._.-_a-_._ .,__.f.- t. c ,1 / = 1 .~ /sl GEORGIA POWER COMPANY i,- /. <, HATCH TLC._ EAR PLANT e f. i PROCEDUR.E C + 9 l-General l' ire Procedure PROCEDURE TITLE i.s ,.s i HNP-42OO PROCEDURE NUM3ER t RESPO55'ginee r in_q En IDLE-SECTION / i h n' SAFE.TY RELATED ( ) NON-SAFETY RELATED ( X) a 9 ._____A____ f APPROVED APPROVED REV. DESCRIPTION DEP T.; -,,.,

  • PLANT DATE HEAD I

MAN ER r ( 9 Pages 1 tk 2 g ,,3.g4 ______ ___.._ p.... ._________..___r___. ms' y + .~ s, l r .________.1______. \\ i I 4 4 I ( .___.,__._____e___-. l t s l I L t. l e,.- [ / i HNP-9 2 . o lh MiMAL SET

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(_U.'_T ! ':_'CT. >q j,l y.,,e .a-.-- ~~~~~~l a,.. ,, 6.' 5 i APR 2219Bk Pf(G LCO','.~tE NO. I INP _e/2 0_Q,__._ ___,_,,_ PROCEDURE " ' " ~ N " " * -- - - _ _- __- _- - _ _ _ _.. _ F - r - 7 ;" - ~ n SECTION ._ __. _ _ _ I._ _ _ _ _...r. r n noir ic.. 3 m.__ _ _ _.a c.. r_..c_i : n. _n y _ _ _ _ _ _ _ _ _. _ _ _ _ _. _ _._ _ _ _ _ _. _ _.... _ _._,. _. n. t,,:

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Oste: s1anature,: %slB3 [ 4rCb, wt n_r - 2/-B I 3" ~S ,. :_")n_ ec-rg__-- .-.--__-____.gg TIO:!'CR INTFMT AS CESCRIDED IN FGAR: 'RCVICICN Cl%MGES. MODE OF OPERA ()( ) No ( ) Yes CltANCE lor /CLVES: ( ) An unreviewed Safety Ouestion ( ) Tech. Specs. (X) Neithcr (See back~for Safety Evaluation if required). Safety Related (h) Non-Safety Related ([) ( ) Yes (g) No Safety / Mon-safety Statur. Change Attach mariced up copy of procedure to this form. REASON FOR REGUEST //r/o/ fora co.p_&_8_ J. 4 ( Q__ _ -4 e._..p/eme, f_ _ _P_/c_

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/ _y a ^ f4foi _/ w 2s - I;/In fo.- _P_ar.__B_)_. a_lh_,_h_y.c_L,' Pa. _C. I I _D.I s _,: Pc.rs_.2.. Cl, a m e j epen_t'.av-p s_c.c~_e.l - Ke.ber.cc.e ^'i?b zis -- a l 2.z._._ - - = i i l f G PlIO RCCC"k.~tOS APPRCP/AL: ( )Yes ( )No PRO Gecretc.ry-l [ _ _ _ __ _____O ut e m. P:.0 irym:ier .,n V M:.:P -9 f. s .t. M. MAL SET e A e

7 a c3, N u. a. _ ..;.m. -~ -~----( I \\ s L: ~. e.e ; P r.:.r.1 Y...P.N...l 1..!,* r..f.O..N -. 4 v / 6 ..N0....--..--------------- -..c_au s e th_e__ __ ___ be This chan< e does not involve.a.n unrev.i.ewed saf.e.ty gu.e.stio_n 1 ence and the consequences.o.f an accident or mal f.u.nction ---..a----- /) w P.ro.b.a_bi_l i t y o..f.occu.r.r -.._ ---

n.ot.b..e.en increa_se_d_ _ _

/have - of.e.R9_1Pm.e.nt _ imp.or_ tant t_o sa fet/. are 1 E Tech Spe This change has not violat_ed the margin of safety as defined in-- ..<M. +... 1 w* 4 6 - ibility of an accident or malfunc.t..i.on This cha ne doe------.n.--- _s not increase the p.o. s s v - Ff.S R.t he. --- l di - f.a. di f ferent. tD' e.o.ther.t.han.ana yz..e. n

