ML20077H880
| ML20077H880 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/21/1983 |
| From: | Thomas Greene, Nix H, Roger W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20077H585 | List: |
| References | |
| PROC-830721-01, NUDOCS 8308110407 | |
| Download: ML20077H880 (165) | |
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GEORGIA POWER COMPANY e 4 HATCH NUCLEAR PLANT PROCEDURE USE AND CARE OF RESPIRATORS PROCEDURE TITLE HNP-8010 PROCEDURE NUMBER
'L dB RESPONSIBLE SECTION SAFETY RELATED ( X )
NON SAFETY RELATED ( ~
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APPROVED APPROVED REV.
DESCRIPTION DEPT.
PLANT DATE HEAD MAN GER 1, __
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4 PROCEDURE Pocket Dosimeter Use and Performance Test PROCEDURE TITLE HNP-8108 PROC $ DURE 5tMBER L.a. b
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e HATCH NUCLEAR PLANT PROCEDURE Turbine t._o_b_e Oil Reservoin Oil Fire PROCEDURE TITLE HNP-1-42OG PROCEDURE NUMRER Engineerin.q RESPONSIBl.E SECTION SAFETY RELATED f
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_in__+>_h.<F.C.A_.*(~(un,_An_ty__en y..r m_ g.,.2,.7r-" a_b_o.v a _+ h_n a ___t_h_e__re v_i_s_i ch__d_o_es__.n.o. t ch_a_n.c.e _t_h_e._-c u_r_n_os e _or n e_rf_o_rma nc_e o f t h e l s.J_s_ ten. s ' - - -2. -- The co_ssibility of an accident o_r m_a_l_fu_n_ction of a differe_n_t_.tvee - - - -= then ancivzed in the FSAP. does_not resul5 frem this chan::e because ~ = ___t_h_e__sys_t_e__resconds and is ocerated as before the chance. "O.# ,3_.__T..h_e_._m3_r_n.i._n o f__s.a._fe_ty -- -- _s d e fi n_e_d i n t h e T e ch n i c a_l_S_c_e c_i_f _i c_a_t i dn s a - - - - - - __. _____i_s__n_ot _r.e._d_u.'c_e_d__du_e_ _t_o_t_h_i_s_r_e_v_i_s _i o_n b eca u_s e. the rev_i_s_ / ,y t P _m__________c_h_a_n.c e_ _e_n..v._l_i_c_'i_t e d_ _s a fdt.v. s y s_t_e_m s e t t i n e s__wh i c_h__w ~ ______s_a_f_e_t'v__l_i_m..i.t_._t_o_b_e__e_x_ce_ed._e_d_o_r__t o a l l o'i a l imi ti n e cer.di ti on for-- - = - - onerations to be exceeded as stated in' Techni_c_a_l..S_re_c_i_f_ic_a_t._i_en_s_._ --___ _,..m_________ __--,,=======.:;-_------ _ _ _ _ _ _ _ _ _ - _ -:,,,. _ _=.=._ _.: =.________ _ - - =. ____=.___.____.______-___ _ - .,=.=============.a-__- ~, ~. ...,,,= = = = =.- ; _- = = = = = = = - - - -.. _ _ - - - - .-___m=====_=___mmm.-------- - - _ = = = = = =. _ _ _ _ _ _ _ _ _ _,,, _ = - - - - .====-- ;.____.==-_._.-.. _n~ m------ .,e -_-__._-_::===___.::.=_=,.A--------__=- .-._,.a. l.g:p3 3 a_- q-- a' S ET - - -.)- m3,10 m -- r-~;. =n-.-.~
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I HNP-1-4205 ,.Cee Title Page '*G Georgia Power n 3 .m ge. T4+1m pag. 1 of 2 PGINE LUBE OTL RESERVOIR OTL FIRE ~ ~ A. CONDITION 1. Fire at the turbine lube oil reservoir has been identified l and reported to the control room, or 2. One or m, ore of the following may indicate the possibility of a fire at the turbine lube oil reservoir: a. Actuation of the deluge system. b._ Automatic start of the fire pump, c. Annunciators: (1) FIRE f2) FIRE PLNP RUNNING c' ?.csY (3) NW CORNER TURBINE LUCE OIL STORAGE TANKS if s B. ACTION ga. 1. Check fire detection panel to determine fire location. 2. Dispatch personnel to determine if a fire exists. 3. Initial actions'of control room personnel and Fire Brigade l should be as described in HNP-42OO, "GENZRAL FIRE PROCEDURE". 4. Extinguish small, localized fires as described in HNP-42CO. 5. For major fires btening out of control; a. Control recm peisonnel. (1) Scram reactor (HNP-1-1025). (2.) Trip turbine. b. Fice Brigade (1) Verify deluge system actuated. Manually initiate by operating local trip lever, if required. I ...... :j 1 ..... - -. -.a- .'w.,.. MbuF SET I
. - 3 __-.. _._ afa va E. l. Hatch Nuclear Plant =<=ae uo. HNP-1 -4205 .eSee Title Page arv m os so a Georgia Power s 3 -e 9eo T4+1o omga p op p (2), Man portable fire fighting equipment to aid fire control and to control secondary fires. i3) De-energize local area electrica1' equipment after evaluating effect on ability to safely shutdown the plant. C. SUG5EGUENT tCTION 1. As specified in FNP-42OO.
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4 s / CEO!;GIA POWER COMPANY. s. l O.J H/iTCK'NGCECAR' PEAL \\R'- i PROCEDURE Clae,1 f i ca t i nn o F Emm,len c i ec, PiiOUUUUhE TITLE HNP -4805 PROCEDURE NUMDER La. b RESPONSICLE SECTION SAFETY REle,TED ( X) NON-SAFETY RELATED ( ) ,._____q_ _a____ APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT .DATE HEAD MANAGT2ft pI.)v L..._, ga... q g 7.f gg O New Procedure 1. "9Y v.,s. ______u_______.___.r esp g * ...>s ____.i ___1 _--___________.c '.*.M.***.h .i.__..h.--.m.6. p.h I .i es. ...4l.e_...s.i.. e %Q.1.} Y k 4MAMF $[1 4
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t_h_a_n_a_na_ lyze _d _i.n.th_e_ _FS_A_R_ _d_oe_s_ no_t_r_e_s_u_lt _f_ro_m t_h.is Er_e_c_e_du.r_e_ _b_eca e_h_e_ a rs t_em. te ssend_s. and _i_s_ gge r_a t eg,a s_ h e,o_re_ th e_ ngc edge, _ _ _ _ _ _ _ _ _ _ e e ,y ..,e .d L _ _T.h_e_ ma_E.n_qf, _s_a f e_*J_ _as _d_e_f_ined_.i_n_t_h_e_ _T_e c_h_n_i_c_a l_ Sp_e_c i_f_i_c_a_t i_o_n_s_ _ _ - d .ev _____-e .n u i s..no t _r_e duc ed_ _du_ e_ t o_ th_i_s 2.ro_c e_d_u_r e_ b_e_cau_s_e_ _the_.P r_oce_d_ ep h a limit d safety system settin~s which would allow a .__...__._c__an~e-_n1_-__eu____-._.--__.____b___-__-________--_.____.. a - di_i f _ _ _. _ _. _ _s_a f_e_t v_ _l_i_m_i t_ _t_o_ b_ e_ _e_x_c_ee_d e_d_ _or_ a_l_l_ow a _l_im_i_t_i_n3_ con oP_e_r_s t_ i_o_n_s_ t_o..b e_ e_x_c_e_e_d e.d_ _a_s_ s_t_a_t_ed _in_ T ec_h_n_i_c_a l_ S e e. G.._-___-... __e-- em - e _ _ _ e - up_______eDe___-__et_en em.. en _ _ etam ..en____e---_-=___es ._e___ee_._ e m - - upe _ _ _ e . GD_e_ene__e___-__..._e9_e6.e.O___ _._g___e9_ e9-.__eW.__-eDe5-_____ e5 _GW__ __ _ _. eD e5 __ eteDED 6 .____-_e-W___e66__ _ m _ MS.66es _ ehe. W e3 _ e. _ _ _ _. e9_6__.-e____ e. eh_43_em e5-eB e _ e.... e - e eh.__.49..-. ep__-_________ eke-e.. ___eD_es.__e_- _upeme-_e D ____________e9-6 _ _ e _ _ e _ e -. as. ae - _ _. _ e - em - - _ _ _ en em. em as e um as 4D - e e -. _ e e - es. e m. O en___ __ _ et .-W_ .e6_ _.eBe-._____e5..._e3 eta _ _ e9_ ..__.en. .e _ _ ep.._. _ _ es es _ _ ep__e-____.D_ ___.et_ _ _ eDem.. _ _ _ e _ 49 - __.- _ GD EDee___e. -_e . _ _ e - - e - _ _ es _ - _ _ sp _es - _ _ et _.-_eDep. e e3e 6_ W ______________-..____....______...._______.'_____________-_-e. ( ..ep....... em .p __=...__----_e.-... ._=_. _=_- =....__ -_=._-===___ __ HNP-9 S 9 M AeWJ F SET
i ~, -, - .. 4 -. E. I. H ATCH. NUCLEAR PLAN _T-HNP-4855 getw.m. GeorgiaPower ek O um ~~ g See Title Paoe 1 of a r CLASSIFICATION OF EHERGENCIES A. PURPOLG I 'This procedure is in-tended to be used as an aid in classifying emergencies during operational *occurences which have emergency potential. B. REFlRENCES 1. Operator Manual for Classification of Emergencies. 2. Matrix of Emergency Actions Levels vs. Plant Event (Appendix A to Operator Manual). C. RESPONSIBILITIES It is the responsibility of the control room personnel to p initiate this procedure as appropriate to respond in emergency ' 59. ' situations. ~ l D. GENERAL s ~.~wD 1. Operations personnel observe via instruments abnormal operating conditions, or are informed of some external abnormal condition. 2. Refer to the matrix and locate the appropriate vertical heading which corresponds to the initiating event. 3. Follow the correct verticle'line down until it intersects with a symbol corresponding tc, an emergency action level. 4. At the emergency action level symbol follow the horizontal line to.the statement of the emergency action level and compare with existing conditions. 5. Repeat steps 3 and 4 until the correct emergency class is identified. 6. Refer to the appropriate tabbed section in the operator training manual for further clarification of the emergency classification. NOTE The number in'the symbol. corresponds to the appropriate tab in the manual. ..,.. i ~,, ' 1 l~4 L fN#1JF SET e .....a.
t 4 ,,mmm,.,, ~~~ See Ti t1e Pace _ 1: L HAT.CH NUCLEAR PLdNI _..___ _ HNP-4855 me re, A O om Georgia Power c:h ~~ g,, y gcy 7111, p,,, 7. Review the material in the appropriate section of the manual to ensure proper emergency classification. .8. After the operator is sure the appropriate emergency classification has been selected' inform -t he Operational Supervisor and refer to'The correct tab for initial' response activities. NOTE The initial response tabs are indicated after the material given for each emergency action level in tha manual. 9. Initiate the appropriate response activities as directed by the Operational Supervisor. 10. Repeat steps 1 through 9 as required by changes in plant status.
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1 ..g GEORGIA POWER COMPANY. o , e HATCH NUCLEAR PLANT PROCCDURE - O eratinIl Personnel Securitv Alert 2 - u-PROCEDUTE TITLE HNP-4901 PROCEDURE NUMDER Lab RESPONSICLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) .._____x --_-------------_1_---__-- APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT 'DATE - HEAD MANAGER /D f 4 Pages 1 & u.i sg< . f/ )l ..._f ) { y_..-. ~ ?_ _/ _ M._G_.___%___.__M______.. '.,I _ _5. P. ages_1.____________.__. _ z_.'_ t,.h. .~ ..________s__________._ - _ _ _ _ _ _ _ _ _ _ _ _ _ _..______ ________ p r_______________- 9 7 ."a..s_ .i.__ I _e.. e l d '9)A HNP-9 l f e 1 I 6 _.t
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o a.b...o..v.a:.th."s.u*. a n 21 ve.d. i n t.b-.:M du.e-.to theia _C.b.a.atS haGr a s. -- _t h_e f _- -- - t_h_e_revi_sion.. does not ch a_.:.s the* curnose nr oerfor _a_n.c.e o =--------- s y s t a-'. - _ - - - - - - - - - - - - - - - - - - - _ = - 2. The.cossibility of an accidiat or ralfunction of a different tyce u. tha_n analv ed in the FSA?. c:ss not result fro-this chance because n __-_he _s.vste_r_resconds' a.n.d _is bsrated as be' fore the chan.ce. t - - - - = - =_ M ~ 5'I' 3. The rarcin o? safety as de#ir.sd in the Technical Soecifications
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,i . -,.n,~ k E. I. HATCH NUCLEAR PLANT HNP-4901 See Title-Page < < oo. >.v ~- 4 5 Q'
- .m Georgia Power ca
~~ See Title Page O 1 of 2 SECURITY ALERT - OPERATING PERSONJ11 A. CONDITION Notification has been received of a security alert involving: A bomb or,other overt threats or A civil disturbance B. ACTION 1. BomD or other overt threats a. The operator will initiate the security alert signal over the public address system and then follow up by announcing: THIS IS A REACTOR STATUS ALERT *
- )."4 b.
The Shift Supervisor will institute an immediate y dispersion of available personnel to search and' inspect vital areas within the ope' rating buildings. If ~,.o - required, the Shift Supervisor will call in additional personnel to a-id-in~the" search:~ - - - ' - ~ - - " - ' ~ - --~~ c. The operating personnel will make a thorough search of the vital areas and report any findings to the Shift Supervisor. d. If a bomb or any other unusual item is located, refer to the BOMB AND OTHER OVERT THREATS Procedure HNP-302 for instructions. e. If unauthorized intrusion is discovered or suspected, the Shift Supervisor will be notified immediately. The Shift Supervisor will then have the main control room access doors locked and notify security headquarters. f. Operations Supervisor refer to H,\\lP-4420, 4520, 4620, and 4720 procedures to determine iF. emergency should be declared. 2. Civil Disturbance a. The operator will initiate the security alert signal over the'public address system and~then follow up by announcing: THIS IS A PLANT STATUS ALERT ** "- ... + l .i th o' MT
1 -- -i .4,,. ge e-yt1 e -Page-E. l. HATCH NUCLEAR P. LAN.T...___ HNP-4901 i 4h 5 LAff Om d ~~ See Title Page 2 of 2 b. Denotes a bomb or other-overt threat. c. Establish communications with the Central Alarm Station. This denotes a bomb or other overt. threat.
- This denotes a civil disturbance security alert.
d. Operations Supervisor refer to HNP-4420, 4520, 4620, and 4720 procedures to determine if emergency should be ' declared. - -A r.i. < .vs-t .; s s en .i i IdsMo' SET
4 6 k.a.e. e c e GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Bioassay P r og.r_am PROCEDURE TITLE HNP-E021 ~ PROCEDURE AUMGER ~ ~~ Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAtu.iY RELATED ( ) -- ~---- _-------__-q_t APPROVED APPROVED REV. DESCR!PTION DEPT. PLANT DATE HEAD MANAGER ..__________-q 4 Pages 1-3, & 5-6 [ f y., j, .----__-..._.f___N_ _ n _ d em'_ _ _ _ _. cji a____ eau.r___ ________ _ ~e.o)-' s
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B . /.. .' ~ E. I. HATCH NUCLEAR PLANT HNP-8021 See Title. Page are 5 See Title Page 2 of 6 2. The Training Department will coordinate the whole body count with department heads to assure an uninterrupted schedule. 3. When the whole body count is, complete, submit the results to a lab foceman for approval. 4. File each person's report in his/her evposure file when a lab foreman's ceview and approval is complete. i E. URINALYgig 1. For suspect or known inhalation cases. WE A fission product analysis may be performed by an outside contractor on personnel suspected j of inhaling airborne activity. This will be done h3
- at the direction of the health physics dept.
3r a. Have each person collect a minimum of 400 ml of urine. st*y The label should contain the person's name, social 1 security number, I.D. badge number and date of collection, b. Send sample to contractor's laboratory as soon aften collection as is possible. c. File a copy of the analysis in the person's file folder j and the original in documentation with this proceduce l material. I 2. Crosscheck Sample a. In conjunction with the analysis, an individual may be asked to provide two specimens, one of which will be used as a crosscheck sample. The other is tc be labeled appropriately. See section E.1.a. The crosscheck sample will be spiked using Cobalt 60 or another fission product oc may be sent without. spiking. b. A 400 m1 sample will be spiked to produce a minimum concentration of EE-7 uCi/ml (this is 10 times the LLD for gross fission products for the vendor). A higher concentration may be used. c. Log actual uCi/ml and spike source used on Fig. 1. If the sample was not spiked or another'i,sotope~used
- /.e
- CCmplete, other.
, p,, - d. The sample will be identified as on Fig. 1. +. '#b A i, W Y W ** r w
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_,~ ~* E. l. HATCH NUCLEAR PLANT HNP-8021 14NP-8021 9 pcqq mw. m ~* Geo iaPowerd ~~ p Pace 3 of E. 4 o, e o. Upon receipt of analysis from the vendor the results will be logged on Fig. 1. f. To determine if results are acceptable the following method will be used.. Divide the results by the error, the quotient is referred to as the resolution. Next. divide the results by the actual uCs/mi and compare this number to the range as dictated by the resolution. I4 it falls within the range the results are acceptable. See Table 1. If the ratio falls outside of the limits but falls within the next larger i set of limi.ts, check calculations and observe l cubsequent results to see if the problem persists, g. Check appropriate results and notify a foreman of
- results, b.
Send specimen to contractqr's laboratory, i. Heep shipping memo until the contractor's analysis report has been received. t J. File a copy of the contractor's analysis report in documentation. Investigation Levels The investigation levels for urinalysis results will be 350 pico curies per milliliter (350 pCi/ml) for tritium or 350 dpm/ liter for mixed fission products. If either of these levels are reported a foreman is to be notified immediately. The foreman is then to Gollow up the report with the actions prescribed in ANSI N-343 - 1978. f E SIElGIl9N3 i If a person's bioersey result indicates an internal 11 deposition greater :han 10% of the maximum permissable burden he shall be recounted everv two weeks until the elimination rate is established and the body burden is below into the 5%. If the deposition is above 25% he will be restricted from work in any bioassay areas until the body burden is again below 5%. In either case the elimination rate should be established I ~ cnd the total commited dose determined. r 4. M's.4US' $1T
- 2' SET
. ~,
1 m ou ~o c ~ E.1. HATCH NUCLEAR PLANT me-soal ..w w See Titla Page GeorblaPower d ~
- ~ ~o 6 of 6 See Title Page
.r QATA DACWAdQ Unnd 350 '_9iW %w*1.5 Semple 10. - Cross check s**ple Souefe used: Cobelt 60 Othee, specify i 8 (ei Actual uC6/*1 * (bi Contrettoes r**ults uC6/ml e (c) The di84eeente betweeve (a) & (b) e resolution I (b) e (c) (d) i (b) e ..b:.H 'r,:f Compece(d) to resolution on Table 1. acceptable unacceptable { I ee r s = s I' Foce*4n notified o4 results. t = Completed by! Reviewed by!.. e l
- 4), 2 of 2 HkP = St'21 RCS 4
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s CFORCIA POWFR COMPANY ,1 ._ _.__..- __ __. !MTCH. NUCLFAR. PLANT PRDCEDURE. l Alart - Empe._qancv Director u PROCEDURE TITLE HNP-4440 PROCEDURE UU5GER ~~~~~~ ~
- 1. a b
. RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFELY RELATED (- ) APPROVED APPROVED REV. DESCRIPTION . DEPT. PLANT DATE HEAD MANAGER [W . _k_ s @._f__ 3 Page 1 _ _ wG_ R* 4 . _ _P_a ge_s_ _1_ &_ _2 _ _ _ _ _ _ _(.W_ _ _ _ ... M b_e_lfQl'._..ilfitf8_) ___p; / l 5 . _ _P_ag e_ _2_ _ _ _ _ _ _ _ _ _ _ _ _ ,_.e_ ext, /=_ $_ _d _N_. ? Pages 1 & 2 It) M_ _'_ (1 /_ _g. s6.f_r/_c_w ,* P ,/c4 . g_ _ f_) _ _ _ e_ _ _s _ _ _ _ _ _ _. - ____~ _____________. ___ d. a 9.*y*84 HNF-9 Ms3 W SET -.4 ' w.