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i [. mom _ _ __ _ __a.E_ _. 1_. H at_c_ _h...N u c_i ca r P_.l a n t... HNP.42OO raxt=as~o S2a Title Paga umuw uo fm Georgia Power A i' ~. ~o See Title Page 1 of 5 G GENERAL FIRE PROCEDURE A. CONDITION. Fire exists at the Edwin I. Hatch Nuclear Plant. O INITIAL ACTIONS 1. Any_ gerson Identifying a fire in process within the Plant area shall: I a. Notify the Main Control Room specifying: (1) The location of the fire. 6 (2) The type of equipment or material involved. (3) The condition of the fire, to the' best of his/her judgement (E. G. - Large or Small). >ggjf( b. For small fires, the per' son identifying the fire should y 4 initiate fire fighting operations through the use of hand held, portable fire extinguishers, or, ~po c. For large fires, the person identifying the fire'should attempt to isolate the fire by closing access doors at the fire perimeter, and, d. If the penson has knowledge of installed fire suppression systems, he/she should attempt to manually initiate the fire suppression systems for the space inundate'd by fire. 2. Control room gersonnel receiving notification of a fire within the plant area s, hall take the following action: a. Notify the duty Operations Supervisor or Shift Supervisor that a fire has been reported. Specify type, exact location, etc. b. As directed by the duty Operations Supervisor or Shift Supervisor: (1) Sound the fire alarm (SIREN) over the plant PA system and announce: 5 ~ ATTENTION. THERE IS A FIRE IN (here specify exact location, such as; unit no., building name, floor elevation and equipment affected). FIRE ORIGADE RESPOND. Repeat the announcement two more times.

< m Y

,i. Mi MIAL SET

I W eat E. l. H tch Nucl ar Plant aaociouat ~o f HNP 42OO are Titio Pega um.ou so 4 9 < L Georgia Power m.(. ..- ~o See Title Page 2 of 5 (2) If~the fire is in an area that could. pose a . radiological hazard, notify Health Physics to respond to the fire area. ('3) If the fire situation warrants, in'itiate the Plant Hatch Emergency Implementing Procedures. Criteria for declaring a " Radiological Event", " Notification,00 An Unusual Event", " Alert", " Site Area Emergency", or " General Emergency" are specified in.HNP-4320, HNP-4420, HNP-4520, HNP-4620 and HNP-4720, respectively. ~ c. The' duty Operations Supervisor or Shift Supervisor -l shall assign an individual to: (1) Establish and maintain two-way communication,s between the Main Control Room and the Fire Brigade. (2) If the fire occurs on a backshift, weekend or holiday, notify Security Headquarters to initiate the Emergency Call List.

  • f)

(3) Monitor fire status and notify the duty Operations l 5 yf ~ Supervisor or Shift Supervisor of changes that g might affect plant or unit operations. ,,D 'C. OPERATOR ACTIONS 1. If the fire invol'ves an area or equipment that could affect plant" operations, the Unit 1 and Unit 2 Control Room operators shall' monitor unit / plant parameters and shall notify the duty Operations Supervisor or Shift Supervisor of any unusual or abnormal. indications which might occur. 2. If the fire occurs inside any building within the main l powerblock, Radwaste System operators, upon hearing the fire l alarm and announcement, shall: 1 .a. Ensure floor drain sump pumps serving the building area ~ affected are in automatic, and, I b. Notify the Main Control Room when the above step is complete. D. FIRE BRIGADE ACTIONS 1. Fire Origade Chief. a. The Unit 2 Shift Supervisor shall immediately respond l. .to the fire, if he is a_gualified member of the Fire Origade. If he is not, the duty Shift Supervisor that l is qualified shall respond to the fire as Fire Brigade ~ I," Chief. He shall: it 1 MiMAL SET

_ no' Title Pcg2. _. _ HNP.42OO union so 1, ol,, Georgia Power o{ 9 ~mo See Title Page 3 of 5 (1) Secure a battery powered two-way radio. (2) ~Immediately report to the nearest available Fire Equipment Emergency Locker. (3) Don his turnout gear and self-contained breathing apparatus. (4) Secure a hand held, battery powered lantern and a 75' length of rope from the locker. (5) Proceed to the fire area and " size-up" the fire situation to determine the need for assistance from the FESG or local Fire Departments., 2. P1' ant Equipment Operators. i a. Upon. hearing the fire alarm and announcement over the PA system, Plant Equipment Operators shall: (1) Immediately report to the nearest available Fire Equipment Emergency Locker. s (2) Don his/her turnout gear'and self-contained breathing apparatus. (3) Secure a hand held, battery powered lantern, ~* spanner wrenches and a length of hose from the lockerl (4) Proceed to the fire area and make contact with the Fire Brigade Chief for further instructions. E. FIRE EMERGENCY SUPP' ORT GROUP (FESG) ACTIONS 1. FESG Chief (Sr. Regulatory Specialist). a. If on site at the time a fire occurs the FESG Chief shall: (1) Secure a battery powered two-way radio and esfablish communications with the Fire Brigade Chief, the Main Control Room and the FESG Assistant Chief and/or FESG Squad Leaders. (2) Don turnout gear and self-contained breathing apparatus. (3) Secure a battery powered hand lantern. (4) Proceed to the fire area and assist the Fire Brigade Chief in his duties. L t. P. kt' I"*' --o.h MiAUAL SET E* _J

l '.' _'?._m ao m E. l. Hatch Nuclear Plant =t=* ~o H N P 420Q _,_. _ _ _ pn_TitlePage.. or nemumuo k 9 I ". < L,, Georgia Power n em ~o See Title Page 4 of 5 (5) Size-up the fire situation and determine the need ,for off-site support from local Fire Departments, if request for assistance has not already been made by the Fire Brigade Chief. b. If off site, when' notified by the Security Department per the Emergency Call List, he shall: (1) Proceed to the' plant Security Headquarters and initiate actions as described in steps E.1.a above. 2. FESG Assistant Chief. a. If on site at the time a fire occurs the FESG Assistant Chief shall: (1) Secure a battery powered two-way radio and establish communications with the FESG Chief and/or Fire Brigade Chief. (2) Don turnout gear and self-contained breathing p/ apparatus. ,g s + (3) Muster members of the FESG at Security Headquarters and await directions from the FESG or ~OT, Fire Origade Chief. (4) Dispatch additional manpower and equipment to the fire area as requested by the FESG or Fire Brigade Chief. (5) Assist the FESG Chief in his duties and provide technical assistance to the Fire Brigade Chief as needed. b. If off site, when notified by the FEGG Chief or the Security Department per the Emergency Call List, he shall: (1) Proceed to the plant Security Headquarters and initiate actions as described in steps E.2.a above. 3. FESG Squad Leaders (designated Maintenance Foremen). a. If on site at the time a fire occurs FESG Squad Leaders shall: -(1) Secure a battery powered two-way radio and establish and maintain communications with the-FESG Assistant Chief or the FESG Chief. (2) Report to the Fire Equipment Building and don turnout gear and emergency breathing. apparatus. e. I it 6-a M b uAL SET