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- 3. _T_h_e._ma_r_c. i_n_o_f__s_a _fe_t_y__a s__d_e_# f _e_d__i n _t_h_e _T_e ch n i c a_l_S_c e.c_i_f_i c_a_t i o_n s--
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m*.x.a uve-e re - g,y. mt HW-GO E.1. HATCH NUCLEAR PLANT Gue Title Page. . w m.__._.. 6 Georgia Power A. JMt 1 of 2 See Title Page o ALERT - EMERGENCY DIRECTOR A. CONDTION Events are in process or have occu, red which involve an actual or r potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small f ractions of -the EPA Protective Action Guideline (PAG) exposure levels. B. REFERENCE HNP-4420 HNP-4520 HNP-4620 HNP-4720 r# e l'). "/. HNP-4853 pf.' C. ACTION 1. The General Manager or his designee will assume the position l of Emergency Director as soon as he can establish himself in an activity center (EOF or TSC). The Emergency Director directs the overall management of the emergency response and .is directly responsible for recommending protective actions in accordance with HNP-4854 to SREC/GEMA. The Emergency Director _may choose to station himself in the EOF or the TSC. He assigns personnel as necessary to perform the duties below. 2. Assure that the TSC, OSC and EOF are safe areas through the use of portable survey instruments. 3. Establish communications with the Control Room and the TSC o r EOF, as appropriate, and obtain information on the diagnosis and prognosis of the accident condition, the estimates or radioactive material releases, and the prevail'ing meteorological conditions. This communication channel is to remain in use for this information as long as necessary. 4. Maintain communication with State Radiation Emergency Coor-a dinator and/or' GEMA and relate the accident diagnosis and prognosis information necessary for these authorities to implement their emergency plans. ..,. s (h 407 3[I .l q __a'
i L. ~..u,.,...., ...~.n "HNP-G O E. I. HATCH NUCLEAR PLANT See. Title Page ,...a w 6 Q m Georoia Power ch ~~ 5 a of a See. Title Page 5. Confirm that all notifications as per Emergency Call List l have been completed. 6. Contact company management for outside assistance. I 7. Assure that State and local authorities and the NRC are l periodically provided with appropriate meteorological and release data, and dose estimates as per HNP-4861. This task should be performed in the EOF normally; the ENN may be used to inform State and local authorities and the HPN may be used to inform the NRC. 8. Assure that plant status updates are provided to NRC and l State authorities at lea'st every 15 minutes. The NRC may be informed by the use of the E-3 and the State may be informed by the use of a dedicated telephone circuit to the Georgia Energency Management Agency (GEMA). r ..c.f, 7 9. Coordinate rescue effort when required. l 10. Assure that all personnel reporting to the EOF, TSC and OSC l. are sut*veyed for contamination and possible high radiation 1 e exposure. 11. Organize personnel and standby to provide further assistance. g la. Establish security. l 13. Develop recovery and mitigation plan. l 14. Gupervise collection of emergency data in the Emergency i Operations Facility or TSC log as appropriate. 15. When appropriate, in consultation with Control Room, TSC, l EOF, and Plant Management, escalate to,a more severe class or close out or reduce emergency class by verbal summary to offsite authorities followed by written summary within 8 hours of closecut or class reduction. Refer to the procedures listed in section B for emergency class criteria. 9 s t 9 i da g i[ fe Md b
4 I .'ER COMPANY
- GECRGIA PC
.,s._-.-__ e a-HATCH NUCLFAR PLANT PROCEDt' E R Podiation Worte Penni t 1.'NP. -9009 PROCECURE NUMGER . L. b n_ RESPONSIDLC SECTION SAFETY RELATED ( Y) NCN_ SAFETY RELATED '( )
_--_a APPROVED APPROVED REV.
DESCRIPTION , DEPT. PLANT DATE 7 y -_ _.I.ER MANAC HEAD -_ / 4 % _ -_ _ _ A_ _ _.h. :). /_c J_'l. 13 General -_e_ r Pages 1-9,,l/p- _&_ _1_7 _ _.._ _ r _ _ -).@_.,.<r /.. _ _ _ _ s,_.c_e_M *.:.:_s / )' .-N _ ]_. . 1 i.,. p14.f. f-l/ ,,s . _. I /c g g,y r f ' 14 _ 15 7 g '9 g cf p 15 Pages 25,&7 w .'lllo . _ ~. l l na 4, [. _.. _ _ / 2' I
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REVISICN CH..NGCO MCCE OF.C 'EndTION OR INTENT AS DESCR. DEO.IN FS I ^ ' " T~ ~ " < ) yes.. (. W ' N o CHANGE INVCtNES: "'( ) An unreviewed Safety Guestion ( ) Tech. Specs. ( M Neither (See bacl< for Safety Evaluation if required). -- Saf ety Related (/A Non-Safety Relgited_ ( ) Safety /Non-safety Status ChanDe ( ) Yes ( lA No Attach marlied up copy of procedure to thi s. f orm. REASON FdR REGUEST__/W d f_7 b47hg_ [/ ~ f.' .1--@.-) M_/ff/N'd. /// f Y/ /db /TI4dAl$ J ^ .Y,.4 - th&4 m k,. --c o y- - r d_ ?_ _ d e <44:. m - mfMM Mk.L./ 3M'dd.f3 04_f4hf ~h @^Yqhl$ M//Mh-m--- ic hb - 54,p+dk I d_ d-ea-- C_ cam / n. &-. L1__ a.th- -- a,- _dh.h a-1:ft.1.l:Id Y _A Y2-h.A.ex! %w Z A e - 2 T &.t2_ .3P C R2.G.b5 _ 0 "~%.b d Y b!_ -Y ' b.td $MA' .)_ ._-,' f& *f-" 6 h Ltl l.? A. ?tL".[12A zhc!wY-mwu a%d 4&!"aa.=85,,,nb &ch
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m = above t_h.p.g_ana].yJf d_in._thg_F.S.M.jp_e_10. t.;has.a CbA0?.f.5 b.tCI.fSR-_-__ - the revision does not chance t_h4 nurnose or nerf._ormance of the ~ system. The_cossibilit.y of an accident or malf.u_n_ction of a differe_n_t tyce 2. tha_n a_n_al.yzed in t_h_e_FSAR doe.s. not resul_t fr.o.m__t.h.is chance becatise -__ - the sy_s_ tem res_c_on_d_s and is operated as_be fore _t_he chance. _= L // The marci.n. of saf_ety a_s defin_ed in t.he_T_echnica_l_S_oe_cifications S.a. --3. J. is not reduced due to t.h.is revision because the.r.e_ vision does not n -2' chance a_n.y limited _. safety syst_em settines which wo_ul_d allow a -m- =- sa_fet'v_ limit to be exceeded or to allow.a limitino condition. for n ooerations to be exceeded as state _d-in' Te_c_hnical Soecifications. -= c. ( w !M 3 \\ ... _. c 3.v ut. M T.. I ~. L
a a -un, ~,, HNP-8008 -- -Erl--H ATCH-N UCLEAR -PLA NT- --. See. Title Page .u a. w 16 Georoia Power A om 9& See.Ti tle Page D 1 of 17 6 RADIATION WORK PERMIT l A. PURPOEE To provide instructions for,the is:suance of and implementation of Radiation Work Permits (RWP). The Radiation Work Permit procedure is designed to provide a capability to control and minimize radiation exposure that is received from work performed in radiation areas, high radiation areas, contaminated areas, and airborne radioactivity areas. B. 'REFERENCQS 1. 10 C.F.R 20 2. Reg. Guide 1.16 py C. CONDITIONS REQUIRING RADIATION WORK PERMITS
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1. Entry into a High Radiation Area, Airborne Radioactivity Area, (as required by Health. Physics), or any area posted "'TT,' with a "MEEP OUT - Radiation Work Permit Required" sign. 2. Entry to the drywell. -3. Maintenance or inspection of contaminated or radioactive equipment in excess of the following limits: a. Smearable contamination in excess of 1000'dpm/100 cm2 beta gamma. NOTE THE HEALTH PHYSICS SUPERVISOR OR DESIGNATED ALTERNATE MAY DETERMINE THAT A R.W.P. IS NOT NECESSARY TO DC.INSFECTION OR MAINTENANCE ON EQUIPMENT WITH CONTAMINATION LEVELS IN EXCECS 0:2 1000 DPM/100 CM. IF THE JOB IS OF A NATURE THAT CAUSES NO MEASURABLE CONTAMINATION TO THE INDIVIDUALS PERFORMINO THE JOG. b. RaIliation levels at 18 inches in excess of 100 mR/hr or where a whol'e body exposure of 100 mR/hr is likely. 4. Entry into areas with measurable neutron exposure. 5. Entry into an area of unknown condition. i ,-6. Greaching' of. cordaminated or. poten'tially contaminstad sys tem. .p i rn.tnar n1 L
. - - ~ - - ~.. ~ 4._ --..o - HP -8008 -E.-l.-H A-TC H -N U C L EA R-P LA NT--- - - ee Title Page n.w ,.o s A 16 Georpia Power c.1 ~~ See. Title Page o 2 of 17 D. ISSUANCE OF THE RWP (Refer To Ficur_e 1) ~ 1. A supervisor responsible for work requiring an RWP should 4 originate the permit. The originator should enter the date, location, Unit number, job description, and names of personnel expected to require access to the controlled area. He'should provide an estimation of man hours required for work in the controlled area and enter his signature in the Requested By section. The RWP should then be forwarded to the Health Physics Gupervisor or his designated alternate. 2. The Health Physics Supervisor or his alternate will review the work to be performed for any conditions which may adversely affect the safety of the plant or personnel. involved. He will log the required information into the Radiation Work Permit Log Book and enter the permit number from the log book on the RWP. He will determine the appropriate work category using Section K and check off the appropriate block on the RWP. .:.:*/ . +' NOTE f s The Radiation Work Permit Log
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Book is a notebook kept in the Health Physics office and con-tains Form 3, Radiation Work Permit Log. The Shift Supervisor may complete the RWP for Health Physics l provided the following criteria are met: A qualicied member of the Health Physics staff is no t a. on site, AND b. The safety of the plant warrants immediate ac tion which would preclude calling in a Health Physics staff member from off site, OR c. Authorization in received from the Health Physics Supervisor or his designated alternate. 3. The RWP should be reviewed by the Health Physics staff to determine appropriate actions and controls to be implemented to preclude exceeding exposure limits and to maintain exposures as low as is reasonably achievable (ALARA). Also refer to paragraph D.G. The area should be adequately surveyed prior to entry or be surveyed at _the time of entry, i-items of protective clothing required shoults be identified, the' type nF monitoring required should be specified and ext,osure recordu:of personnel involved should be reviewed to ao ure cuposures will remain ALARA and within~ permissible limits. 'IMija' SE1
-.~ ., m m., ~, 4-!NP.-8003 - - -E: 1.-HATCH-NUCLEAR PLANT -. See. Title Page m u c wa 16 Georgia Power d,A 3.a Gee.Ti.tle Page O 3 of 17 4. Temporary shielding may be specified in order to reduce personnel exposure, to reduce background levels in frisking areas, or to bring radiations levels into compliance with plant and regulatory limits. This type of shielding should only be. installed for specifi,c time periods such as: for the duration of a job, until the next scheduled ou tage or as directed by plant management. Any shielding specification must be. subjected to the applicable work controls and design reviews described in procedures HNP-8 Maintenance Request and HNP-809 Design Change Request. 5. The Health Physics Supervisor or designated alternate will review the RWP, enter the estimated man-rem, expiration date and time, sign the RWP for Health Physics approval, and remove the Health Physics copy for filing. A Man-Rem estimate will be made only for RWP's with work area dose rates of > 10 Mrem /hr or hot spots > 100 Mrem /hr. NOTE .d 't' Estimated man-rem = Estimated man hours x average dose rate in rems / hour. l- .j 6. Some Radiation Work Permits require an ALARA evaluation prior to issue. As man-Rem estimates increase further ALARA mea =>ur's should be considered for implementation. For RWP's e with Man-Rom estimates of 1 or less, no_ formal ALARA evaluation is required. RWP's with estimates greater than 1 should be routed to the ALARA coordinator for evaluation and processing. An ALARA review should also be performed in conjunction with any RWP which covers the use of a temporary radioactive liquid processing system or storage system. The review will determine the possibility of a release to the environment, the precautionary measures to prevent such a release, and the actions necessary to resolve a reinase if it should occur. 7. The Shift Supervisor will review the RWP for any operations l or conditions which may adversely affect the safety cf the plant, enter the approved date and time, and sign tha RWP.. The Control Room copy of the RWP will.be placed en File in the Control Room. NOTE Approval to start work will be ~ in effect after the RWP is signed ' by' Health Ph sics and Shift y Supervisor. See D.S for exception, .,a e f J tknV MT.
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-E-IrH ATCH-NUCLEAR PLANT- ---- _jf-acos _ See Title Page 16 Gebroia Power cl(% o.u a See. Title Page 6 4 of 17 8. The Supervisor requesting the RNP will review the RWP to l familiarize himself with all requirements. The original RWP will then be taken to the jobsite and posted at the entrance to the jobsite on the clean side of the step-off pad. The supervisor should.. ensure that the workers have seen the RWP and are aware ofsC'i.. requirements. .-r, 9. In some.situat' ions where the plant needs immediate attention l due to an emergency condition, a job may commence prior to the sign-off approvals of an R.W.P. by the Health Physics Supervisor or his designated alternate and the Shift Supervisor. The approval to work, in these situations, will be contingent on the policy that a Health Physics person will accompany the workers, will perform the necessary radiation monitoring at the work place to protect the workers, and will give the workers proper instruction in radiation protection. The approval to work will also be contingent on the proper clearance and tagging of the effected equipment by the Shift Supervisor and his staff. l . -r/ 'f ' E. ADDITION OF, PERSONNEL NAMES TO RWP's While an RWP is-in f orce -the-addition.of-names of -personnel.to. - r ~ ~~n the RWP may be made only on the approval by the Health Physics staff. The work assignment of the person being added gust be directly related or associated with the job description on the RWP. When approval is granted, the person's name will be entered on the original RWP at the job site and on the Health Physics copy in the Health Physics Office. F. PERSONNEL RESPONSIBILITIES 1. Supervisor responsible for work under RWP. a. .The supervisor is responsible for assuring that personnel working on the job know the protection requirements. b. IF Health Physics monitoring is specified on the RWP, the work supervisor will notify Health Physics staff when the job is to start. c. The individual shares a responsibility to promote an awareness of good ALARA practices. 2._ Personnel performing work a. Each person entering and exiting'the RNP ' area must enter data'on the RKP Time Itecord (Figure 2) or on the L dosimeter sign in sheet (Form 1), or ensure that this data is entered on the righ t sign-in sheet, (i.e. by H.P. tech.). "srijF MT
. 4m ..o u m.,.~ e -soos-- Y E. l. HATCH NUCLEAR PLANT See..rit1e Page ..m.w. 16 A m Georgia Power dh ~- 3,, 17 See Title Page 2 b. Each person must be familiar with all requirements and l Instructions written on the RWP. 3. Health Physics Staff a. The Health Physics' staff will provide radiation surveying and monitoring as required by the RWP. b. The Health Physics staff will assist the Supervisor-in-char _ge and personnel by providing guidance in radiation protection matters to minimize exposure. c. The Health Physics staff shares the responsibility to promote an awareness of good ALARA policies. G. TERMINATION OF THE RWP. 1. When the job is to be terminated, the RWP with supplementary g ' sheets attached, must be returned to the !!aalth Physics ./ f Officesby the Supervisor-in-charge of the work, or his alternate. -.o,,: " 2. An RWP should be terminated for the following reasons: a. Completion of the job. b. Cancellation of the job or RWP. c. Expiration of the RWP. (1) Twenty-four hour limit. (2) Time limit as noted on RWP. d. Change in radiological conditions. NOTE No further work will be performed under the RWP once the permit is terminated or expired. 3. The Health Physics Supervisor or his alternate will mark-the RWP as terminated by checking the appropriate reason For termination, entering the time and date of termination, and signing the RW? in the Terminated Gy section. He will tnen mark the time and date terminated'in the R<tdiation Werk. Permit Log Book. r.- tlanW'$lT
I 4 34A.4 WUMt NU Ar *1eQW A., HNP-8008 Gee 1Ttle 1%ge- _._E. LHAICH_ NUCLEAR PLANT __ -.-. w 1G 6 .,, u Georgia Power ni s of rr g,,.n11,g,g, 4. Prior to filing in documen tation the original copy of the RWP, the Laboratory Supervisor (or alternate) should review l the cb11ective exposures associated with work in the controlled' area. For jobs involving greater than.10 man-rom collective exposure, or where the' actual man-rem exceeds the estimated man-rem by 25y.,,a copy of the RWP data should be forwarded to the Alara Coordinator or his designate for an ALARA past job review. When the original copy of the RWP is l filed, the Health Physics copy may then be removed and destroyed. H. ROUTINE R4DIATION WORK PERMIT 1. Jobs that continue for more than 24 hours such as in
- outages, (i.e. turbine overhauls, etc.) a routine R.W.P. may be issued.
Routine RWPs will only be issued to areas with constant H.P. ' coverage or an H.P. assigned to the control point unless approved so by an H.P. Supervisor or Foreman. 4 Routine RWPs will have " Routine" written at the top and bottom to distinguish them from RWPs that expire after 24 y 'Y' hours. Routine RWPs will be terminated at the efid of the 4 month.i ~. e v 2. Routine R.W.P.s will be issued according to section D. except it will be stapled to a folder with dosimeter sign in ~ sheets and a recent survey. Each dosimeter sign in sheet must have the R.W.P. number, date,.and work category filled out. 3. When airborne conditions exist in the work area involving routine RWPs, the following additional steps will be taken for completion of Form 1-A. Air sampling program will be followed as per HNP-8013.. Weighted MPC values will-be calculated and proper action taken for personnel entries into airborne radioactivity areas. The action requirements for weighted MPC values designated below are as Follows: a. Less than 0.25 weighted MFC. No control of MPC-HR exposures required. b. Greater than 0.25 weighted MPC but less-than 1 MPC. Use respirators and limit exposure to airborne radiation as far as practicable or_ keep track of MPC-FRs in.the following manner: (1) Enter the result of the air sample analysis on the NPC-H log sheet (Form 1A). y ![r.%dF M1 a
~~ ..,m~,.. E L HATCH. NUCLEAR. PLANT-.--.-- .e HP -8008 .m . sco mrs Page s,, A is m Georaia Power"M ~~ See.Ti t1e Page D 7 of 17 (2T For each entry calculate the total time in hours, for those individuals who did not receive any ~ respiratory protection for either particulate or iodine or both.- MPC-HOUR = MPC fraction x Total time in Hours c. Greater than 1 MPC-HR but less than 10 total MPC-HR
- aust be restricted to 35 per week.
All steps in 3.b must be followed. d. 'MPC-HR values should be transferred to Form 5 of HNP-8010 from Form 1-A for each individual on a daily basis. A daily margin of MPC-FR should be supplied to the control point Health Physics technician, and he will use this to con trol stay time. 4. In areas where work continues 24 hours a day the routine R.W.P. will be left at the control point for the duration of the job. At the and of each shift change the dosimeter sign j g tf. in sheets will be pulled and new ones attached. 'The -F completed dosimeter sign in sheets will be sent to dosimetry for dose recording. "..tj 5. The minimum survey f requency for routine R.W.P.s is every 24 hours. The H.P. Supervisor or Foreman will review all routine R.W.P.s and may set a more frequent survey requirement, according to radiological hazards' associated L with certain areas and the type of work being performed. Once the survey-is performed and is written it is sont to the H.P. off' ice for review and a copy is made. The copy is sont back to the control point to be attached to the routine RWP. NOTE If a routine R.W.P. is not used, a current radiation survey will not be updated and attached until the R.W.P.'is put back into effect. I. BLAN!ET RADI ATICN WORK PERMIT .1. For certain" routine or' repetitive work, a Radiation Work Permit Form may be issued to Operations,-Health Physics and Radiochemistry groups, Plant Supervisors and designated inspection and survei11anceLgroups, and marked SLAN'GT at - 'the top and. bottom of the form. The Glanket RWP must be approved by.a Shift Supervisor, the' Health *Fhysics l' Supervisor. or designa tud alternate end an. Appropria te member of supervision -of the - group to perf orm tbo.Werk. The:Glanket d FAP will be' valid.until cancelled by Health Physics or'until the last Friday in each mon th.. 9 e. . ^ N;. y -,, M, .. C ,e .. O ~.. i s,
= .-..,w n.n - HNP -8008- 'ETHATCH NUCLEAR ~ PCANT- ~~ See Titie Page %ec.u 16 4 uw bc3roia Power cda i Goe Title Page C) 8 of 17 2. The approved permit is stored in a protective holder in a book in the Health Physics Office. Exposure rates and a log of personnel doing the work are not entered on the Blanket RWP form. Such records are kept on Forn 2,' Blanket Radiation Permit Entry L p,After personnel complete work under the 4 Blanket Permitt-jh.p.nformation required on Form a MUST BE recorded. ~ ' NOTE a I Record information for each RNP area entered. J. REGUIREtGNTS FOR ENTRY INTO HIGH RADIATICN AREAS 1. All personnel entering a, High Radiation Area where the field dose rate
- is expected to be greater than 10C0 mr/hr must i
obtain a high range dosimeter from the Health Physics Office l before entry. [ .f[ 2. All personnel entering any High Radiation Area.(greater than i. 3 or equal to 100 mr/hr) must notify ~the Health Physics Office i before entry. This applies both to regular RWP holders and Blanket RWP holders. -.p 3. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or 1 more of the following: a. A radiation monitoring device which continuously indicates the radiation dose rates in the area. A-radiation monitoring device whdch continuously b. integrates the radiation dose in the' area and' alarms when a preset integrated dose is received. Entry into i such areas with this monitoring; device may be made after the dose rate levels-in'the area have~boan l' established and personne1'have been.made knowladgeabla ~ f them. l o .An individual-qualified in radiation protection c. procedures who.is equipped with a radiation dose rate-meni tnring-device. This individual shall bd responsible for providing positive control over . activities within the areas.and shall perform pariodic radiation surveillance. .4.. The' purpose'of these three1 options is-to assur.esthat- "adequata dosimetry is,provided to nssess.radiatzen etposure.' to assure that personnrel enterind thosefaceas' ace prop!cly informed pm to the-radiologica]-.conditiens of the'aren, and' ,to assura;that..the required Equipment fornentaring'has-bien s p.rovi d 2 0..