-i fu=om E. I. Hatch Nucicar Plant =on== ~o HNP.42OO sao Title Pega ~ uvisio~ ~o '., i Georgia Power A -- ~o See Title Page 5 of 5 (3) Secure a battery powered hand lantern. (4) Report to Security Headquarters, if the fire is in the main plant structure, or to th,e fire area, if the fire is i.n any other location. (5). Perform firefighting duties as requested by.the FESG Chief or, Assistant Chief. b. If off site, when. notified by the FESG Chief or Assistant Chief per the Emergency Call List, he shall: (1) Report to Security Headquarters and initiate' actions as described in step E.3.a above. 4. FESG S, quad members (designated maintenance personnel) a. If on site at the time a fire occurs FESG Squad Members shall: (1) Promptly respond to the fire alarm and report to e:fj *f ,,-v the Fire Equipment Bdilding. s (2) Don turnout gear and emergency breathing apparatus. UTi (3) . Report to Security Headquarters, if the fire is in c the main plant structure, or the fire area, if the fire is in any other location. (4) P e r f o'r'm firefighting duties as directed by the FESG Squad Leader or FESG Assistant Chief. b. If off site, when notified by the FESG Squad Leader per the Eme'rgency Call List, he shall: (1) Report to Security Headquarters and initiate actions as described in step E.4.a above. F. FIRE. FIGHTING ACTIONS Fire fighting actions are defined in plant firefighting procedures, 4200 series. Reference the appropriate procedure for the area involved. ~, ,j,, j... _ . p% MiAUAL SET

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  • HATCH NUCLEAR PLANT.

L, J.e PROCEDURE m Portable lon_ Chamber Model RO-4A Op_eration/ Calibration PROCEDURE TITLE HNP-8145 "2^~ PROCEDURE NUMBER Lab RESPONSIBLE SECTION ww-- 7.. s.4-.. SAFETY RELATED ( X) NON-SAFETY RELAlED ( ) 7 APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER .-----.. - - _ - - - - _ - - - - - - - _ _ - - _..-A A m s 1 Pages 1-5 and 7-8 M W _g/tn+-c to f)_. re, T U > N,:oc., .p = m 44e e. e+ 4...+-' 4 -___---_2-a_.. s HNP-9 9 MAMAL SET j s.~af.'.e% ds'.4 i"[ ght>vard W M L2.y m e,d h % M eggs l2

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. M in.M/f ;-4.,,1,_"# REVISION CHAtMES MCCE OF.CPr.RATJCet OR INTE (41 *'3 :T v 4 ( ) Yes (r) No m_ m, 5A$d-WCHANGE INVOtNFS: YY.S[.',1( ) An unrevievied Safcity Guestion ( ) Tech. Spec. '( d either w: (See back for Safety Evaluation if required). J -. ~ m.s.. -. . ( .) W~ ' Safety Related ( Non-Safety Related ......1 b I. Safety /Non-safety Status ChanDe ( Yes ( o " ~~ ~~' W :' @ Qi..- l Attach marked up copy of procedure to thi's form. p._,

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.n .=, n ~ ~ ~.- h.M?P.t.The revisiodlif this~orocedure does not-constitute an unrevie w e.. u..qm n e.,,. - li d beloa.'~ ^ - - - - - - ~

ci ~ _~ quest _i.o.n as exp a ne and th.e q.q.je' uences.of an accident n

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The probability of occurr.e.q- 'M-Y'.h ad.. are nbt increased or malfunction of eguicment icoortant to safety- - - - ~.ga- - ~_. _ a%m above thosg. analvra,.d. in th.a. Fy3 d. a in 1.bao.r,b1'.0.ca.S b.am.JAe m..._. u-my M s. sgq_a. perfor ance of the------------ w ~~ ~ ~ the revision do.e.s n..ot cha.nce the ou.rcose_ or ~. n 54 , eg.u -_ i m.:y< n, - --.1s te m.-- s y w.. a x. ~. . g,,. . ~. ' tiedofadifferen.t.tyce.

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n ., 9' m%~%.x The possibilit of n ac idsn lf - -- y -.a.- -..c.--- t or ma un c. 2. ot result fro.m.-this chance becabse f.C " ~^ 1_ n d: - an analyzed in the FSAR-ss n-_ p n s E_ ~ th . R:; w. the s stem resconds and is c:erated as before the chance.