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__.--E: Ir H ATCH-N UCLEAR -PLANT-m't-n on, As**esv A t Gee Titie Page m, -.v 16 A un Georgia Power ci ~~ Gee Title Page o 9 of i,s NOTE .hField dose rate is referred to as the dose rate approximately 18 inches from a ~ poin t or line source, or any, area dose rate greater than 1000.mc/ar. M.- EXPCEURE CATEGORY DEFINITIONS (REG. GUICE 1.16) The following is to be used for determining the work category of the RWP. 1. Routine Surveillance and Inspection (RSI) All inspections or surveillance that is continuous or r.epetitive in nature. a. Inspections of pumps, valves, systems, etc. b. Routine observations in Radiation Controlled Areas. s t c. Inspection of all mechanical or electrical components that does not involve physical work on that system. ^p d. All Glanket RWPs except in the case of work involved on special categories, i.e. R.O., W.P., S.P.M., I.S.I., or R'. P. M. 2. Routine Plant Maintenance (R.P.M.) All plant maintenance that is routine in nature. This includes all maintenance that is performed or can be performed during normal plant operation. a. Repair of all valves. b. Repacking of valves. c. Rebuilding of pumps - RWCU, FPCU, etc. d. Changing oil in system. e. Repair of electrical notors and components - MOVs, Breakers, Motor Con trol Centers, etc. f. Changing of filters in HVAC filter trains.. g. Greasing of pumps, valves, and motors i 1 Ib4fjF.Idl ~
.r . w.,,, a ... w ; <n HNP-8008 See Titic Page 16 4 sm Georoia Power cd ce. Title Pcge C) 10 of 17 a 1 1 h. Checking shaft voltage readings on components. 1. Welding, grinding, lapping of components associated with systems. 3. Special Plant Maintenance (S.P.M.) Refers to special maintenance not usually performed during normal operations. Most major maintenance is associated with outages. a. Removal of feed water spargers. b. Radiographic excminations of all components. Repair of major stdam supply delivery components - c. MSRs, MSSVs,.MS1Vs, SRVs, FWHs. d. Repair Turbine rhechanical components - Main Turbine and ,fT RFPTs. ? s e. Removal and replacement of in-core tr.onitors, TIPS, LPRMs, IRMs, SRMs, etc. ..f . -. s a f. Installation of new electrical systems or maintenance on those systems outage related - pulling cable, ~ etc. removal of insulation, g. In RPV maintenance, i.e. Cladding Removal, Jet Pump Removal, etc. I 4. Refueling Operations (R.O.) All work performed that is directly related to the refueling done during a refueling and maintenance. outage. a. Removal of RPV Head, Dryor Separator. Moisture Separator, Drywell Head,.etc. b. -Moving of new spent Fuel from RPV to fuel pool or from fuel pool to RPV. c. Fuel Sipping. -d.- Gamma Scanning. e. Inspeetion offnew fuel.- j'
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...m.- s. .m..,., HNP-POO8 --E.-IrH ATCH NUCLEAR PLANT---- See Title Page 16 A ..m Gcr~ia Power e,+ Gee Title Page 'O 11 of 17 5. Waste Processing (W.P.) All work that is associated with radioactive waste processing. ~ room. Capping of c.4c.r 2n,Radwaste drum capping a. b. Compacting of trash. c. Washing down of Drum Capping Rooms, Hopper Rooms, and Centrifuge Rooms. d. Radioactive Waste Shipments - loading, surveying, and processing. e. Maintenance personnel removing and replacing lids on shipping casks or operating cherry pickers (cranes). 6. In Service Inspection (I.S.I.) ..) ..i ' All work associated with inspection of Reactor Vdsnel, Steam / Supply'or Delivery components that has been in sarvice. All non-destructive tegting and/o.r._ inspection of. components to.. ".~2'. ; determine quality of that component and/or system. Inspection of components that have been in service and preventive inspection of equipment that has been in service. DutaGe-related inspection of reactor vessel or associated components. a. Dye penetrant testing (PT). b. Ultrasonic testing (UT). c. Radiographic testing (RT). d. Magna Flux testing. eP g 9 ? ' firaiJ F SET s
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l n. ..~m.e o.~o - ~ ~ -. A. i< ' G EORG I A-POWER..CDMP AN Y-9 4 HATCH NUCLEAR PLANT PROCEDURE Stabilized Assay Meter, SAM-2 PROCEDURE TITLE HNP_8142 PROCEDURE NUMBER 4.a b .....nea)ONSIBLE SECTION SAFETY RELATED ( X ) NON_ SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE ______' HEAD MANAGER
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IN FSAR: REVISICN CH.',NCEC MCCE CF'f. *r:.;TIctt OR INTENT AS DEGCRIDED l (. )'Yes ( [ No CHA? JOE Irf/OtNFS: ( ) An unreviewed Safety Guestic.n ( ) Tach. Specs. ( ) Neither (See ba cli for Safety Evaluation if required). ( Nr.n-Safety Related ( ) SafetyRn[$ted ( ) Yes ( /) No Safety /Nc.n-safety Status Change Attach marked up copy of procedure to thi's f,orm. REASON FOR REGLF.5T ...M
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E l.-H ATCH NUCLEAR. PLANT _._._ _
4{ -t m w See Title Pace 3-om I 1 of 15 See Title Page STABILIZED ASSAY METER. SAM-2 OPERATION AND CALIBRATION A. PURPOSE To establish.a standard technique for the operation and Model SAM-2; calibration of the Eberline Stabilized Assay Meter, and provide a method of operation to determine I-131 concentrations in samples. B. SAFETY-Observe safety rules outlined in Georgia Power Company 1. SAFETY, Section "O.," Observe radiation protection procedures when calibrating the 2. instrument with radioactive sources.
- [,'
C. REFERENCES Stabilized Assay Meter Model. SAM-2 Technical Manual. 1. ~ m.p.. Eberline Instrument Checkout Procedures. ~ J 2. D. TEST EOUIPMENT 1. Electrostatic Voltmeter 2. 100 meg ohm load 3. Mini-pulser, Model MP-1 4. Calibrated Ba-133 source E.' DESCRIPTION OF INSTRUMENT The SAM-2/RD-22 combination provides a portable gamma 1. spectrometer that has been set up to be used in~ emergencies for analysis of low volume air samples for I-131 activity. It provides dual channel analyzer with scaler and ratemeter readout of either channel or scaler readout of the sum or difference of the two channels. 2. Stabilization is obtained from An-241 doping.in the RD-22 detector scintillation' crystal, which yields pulses that are counted and used to control the high voltage. applied to the-This maintains a constant gain throughout the detector. entire system. ,,,f d
.s,... l ~ -E--l.-HATCH NUCLEAR-PLANT- --HNP-8142 y ,i* See Title Page m.e w 3 am See Title Page 2 of 15 3. A rear panel switch disables the stabilization circuit so the instrument can be used as a conventional scale'-ratemeter-analyzer with other types of detectors. r 4. The instrument may be powered either from A.C. line or an external battery pack. F.. DESCRIPTION OF CONTROLS AND CONNECTORS 1. External Controls a. DETECTOR: Connection to detector; MHV series coaxial. b.' H.V. ADJUST: Ten turn calibrated dial for setting and changing high voltage when operating in unstabilized mode. Functions as a high voltage limit control when in the stabilized mode. c. THRESHOLD: Ten turn calibrated dials for setting and y changing baseline sensitivity for each chanrjel. ,r.s.
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WINDOW: Ten turn calibrated dials for setting and changing range of pulse heights to be counted for each
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channel. e. IN-OUT: Switches to select gross counting (OUT) o r PHA (IN) for each channel. ~ f. +, OFF, -: Switches to select additive, subtractive or non-counting mode *or each channel. g. TIMED-STOP-MAN: Switch to select counting mode. h. RESET-START: Switch to reset all appropriate circuitry to zero and start a counting sequence. i. COUNT TIME IN MINUTES: Switches to select desired counting time. J. RANGE SWITCH: Selects range of rate meter of 500, 5000, 50,000, or 500,000 counts per minute (CPM). k. CH1, CH2: Switch to select which channel is displayed on rate meter. 1. RESET: Returns meter reading rapidly to.zero when depressed. m.
RESPONSE
Controls response time of t$e meter. C n. POWER:. Switch to supply power to instrument (rear panel). q' th:01W SU
n ~. 1 1 ma own w s.+ avv4 y,,- - -EtHATCH-NUCLEAR-PL-ANT --- HNe-8142__ Sue Title Page ....w. w 3 GeoroiaPower A um ~~ See Title Page o 3 of 15 c. BATTERY: Connector for plugging in external battery .(rear panel). p. STABILIZER: Switch selects stabilized or unstabilized operation (rear panel)., ^ q. DISPIAY DN-OFF; Switch disables digital display to conserve battery. r. 115-230: Switch selects 115 or 230 VAC operation .(underneath chassis). s. AMP OUT: BNC connector which provides an output for connection to a multichannel analyzer. 2. Internal Controls a. GAIN (Channel 1 Amplifier Board): Control for adjusting gain of amplifier. .A ~ ',? ' b. TIME (Timer Board): Control to calibrate time base when operating with external battery. ' ~Yi c. RATE METER CALIBRATION (Rate Meter Board): Controls to calibrate meter reading. d. SENSITIVITY (Stabilizer Board): Controls stabilizer setpoint. G. OPERATION OF INSTitUMFNT 1. Verify that.the RD-22 detector is properly connected to the SAM-2 detector connector. 2. Connect SAM-2/RD-22 to power supply and turn POWER switch CN (rear panel). i 3. Operate STABILIZER switch to ON (rear panel) and set CH1 switches to "IN" and "t." I 4. Set CH1'THitESHCLD and H.V. ADJUST to settings determined from last calibration. See label on top of instrument. S. Set CH1 WINDOW to ".72" l l 6. Turn CH2 THRESHOLD to "4.0" and place CH2 WINDOW to setting determined on Date 'ackage 3- (Data Sheet 37.. 7. Place CH2 switches to "IN" and " " for background subtraction. MAJ;1JF SET
t ..o HNP-8142 _ 7*~ -E: 1:' HATCH-NUCLEAR PLANT-e w. ~ See Title Page 3 GeorgiaPower A we .,f 1, 5 e Title Page 8. Set Display ON-OFF switch to "CN". 9. Set desired count time and TIME-STCP-MAN switch to TIME. 10. Place the sample, enclosed in plastic, in the proper geometry to the detector.and press the RESET-START switch. Note the shelf number on Data Package 1 (Data Sheet 1). 11. When counting is complete, the value in the display is " net" counts for the Iodine activity. NOTE If negative counts are obtained when counting a sample, CH2 switches must be set to "OUT" and "OFF" causing gross counts to be* observed in the display. Recount sample and then substract background found on Data Package 3 (Data Sheet 3) manually to obtain net counts. 12. Using Data Package 1 (Data Sheet 1), calculate the Iodine ..p[ concentration of the counted sample using the following 7f formulas: J' a. Silver Zeolite Cartridges: (NET CPM) (4.5 x E-IO) (Volume in Liters)(.95)(D.E.) Iodine Activi.ty (uci/cc) = b. Charcoal Cartridges: (NET CPM) (4.5 x E-10) Volume in Liters)(.99)(D.E.) Iodine Activity (uci/cc) = NOTE 1. 4.5 x 10 = conversion factor to get from disintegrations per minute to microcuries. 2. .95 = filter media collection efficiency for silver zeolite cartridges. 3. .99 = filter media collection efficiency for charcoal cartridges 4. Volume in liters of sample = sampling time (min) x flow rate of air sample (LPM) f S. D.E. = detector efficiency at specif c' shelf height I .,,. 4 Net CPM = Net counts per minute of sample; net counts i s 6. divided by; count time. sl l f[MijF SE1 4
1 ,,.vu - HNP-8142 --E-l.-HATGH NUCLEAR-PLANT ,,,-,o . 4 See Title Page 3 GeorgiaPower b um s,, is See Title Page 13. Opera,tional calibration must be performed DAILY when instrument is in use. See Section I. H. CALIGRATION - SEMI-ANNUAL C'duTION High voltage exists in certain internal components, so extreme care should be used when instrument is removed from its case. 1. High Voltage Adjustment - - ~ Plug instrument into A.C. line and connect a 10b meg a. ohm load to the DETECTOR connector. b. Connect a 3KV electrostatic voltmeter to pin A of the High Voltage Power Supply making certain the High ..y,# Q 1tage Power Supply is plugged into its socket. ' p ). Operate POWER and STABILIZER switches to ON (rear c. panel) and check the high voltage output versus the high voltage settings as indicated below: 9 e HV ADJUST HIGH VOLTAGE S.0 900 - 1100 volts 1400 volts or more 10.0 Record MPL number of electrostatic voltmeter used on-Data Package 2 (Data Sheet 2). d. Set the HV ADJUST control to limit the high voltage at 1500 volts. Record this setting on Data Package 2 (Data Sheet 2) and place a label on instrument bearing this HV ADJUST setting. 2. Calibration of Count Rate Meter a. Connect an MP-1, Mini Pulser to the Ol-it:CTOR connector, setting a pulse height of approximately 300 mv and a frequency of 400 CPM. Record serial number of MP-1 on Data Package 2 (Data Sheet 2). b. Place CHI switches to "+" and "IN", CH2 switches to "OUT" and "OlF". ~ c. With the range switch on X1, adjust the X1 calibration potentiometer on the cate meter board 'foF a reading of 400 CPM on the meter. ....s l[p;ljy SET m'
~ ~ j -on, H"-814 'L -~ E& HATCH-NUCLEAR PLANT mw. w See Title Page 3 p um Georpia Power cA ~~ 6 of 15 See Title Page O d. Repeat with 4000, 40,000, and 400,000 CPM on the X10, X100, and X1000 ranges respectively. Record results on . Data Package 2 (Data Sheet 2). e. Check linearity at 100, 1000, 10,000, and 100,000 CPM on the res:..x.ive. ranges. Do not record results, but if lineari-&ts not i 10% repeat steps 2a - Ec. 3. Adjustment of Linear Gain Set the CH1 THRESHOLD control to 3.64 and CH1 WINDOW a. control to 0.1 b. Place CH2 switch td "OFF." Operate the CH1 WINDOW switches to "IN" and "t" and c. place a Ba-133 source in proper geometry to the detector end face. .. T d. Adjust the GAIN control on the CH1 amplifier - PHA Y~ board until the maximum count rate is obtained. Take several O.1 minute counts to confirm that the 364 kev ~ peak -lies between. 3.59 and 3.61THRESHPLD sefting.... I f ~# there is insufficient gain to place the peak at 3.64, 2,. adjust the stabilizer SENSITIVITY control CW until the J peak is below 3.64, then adjust the GAIN control CW until the peak is approximately 3.64. 4. Threshold Determination Set CH1 THRESHOLD to 2.5 and CH1 WINCCW to 0.1 a. b. Set CH2 switch to OFF. Place a Ba-133 source in proper geometry to the c. detector and face. d. Set count time to 1.0 and TIMED-STOP-MAN switch to TIMED. Do a series of counts advancing the THRESHOLD by e. increments of 0.1, up to a THRESHOLD of 4.0. Record results on Data Package 2'(Data Sheet 2) and plot data graphically on Data Package 2 (Data Sheet Ea). Plot the threshold settings on the X-axis and counts per minute (CPM) on the Y-axis. f. Determine the peak THRESHOLD settingJrom this curve and then using a WINDOW setting of 0.72,' calculate the ,f optimum TliRESHOLD setting by subtrac ting one half of the WINDOW setting from the peak THRECMCLD setting. .___-_._..m_
t t >muw w HNP-8142 --Er1.-H ATCH NUCLEARPLANT.._ _ www _ _ __..e . 4 See Title Page 3 GeorgiaPower d ~ ~_7,, 13 See Title Page g. Place a label showing the optimum THRESHOLD setting and ~ instrument for j:he WINDOW se tting of O.72 on top of the ,later reference. Record the optimum THRESHOLD setting on Data Package 2 (Data Sheet 2). S. Detector Resolution Deter,mination Detector' resolution can also be determined by using the a. curve drawn from the data in step 40. b.
- Determine the peak THRESHOLD setting from this curve and record on Data Package 2 (Data Sheet 2).
Determine the THRESHOLD setting at one half the peak c. count at a THRESHOLD setting greater than 3.69 and record on Data Package 2 (Data Sheet 2). d. Figure the detector resolution as follows: .... T % RES = 2(High setting for 1/2 peak - peak setting) ______________u__ x 100 's-s ' Peak Setting s ~ The resolution should be 15% or less. Record on Data ,3 e. Package 2 (Data Sheet 2). I. DAILY OPERATIONAL CALIDRATION Verify that the RD-22 detector is properly connected to the 1. SAM-2 DETECTOR conne ctor. 2. Connect SAM-2/RD-22 to power supply and turn POWER switch ON (rear panel). 3. Operate STABILI2ER switch to CN (rear panel) and set'CH1 switches to "IN" and "+." 4. Set CH1 THRESHOLD and HV ADJUST to settings determined from last calibration. See label on top of instrument. S. Place'CH1 WINDOW to ".72". 6. Get CH1 switches to "IN" and " t", and.CH2 switches to "OUT" and "OFF". 7. Set Display ON-OFF switch to "ON". 8. Get count time to 1.0 minute and TIMED-ST'OP-MAN switch to TIMED. fS*JF SET
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l .va - - --Erl.- H ATCH -N UCLEAR-PLANT- - -- HNP-8142 See Title Page us.u w GeorbiaPower A ~ ~~ 8 of 15 See. Title Page 9. Record a 1.0 minute count of CH1 background at these settings on Data Package 3 (Data Sheet 3). 10. Set CH1 switches to "OUT" and "OFF", and place the CH2 switches to."IN" and "t." 11. Place the 'CH2 THRESHOLD TO 4.0 and adj ust the CHa window until it equals the background count found in CH1 (The difference between CH1 & CH2 should not exceed 5% if possible.) Record the CH2 window setting on Data Package 3 (Data Sheet 3). 12. Set CH1 switches to "IN" and "t" and CH2 switches to "IN" and " " 13. Place a Da-133 source in~ proper geometry to the detector on Shelf # 3 and count for 5 minutes. Counts observed in the display window represents the NCT counts of the source with the background subtracted. Record in counts per minute on .,...d Data Package 3 (Data Sheet 3).
- 3. '
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NOTE s ~ "A If negative counts are obtained when counting a sample, CH2 switches must be set to "OUT" and "OFF" causing gross counts to be observed in the display. Recount sample and then substract background found on Data Package 3 (Data Sheet 3) manually to obtain net counts. 14. Divide the NET counts per minute of the source by the known disintegrations per minute of the source and multiply by 1.19 to get the efficiency of the detector (D.E.). NOTE The 1.19 factor accounts for the difference in yield of the Da-133 and the I-131 gammas. 15. Repeat steps 11 and 12 with shelves 4 and 5 to obtain a-detector efficiency for each of the three shelves. 16. Complete Data Package 3 (Data Sheet 3) on a daily basis, only when SAM-2/RD-22 is in use. ~ 1 ~. l ~ l ..s ~ (faally SET 3
er WP-8142 -n '-T,' -E-l.-HATCH NUCLEAR--PLANT -e rwn w 0 See. Title Page 3 vaia ~~ Georgia Power - ,,, is g,,.ritie eag, PROCEDURE CATA PACHACE occtre4T ic: HNP-8142-1 SERIAL NO: RO3-MPL NO: RTYPE: G15.14 ~ XREF: TOTAL DEETS* 2 ..wM FREQUENCY: As Required ...j. y, COfLETED BY: .., s. ,:n - DATE COffLETED: p I HAVE REVIEWED THIS DATA PACMACC FOR COfLETEPESS AND AGAINST ACCEPTANCE CRITERIA IN ACCORDAtKE WITH I4f-830. ACCEPTABLE LNACCEPTABLE REVIEbt'D BY: DATE RENIEWED: REMARKS: Page 1 of 2 M -8142 R03 FIGURE 1 Page 1 of 2 10MA' SET ,'~ ,i s - _. -..- u
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_._ -E.t HATCH NUCLEAR PLANT - W W -8142 Sue Title Page <t vw. r.o 3 3,, See Title Page 11 of 15 s PROCEDURC DATA PACKAGE DOCt.F1ENT NO: HNP-8142-2 .s SERIAL NO: RO3-IPL PC: RTYPE: C15.14 XREF: TDTAL DEETS: 3 -e . A. FREGLENCY: Semi-Annual s'J-M- COPPLETED BY: y m* J ' DATE CQfLETED: ! IMVE RENIEWED THIS DATA PACKAGE FOR COMPLETE?ESS Arc AGAINST ACCEPTANCE CRITERIA IN ACCORDANCE WITH l+P-830. r ACCEPTADLE UNACCEPTABLE 1 REVIDED BY: DATE REVIDED: .c '~ G li RCMARMS: Page 1 of 3 FN8-8142 ~R03 FIGURE _2 Page 1 of 3 f,041Ju SET.
... ~.. - 1 1 m,,,,.< m m., m, .. ~ - E ITHATCH NUCLEAR PLANT-- -- HNP-8142 . _. w; See Title Page ..a w .a van 3 Georgia Power tc. 1a,, is See Tit 1e Page DATA Pact <Ar.E 2 \\, DATA SHEET 2 INSTRUMENT: SAM-2 LOCATION: MPL NO.: lAL10. ACTUAL DATE: THAESHO.D CQtji9 fS COURCE COUNT CALIO OY: 2.5 RATE AS FCLND AS LEFT 2E CPM CPM CPM ___@.7 m.1 400 _._2. 8 SN 4000 2.9 40000 3.0 400000 3.1
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~4 H N P-4848 See Title Page uv s.o o 4 o Georgia Power m 4. cm J. See Title Page 1 of 11 DETERMINATICN OF THE EXTENT OF CORE DAMAGE UNDER ACCIDENT CONDITICBjS A. PUDPOSE To provide instructions for determining the extent of core damage under accident conditions. B. R_EFERENCES NEDO-22215 " Procedures for the Determination of the Extent of Core Damage Under Accident Conditions" by C. C. Lin. C. SAFETY Observe good radiation protection practices when handling samples to minimize personnel exposure. D. PROCEDURE Obtain a reactor water sample and a drywell atmosphere sample by atsing the. installed Post Accident Sampling System (PASS). Deturmine th'u corrected activity concentration in micro-curies per gm (uCi/gm) decay corrected back to time of reactor shutdown. This correction can be done by entering the time of the reactor shutdown 2.nto the computer for the sampling time. Determine the corrected concentrations.of the indicator isotopes I-131, Cs-137, Xe-133, and Kr-85. Multiply the concentrations of I-131 and Cs-137 that are in the reactor water'by 1.22. Multiply the Xe-133 and Kr-35 in the drywell atmosphere sample by O.786 for Unit I and 0.795 for Unit II. AFter mul tiplication, the resulting concentrations are the normalized concentrations and can be compared to the charts developed by General Elactric and included in this procedure as Figures 1 through 4. Any damage to the fuel in the core can be determined directly from the graphs by reading percent of damage versus corrected concentration in uC1/gm or uCi/cc. E. OTPEP FACTOR _@ For further refinement of the core damage estimate, cons' tit the reference in Section D. Some other factors that may'be useful in determining core damage are su:miarized as follows. 1. Containment Radiation Levels Containment radiation level provides a measure oF core' damage, because it is an indication of the'ienventory of / LIAhUAL SET
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mxt= = HNP-Son Title Page um.o,. o O. O Georgia Power an 2 of 11 See Title Page airborne fission products (i.e., noble gases, a fraction of the halogens, and a much smaller fraction of the particulates) released f rura tha fuel t.o the containment. Containmen t hydrogen levels, which are measurable by the PA'35 or the con tainment gas analyzers, provide a measure of the extent of metal-water react. ion which, in turn, can be used to estimate the degree of clad damage. 2. Rpactne Vessel Watnc Level Another significant parameter for the estima tion of core damage is reactor vessel water level. This parameter is used to establish i f-there has been an interruption of ,adequa-te core cooling. Significant periods of core uncovery, as evidenced by reactor vessel water level readings, would be an inlicator of a situation where core damage is likely. Water level measurement would be particularly useful in distinguishing between bulk core demage situations caused by loss of adequate cooling to the entire core and localized core damage situations caused by a Flow blockage in some portion of the core. 3. Main Steam Line Monitors There are other parameters which may provide an indication that a core damage event has occurred. These are main steam line radiation level and reactor vessel pressure. The usefulness of main steam line radiation measuremen t is limited because the main steam line radiation monitors are downstream of the main steam iso 1' tion valves (MSIVs) and a would be unavailable following vessel isolation. 4. Reactor Vessel Prau ure Measuremont Reactor vessel pressure measurement would provide an ambiguous indication of core damage, because, although a high reactor vessel pressure may be indicative af a core damage event, there are many non-degraded core events which could also resul t in high reactor vessel-pressure. 5. Detection of the Less Volatile Fis:;lon Products There are other measurements hesides radionuclide measurements which are obtainable-using the PASS which would further aid in estimating core damage. Detection of such elements in the reactor coolant as Sr, Ga, La, and Ru is evidence of fuel melting. These indications could be-factored into the final core damuge estiinate. c 's. , + ,..e- +e --e..m eo e e..m w e w. .e-. +-.
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- - - a.~ew x. _- ? -- m w - u., =, ~ ?- .n._ - +., __ [=*cm E. l. Hatch Nuc! car Plant et= ~ H N P-4848 See Title Pago %,,so o 4 o Georgia Power am ~~ o,. Cee Title Page 3 of 11 6. Metal-Wa f or Reaction n F Hydroqen in the Containment The extent of fuel clad damage as evidenced by the extent of me tal-wa ter reaction can be estimated by de termina tion of -the hydrogen concentration in the con tainmen t. That concentration is measurable by either the containment hydrogen monitor or by the post accident sampling system. A correlation has been developed which rela tes con tainment hydrogen concentra tion o t the percent metal-water reaction for Marl < I type con tainments. Tha t correlation is shown in the curve below. Steps 1, 2, & 3 below indica te the method by which Plan t Hatch can use the correlation to determine the extent of clad damage. Step 1: Obtain contair. ment hydrogen meinilor reading, (H), in %. Step 2: Using the curve below, determine the metal-water reaction For the reference plant, MW rei. Step 3: The metal-water reaction for the actual inplant conditions (MW) is determined from the following equation: '-~ t \\ %MW = (MW ref ) x 0.655 S i l i 1 i l. t .. L....... _ _ _.._ _ _. __. l ._. ENUAL. SET ;
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E. l. Hatch Nuclear Plant 'i = aa m mac ~ HNP. 4 8'+8 ' Soo Title Paga uviso=~o 4 0 Georgia Power ad. e... - ~o See Ti tle Page 5 of 11 7. Containment Radiation Level Readings An indication of the extend of core damage is the containment radia tion level which is a measure of the inventory of fission products released to the containment. The purpose of this step is to present tha t correlation and provide a method whereby-Plant Hatcle can use the correlation to determine the degree of core dar.w g a. The procedure for determination of fraction of fuel inventory released to the containment is as follows: Step 1: Ob tain containuent radiation monitor reading, (R), in Rem /hr. Stup 2: Determine elapsed time from plant shutdown to the containment radiation monitor reading (t) in hours. Step 3: Using the curves below, determine the fuel inventory release for the reference plant (I) ref in %. Step 4: Determine the inventory release to the containment (I) using the following formula:* (I) (I) ref x 0.445 = /. t,iAtiUAL SET .____________-m_.___ m .__1-
E. I. Hatch Nuclear Plant
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k O Georgia Power a ~~ o.m See Title Page 7 of 11 ~ 8. Ap.p_lication of Other Significant Parameters to Core Damase Estimain As noted previously, procedures have already been developed which provide an estimate of core damage based on radionuclide measurements. Based on these procedures, an initial assessment of core damage is made. Based on a clarification provided by the NRC, that assessment would appear in a matrix as follows: Degree of Minor In termedia te Major Degradation (410%) (10% - 50%) (7 50%),__ No fuel damage t-----------l-----------* Cladding fail'u're 2 3 4 Fuel Overheat 5 6 7 Fuel Melt 8 9 10 As. recommended by the NRC, thera are four general claf.ses of damage and three degrees of damage within each of the classes except for the "no fuel damage" class. Consequently, there are a total oF 10 possible damage assesspent categories. For example, Category 3 would be. descriptive of the condition where between 10 and 50 percent of the fuel cladding has failed. Note that the conditions of more than one category could exist simultaneously. The objective of the final core damage assessment procedure is to narrow down to the maximum extent possible those categories which apply to the actual inplant situation. Y MANHL -SET '
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0 Georgia Power h ~. ~o e.,E Gee Title Page 9 of 11 FIGURE 2 NEDO--2P.? 15 S t.' gt t urL7f>%w ~ UrrtR HELEALC Llulf (CET CSTIMATE ,/ LCvrtR fttLt A$t Livi? I m/ / 10 ./ ./ / ~ / / p / / / ,/ / / / / / / / = b / / / / k 'O, -~ / / / / / / f ~ / l / / / u / / / s / / E / / "3 / / 10 / 5-p t / / / c / / 5 / / 5 / u / Ct A00iNC 5 astunt / / / UPPER RELEASC LIMIT C 10 ? / DEST C3tli/ ATE g / p ~ / LO'At*t RELEA$t LIM 47 ., / / / / 0.1 NonuALSHuTCOWN / CONCINTH ATICN / iN ataevon n trR / / UPPtit Ltuif. D 3 Cite / h 0M 64 AL. 0 03 e.C.ig ./ j 10-2 ,,,,,d ,,,,3 ,,,,,,3 ,,,,,j 0.1 1.0 10 100 9.CLADOING F AILunt 1.0 10 100 l- % FUEL MELTDOWN ^ 'g Figure 2; Rela tionship bistween Cs--137 Concen'tration in the Primary Coolant (Reactor Water + Pool Water) and the Extent of Core Damage in Reference P13nt- -.. -... ~. - MANUAL SET
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._.,_z E. l. Hatch Nuclear Plant c,~>ms c'e="<gg HNP-Seu Title Page Havis o= ~o b O Georgia Power a_. e.,t 10 of 11 Gee Title Page FIGURE __3 NEDO-22212 t o FL, CL *
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jh CEST ESTiuATE 7 / p / ~ Lontra ntLE A3C LIMIT / 'd /: / / // // / /} // / / / ~ 3 // / 2 // / 10 // / // 5 / y/ / / / ~ / 5 / g ,/ / / / / 5 / / to -= / ~ E f / r ./ o 5 / = 7 / / ct A00tNG r ait ut,E s / UPetR RELta5E LIMtf / 1.0 / EEST ESTlWATE 7 d . / / LOWER MILE ASE Liut'T / ~ / / / / 01 r/ esonvAL ortn AtiNo
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i __-... _ ~ _, = _ =... _ t -- ~ ' - - ' ~ e GCORGIA PCh" R CCNPANY 1ATCll NUCLEAR PLANT PROCEDURE PHR - Core Coray Corner Room Fire I3i,s L,1,.C_.L...... I.i.L t. L. unt 4 HNP-42G'7 PROCEGUF.E NUMOCR s Enq.i n : o n _t n.<.I RESPONCICLE SECTIGil SAFETY RELATED ( X' ) h3N-SAFETY RELATED ( ) ______.______1_______________._____.._. AFPROVED APPROVED DEV. OESCPTPTION DEPT. PLANT DATr. I HEAD _____,'_>2R MANA .r r- ~ 1 Pages 1&2 ' ~ ' ,g 7 .________________7 n i . _ ____ _____ s_ _. i a r e t t 9 i l ,s ________-w,-_-.. HNP-9 ' MANUAL SET
A -- - ---~ . -~ ?yn.Gu B proct'ni t9C_ G.rv t. t.e..:-. Drdt t CT 2 I PROCCOUGE NO. IcP-k- E b_-_-_- Rovis(on No. L!-_-- ( W n U: m T:~ D P.Y f: w * .- - - - D_ n i.",R Tt O :T t#ca t.PP:enve, Dist e ; Sign 0ture: 5 b dYb O,i t e : nO S~- y.ag REVISION CHeN0CG MCCE CF CPERATION OR INTEN AS DESCRIDED IN FSAR: .( ) Yes ( .). No j
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( ) An unreviewed Safety Guestion ( ) T^e ch. Sp e c s. (~ ) Neither (See bacle for Safety Evaluation If. required). Ssfety Related ( /) Non-Safety Related ( ) .~. Safety /Ncn-safety Status Chr.nce ( ) Yes ( No I At tach inriri:ed up copy of procedure to this form. R.,EASON FOR RECUEST .h...c. '. hie n sh. 2. A. l a_2 b 7 8, d #'l 4 v1 ${sk~cnl -y-- NsY { C 45pmenY ho h:e ,9 clis _en e,rm la.e.c{. T*'h e. (- corre s.,oonel,% %M-a eelpmed slwIdalu li_s-cle-e_,,em,,. ised. P 9 t - - - = t ~ -~~- -- PCD RC& T:03 cvaOVAt.: (/)'ves ( )No L- ~ . _e _ 83-D FR,6eccgury r 8 .J _ 7-J 45 s. FMs nwater -- te._msd-u- D.. t e a w-MANU L'SE
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onerations to be excet$ded as stated in Technical S_nec f ca_t_on_s_.____
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_. _ = - ~ ~ ~ ~E.~T." Hatch Nucl5ar Plant ~' ~ ~~ a~~ ea==* ~o i HNP.4257 e See Ti tie Page may,3 o=.~o Georgia Power s ..e. ~o o.. hlQ See Title Page 1 of 5 RHR - CORE CPRAY CCRNER ROOM FIRE A. CONDITION 1. Fire in either RHR - Core Spray Corner Room has been identified and reported to the Con trol Room, or, 2. The following symptoms indicate a possible fire in either of the RHR - Core Spray corner rooms. a. Main Control Room alarms indicate: (1) Low level RHR - Core Spray discharge 1ines. (2) Spurious RHR - Core Spray alarms. (3)- -High-temperature RHR or Core Spray pumps. b. Emergency cooling units T41-0002 A or B and T41-8003 A or B start. c. Loss of RHR and Core Spray pump status indication. ~ d. Loss of RHR and Core Spray valve indication. Spurious valve movement - RHR and Core Spray systems. e. f. Unexplained instrumentation abnormalties. g. Smoke in the ventilation system. D. ACTION 1. Initial actions of Cont'rol Room personnel and Fire Team members shall be as described in HNP-4200 " General Fire Procedure". 2. Additionally, the Control Room Operator shall, a. De-energize the following equipment: (1) Reactor Building Supply Fans T41-C001 A & B & 2T41-COO 1A & B. (2) Reactor Guilding Exhaust Fans T41-COO 7 A & B & 2T41-COO 7A & B.- 1 (3) Decon and CRD Repair Area Fan T41sCOO3. 9 6 51ANUAL SET l
.~- __n 'E. t.' Hatch Nuclear Plant ~~ - e=a=ac ~o ~ ^ ""a= - ~ ~ HNP 4257 l See Title Page l asmio= ~o
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_,_,__.g-... Georgia Power s l ..m ~o a of 5 See-Titie Pa"" 1 f (4) Refueling Floor Gupply Fans T41-COO 2 A & B and 2T41-COOC A & C. (5) Refueling Floor Exhaust Fans T41' COO 5 A & B and { 2T41-COO 5 A & D. l (6) Emergency Cooling units in the affected corner room, T41-BOO 2 A & B and 2T41-DOO2A & B (s.e. j corner room) or T41-GOO 3 A & B and 2T41-BOO 3A & B (n.e. corner room). (7) RHR pumps E11-COO 2 A & C and 2E11-COO 2A & C (s.e. j corner room) or Ell-COO 2 0 & D and 2E11-COO 2B & D (n.e. corner rarm). -- { (8) Core Spray pump E21-COO 1 A and 2E21-COO 1A (s.e. corner room) or E21-COO 1 D and 2E21-COOlB (n.e. corner room). { (9) Jockey pump E21-COO 2A and 2E21-COO 2A (s.e. corner room) or E21-COO 2 B and 2E21-COO 2D (n.e. corner room). l z b. Monitor plant parameters for abnormalties. C. F7RE FIGHTING STRATEGY 1. The Fire Team shall proceed to the fire scene via the Unit 1 Reactor Guilding southwest stairwell to the 130' elevation. Proceed across elevation 130' to the affected corner room. (See Figures 1 through 3). CAUTION: Fire may adversely affect the structural integrity of the platforms and stairs. 2. Fire Team Leader ensure affected electrical equipment is-de-energized. i 3. If the fire is in the southeast corner room, I Utilize the hose station on the south wall of the a. l reactor building 130' elevation near column R4 or the hose station in the 87' elevation of the corner room to attack the fire. 4. If the fire is in the northeast corner room, a. Utilize the hose station on the east' wall of the i reactor building 130' elevation near cuiumn RS, the hose station on the south' wall of the HPCI room or the hose station on elevation 87' of the corner room to attack the fire. MANUAL SET
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n $C bl % '.lU g() 1 gg.e3 Pnocrniing_gEh*,1gige_GQugGI s. j... ~PROCEOUnEN'O.Ht'P__h./j_ O. novision No._ /_/o_______ ---______________1_ ___________ n.7esnpsuI m eg ce_2ej.i.r,__.___ ________mwswn nv ca ut; signature,: 7 ', cate: n name; 4i N0 //,#_1 f _ _ f, $/1_.//_ / 1 Al 9 f 5 = REVISIC ' CHATOEG MOCE F.CPERATICM OR INTENT 'S CEGCRIGEO IN FSAR: ( ) No ).Yes ' ~ -.*...-( An unroviewed Safety'Gtiest' ion ( 7 Tech. Specs. (' Neither CHANGE INVOL.VES: - **( ) if r? quired). (See back for Safety Evaluation Non-Safety Re5ated ( ) SafetyRe[ated ( ( /-r"f7o' ~ ( ) Yes Safety,'Non-saf ety Status Change copy of proceduYe tN thi's form. y '.a&&f%2'_'es? Mj -#=;$;.swigLlw -l-Attach marked up REASON F6R RECUEST ff)gh 3),r,, g/_fg JD l & & seke/ a, M_ 7 _s___A,.__ . L_ O?.ae Z )g /,,f, g ~ g y / h n, ) h ] /[/ /
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t-E. l. Hatch Nucicar Picnt a=ouwac ao mpa HNP. 8010 s e5'oa w See Ti tie Pat}e 1T Georgia Power s. c'.. '1 of 36 h, 4 o.m See Ti Ma Paoa USE AND CARE OF RESPIRATORS A. PURPO?E To provide instructions for,the proper selection,
- use, control and storage of respiratory equipment.