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c ,y ~- ~ .y. The marcin. of.-safety as defined in.t.he Te.c.hnical. Scecifications -- F W. v / .a_ . t :., ; Y ~ -; _~.' 3. is not reduced due to this rev.ision because the. revision d y. & )_._.. .v A chance an.v lim.i..t.ed-safety s.ystem settin.es which woul.d. allew a---- ...a - ~ , w :.n. itine condition for t....._.-

l. l,imit to'be exceede.d or to allow a lim - - - -

r,-... safet; l e-erations to be exceeded as stated.'.in' Technical Scec.ifica )ir .op -_ m. y, - -. = = - - ~ . ---N 4 --*" N "****""#* o + y _m,-.,._ _g e e t.

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?~ =xt== ~O- . w_. _. a_... HNP-8145 RENN NO. Mon,.T,itle Pc.g2 a.a.. - E ~~. 2 zE-a... b _o , ~... 7, p in g; n g;p ppgp. ,+ a. -e+q m i op g m =.- g ..;e.w.m ..e ,as .~.y sws,v.m.m.w. s (g&gfr::. / ;r "w '. PORTABL.E ~ iCM_f' 5 %.h,. : A<r- ~- 1 J NER"MODEL RO-4A OPERATION / CALIBRATION .n..-,,- f.S*NsiN%5r, i u ~ r c; " W__.. -PURPOSE *.-_ I' ~ ' ...s p g,9,7.w :=. <gw.: m~.n To..,.. ensure the im-ent~is. calibrated properly and to p'rovide u

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^ i tySWMiguides"for the c - tww,.m. n x .r m._ y.,,,. %.m %.Gy c%';B.~.. SAFETY T, . _.,.,. ~... _,. m. m s< n, ~...n ..m mme.m. m p%.,.~.,3 .=r4.~r.. ~s n.<vp % e. 9 EObserve Radiati:-

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. 3 ~ % 2 64.;YC.3 REFERENCES. '? 1 b:fnpp x..., a g,v..gmu. u. .m HNP-8115-Jn_ _ _ _'._,f.g 'T;1.__fGamma CaliLr:t.c Procedure, _ g. W: . ~ - i w.,. _ ~. ~

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....~.-.~2. -Eberline Cor.;. Check Out Procedures t p* 177'; 7 ?* o ~ s ' '. * ~ t m .? ' 'i ~._3, .~RO.4.A.Tec";- Manual -_ . _.~ -., , _a. ~ ,y , a ..,?. % ~. J.. D.. TEST EQUIPMENT 1. w g .s\\r .. r 7-.- ~ m1.m.. Gamma Ca,;. -. ;r.. ~. - m n. .;,j n.- C?$ptrah c.; m u

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' Depleted U v ',- Beta Source #U235-6 l s l.~..--.. E. , DESCRIPTION C. 1_. MENT .~

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,~. _ t you ale air ion chamber used to measure beta, LL

The RO-4A is &

i gamma, and X-r.=f 2ation. The RO-4A has two linear ~ ranges of operation to me?co dose rates. The Rd-4A is vented to f ~ atmospheric pr and is designed to have flat energy response i into the X-ray ree-a. The model RO-4A is sensitive to beta, 'f gamma, and X-r e !ation and is calibrated to beta and gamma radiation. A sing;_ rotary switch turns the instrument.off, checks zero.setti~ and selects range of operation. ,7 F., DESCRIPTION,OF CC 21.E 1.. Function Swi; Four pos stary sw'itcts tha,t turns the instrument OFF, checks ins. _ .,t ZERO,. and selects the range of operation. k' 2. Zero Knob Used to set.the LCD display to zero when the Zero switch . position-is se. acted. a .x . n,,- . (... s,. ' '. 4 .oy. MiMAL SEi .h u A., - d

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7 Two variable resistors, one for each range. ' %;n,,.. ~ r.. We&& @. 4, LighE Button 5

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mw .. - ~.. kg _;.3 % 7 ,nWhen the LIGHT button it' depressed, the lamp inside the LCD m x m,,..-. e - _ -.wilI come on. ~ .n ~ m.m;;w kggg.acw. h;6.. -. sa. s.;ln the mr/b: range full scale reading is 1999 mr/hr. kMNr m ~ ~When 1999 m.-/hr is exceeded, the LCD will display' a 1 tWW PF/ F "* w ~ (one) in tM far left side of the meter and all blanks g;;, =x =.; d.. w. ~