maintenance, This procedure covers the following respiratory devices: MSA Ultra Filter Respirator Pressure Demand Apparatus (Air Pack) MSA MSA ' Constant Flow Air Line Respirator ' NPO Supplied Air Respirator (Hood) 8. REFERENCES 1. 10 CFR2O para. 20.103 - MSA Respirators Instructions for Use and Maintenance 2
- .. d NPO Supplied Air Respirators Instruction Manual
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3. 4. A.N.S.tI. Z-88.2 (1969) ~co*, C. SAFETY Observe Radiation Protection Procedures. D. MANAGEMENT POLICY It is the Georgia Power management policy to minimize the inhalation of airborne radioactive materials to all personnel assigned or visiting Plant E. I. Hatch. For this reason it is mandatory that personnel at Plant Hatch adhere to all procedures, and policies relating to the respiratory protection program. The management policy will be normally accomplished b.y the including process, application of engineering controls, Periodic evaluation.of containment, and ventilation equipment. respiratory protection program will provide the management .the with the means for determining what additional measures, equipment and controls may be necessary, where practical,.to further mee't the' objective, while in turn reduce the need for-wearing respiratory equipment. Routine plant operations are planned activities that are Frequencies. generally repetitive and occur with various Operations of this nature have been considered in the design of the plant and appropriate equipment installed to minimize most airborne situations. - +, q 4-. _.... ,.._ _ c _...: __.. _ MiMs' SET ,.l. 'v
"fa= E.1. Hatch Nuclear Plant au= ~o HNP. 8010 atoon ao c,53ce Tiiile Page ". 4 k 17 Georgia Power s 2 of 36 Sne Ti tle Pace The use of respirators as a substitute for practical engineering controls in routine operations is inappropriate. Therefore the installed process, containment, and ventilation equipment will be utilized, in addition to preplanning of work, to minimize the use of respiratory equipment. Nonroutine operations are acti,vities that are either infrequently that adequate nonrepetitive or else occur so limitation of exposures by engineering controls is impractical. For operations of this type respiratory equipment will be used where needed to provide protection. Emergency operations are unplanned events characterized by risks sufficient to require immediate action or mitigate an abrupt or rapidly deteriorating situation. Procedures have been issued for handling most emergency situations and are contained in procedure series HNP-4000-4999. Adequate quaritities of and locations for respiratory protection equipment are provided to handle emergericy situations. Training and retraining of personnel in emergency situations requiring respiratory protection is provided. Prior to issuing a respirator to an individual, he/she will be informed of the following policy: Persons wearing respirators in may leave the area at any time for relief from respirator use .,J ' the event of equipment malfunction, physical or psychological c distress, procedural or communication failure, significant deterioration of operating conditions, or any other condition that might require such relief. E. REGULATORY REGUIREMENTS 10 CFREO paragraph 20.103 specifies regulations regarding exposure of individuals to concentrations of radioactive materials in air in restricted areas. This proceduro has been written to carry out the regulations. F. DESCRIPTION OF RESPIRATORS 1. Ultra Filter Full Facepiece Respirator This respirator is a full facepiece unit with a single or -double cartridge providing protection factor of 50 against less dust, fumes, and mists having a time weighted average than-0.05 milligram per cubic meter. The respirator with the rectangular ultra filter cartridge has an approval No. TC 21C-150. The respirator with the round ultra filter Type H cartridge has an approval No. TC 21C-155. . - - + , g ?.-.._._ g MMUF SET .'=i ..u & r
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Georgia Power a2 ..m ~o 3 of 36 9ee Titia Pace NOTE It This respirator removes only dispersoids from the air. gives'no protection agains t gases, vapors, or oxygen deficiency (less than 19.5% O ). 2 2. Pressure Demand Apparattti (Air Pack) The Pressure Demand Apparatus (Air Pack) consists of a high pressure cylinder, a pressure demand regulator connected by a facepiece and tube a high pressure tube to the cylinder, assembly with an exhalation valve, and a harness assembly for mounting the complete apparatus on the body. The unit maintains a slight positive pressure inside the facepiece during inhalation, thus minimizing potential air in-leakage into the facepiece. The unit contains an audible signal device to indicate when the breathing supply has dropped to The unit a point where the user must return to fresh air. is rated for 30 minutes service. Actual service time will depend on the user and his level of exertion. The unit has ,,,g' an approval-No. TC13F-29. It can,be used in oxygen deficient and in toxic atmospheric conditions and has a protec' tion factor of 10,000 for particulates, gases and
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3. Constant Flow Air Line Respirator - Full facepiece The Constant Flow Air Line Respi.rator is a respirator approved for use in atmospheres not immediately hazardous to life or health. The unit consists of a facepiece and tube assembly, low pressure control valve, from 25-200 Feet of air hose, and a portable air filter and regulator. Dreathing air for this unit is provided by the plant service air compressors. The service air is filtered and redutec in pressure to 35-40 psig by the portable air filter and With regulator to meet the requirements of the respirator. this respirator, a continuous flow of brea thable* air is supplied to the facepiece and provides a cooling effect as The it meets the respiratory requirements of the wearer. unit has an approval No. TC19C-T8 and provides a protection factor of 2000 for particulates, gases and vapors. 4. Hoods The Supplied-Air Hood is approved for respiratory protection agains t atmocpheres not immedia tely dangerous to life or health and contains 1 19.5% oxygen. The unit consists of a hood, cape, air distribution unit, belt, air line hose and source of clean respirable air (Class D oP higher quality). The respirator has a MSHA-M105H approval TC-1SC-140.,, _ -.----.v-..,,,.. - _ - ~+=m
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E. l. Hatch Nuc! ear Plant moa== ~o C#'fca HNP. 8010 avsou o ,,$ee Ti tle Page k 17 Georg. Power s a .4 ,.m ~o 4 of 36 Soo Tit 1e Paqn t A pro tection factor of up to 2000 may only be used when the air flow is maintained at the manuf acturer's recoranended maximum. rate of 15 SCFM. The following Table will be used the Air Supplied Hood. to esfablish pressure setting's for PRESSURE RANGE (PSIG) LENGTH (FEET) NO DF SECTIONS MINIMUM MAXIMUM 25-50 1 or 2 20 34 (28*) 25 45 75-100 1-4
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125-175 2-6 38 55 200-275 2-6 .---_----_--_----.-__--------.i.------.----_..--------------, Maximum Pressure of 28 PSIG will Hansen (D) and snap-tite (D) Httings. .. d NOTE A 'dv. the A prot;ection factor of 2000 may only be used when
- ~T, pressure is regulated at the maximum pressure settings listed in the above Table.
Pressure settings less than the maximum. range and greater than minimum range will drop the protection factor to 1000. Never set pressure below the minimum range nor higter than the maximum range. G. SELECTION OF RESPTRATORS FOR USE NOTE Respiratory protection devices may be required in any situation arising from plant operations where the potential for airborne radioactivity, oxygen deficiency, or toxic atmospheres exists. In such cases, the air will>be monitored by Health Physics or other qualified personnel and to the the necessary protective devices specified according concentration and type of airborne contaminants present. It is the responsibility of the individual and his supervisor to notify Health Physics personnel when working witn to become radioactive or hazardous material that are likely Every precaution should be taken to keep air airborne. contamination to a minimum through use of proper ventilation and prior.da. contamination of equipment or work areas. Ib. -...-..--_.,... g.. +. 4
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y ~ao= E. I. Hatch Nucicar Plant a=== ~o Y H N P-8010 t Gac Ti t1e Paga am'ou ~o k .f 17 Georgia Power s c.m Na Ti+1a Pana 5 of 3G 1. Regulatory limits and rules. Respiratory protective equipment will be selected to provide a protection f actor grea ter than the mul tiple by which peak I concentrations of radioactive materials are expected to exceed the values specified in Table I Column 1 of Appendix 0 to 10 CFR20. The equipmen't selected is to be used so that l the average concen tration of radioactive ma terial in the air that is, inhaled during any period of uninterrupted use in an airborne radioactivity area, on any day, by any individual using the equipment, will not exceed the values specified in Table I, Column 1 of Appendix B to 10CFR20. F.or purposes of this procedure, the concentration of radio-active material in the air tha t is inhaled when respirators are worn may be initielly estimated by dividing the ambient concent ration in air by-the protection factor specified in 10 CFR 20.103 Appendix A. If a respirator user's intake of radioactive materials is la ter determined by other measurements to have been greater than that expected from j initial estimates of radioactive materials in the air the Ye. ' user inhales, the greater quan tity-is to be used in.... _ __.. _ _. 'f evaluating exposures. If it is less than that initially e s t imiit e d, the lesser quantity may be used in evaluating ~.3, exposures. 2. Administrative rules and limits. ,a. .Section.E and paragraph G.1 prescribe rules and regulations which shall not be exceeded. For administrative purposes Table 1 will be used For selecting respirators. b. If airborne conditions exist which require consideration toward exceeding the administrative limits in Table 1, a laboratory suparvisor mu.it be consulted and his approval received before using greater values. 3. Golection procedure. a. Determine the radiological (external radiation and airborne) conditions in the work area using the procedures HNP-8005, 8012, G013. Air samples should be taken as near the breathing zone whera the work will be performed as possible. (Also if the worker has to pass through an airborne area to get to the work place). b. 1." air sampling confirms that an airborne condition, as defined in HNP-8003. exists in the worR a'rea, respiratory p ro t action,_egui nnen_t3 increased l g4 sur ve i IIdn~c e, or limitation of working times is ___ _ warranted. Mhua' SET .. s> t
ha E. l. Hatch Nuclear Plant =aowe ~o H N P-8010 I atwsion ao .Coe Titie Pag'e k 17 E. Georgia Power s .o om 6 of 36 een Titia Papa c. Consiter the type of work, work hazards and locations, time 1o complete the work, ambient condi tions at the work 1) cation, equipment to be used by the worker. and the poten tial for airborne conditions to develop during the work period (i.e. highly contaminated areas and equipment, opening of equipment during the work,' air movement in the work location, cutting and welding work, etc.). Consult w'ith a laboratory supervisor or designated d. alternate and select the proper respirator for the work conditions using Table 1 and paragraph b and c above. Issue the respiratory equipment per Section H. e. The worker, after proper training, will wear the. respirator using Section I as guidance for danning the ~ equipment. 4,. Determination of Airborne Radiation Exposure. .= Anytime an individual is'likely to inhale, for any two y, a. --- hours in a day or ten hours in one week, radioactive -*t-- materials in uniform concentrations as specified in Appendix 0. Table 1 Column 1 of 10CFR20, the following .:o -# calculations shall be made to determine levels of airborne radiation exposure. b. From the data on HNP-8013 Data Package 1, Data Sheet 1 and HNP-8008 Figure 2, calculate the exposure to airborne radioactive materials as follows: K MPC - HRS = Hours in Area multiplied by A c t i v i.ty__fj (PF) NPC N=1 N N WHERE H = Number of nuclides in the air th Activity oF the N Nuclide in uci/cc Activity = N th Protection factor of the respirator for the N PF = N Nuclide (See 10CFR 20.103 Appendix A) th MPC = MPC of the N Nuclide in u ci/cc N Hours in Area = Stay time in the airborne area in hours in MPC. HR!5 ' Fos' the c. Log the airborne exposure -- ~ 4~ 7.4-- appeopr-iate day-nn Form S (Data Package 3) using the ~ ~ results obtained from G.4.b.
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i H N P-8010 uv*cN ao ../ Gee Title Page 4 7 Georgia Power a.A ..o ~e om % Title Pane 7 of 36 NOTE If an individual's airborne exposure ext.eeds 2 MPC HRS in any one day or lo MPC - HRS in any une week then that individual's intake will be assessed by appropriate methods as outlined in Section L and all his exposure to airborne radioactive ma terials will be ' documented on Form' G (Da ta Package 3) for the current calendar quarter including those amounts oF exposure below 2 tPC - Hrs. in a day or 10 MPC - Hrs. in a week.. H. CONTRl'M_3, ISCUANCE, PROPEN UGE AND RETURN OF REEPIRATORY EGUIPMENT 1. The Health Physics staff controls the issuance, proper use, inspection, cleaning and repair, testing and fi t-t ing,, spare parts, and quantities of respira tor equipment requi: ed. (The Regulatory Specialist handles special training for the fire brigade team on SCCA). Training is conducted by the Training Department. d. Respiratory equipment will be issued only,to. j = r. _..__f._..._- .._...g_. . Those persons who have been trained, fitted and tested fbr that type equipment. . :-vv b. Those persons whose facial hair does not interfere with the seal of the respirator. c. Those persons who have received medical approval by a physician to wear respirators. 3. Only MSHA/N10SH approved equipnient will be used when taking credit for the use of respirators in protecting personnel from airborne activity. 4. Respiratory equipment will be issued using a Radiation Work Permit procedure, except during emergenc, conditions. 5. Adeqimte surveillance and surveys of the work ac-tivity by the Health Physics staff will assure proper use of the equipment. E., The Health Physics staf f will conduct an adequate number of air surveys during the work period to verify and assess radiological conditions and exposure to personnel. 7. Facelets will not be used for protection against airborn radionuclides. 8. Equi pmen t. will be used within the, limitations -for its type and make of use as described in this procedure. __..-__..y.,__ [' f63tja' SET
E.1. Hatch Nuclear Plant ~xwu= ~o f'= HNP. R010 ) nvmo= ~o Gee Title Page 17 x' Georgia Power m + 8 of 36 Sea Title Pano 9. Only the SCBA equipment is to be used as emergency devices. 10. Where required, spectacle kits will be Furnished to permanent plant personnel. 11. Where required, goggles, anti-fog compounds and communication gear will be furnished to respiratory users. 12. Contact lenses are not to be worn with full-facepiece respirators. Air purifying respirators are not to be used in oxygen 13. deficient atmospheres or atmospheres immediately hazardous to life or health. 14. No credit will be taken for use of sorben t cartridges, against radioactive materials. IS. Only high efficiency cartridges, as described in Section F will be used in air purifying respirators when making allowance for the use of respiratory equipment in estimating -g, exposures of individuals to airborne radioactive, materials. j . _ f _,_.. 16. Filter, cartridges on air purifying respirators must be replaced with a fresh cartridge after one work day's use by .-w# one individual. 17. Respiratory equipment except emergency equipment, will be issuad by and returned to the Health Physics staff. Issuance will be controlled through an RWP permit, a Respirator Clearance List (or Respirator Clearance Card, ) and the use of Form 6 (Data Package 4). The normal method of issuance will be through the use of the clearaice card unless exempted by the H.P. Superintendent or designee. In lieu of Form G (Data Package 4), Health Physics may coni.rol issuance and return of respira tors at established control points by the worker surrendering the respirator clearance This card to the Health Physics technician upon issuance. card will be retained until the respirators are re turned. I. USING THF RESPIRATORS 1. Health Physics will issue the proper respirator for the work to be erformed. NOTE ( is emphatically advised that he l a. Each respirator user I should immediately leave the area for relief from respirator une in case of equipment malfunction, physical or psychological. discomfort,'ui* any other reduction'in the protection - 4-condi. tion _ihat..mi gh t cause afforded the user. ~~ ~ .} f6Ma' SET .g Q .i.
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- 7 9 of 36 San Ti+1a P A <in Respiratory protective devices should never be worn b.
when a satisf actory face seal canno t be obtained. Custom Comfo Aerosol - half face respirator will not be c. used for respiratory pro tection. 2. Full facepiece w/ type H Ultra Filter Cartridge. Perform Steps I.6. for donning the facupie<:e. a. Remove the facepiece after use per subsection I.7. b. 3. Constant flow air line respirators (full facepiece). i. Inspect equipment as per Step N.1 and N.4. Bleed off the house service air line to remove any b. condensate which msy have formed in the sys tem prior to connecting the portable Filter and regulator to the service air line. 29 Connect the portable filter and regulator u, nit to a ~. ' c. f house service air line, using the air hose provided. / Attention should be made to keep the unit out of the contaminated area; but if this is not possible, it
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should be wrapped in plastic. Operate the unit in the upright position only. Tag the service air outlet with a "To Be Operated by d. H.P. only" Tag. Bleed off the Adjust the regulator for 35-40 psi. e. filter trap for moisture. control valve on a belt'or loop on the left f. Place the side of the body. Put on the facepiece as in subsection I.G.. g. h. Connect 25-300 ft. of MSA air hose f rom portable filter Then connect regulator unit to the control valve. facepiece breathing tube to the control valve. do not remove i. A'fter leaving the airborne or work area, coveralls and the facepiece until outer pair of gloves, shoecovers are removed. (This may.not be possible in all cases). from the j. Disconnect breathing tube and air line' hose con-trol valve. Disconnect air line_ hose at outlet of filter regulatoe unit. - - +.. - -. ; 4... L_.. traw w ".L.. l ' .2
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o. ..m ~o Ana Titla Pana 10 of 36 k. Remove facepiece as in subsection I.7. 1. Shut off air supply to filter-regulator unit and
- disconnect hose.
NOTE ,Do not perfofm'this step until all persons are through using the filter-regulator unit. Place all equipment in designated place for surveying m. and cleanup. n. The plant service air compressors are equipped with a Control Room annunciated high temperature alarm.. If the Control Room recieves a high temperature alarm, they will announce.over the P.A. system that high temperature conditions exist in the Unit 1 and/or Unit 2 service air compressors. They will also announce that all personnel using in-line air respirators are to remove their respirators and exit the work area ._.k*T-following proper undressing procedures. The Control Room will also notify the Health Physics Foreman who Mill assure that all persons using air line respirators p. have removed their respirators and exited the work area. .p 4. Constant Flow - Air Line Respirator (Hood) Follow Steps I.3.b.,'c., d., a. b. Adjust the regulator pressure according to F.4.b. c. After hood is inflated, place headpiece over head seating lower edge of headpiece securely on shoulde.s.. d. Place inner cape against' body and smooth out folds and wrinkles. Tape inner bib.together s:.t sides. Fold inner cape at shoulders to eliminate the excess e. material extending over shoulder. f. Put en outer protective clothing and smooth out folds and wrinkles of outer cape against outer P.C.'s. 9 Tape outer capes together at sides. Tighten belt over outer cape and connect air line to belt. Adjust hood j assembly, for minimum restriction of head movement. h. Reset pressure regulator as necessary to assure l adequate air flow (Gee F.4.b.). 1 ^ 1 6):UF SET. .e s
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17 aevision ~o M Gcorgia f)ower m Rau Ti+1o I%, n o 11 of 36 5. MSA Air Pack Model 401-pressure deinand, a. Check the pressure gauge in the'.cylinuwe valve to . insure tha t the cylinder is Full (2216 p'si pressure). If there is less pr3ssure, the service life.will be reduced accordingly. b. Put on'the apparat,us using either. of ti.e followin<b wrt hods: (1) Open th'a. 2 id of the case and t[xtend the shoulder straps to their full leng th. Lean forward; grasp the cylinder and backplate firmly, $ith both hands, between the cylinder' clamp and the waist belt. Lift ihe apparatus straight-up and over the head and rest it on ycyr back.n The shoulder straps will fall into place over the shou 2ders. Adjust straps befare straigh tening up. Fasten waist belt snugly. Should'further ad,iustment be s ~- necessary, lean forward and adjust str6ps. 7Use of j chest strap is oldlonal. -7' ~ .A.f ' (d) Extend narrow shoulder straps. Don,the apparatus like a.vint. LeGa forward while the shouldeF ' " -- ~~ straps ar's, beiny adjusted. Fasten waist belt .Tc'; securely and snap; chest strap if desired. m Open the cylinde,r ve(ve 'h3ndwheel fully (at least 3 c. turns) and closo thE Oy-Pe,is (red) ' handwheel on the
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This is necessry as the n'rjssure Demand Requistor is' spring loaded and air will Clow automatically if the outlet is not blocked.
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. f.. k 17 Georg. Power m ia -,c = ~o em Title Paon la of 36 9 Connect mask hose to regula tor. Open Main-Line Valve fully. h. Breathe 1normally as the apparatus automatically satisfies any breathing' requirement. NOTE It is necessary to periodically check the pressure gauge on 'the Pressure Demand Regulator as it continually indicates the pressure in the cylinder. When the needle reaches approximately 540 psi on the pressure gauge, the Audi-Larm Gignal will begin ringing. When the bell starts ringing, or when the pressure reaches 540 psi, it is time to return to fresh, air. g NOTE During normal use the Dy-Pass (red) valve is closed and j is used only if the Pressure Demand Regulator becomes ,0. < inoperative. It provides a continuous flow and shbuld ' --f -- be -opened and the Cy-Pass valve ad,iusted to provide the flow desired. Leave hazardous area immedi+tely since ~..o, life of apparatus is greatly diminished when By-Pass valve is being used. 1. After leaving'the airborne area, do not remove the facepiece until outer pair of gloves is removed. If high contamination conditions exist in.the work-area, then two pair of rubber gloves should be worn to prevent spreading of contamination to the hands. All practical efforts should be made to keep the regulator ~ tank and harness From be coming conta.aine ted. J. Unlock the~ lever on the cylinder valve and close the valve. Do not use excessive force as the talve closes leaktight with little effort. k. Release pressure in high pressure hose by breathing until air is exhausted. NOTE Do NOT use-By-Pass valve to exhaust air pressure. 1.- Remove :faceplece as in subsection I.7. 4 ,. g _ 4 M p uF' SET 6-I.,......
Ereat E. l. Httch Nuclerr Plant e=awat a H NP-8010 PM4QN W ,iSee Title Paga 7 Georgia Power os c... 13 of 36 Rao Titla Pana 6. Donning the facepiece a. Inspect the facepiece to be sure that all paris are in i; nod condition and installed properly. Rubber parts should be pliable and not cracked. See siection N for details. b. Pull out the Facep*idce headband straps so that the ends are at the buckles and grip facepiece between the thumb and fingers. Insert chin well into the lower part at the facepiece and pull the headbands back over the head. To obtain a firm and comfortable fit against the facepiece at all points, adjust headbands as follows: (1) See that straps lie flat against head. (2) Tighten lower.or neck straps. (3) Tighten the side straps (do not touch forehead or front strap). k . - f/ Place both hands on headband pad and push in l (4) f,p ' toward the neck. s "3, - (5) Tighten forehead or front straps a few notches if necessary. (6) Check for proper seal using the field testing procedure in subsection J.2. 7. Removing the facepiece ~ a. After using the respirator remove the outer pair of contaminated gloves. Gend your body forward at the waist until the chest is parallel to the floor. Then remove the facepiece'by grasping the cartridge housing and lifting outward. (For airline respiraters and SCCA's, grasp breathing tube connection at the facepiece). CAUTION Care should be taken when removing respirator to insure that.open areas of the face do not become ~ contaminated from contact with the equipment. AVOID UdOECESSARY JERKY MOTIONS WITH TI-E FACEPIECE AS ANY CO;4TAMINATION MAY BE SHAMEN OFF AND CM TO YOU. If high coniamina1 ion conditions exist in the work ar ea, these two pair or rubbe' gloves should-be worn to;provent the possible spread of contamination. ~-ey;.J' .. J Mh0F SET-5 g 'c ..o ~~
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'~ HNP. 8010 armsiow mo Gee Title Pag'e k 17 Georgia Power m ,m.o 14 of 36 Rou T4 *1 a Pann Place faceplete along with all associdted respiratory b. equipment in a deisgnated location for survey and cleanup. DO r10T place in con tamina ted clothing storage drums. 9
- HARNINf, Respiratory equipment is.a personnel safety device and should not be mistrea ted (i.e.
thrown, kicked, dropped, mutilated). Personnel found abusing this equip nent wil'1 receive disciplinary action. c. Survey yourself for contamination, making a very thorough survey of the face and head. If contamination is found contact Heal th Physics immediately. J. FITTING AND TESTTNG 1. Initial' Fitting and Testing Each person requiring the use of a respirator will be a. individually fitted for the particular facepiece prior .. f./ to being allowed use of the respirator equipment. No person with Facial hair interfering with the respirator sMal area will be fitted and tested. ..pD Any facial abnormalities will be documented on Form 2 b, and will assist in identifying those persons who might have more difficulty in obtaining a good seal with a 4 respirator.' c. A quailtative or quantitative test will be performed for each type of facepiece. Cuantitative tesi results, (if employed) will be documented on the strip chart paper and filed wi th the Form a in the individuals dosimetry file. Cee INP-8033. The qualitative te s t will be performed as follows: (1) The person dans the respirator with an organic cartridge attached. (2) The person checks the Tacepiece seal using the negative; pressure tes t as described in J.2.b. ( 3") The instructor will test the fit during normal breathing by waving a cotton or stent.il b rush filled with isoamyl acelate' gently near the pariphery of the Facepiece. Smoke tubes, when available, may also be used. 'If udor is dett.cted, the wearer mus t re-adjust the f acupiece and the test redone. - -. - _ _ m f_ _._ _ _ f.6MF SET L ~
E.1. Hatch Nuclear Plant axe== ~O i7'wa' H NP-b010 t MVI$10N NO C,%!eTitinPagp Georgia Power an 7 ... O 15 of 3G Ana T4+1o Pana NOTE i When practical, a test chamber will be used in lieu of th9 cotton or stencil brush. Evaporate about 173 milliliters of isoamyl aceta te for each 1000 cubic feet of room Oolume. (Do not use heat for evcsporation).
- (4),The instructor.may'then have the wearer perform the following movements:
(a) deep breathing (b) moving head from side to side (slowly) (c) moving head up and down (slowly) (d) frown (e) talking (e.g., speaking a short passage aloud) (f) normal breathing. .. g. --/.- - - - (5) The instructor will therr re-check the seal with fJ. isoamyl acetate or smoke tube. t (G) If the. tests are acceptable (no leakage) it will
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be documented on Form 2. 2. Field Testing a. Where practical, respirators will be tested in the field using uither amyl acetate or irritent smoke. b. Where it is impractical, a negative pressure test will be performed as follows: (1) Close off the inlet opening of the canister or breathing tube by covering it with the palm of the hand (2) Gently inhale 50 that facepiece collapsus.slightly. (3) Hold breath for 10 seconds. (4) If facepiece remains in slightly collapsed condition and no inward leakage of air'is detected, the tightness of the respirator is - satisfactory. (5) -If unsatikfactory do not use the, respirator and contact Health-Physics.. - --- y 4- : d 4 +* ie ' e, (6 M W SET .s.
E;l.-Hatch Nuclear Plant - = = = -mm HNP. 8010 j' " " " " ~ Soo Titio Page A i Georgia Power al 16 of 36 sa c. Ti+1a Pana H. [@IC AL._,R.JGU1PIPENT All personnel who wear respirators will be evaluated by competent requiring such use. The medical per.sonnel prior to an assignment if the individual is physically able to evaluation.will determine A perform the work and use the respiratory protective equipment. conditions are physician will= determine what health and physical The medical statt,1s, of 'each respirator user will be l pertinent. reviewed annually. L. OTOASSA1S Ahn 9URVIYS 1. Air sampling and contamination surveys A cotr.prehensive air sampling and contamination survey prooram is in effect to identify radioactive hazards to evaluate individual exposures, and to permit proper selection of respiratory protective equipment. Surveys are routine and special basis per the use of performed on a procedures HNP-8013, 3012, 2003, COO 5, SOLO and applicable instrument operating procedures. High-efficiency (greater . ;ST than 99%) filter media are used to measure airborne [, particulate concentrations. Activated cheercoal is used to deterraine radi o-iodine concentrations. 'D 2. Bloassays NOTE Refer to UNP-8021 and 8009-a. Whole body counting - (1) It is the intent to obtain a whole bocy count or urin =1ysis on each G.T'.O..ampicyee who may hate been exposed to' airborne radioactivity a t leas t once each year. (2) Whole body counts will also be made wh'ere suspect internal contamination has occurred. b. LJrinalysis (i) A fission product and tritium analysis may be performed on personnel who may have been exposed to airborne radioactivity. (2) The above analysis will be made, when deemed j-necessary, where suspect interr:al contaaunation has occurred.
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'17 of 36 ew n T4t1n P.m Other l c. throat swabs or washings and breath samples j (1)
- Nasal, will be performed as nccessary on suspect inhalation cases to serve as a qualita tive exposure index for radionuclides.
l d. Follow up analyses-(2) Follow ~up analyses (Whole body counting, urinalysis, nasal throat swabs, breath samples, etc.) should be performed and be frequent enough to evaluate the uptake of radionuclides after an incident. The sample collection should be appropriately timed to permit accurate evaluation of the total intake and the resultant dose.. Refer to HNP-8021 sect. F and HNP-8134 sect. E.4 for details of W.s. Counting. NOTE It is noted that there ars extenuating circpmstances ~d '$ -Y.'----- --._.... which may prevent whole body tounting of all personnel affected by this procedure. Such situations as persons leaving the plant site without proper notification to a'trh the management, whole body counting equipment malfunction at critical counting times and scheduling impossibilities will prevent a 100% whole body counting The frequency oF these events, should not program. diminish the overall effectiveness of the biuassay program however. M. RFSPIRAlM.(AIR REGUIREMiNT All breaihing air supplied by air compre.ssors and bottled 1. air will meet the minimum reijuirements of Grade D air as If preecribed by the Compressed Gas Association.or better. service' air high temperature alarm is received for then air quality can no longer be guaranteed' ~ compressors, due to possible CD concentrations. Sea Ge ttic n I. 3. n. For ' details. taken Samples ofiair from air-supply. sources will be 2. quarte'rly and mailed to an outside laboratory for testing. Oxygen and breathing air are not to be used in the same 3. apparatus. 4. Proper fitting: will'be. used with supplied air equi.pmen t.
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f' 6mo w fine Title Page k 17 Georg. Power c . #*~ ia .m. 18 of 36 ~ Mau,T i +1 o P;ma 6. All air cylinders used in the MCA 401 units will have the on the cylinder. words "Greathing Air" N. ItCPECTIOM.ANO MAINTENANCE All respirators shall be inspected routinely before and after A respirator that is not routinely used but is kept for emergency use shal,1.be i'nspected after each use and al. each use. ready least monthly to insure that it is in satisfactory working condition. All rout ~inely used respirators shall be inspected beFore and af ter -use and a t least monthly and shall have. an inspection-sticker. An inspection s ticker shall be attached to the outside and inside- ~ inspection of each emergency respirator container and a record of 1), Respirator Monthly Inspection kept on Form 3 (Data Package shall Any respirator not meeting inspection acceptance Report. be repaired or replaced. Respirators will be repaired only by personnel designated by a laboratory supervisor. (SCGA Tx Constant Air Flow) 1. Facepiece and breathing tube Inspect the facepiece and bre.athing tube for signs of
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a. .f, inechanical damage, Tears occur most frequently about strap attachments, p# outlet valves and hose. Discard equipment damaged in this manner. Check the protective tape and metal band bindings for b. deterioration. Replace as.necessary. ~ c. Inspect L,4 tab assemblies on the facepiece used for atteching head straps. All buckles should be present and in good, operating condition. Discolored or Check the' lens for looseness'and damage. d. damaged lens should be replaced. Inspect the exhaust valve for proper sealing of the t e. rubber diaphragm. Replace as necessary. i. Check breathing tube connections for deterioration and f. damage and tightness. Repair or replace as necessary. In addition to Step Ultra Filter Respirator-Full facepiece. 1 a. 1, just prior to use: a. Check that the type of cartridge is correct and that the cartridge is coupled to'the respirator securely. that the: Examine the cartridge for'dqmage anf-check b ~. r,,.4, ._l olitt,_ sap t has no t 13een removed. D h 6 e e., en,. M*s4UF SET b .c
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Georgia Power A See Title Pcge [ 19 of 36 gon Titin Pana 3. Pressure Demand Apparatus (Air Pack) In addition to Step 1, perf orm the following: Check for proper operation oF cylinder valve assembly. a. b. Check main pressure gaug,e for proper operation and that air cylinder is full.(2216 1 100 psig). If cylinder pressure is less than 2116 psig, remove air pack from service and recharge. Inspect condition of hose connection and hose to c. ' cylinder valve assembly. If hose is crac.ked replace it. d. Check operation of Main Line (yellow) valve by operating it. Check operation of' low pressure alarm monthly by e. closing cylinder /alve and cracking the Main Line (yellow) valve t, pen. This should let the pressure decay of f so the alarm should sound a t about 540 psi. g ~ ~h -f w Check operation of regulator bypass (red) vk1ve by operating it.
- -r Inspect all belts for signs of fraying.
Inspect around as g. side strap buckles. 4. Constant Flow Air Line Respirator-In addition to Step 1 4 perform the following: Check the operation of all couplings by mating them to a. working couplings. b. Check all hoses for cracks and leaks. Connect the portable air filter regulator to an air c. supply and check operation of the gauge, filter, regulator and inlet and. outlet couplings. Check the filter trap for moisture. Pressure gauge should read 35-40 psig. NOTE Filter media for filters will be changed after each refueling outage for the units used during the outage. 5. MSA 401 SCFjA Inspection Checklist Refer to the checklist while performing the monthly a. inspection. Comply with each item l hted. -See Form i -- - -. - - 7 g -(Figure 1 1.. ~- - $1*MUF SET E
+. E. l. Hatch Nuclear Plant a=== ~o. a m ovat HNP.- 8010 acv5 o" No See Titio Page A 17 g Georgia Power s ..m ~e 20 of 36 909 Titla Pa r!p G. S.C.B.A. Dreathing Air Tanks (Model 401 Air Pack). Each steel tank will be hydros tatically tes ted to 3360 a. psig. on a 5 year frequency. Each aluminum.and fiberglass tank will be b. hydrostatically tested to 3300 psig on a 3-year frequency. Form 4 (Data Package 2) will be used as a master list c. for determining when the testing will be performed. d. ' Testing documents will be filed in the Document Room. 7. S'emi-Annual MSA 401 Regulator Testing. six morrths using Each regulator will be tested every a. the MSA Portable Regulator Tester. b. Once the regulator passes all the tests as described in the MSA Portable Regulator Tester Manual an inspection sticker will be placed on the regulator bearing the g ~ f. ' date it was tested. In the remarks sec-tion of the monthly respirator c. "G, inspection sheet FOGM 3 (Data Package 1) for the note it was particular MSA 401 that is being tested, tested and that it passed or failed its test. ' Regtilator testing for Manifold-filter System (con tinuous 8. flow respirator) Regulators will be tested annually using a calibrated a. 150 psig test gauge or equivalent. Test gauge can be obtained f rom the Tes t Shop. The regulator gauge must read plus or minus 15% of the b. test gauge before it is accep table for use. Regulators acceptable For use will have an inspectic.: c. it ms sticker placed on the regulator bearing the date t'ested. NOTE Only personnel trained and certified by MSA will be approved to repair MSA 401 Regulators. m. e .. 7 3., g__ _ _ __ __ __. _. __. _ _ _ .~ ~ . -~ -- MAlldF SET
E. I. Hatch Nuclear Plant moaan ~a - t~= HNP. 8010 MON NO h GeorgiaPower A .Soe Title Page 7 ..m ~o 21 of 36 naa Ti tla Paca O. Cf.EANING AND RANITT7ING use to Monitor entire equipment as soon as possible af ter 1. determine level of contamination. Pay particular attention If a to filters, - exhaus t valve housing and straps. respirator can't be cleaned below the following limits it chould be taken out of service. Alpha surveys are not required unless alpha contamination is suspected. a. Fixed contamination: Beta-camma-0.2 millicad per hour above background at contact. Alpha-50 d/m/ probe area b. Smearable contamination: No detectable removable activity using a standard swipe technique (disc smear over 100 cm 2- ). ~ J/ /. ' 2. Facemask and breathing tube. ~ f The facepiece and breathing tube assembly of respirators must be cleaned, sanitized, dried, surveyed and inspected
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after each day's use as follows: Add one package of powdered MCA Cleaner-Sanitizer per a. gallon of warm water (about 120 degrees F.). b. Immerse equipment in the solution and scrub gently with a soft brush until clean. Take care to clean the exhalation valve in the facepiece and all olher paris that exhaled a.ir contacts. A dishwasher may be usa;l in lieu of hand cleaning. c. Rinse in plain warm water (about 120 degrees F.) and then air dry. NOTE [ Do not fold head straps in-f ront of face piece for s,t o r a g e. d.- Survey the equipment.for radioactive contamination. The facepiece and breathing tube (s) must h-sve no detectable removable activity using a standard smear survey technique. Fixed contamina tion.shall not ex ceed 0.2 millicad/ hour al contact beta-gamma and 50 dpm/proba area alpha. Alpha surveynare not required unless alpha contamination is suspected. .p g.. m.- l' Wp?uUW SET s ..w
E. l. Hatch Nuc! car Plant acu== ~o l' HNP. 8010 nws.o~~o , ee Ti.tle. Pane S Georgia Power A ..m ~o See Titta Pace 22 of 36 Place routinely used facepieces after inspection in a e. clean plastic bag and store in their assigned storage locationr.. (During periods of high usage i( will be accepiable to delete the clean plastic bag storage requirement). Place respirators assigned fo. emergency use only, after inspecting, in the compartments built for them and return them~to their storage locations. NOTE Respirators should be packed or stored so that the facepiece and exhalation valve will rest in a normal position and function will not be impaired by the elastomer setting in an abnormal position. 3.- btherequipment (harness, regulat.or, air cylinder, hose). a. Remove the used air cylinder from the Pressure Demand Apparatus (Air Pack) and decontaminate by wiping with a wet pad of Cleaner-Sanitizer solution and then with a dry pad. ..d, - _._y _ _...._ _....h. _ Wipe down harness, breathing-bags, regulato'r and hose with wet pads as necessary to reduce the transferable 1 contamination to less than 1000 dpm/100 cm beta gamma and 100 dpm/100 cmA alpha. Alpha surveys are not required unless alpha contamination is suspected. c. Survey equipment after drying to verify contamination levels do.not exceed those'in Step O.3.b. d. Attach a fully charged cylinder to the harness and regulator assembly ~of the Pressure Deuand Apparatus (Air Pack). e. Store equipment in their designated areas. P. REVIEWS __AND RECORD _5 1. A laboratory foreman will routinely review renpiratory practices and procedures to assess the program efrectiveness. 2. Timely assessments-of a particular individual's intake will be madu if and when required and adequate records will'be maintained for summary review and evalua1 ion. 9 s 8e
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~.. i"*vC b.1. Hatch Nuclear Plant =wu.< ~o I H N P-8010 - 8 aevisiou m. Coe Title Page de Georoia Power A 7 o Ona Title PAia 23 of 36 3. If an individual's intake exceeds 40 MPC hrs. in seven consecutive days an evaluation will be made and at-tion taken to ac.sure against recurrence. Records of the occurrence, evaluations and actions taken will be kept in a clear and readily identifiable form suitable for sumnary review and evaluation. Radiation Occurrance Forms (HNP-8005), Personnel Contamination Report (HNP-8009), Radiation Work Permits (HNP-BOOS) in additiou to survey records, bicassay resuPts, etc. make up mos't of these records. t D e N .d - s. j
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^"" t:. l. t1atCn INUCIGar l"lant enocrouac ~o HNP. 8010 Cee Title Page k 17 atmo= ~o Georgia Power na 24 of 36 % Ti+1.- Paqo APPEl%"OI X I RECTTON TITI.E PAGE NO. 1 A Purpose 4 1 B Safety C Reforences 1 D Management Policy" 1 ~ E Regulatory Requiremenis 2 F Description of Respirators 2 G Selection of Respirators for Use 5 H Con *rol Issuance, Proper use, and Return of Respiratory Equ.ipment. 7 I Using ti.e Respirators 9 3 Fitting and Testing 15 .g
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/ K Medical Requirement ,-o L Bioassays and Gurveys 17 p M Respirable Air Requirement 18 N Inspection and Maintenance _ 19 O Cleaning and Sanitizing 22 P Reviews and Records 23 Table: 1. Airborne concentration limits for respirators 26 Forms: 1. Inspect. inns nf 401 SCPA d9 2. Re5piratory Protection Training Form 2A
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~ Respiratory Protection Training Form L2B i.O 3 *. Respirator Monthly Inspection Report 30 4. MSA Respirator (Model 401) SCBA (Tank Hydrostatic Test Master List) .32 i 5. MPC-HR tracking (Yearly) 34 6. Respiratory Issuance-36 4-_ g__ ~_ 0 g t.h M W SET
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^ - u.....usw....uv.ou. HN P-8010 ) misica a.o ISee Title Page g 27 Georgia Power ca ..mo w 25 of 36 'qnn Title r'ana TABLE _1_ AIRPORNF CONCCNTRATION LIMITS FOR RESPIRATOR _3 AIR PLIRIFYING RESPIRATORS "- AIRCCRNE CCNCENTRATION Full facepiece w/ type H Particulate activity less than Ultra Filter cartridge 40 times MPC ATMGSPHERE SUPPLYING RESP.* 1. Air line respirators Full facepiece-constant flow - Particulate, gas and vapor activity less than 1600 times MPC Hood-constant flow - Particulate, gas and vapor-activity less than 1E.00 times MPC when pressure is maintained at manufacturer's maximum rate (See F.4.) ,f. Suit - constant flow - No credit allowed unless suit 4 -- - f,- --- is MSHA/NIOSH approved. See a laboratory supervisor s ,-n - Air line and air purifying respirators can only be used in atmospheres not immediately hazardous to li"s or health. 2. Self-Contained Breathing Apparatus (SCCA) 1 MSA Air Pack Model 401 Pressure - demand Particulates, gas and vapor activity less than 10, GOO times MPC. However, may be used in emergency condi Lions in unknot m - concentrations of airborne acti-vity. Must also. consider external radiation hazards and o ther limi-tations (skin absorption, etc.). e l l g C --~-~~.p-e O9 9 e MaadF - SET a g
E. I. Hatch Nucicar Plant ra== ~o spm HNP. 8010 a*v'Sio" No .Sco Title Page Q ty .1 > 6 Georgia Power ca em ~o 26 of 36 'c3 c a Title Pana FIGURE 1 FORM 1 INSPECTION CF 401 SCCA FORT 1 Fr.us _1 INS"ECMC J C" =01 CC$ A 'tems cf insoe:tien en facepsece 4,J liraathin.J tube. 1. I,su o fs:e:teca is a 401 tras'. wsth spring loadeo exhaust e. valce. b.
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Cracki,: ce ru-tures. Tears areund strap attachmer.ts. Cutlet valve and hoses. d. e. Cete-t--ati.an etal band bir.cs. ss. f. Stuck euraust valve. 7 Cate;ef enheust valve. h. Dete-iteetien. dar age.. tight.es s of breathing tube. s'.
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J. Cre:him? or fetericeation of ;askets between facepiece, hese, re;ulator and hose. Insu e all strass on faceptace.re adjusted fully out. k. a .8 Iter s of inspe: tion on Pressure Ca ar.d A;paratus (Air Pack). '7-2.
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Insu s cyliafar is full. e - 4. Inspect cvlinder f or ohysical damage. 8. Camage and proper operation cf cyllncer valve assemoly.