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.T 7to the right of the 1 ~(one). yi -~

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=~ ;w:- . w - e~~ Tr 1 J n ;. _ _ b. ;. In.the R/hr range the full scale is 199.9 R/hr. IIf 2 . F 5. 3... d.. ~:.. ?. - - this scale is exceeded, the LCD display will display a . e, u u x, e. c - a - 1 (one) in the far left of the LCD readout-and all -s c. = .nc =. x . r. . blanks to the right of the 1 (one). -. .a,.. - _ _. ~ ,p yy G._ OPERAT10N OF INSTRUMENr +e 3- ~. t -v C. L; r. .r/:b3h.dh;n:.f."a$$.s cal su c M. {nsurethe in,strument is calibrateu. i + C*),, v.r t. : :2. . Turn the range selector switch to the ZERO position. Adjust s..- ? X,;._.' ". _ _..._..~__the ZERO KNOB t 1i1 the LCD display reads 000. ,. ~.. -... 13. If the batterles are low, a star will 'be displayed on the , ;521 ' 'LCD display 13 fthe upper.left hand corner. 3 .m m l 4. When measuring ta or low energy gamma or X-ray emissions, c:._ _ ~ open the sliding beta shield on the bottom of the case and g 'g 3.- ' face the bottom of the instrument toward the radiation source. To oper or close the shield, depress the friction N. , ~.. release button s.d let the beta shield slide open. Protect l the thin face against damage by puncture and radioactive contamination. NOTE The effective center of the ion chamb-is marked by dimples at the frant and sides on the instr ment ' case. The zero l setti: 1 of the instrument may be check in a riadiation field by sole ng the'-ZERO position. S b

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When high gamma dose wig;kT.ZO.~ c rat-nt, low beta dose rates may go aja e. unt ss a smear is taken and removed from 'p; g s.rf.c g ~;c.-gnp ar-ed for beta dose rate. 4 r- .+ % gz .;s. - _C77_'?C ~ b..' Wh'= it differences are seen with the beta N. .J -win.

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er readin0 with the' beta window shut.

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2E_.1 the th the beta window open and closed.

w.~n...-. m. a + 7.n.. y , M, S, t?.i NOTE .c - 2' e+wr% gou es4 %. en g. ..r reading above will ....,.. ~. 4

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.ue dose rate, exposure c E + _"-.r...,

rue field dose rate.

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-r is practically the - - - ' _ ~ '.T. s. ~ 2,- - ; s11 beams, point sources,.. -. - -. - 7"'-CC i, ~~~ ~ line sources will give~ M a Jing less than actual ex-te and must be evaluated ~ ' - ividual basis. m ,s.m.o ~.. - -.2. Beta Rac ., r, _. _. Ip4 The betc e rate for a source at least as large as ~.. the wini +A is meter reading window open less the metc .ndow closed times beta correction factor on the si instrument. 1. GAMMA CALIBR_ TRUMENT (Guarterly) ~ C'AUTION field intensities or calibration of the >otentially hazardous . e l'.. Obser.ve precautions overexposure. C A sj. - p -' t

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t g 1 n _- - Georgia Power n -- om .- ~e 4 of B .See Tit 1C Pace ~ ~ ^ - - .K'4~ ' uwwes.: s-hbh. J^' NOTE >~..:~ 4 - It is very important that the Jn inside of the chamber assembly ec.e i be kept' dry due to avoid leakage a pggy.'.C '~ i -currents due'to moisture. If the i ~~ ' 4 y ~se r ~ desiccant becomes saturated the Z_._" X ,_;RO-4A becomes erratic due to U D1 moisture, renew the desiccant FEG~ ~ crystals and cycle the instrument between room temperature (or lower) 8 7-7, [ ' -and + 140 F three or four times We a:

to flush the chamber air across the G 7, u.