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c. d. Demege aad eerper cperation cf lod pressure alarm. (5*O PCI) Cate;e to cor ections en h:sa f ram cylinser to regulator. e. F. Cama;e and proper operation c' pressure gaege on terk. Cra!bs t-hese from requialcr to cylinder. g. h. Ceeratien of main line (Yells.). i. 0:e atio of tvress line (R.4). Check air tightness t,y presnure Jrd; (see section 1.5.d.& ..j. e.). 4. Unusuel stunfs in the retalet:e (whistling, chattering, clifwing, or rattling).* 1. Damage and proper operation of the pressure gauge en the regulater. Physscal or rechanical dara;a to the requiator. m. Fraying c6 belts and streps :n harness. n. Insure all belts and straps are adjusted fully out. o. Insu e all buckles will wurk pro;erly. r p. Insure cylinder is in the harness correct. q. l vfP-8010 R17 l ~,. t
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Uiom E. I. Hatch Nuclear Plant eaxta= ~o HN P-8010 "S'"" 17 . l @,he Title Page ,f '.,c Georgia Power s e e 27 of 36 (3 o e ' T ! t l o Pano FIGURE 2 FCGM 2A REOPIRATOR1 PROTECTION TRAINING FCRtj F E _gA ' RE99tRATCRY crOTC;TTOJ TRAf*l!*C ,7s INIT!eM., TRAINING DATE: FW E (last, ftrst, midJte initial) CPC DEPU. BMX;E e S.S. # OR CO. I have received instructions in respiratory protection, and I have I may leave an area when using a respirator at any been advised that time for relief from respirator use in the event of equipment malfunc. tion, physical ce psychological dtstress, procedural or communication failure, significant deterioration of caerating conditions, or any other condition that might require such relief. yj. .o TRAltEE SIGNATURE t eo m)< 6 Fit Test Results: Acceptable Unacceptable Written Test Results: Acceptable Unacceptable The above individual has been trained to use the following respirator systems: 1. C McA Ultra Filter 2. C Cc stant Flow 3. C F1'M 403 Air Pack e DATE: CCPPLE*ED BY W -8010 R17 9 , ; g..... __.. --. ~.. 4e.. e-trap sn l i .z, t
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17 Georm. Powerm a 1 .. No oarc .o O Gnu T i + 1 p ' P em a 28 of 36 FIGURE 2 FOnli 23 ~ RESPIRATORY PROTECTIO!! TIMINING FCGM 2"J . RESPIMATCPV y'OTEC*Irfi T'/.!'itP:C EXE.T O C'1 TRAlt.tC CATE: f%'E (last, first, maddle anttaal) GPC CEPT. 6Gd a S.S. # CR Co. - I have received instructions in respiratory protection, and I have be+n aJsised that i may leave ar. area when using a respiratse at any ti's for relief from respiratce use in the event of equipment malfunc-tien. pbesical or peychological distress, procedural or cc:rinunication failure, sig9&ficant deterioration of operating conditsens, or any ot'er cen14 tion that vr.ig%t require such relief. TRAlfEE 514%%1UitE e , J.
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E. I. Hatch Nuclear Plant " ama' axima ~o I H N P-8010 s ""5SN S See. Tit 1e Page j Georgia Power d 7 ..m ~o 4 r. Titie Peano P_3 Of 36 PROCE X,EE DATA PA".hACE DOCLT.ITFC: RP-C D-1 SGIAL. PJ0: R17-PFL NO: ti/A RTYPE:_QL5.14 . XREr N/A TOTAL QCETS: 2 g FREQtE'JCY: !Tdn th' y 'J. . y s CCMP'_ETED BY: s ..'.-s ' *I) 6 CATE C TLCTED: ? H1'M :i'.'IE'E THIE DATA PAC.<ACC FOR CC'PLE*'LNEOS APO AC# * 'iT ACCO'TA?.tE CRITERIA IN ACCCRCAt.CE WITH HJ2-d30. ACCEPTACLE LP.M:CEPTABLE REVIEWED BY: DATE REVIE'4D: RE!*APMT: Pa;w 1 of 2 HP-8010 RIT FIGURE 3 .__.,..y. Page 1 o f i2 If3Jiuo' SET . 1 s. .n. l 1
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Meat E.1. Httch Nuclear Picnt ma=== HNP.8108 8 @( "v'S" Im GeorgiaPower A See Titic Pcgo 1 of 9 Eco Title Paae POCHET D_OSIMETER USE AND PERFORMANCf TEST A. PURPOSE To ensure that the instrument is leak tested and response tested properly and to provide operation guides for the user. B. SAFETY Observe radiation protection procedures. C. REFFRENCE ANSI N13.5-1972 D. TEST EQUIPMENT 1. Dosimeter Calibration Board 2.' Gamma Source _q
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Dosimeter Charger oy, 4. Timer E. D_ESCRIPTION OF INSTRUMENT The pocket dosimeter is a pencil shaped ionization chamber that measures gamma radiation and gives an instant read-out in millicoentgens or roentgens. The dosimeter is basically a The capacitor is capacitor with a single movable electrode. charged to a predetermined voltage which results in a given separation of the two electrodes. When exposed to X or gamma radiation, or both, ionization occurs in the chamber surrounding the electrodes and causes a decrease in the charge on th? This results in a change of position or deflection electrodes. of the movable electrode. The magnitude of the deflection is a function of the radiation exposure and is observable through a self-contained optical system. F. OPERATION OF INSTRUMEbfr NOTE Handle dosimeters with care. These instruments are delicate and expensive. 1. Check that the dosimeter is not visibly damaged. .......,...g I y ;, f,630 F SET
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== =m ~o f HNP-8108 See Title Page nva.o~ ~o Georgia Power A 6 ... e nho Ti+1e PaQ L 2 of 9 2. Clean optical eyepiece of dosimeter with lens tissue paper as often as required. NOTE Dosimeters will be routinely checked for radioactive contamination by the Health Physics s taFF. However, if the user suspects contamination of his dosimeter, he should notify the Health Physics Staff immediately. A contaminated dosimeter should not be used. 3. Zeroing of dosimeter a. Place dosimeter over charge connector on dossmeter charger and depress dosimeter. b. Look in dosimeter eyepiece and adjust hairline to l zero. Remove the dosimeter slowly. I Check its zero by reading the scale with the dosimeter c. in a vertical or near vertical position. g .,., j NOTE t The initial (zero) reading and final .,.-3 reading of the dosimeter must be made J with the dosimeter in approximately the same geometrical position, i.e., read vertically or near vertical. 4. Reading of dosimeter for dose. Read the dosimettr as in step 3.c. NOTE If the reading is 75% of the fullscale deflection or greater the dose must be logged and the dosimeter re-zerced. Notify the Health Physics Staff. t!OIE If at anytime the dosimeter is dropped or erratic rea' dings are noted by the user, the Health Physics staff should be notified in order that another dosimeter may be issued if deemed necessary. G. EXPOSURE OF INSTRtFENT 1. Charge-leakage test (saUF SET b
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Georgia Power i .. - ~. _Sa= T4+1= P=ga 3 of 9 Adjust the hairline on the dosimeter using the a. dosimeter charger for a value of "O". Record value, f date and time and dosimeter serial number on Data Package 1 (Data Sheet 1). b. Store dosimeter in a radiation free area (less than 0.02 mR/hr) for a period of about 48 hours. l c. Read the dosimeter at end of storage period. d. Enter the reading, date and time of reading on Data Package 1 (Data Sheet 1). e. Determine the average rate of charge-leakage per 24 l hours and enter the value on the data sheet. f. If the average charge-leakage exceeds 2% of the fu11 scale reading per 24 hours, tag the dosimeter as having failed leak rate test, and mark the tag with the date of test and initials of tester, .. ev g. REPEAT STEPS a - f a second time for failed l J.f ' dosimeters. If the dosimeter does not meet the 2% 1 cciteria the second time, it is to be disposed of or repaired. l .=3, 2. Gamma Source Exposure a. Record dosimeter serial number on Data Package 2 (Data Sheet 2). b. Post area where exposure is going to take place in accordance with HNP-8003. c. Adjust the hairline as in step G.1.a and log the reading in the Reading Before Exposure column. d. Place the dosimeter (s) in the Dosimeter Exposu:e Board. ELG5 This applies to low range dosimeters only, high range dosimeters are normally calibrated using the Gamma Source stored in the well in the instrument calibration room. This utilizes higher dose rates for calibration without higher exposure to pursenel. e. Determine the time required for an exposure of EO% the j fu11 scale reading. Record in the appropriate column on Data Package 2 (Data Sheet 2). t.1*M U F SET
E. I. Hatch NuCicar Plant ~ximaw =n >"l HNP 8108 navisia w See Title Page g 6 Georgia Power cA 4 op g Ca= T4 tin Paga-. f. Place a gamma source in the center of the board and start the timer. g. Read the dosimeter (s) and record in the Reading After Exposure column. i. Determine the net exposure. ~ J. Determine the efficiency by dividing the net exposure by the calculated exposure. k. The dosimeter indication should be within -10%, +10% of l the calculated exposure. If it is not, it is probably defective. Perform another complete exposure on the dosimeter. 1. If the dosimeter does not meet the -10%, +10% criteria l the second time, place the dosimeter in a " Fail Cal" box for return to a vendor or disposal. e_ $ e j. 'I Dosimeters are Icak-tested and calibrated twice annually, usually once every six ~ 'T, months. H. CARE AND MAINTENANCE OF INSTRLV.ENT 1. . Handle dosimeter with care. These instruments are delicate and expensive. 2. Clean optical eyepiece of dosimeter with tissue paper as often as required. Also visually inspect its physical condition. 3. Check dosimeters for both loose and fixed contamination according to the following schedule: a. Dosimeters in use: Check as often as dictated by the possibility of their becoming contaminated. b. General dosimeters in dispensers: Check on a routine weekly basis. c. All dosimeters: Check just prior to their charge-leakage test and calibration. d. Immediately replace any personnel or general dosineter found to be contaminated with an equivalent dosimeter from stock. . - - :--. q-; D f.t>Aus' SET '? v
E. I. Hatch Nucicar Plant a=== ~o -.ym.6 HNP-8108 s 4 '=om .See Titio Paga Georgia Power A 5 of 9 no. T1+1a pag. Decontaminate and clean dosimeters as necessary by e. removing the clip and washing both the barrel and clip with soap and water. Observe applicable radiological safety practices and rules. Exercise care, particularity with the charging end of the dosimeter. f. Immediately replace dosimeters when found defective. ..s. .n e_,_. 1 .*P l ~ e~ ~ 7g+ - - f.1'sM A' SET ^
E. I. Hatch Nucitar Plant ~xt= = X*f e at HNP-8108 Georgia Power A Jee Titie Paga ..mo 6 Of 9 g Ti+1m P a ri n ' PROCEDUIE DATA PACHAGE DCCUMENT NO: ma5-8108-t SERIAL NO: ROG-MPL NO:__ RTYPE: C15.14 XREF: TOTAk. SIEETS: 2 FREQUENCY As Recuired .. ~f/ --.f,'~..-. COMPLETED BY: rs. t DATE COMPLETED: ".~.1% I HAVE REVIEWED THIS DATA PACHACE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERIA IN ACCCROAtCE WITH HrP-830. tFJACCEPTABLE ACCEPTA01.E REVIEWED BY: DATE REVIEWED: REMARKS: 'Page 1 of 2 IN8-8108 R06 -.-----..7,..g..__ FIGLHE _1 - Page 1 of 2 O f.1'sAU F SET ',.o
o ~ [J.ao= E. I. Hatch Nuclear Plant aoct = ~o 3 HNP-8108 a.visiom mo See Title Page 6~ Georgia Power s o... 7 o+ 9 n. r m. n,c. pATA PACHACE _1 (Odta Chest 1) DOSINETER LEAKhCC CHECK ~ i TESTED BY r. Fu.1. SCALE READING ^ i 2% F.S. = CODE FIRST SECOND CHARGE PAS N l. SERIN. I NUMDER READING READING LEAHACE TEST (1) (2) (2)-(1) CR ( )* ( )* ( )*' NO ~ n .. :M. .q. s
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E.1. Hatch Nuclear Plant mocrcum ~o t HNP. 310g-e a vis.o~ ~o See Titio Pegs Georgia Power A S '., 'cm Sce 74+1= Pn ga g op g PROCEDURC DATA PACHACE DOCUMENT NO: HNP-8109-2 SERIAL NO: R06-IPL NO: RTYPE: C15.14 XREF: TOTAL SKITS: 2 '~ FREQUENCY: As Recuiraft .v/ YJ-9 COMPLETED BY: 5 ~ ~~ OATE CCMPLETED:
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^;~aa' E. l. Hatch Nuclear Plant .*a ouno.o HNP-8108 ainsio ..o See Titie Page Georgia Power eb 6 ..e c, 9 op 9 Gnp Titin Page D^T.Q CAClieGE G (Da t.4 Shwet 2) OrnierTqa exposung icc_ CM.InstATCO OY CATE COLitCE COCE Fli.L. SCALE RCA0tt4 fict.')!r!C fiF/O t ra TOTAL. PASCCD CCFCE AFTER tCT T !:'E C/LCt.1ATEQ EFF. TEST RCPRHS CCRJrL Cyromt:" CXPO50ftC EP.POSURE EXPOGED CXPCSLnE (3)y(4) /CR to F A r-3~.ft (1) (2) (3)*(2)-(t) (4) 1s t >= c ( >= "~ ..'Y f. .. :1.. ,D s l
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3 GEORGIA POWEN COMPANY ~. [*' HATCH NUCLEAD PLANT PROCEDURE __ -Wh o l e. G...o..d v C o..un t a r Sve, toms PROCEDURE TITLE HNP-81~W PROCEDURE NUMBER Lab ~ ~ RESPO55. I6. LE GECTION ~ ~~~ SAFETY'RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER y .f, h_. M g,, t/ g. 3 General Revision ce W-_ _tYO_k.(.$:bb4Y../ _.b . "d. }. a' f aae_s 3-L.7.L 4..L,-U.-. 1 . t ,.e p l 1 1 ) HNP-9
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ra== E. l. Hatch Nucicar Plant aaoamas ~o e HNP.8134 See Title Pa(}e nevso= ~o g '. e Georgia Power AA ~m ~o See Ti tle Page 1 of 14 WHQif OODY COUNTER SY!',TEMS A. PURPO!E - To provide instructions-for the operation and calibration of the Whole P,ody Counters (W.B.C.). B. . RriFERENCES Operating and Service Manual: 1. Ortec, Preamplifier, Model 113. 2. Ortec, Amplifier, Model 485. 3. Bioassay Program HNP-8021. 4. Nuclear Data Model GG Multichannel Analyzer. 9. Ortec Hi Voltage Power Supply Model 456.- .f/ If $..... 6. Nuc. lear Data A.D.C., Model 575. l { t 7. Ortec Hi Voltage Fanout, Model P1. ., n / 8. Ortec Modular Systems Bins, Model 401A. 9. Ortec Model 401A Din Power Supply. 10. Thallium drifted Na(I) crystal detector 5" X 4" (Torso). l l 11. Thallium deifted Ma(I) crystal' detector 4" X 4" (Lungs). l 12., Thallium drifted Na(I) crystal detector 1.5" X 2" (Thyroid). l 13. Hewlett-Packard 98450 calculator. 14. Hewlett-Packard 9BSDM Flexible disk drive. 15. Applied Physical Technology Geries GOOO[W.D.C. Mechanical Operation, Installation and Maintenance Manual. 16. Applied' Physical Technology W.B.C. Data Analysis Package Program Manual. 17. A.N.S.I.'N343-1979 American National ~Standand For Internal -Dosimeiry For Mixed Fission And Activiation Products. ?. 4 ...---.-~--.3-~~-- - ~ ~ ~ ~- 95 m. -w a 4 dsMs' SET. _ _ _. _ _ _ _ _ _ _ _ = _ _. - - - -
E.1. Hatch Nuclear Plant
==== ~o 7am HNP 8134 4 u m o.~o See Titie Page 4 Georgia Power cA ~ ~o . c - 2 of 14 Sco - Ti t155 Pane C.. SGTD' t 1. Observe Radiation Protection Procedures. ~ 2. Refer to Chemical Safety Manual. D. STANDARDB The W.O.C. 's a're checl<ed daily for energy calibration, when in operation. .The W.G.C.'s use 3 Eu-152 sources. They are checked l Some annually for efficiency using a variety of mixed s tandards. of the. isotopes normally used include Na-22, Y-SS, Cs-137, Sn-113, I-131, Cs-134, Co-53, 2n-65, Co-C.0, Mn-54, Fe-59 and Cr-51.- Consult Lab Foreman to decide which to use. E. WHOLE BCDY COUNTER 1. Description of Instrument. The Whole Body Counter (W.B.C.) systems consists of equipment listed in C., References. The 3 Na(I) Detectors 4 .;.[ are connected via high voltage coaxial cable to -the high -.v._, . v.oltage fanout. High voltage fanout is fed dire'ctly from the high voltage power supply, model 456. Signal is provided to the amplifier input via coaxial cable from the preamplifiers. The amplifier output is connected to the ..y
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A.D.C. via coaxial cable and then to the Multichannel l Analyzer Exit 1 over multiconducter cable and then from ihe multichannel snalyzer RS-232 interface output to the Hewleti-Pacl<ard 98458 Calculatoi'. The amplifiers, high voltage power supply, and high voltage fanout are mounted in-l a NIM-BIN chassis. 2. Description of Controls. The controls are listed and described in the'operai.ing manuals for the respective equipment in'the sections noted. a. Na(I) Detectors - No controls. b. Preamplifier - See section 2 oF reverence'D.1, Ortec l Proamplifier Model 113. High Voltage Power Supply - See sections 1 and 2 of referentes 8.5, Ortec High Voltage Power. Supply Model l .c. . 456. g d. Amplifier - See sections 2'and 4 of reference G.2, ] Ortec Amplifier Model 485. N 1 0 ~~. ; n. -. S
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W= E. l.' Hatch Nuclear Plant mx.== ~o HNP 8134 mv s.o= ~o lGoe Title Page k 4 5 '. Georgia Power i .. o.. 3 of 14 See Ti tle Page High Vol tage Fanout - Used to supply each detector with e. a constant voltage (1000 volts). F.- Din Power Supply - See section 2 and 4 of reference l B.9, Ortec Cin Power Gupply Model 401 A. Multichannel Analyzer .See section 4 of references g. ,D.4,. Nuclear Data Multichannel Analyzer Model ND66. I APT Whole Body Counter Chair - See section 3 of h. reference B.15, Applied Physic.a1 Technology, Inc. j Mechanical Operation, Installation, and Maintenance Manual Model WCC-OOOO. ' i'. Modular System Bins - No controls. j. 98458 Calculator - Cee Chapters 1 and 2 of Ref rence B.13, Hewlett-Packard 98450 cal cula to r. 3.. Operation of Instrument . f/ MGTE .;f. f. These are standard switch positions. Switch positions may t
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vary. Standard Switch Positions for Operation. a. (1) Verify that power cords-from all equipment are connected to a grounded 115 voit line receptacle. (2) Verify settings on Thyroid Amplifier are as follows: . (a) Coarse Gain 1(nob: 4.0 (b) Fine Gain 1(nob: G.O (c) Positive Negative Toggle Switch:- Nega tive (d) Unipolar - Olpolar Toggle Switch: Bipolar (3) Verify settings on Lung Amplifier are as follows: (a) Coarse Gain Mnob: 8.0 l (b) Fine Gain Knob: 5.0 3 (c) Positive - Negative Toggle Switch: Negative (d) -Unipolar - Gipolar Toggle Switch: Bipolar i...~.~. 3 ;....... I- + - M's.nUW SET ,f l ,j . ~.
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f HNP 8134 ne m io o See Tiile Page i/bm Georgia Power b Gee Ti-t t o Pane 4 of 14 l (4) Verify settings on Torso Amplifier are as follows: (a) Coarse Gain 1(nob: 8.O (b) Fine Gain Knob: 5.5 .( c ) Positive - Nega tive Toggle Switch: Negative (d) Unipolar - Olpolar Toggle Switch: Bipolar (5) Verify settings on Torso, Lungs and Thyroid Preamp 11Fiers are as follows: (a) Input Cap. Knob for Torso: 100 (b) Input Cap. Knob for Lungs: 100 (c) Input Cdp. Knob for Thyroid: 100 (6) Verify settings on High Voltage Power Supply are as follows: .4 'd. (a) Power - Off Switch: Power (b) Voltage Output Switches:
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J 1. Six position switch: 1000 2. Five position switch: O 3. Ten-turn potentionmeler: 1. (c) Polarity Switch (rear panol): Positive -(d) Control Switch (rear panel): Internal (7) Verify settings on Multichannel Analyzer are as follows: (a) Power On-OFF Switch: On (8) Verify 90450 calculator and 9885H Flexible disk drive are operable. (9) Verify On-Off Toggle Switch on Nim-Bin is on. (10) Verify settings on'ND575 AOCs are as follows: t (a) Conv' Gain - 256.-- -(b) Coin-Anti-set to GFf 1 Mp M W SET L-
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=== ~o HNP.8134 I l See Title Page um.o= =o '1 GeogiaPower d ~ See Titla Page 5 of 14 (c) Acq-Strb-set to Acq 4 b. Power Up (Ortec High Voltage Power Supply Model 456) k1) Check to see that power switch is in the Off Position. i (2). Plug the AC power cord into the appropriate receptacle. (3) Set polarity switch on rear panel to positive. (4) Verify high voltage cable is connected from the output on the.456 to the input of the High Voltage Fanout. (5) Set the Front, panel selector switches and 3 ~ potentiometer as.noted_in-E.3.a.(G).(b). (6)- Turn on the power with the toggle switch on'the front panel. Instrwnents are now ready for use. ~l;g f. c. Chair Counter Operation s (1) Verify high voltage is' energized and adjusted to ,e the setting as stated in E.3.a.(6).(b). (2) Note that power (ac) is applied.to.the NIM BIN, the multichannel analyzer and the calculator. s (3) For calibration purposes and for normal counting of people the thyroid-detector is normally positioned vertically at marker 21. The horizontal position should be as-close to the individual or source as possible. :If this position is not reasonable, adjust vertically and horizontally so.that the detector is positioned just under the individuals chin. (4) The chair has 2 motor driven controls to raise tne seat vertically and move.the chair horizontally. The vertical ~ adjustment lis normally at mariter 14 - f or calibration and. counting, - unless the subj ecu lungs do not appear lined up with.the, lung ~ detector (located on the.back_ rest _of the_ chair). ~,.. t .... 3.,,; ~ a M*sMF : SET 3 .,~ - ~ ~.