desiccant. l C CAUTION = F2~ % -Avoid any contact with electrical 4 ggr _ ~ components with the hands as q .jn, damage to the amMifier will occur. n.u. - N -D f 1. Turn the function selector switch to ZERO and ensure the LCD (?? N ! Q ' display reads zero. M38 e1.1 '2~~~ 2. Ensure the low battery light on the display is not on. ] b; :. If^ 3. Turn the range s' elector switch to the mr/hr range, place the instrument in,about a.50 mr/hr and 150 mr/hr gamma field 7 respectively, and check the meter readings. Record readings on the Instrument Calibration Data Package 1 (Data Sheet 1). ~ -. ~.: fr _ _. -4. Turn the range selector switch to the R/hr range. Place the instrument in about a 50 R/hr and 150 R/hr gamma field .~ respectively, and check the meter readings. Record the readings on the Instrument Calibration Data Package 1-(Data Sheet 1) in the "As Found" column. 5. If the instrument reads within 1 20% of the actual dose rate in step I.3 thru I.4, write all valves recorded in the "As Found" column and proceed to Section J. ~ 6. If the, instrument does not read within 1 20% of the actual values in each field, continue with Step I.7. 7. Turn the function selector switch to the mr/hr range. Place instrument in about 50 mr/hr field and' adjust the control resistor which is located neares't the' nose of the instrument ~ on the circuit board. Adjust this resistor until the meter - indicates the field reading i 20% of this value. Check the l 150 mr/hr r'ea d in 'g and ensure its i 20% of.the true field ~ reading. Reccrd meter readings in the "As Left" column. ,, / 4 M AMM. SET N4F M IN M Y8h

y ;.A o E. 1. Fla>....tch Nucl ar Plant .. ~. wJ wem awa== = . & Y!.h;: - ~ HNP-8145 d: W,Y,x-~ rS;g Titic Pag 2 n .MCN W. W %.4 ?~ Georm. Power n{ =- 1 a 1, _ om we -See Title Pace A-b T 5 of 8 ' (# v.- > ;y, }. w m - I .m. w u r.@.e ~B. Turn the~ function selector switch to the R/hr range. Place l the instrument *in about a 50 R/hr field and adjust the j.a.-. _ _ control resistor which is located nearest the back of the y~f ^ < - ;_- - ' instrument. w -- g;;!mt 7:tf mig ". NOTE ~ om m, j g. R* The dose. rates used to calibrate WT~~~ ~ 'the R/hr scale are very high. hw 3.+

~

The instrument must be taken out .of the field and then the resistor 8 H- ~' turned and then the instrument put ~~ d_ie.- back into the field and checked. _ ~ m

  1. ~

a. Adjust the R/hr resistor until the meter indicatbs the e% .,. -.. ~ field reading of i 20% of this value. Check the 150 ~ p H,. ' 7 F. R/hr reading and ensure its i 20% of the turn field A -. _.- reading. Record meter readings in the "As Left" column.

4..

4 J. BETA _ CALIBRATION OF INSTRUMENT (Guarterly) I h"77 r n @ -N I 1. Zero RD-4A, place instrument on ce'nter of the beta source (:$j.f ' slab (beta window closed) and measure gamma radiation, i g,.,_'$.. d tre record in the "As Found" column. Open beta window (as in , a _.~ ~ G.4) and measure radiation level, record in the "As Found" ~~-i y ~M _~.~ column. Subtract the gamma reading from the beta, gamma 17 reading..Thi's is the best indication. N .~. f1 ~ Determine a b' eta multiplication factor by dividing 230 (Beta e ~ slab reads 230 Mrad beta) by the. indicated beta dose rate. Record this yalue on Data Package 1 (Data Sheet 1). n... ~ U, ~ ~ After calibration is complete, replace calibration sticker and beta multiplication factor on instrument. CAUTION When RD-4A need's to be removed from its can, use caution when ~ replacing can, beta window on detector can be punctured'by the bolt on the +ansion bar in the can. N_OTE_ When adjusting control resis' tors is complete, replace caps on resistors while in field so if resistor turns while caps are t being' replaced causing meter

/.

reading to change, it can be s determined.

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