.n...___ = =. _ y &at E.1. Hatch Nuclear Plant eaccioui 6 o j' HNP 8134 See Title Page acriuo ~o d. Georgia Power d Sep Title Page 6 of 14 (5) The horizontal control should be in the normal position so the subject can have control over the forward and reverse motion of tha chair by utilizing the permissive lever located beneath the subjects right hand. The forward position is normally at marker 3 but adjustments should be made if necessary. (6) 'The marker positions should be entered into the computer program when they are called for. i {' d. Acquiring Spectrum: (1) Select any one OF the four memory segments by pressing the ADC pushbutton and obtain one of four memory segments. Press the ERAS button and INIT button to clear spectrum for each ADC segicent of any stored data. Repeat the above process to clear the other two ADC's. (2) Type in AU-1 and press RETURN to acquire a .d spectrum. . j.
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Analyzing Spectrum ~~~ ~ I ~ 3i - (1) Using the 98458 calculator type in LOAD "BCGRAP: 4 F8" and RUN. Input data as required by the display statements. See program document description for details if needed. (2) After acquiring the spectrum, input in-to the computer the ADC number and group (ie(1,1)(1,2)(1,3) or (1,4) and p.uss (.ontinue and 2 the 9965 will read the spectrum from the MCA. The 98450 Thermal Printer will provide a hard copy of the results From the spectrum. 4. Interpreiation of Results NOTE Refer to ANSI M343-1978 for additional details. The spectrum acquired by the W.C.C. is prin ted oat by the 99450 Thermal Printer. Both the Torso and~ Lung Deluctors identify (11) eleven isotopes of interest. The' isotopes are Ru-lO3. Da-140, Ru-LOC, Cs-137, Ir-95, Cs-134, Co-SS,.Mn-54, Fe-59, 2n-65 and Co-GO. These i so topes ar a - o i-.. maj o r interest because offtheir long half-life (s) and abundance. 9 e.a.w.
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i: E.1. Hatch Nuclear Plant -o= aw a = = ~o-i HNP 8134 Geo Tit 1e Paq'a mm.on ~o Georgia Power A ^ 1/ .m mo See Title Pace 7 of 14 i When the analysis is complete the technician performing the Wholo Body Count (W.D.C.) will review the printour for any isotopes or unknowns which may have been identifled or Flagged. If any were identified the cause will be investigated. Things to look for might in c l ude ;. (1) post.ible externM contamination on the persons clothes or on their skin To confirm this, the person needs to shower and get another count in a,dispdssble paper suit or other non-contaminated clo thing. (2) Con tamination on the Whole Dody Counter itself. To confirm this do a WGC on the empty chair. If an unknown was flagged the technician may run the "BCRAP" program which allows the technician to identify and quantify unknown peaks. 3 Once it has been determined that the contamination was not external or contamination on the Whole Gody Counter itself, the contamination should be considered internal and based on the % derived organ burden (% D.O.B.) the following action should be taken. If % D.O.B. is greater than 10% the results should be stored on th'e computer and the individual should be r e c o u n t e d ~t'o -~ determine his equivalent 50 year dose in mrem. The ~ $, individual should return within two weeks for a follow up count and every 2 weeks thereafter until, (1) the % D.O.B. decreases to less than 5% D.O.G. or, (2) the ef fective half life has been established. AFier ibis the yearl)r program can.be reestablished. In addition, the W.G.C. printout (s) should be reviewed for accuracy and errors and a bioassay program should be established (i.e. collection of urine samples) as per HNP-8021. Tha Lab Foreman or Supervisor shell be consurted to determine'whether work restrictions (i.e., individual should not be allowed in R.W.P. areas) er referrals for therapeutic treatment are required (i.e. greater than 100% D.O.B.) Refer to HNP-SO21 Section F for work restrictions. [ .He should also determine the cause of the contamination (i.e. Individual may need additional training, respirator / protection program may need revising, air' sampling program may need revising, etc.) and take corrective action _if necessary. NOTE If tha % 0.0.P. is greater than 10% the individual should be - immedia t ely surveyed thoroughly f or ex teriial t:on tamination. g E.pt=ee e emewee
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==== ~o [f o= HNP 8134 cusio= ~o ,Soe Ti tie Pag' e i< L Georgia Power A .m ~o 8 of 14 See Titita Pa ct e r If tha individual was externally contaminated then another who l s. body count should be performsd. If the second result is demonsirably less than the first, thereby indicating tha t external contemination may have been a conicibutor. Further showarino and recounting should continue until two consecutive results indicate no significant change. If the results are still greater than 10% then the deposition must be considered to be partly internal and an indirec t bicassay should be foll owed immedia tely. If individuo1 is terminating or leaving Plant Hatch a Lab ioreman or Supervisor should discuss follow up steps with the individual before he leaves. If %D.O.D. is greater than 1% but less than 10% D.O.B. the c'esults.should be stored on the computer and the individual should be recounted to determine his 50 year dose in mrem. The individual should return within 2 wee'n. for a Follow up count and every 2 weeks'ihereafter until the % D.O.G. is less than 5% D.O.B. and the effective half lite has been established or as directed otherwise by the Department Superintendent or manager. After this the yearly program j can be reestablished. .s, V. In addition, the W.O.C. printout (s) should be reviewed for z accuracy and errors. The Lab Foreman or Supervisor should --o - P determine if (1) urine samples are necessary, (2) work restrictions are necessary, and (3) retraining of individual ~ is necessary. Refer to HNP-SOa1 Section F for work restrictions. If % D.O.G. is less than 1% D.O.D., the results should be stored on the computer. The cause for the internal contamination should be determined and corrective actions iaken, if necessary, and the individual should be maoe aware of the contamination. Consult Lab Foreman or Suvervisor to see if-other than yearly W.D.C. 's should be done. Some low level Cs-137 contamination could be caut.ed by consumption of wild game such as deer, squirrel, quail, eie, thac consumed Cs-137 from the fallout of atom.bu.L blasts in previous years. Normally, the com;' uter printouts are stured in the individual's dosimetry file. 5. Daily Calibration Verify that detectors and controls are operating as per a. section.3., Operation of Instruments. 4, e- "' ' * ^
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t- ,~,3 E. I. Hatch Nuclear Plant ~oa= a ma= HNP.8134 8 avmo o 2,.eeTitlePage Georgia Power ch G 9 of 14 Gee Ti tle Page Remove the chair cushions and position the bottom half b. of the Phanto;a in the chair. Center one of the Eu-152 Position calibration sources on the thyruid detector. the other two Eu-152 sources on top of.the Phantom ceniered in front of the Torso and Lung Detectors respectively. Then position the APT WBC Chair Model 6000 Front-to-back at 3,. seat height at 12 and thyroid detector at 20. Then acquire spectrum as per section 3.d.(1) and (2) with a count t,ime of 300 secont's. FB" Using the 98450 calculator type in LOAD "GCECAL: c. and RUN. Input data as required by the display statements. The purpose of this program is to provide a means by which the energy response of the W.B.C. After the 6000 may be calibrated for each detector. Five well defined spectri.rn has been acquired including gamma peaks per detector energies being 344 Kev,-77') Kev, 965 Hev, 1100' Kev, and 1403 Kev the calculator calculates the approximate location of the peaks and the technician is given the chance to currect the peak's centroids by computer entry. These centroids ,g are used as the data points in a linear regression
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- - ' - ~ - - _.. _.. analysis to determine the energy coefficients (i.e. energy offset (Rev) and energy gain (Kev / channel). The Technician is given a chance to store these energy coefficients For daily use. The print out is stored as the " Daily Energy Calibration Program" of this procedure in Documentation. 6. Annual Calibration NOTE Normally the WCCs will be calibrated with four isotopes ; Ce-130, Y -80, Sn-113 and Cs-137. Consulc the Lab Foreman as to any clianges in the above. Refer to Reference No. 1G for directions to the proper operaLion of the computer programs. Verify that detectors and control are ope: rating as per-a. section 3., Operation of Instrument. bsingthe98450calculatortypeinload"BCEDAT: FB" b. The and RUN. Input data as required by the display. the purpose of this program is to store data for calibration s tandards to be used by the standisrd calibration program. Data input will consist of Isotope Name, Energy, Assay Date, Dis /sec., Gemme. Fraction and Half-Life for each sour,ce used in the calibration.- ?he% OE
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bao= E.1. Hatch Nuclear Plant mu-< ~o HNP.8134 accono ,.' Sc o Title Page .. # 0,. GeorgiaPower d i ~. 10 of 14 Goo Titta Pana c. Remove the chair cushions and load the lower torso of the phantom with three one liter bottles or calibration standard. Get the upper torso part of the phantom on "the lower part. Load the phantum with two one liter ' bottles of calibra tion standard, insert tops onto the 'phantnm. Insurt the thyr oid phan tom and load wi th one 15 ml vial of calibration standard. Move chair into standard calibratrofi posiLion. Ac' quire a 300 second spectrum for all detectors. NOTE For all counting on the WSC -COCO chair, the front to back should be set at 3, the seat height at 14 and thyroid detector at 21. Using the 93450 caiculator type in LOAC "DCSTND:F8" and d. RUN. Input data as required by the display statement. The purpose of this program is to compare the total observed counts produced by a calibration sinndard with ,.. v/ the known amount of the particular isotope used to
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generate the spectrum which allows the determination.of...._... e the efficiency of the system for detection of the
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NOTE (The icwer torso and thyroid are counted in conjuncilon and a seprate count is done for the lung detector without the source being placed in the Phantom Torso and Thyroid, perform section b.c for eac.h). The sources used are from section D Standards. As a result both the efficiency and resolution are stored for each isotape for each detector. Af ter com;)1eting step c., then type in LOAD "BCEFF:F8" e. and RUN. Input data as required by display statements. The purpose of this program is to calculate the efficiency results From the efficiency s.tored in step (d) For each detector (i.e. efficiency as a function of energy). These efficiency parame tecs are stored for each detector _for use by the "BCGRAP" program. F. After completion of step e., then type in LDAD "GCREG FC" and RUN. Inrui data as required by display statements. The purpose of this program is to calculate the resolution results from the resciution stored in stei, d. F o r ea ch d e t e cto r *LA. e. FWHM (KEiV) as a function of unergy (l(EV ) ).* The resolution parameturs- . gs.w de d itored-f or-ea ch-dote cto r--fo r-use-by -the -"ECGRAP"... _._ g - - - = progera. L M*>Jsu 8'.. SET 0 L a ~%.s
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4 Georgia Power c.s om 11 of 14 So Title Page 9 Th s> calibration data will be a computer printout titled (Daily Energy Calibration Program) and sLored in documentation after the Lab Foreman okays its release to documentation. 7. Source Check checked on a The Ttreso and Lung deter tors will be source routine basis.. The activity detected by the detectors will .be comp; ired with actual activity. The rotation and calibration of standards will be maintained by the Dosimetry Staff. The standard calibration sources are the isotopes listed in section D., Standards. 8.* G'uarterly Crosscheck Analysis On a quarterly basis, a vendor will ship us an unknown a. sample to be loaded and counted in our whole body phantom. b. The phantom will be counted, with sources loaded, in %,j the routine fashion (see section E.3, Opera. tion of /- Instrument). s Upon completion of measurement of these unmarked c.
- g, the plant personnel will repor t by Figure 1
- sources, (Crosscheck Report) the results for the source values to the vendor.
d. The sources will also be returned to the vendor upon completion of the measurements. The vendor will compare'the reported values to the e. actual source values to detarmine if the reported values are in agreement with the actual values. f. Th 52 basis for this agreement-will be the NRC's " Criteria for Comparing Analytical Measurements", Figure 2. g. AFter the evaluation of the plan t report, the_ vendor will write a letter report to the plant certifying -t ne a,greement or non-agreement with the known source values. This letter from -the vendor will serve as_ evidence of h. in calibration and procedure verification and stored Documentation as the "Crosscheck Report". i. This procedure will be' repeated each. time that a verification is required. __.._...94..._... c Ib. HIF SET- ^O -S. 3 . i. s-.... or r-e-.
E.1. Hatch Nuclear Plant ~^***v- ~=== ~o l HNP 3134 See Tiile Pag'e uno= ~o 4 3 $m Georgia Power n Snp Title Paqn 12 of 14 G. MEGUENCY OF_,tJMOLE BODY CCt NrG All ' personnel assigned to Plant 1-la tch who bio -assay areas may enter. should have a whole body count as soon as practscable followinq assignment (before entering the area). This will be the baseline count. A final count should be parformed prior to termination or transt er t rom Plant Hatch. 'All personnel snould have additiona} Whole Pody Counts on a yearly basis. However, if in te rnal contamination is suspected, more frequent Whole Body Counting should be 'done as recommended by a Lab Foreman or Supervisor. All nonfacility personnel (i.e. not assigned to. Plant Hatch) including visitors and contract personnel who raay enter bio-assay l areas (i.e. R.W.C.U. pump rooms, Radwaste drum lines, Airborne Areas, etc.) should have a preliminary count (before entering the area) and a final count (after leaving the area for the last time) unless otherwise directed by a Lab Foreman or Supervisor. Any visitors or contract personnel not entering bio-assay areas do not need a Whole Body Count. -fY e ~ j, ?! t
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E. l. Hatch Nuclear Plant . ~"em = < =~ ~o HNP 8134 See Title P. age ac us,o* ~o Georgia Power b ..e.. ru p Titie Pa<ia 13 of 14 FIGURE 1 CPCSSCI 'ECI( REPORT SOUPCES UCEO; i ) C p C.0 ( )Cs,137 ( )Other Sr1UPCE LADEL: W.B.C. LOCATION: O 'rotected Area G uilding 10 PEGULTS: Lungs and GI uci Thyroid uci .]__. I ". 3, CONPARISON: ( ) Agreement ( )Non-Agreement REMARKS: CCb'PLETED BY DATE 3..g_.- f:1'sauF SET ~ .u
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- PAR 7NG ANALYTTCAL M'I/ClJJEMENTS This attachment provides criteria For. comparing results of capability tests and verification measurements.
The criteria are based on an empi r i cal relationship.which combines prior experience and the accuracy needs oT this program. In these criteria, the judgment limits are variable in relation to i ts the compar,ison of the NRC Reference Laboratory's value to associated uncertainty. As the ratio, referred to in this program as " R r: sol ut i on" increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decreases. LICENSEE VALUE / ~> ' R AT I O = - - - - - - - - - - - - - - - - -- 'I - NRC REFERENCE VALUE s POSSIBLE POSSIBLE
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HESOLUTICJ AGREEMENT AGREEMENT A AGREEMENT R, 3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.6G O.'5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.00 - 1.25 0.75 - 1.25 0.6 - 1,66 200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 "A" criteria are applied to the following analyses: Gamma Spectrometry where principal gamma energy used for* identification is greater than 250 Hev. Tritium analyses of liquid samples. "O" criteria ar'e app' lied to the folicwing' analyses: Gamma-Spectrometry where principal gamma energy used for identifica tion 14 lesr, than 250 Mev. 89 90 ~ Se and Sr Determinations. -- -.- --,~, 4,g y - p n, 1 oun teL on,.the. same. dale _.using...the_ syme _,_. refnrence nuclide. ..k.. I ~ .L 6sw w
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IImm E.1. Hatch Nuclear Plant aao a cca n o HNP-8135 a"'5'o" Georgia Power e'4 ',j 5ee Title Page d El ,_o U' i of 7 App Titto P a gg__ HAND AND FOOT MONITCR HFM-4A CPERATION AND CALIBRATIQN A. PURPOSE To ensure that the instrument is calibrated properly and to provide operation guides to the user. B. SAFETY _ Observe radiation protection procedures. C. REFF_HENCE 1. Technical manual fur hand and foot monitor, model HFM-4A. D. EGUIPMENT 1. P-10 gas (10% methane, 90% 4.cgon). 2. Electrostatic voltmeter. 3.' Assorted check sources. g [, E. DESCRIPTION The HE1-4A provides a fast go/no-go indication of beta-gamma f 1. The contamination on the hands and shmas of personnel. w'" instrument design allows an individual to monitor himself/herself. The instrument is entirely digital. All controls are internally mounted. Indications as to the status of the instrument and whether a person being monitored has an level of radioactive contamination are provided unacceptable on the front panel by solid state LED's and an audible alarm. The instrument has three channels, each monitoring beta-gamma radiation. Each channel has a separate alarm Each channel monitors its cwn switch for beta-gamma. back[round continuously in pre-set time segments while the 9 HFM-4A is unoccupied. The most recent background count is 3 stored in memory and is subtracted whenever someona steps onto the HFM-4A to be monitored. The electronics of the HFM-4A are solid state, mostly integrated circuits. All major circuits are plug-in circuit { boards. e [ * * * - "
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~ ' rom E.1. Hatch Nuclear Plant = =< ~o l HNP-8135 Soo Title Pcg2 A . Mm Georgia Power cia ..m ~o Sce Tit 1= pag = 2 of 7 2. Indicators: a. Front panel, visual 1. Counting background yellow light-emitting diode. (LED). 2. Counting activity , yellow LED 3, Recount -- red LED 4. OK - green LED. High background - red LED. 5. ~ 6. Fail - red LED 7. Hands beta gamma - red LED. 8. Left foot beta gamma - red LED. 9. Right foot beta - gamma - red LED. - 10. Inlet gas flow - flow meter (20 - 240 cc/ min.). 11. Outlet gas flow - flow meter (20 - 240 cc/ min.). b. Front panel, aural: The Sonalert " squealer" is l actuated when any of the following alarm conditions exists. ..T - 1. Recount 'f 2. High background 31 Fall 4. Hands beta gamma
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Left Foot beta - gamma 6. Right foot beta - gamma The Sonalert also " beeps" (approximately a SOO-millisecond tone) when the count - time for a person being monitored is complete and also if the gas inlet pressure falls below the recommended level. I 3. Detectors a. General 1. Window thickness: 3 mg/cm2-aluminized mylar. 2. 4 pi beta efficiency: Approximately 20% 3. Gamma sensitivity: Approximately 50,000 cpm /mr/hr. 4. Counting gas: P-10 (10~ metha-9, 90% argon) M 6 -...34--.....-.----------. S 3 y 4 -wv
f== E.1. Hatch Nuclear Plant ~u== ~o 7 HNP-8135 .Sec Title Pags %visio~ ~o .A Georgia Power d 4 _o See Title Pace 3 of 7 F. DESCRIPTION OF CONTROLS AND CONNECTICNS 1. Front panel a. LH (Left hand) Simulate Switch: Performs the same function electronically as the switch which is actuated when a hand is inserted into the left hand cavity. Button must be depressed to accomplish function; used when. monitoring right hand only. b. RH Simulate Switch: Same as above except used when monitoring left hand only. c. Gas Flow: Screwdriver slot gas flow control valve used in conjunction with the front panel mounted flow meters to set gas ficw rate through detectors. 2. Back panel a. 115/230 VAC Switch: Changes the configuration of the power transformer primary as appropriate for the indicated voltage. .;/ ~g' b. Power: Turns instrument ON and OFF. Rbset Start: Resets counting circuits to zero and c.
- ~is starts new count when CYCLE switch is in the MANUAL position.
3. Internal - Control board (10721-00) a. OPN (operational) MODE switch - determinas the channel or combination of channels for which tha counting circuitry is active-FEET. HANDS OR FEEi AND HANOS. b. MODEL switch - Provides the Logic manipulation required by the instrument. Model switch should be set for MODEL "A". c. CYCLE switch - In the " AUTO" position, all sensor switches are interlocked into the counting electronics. In the " MANUAL" position, a new counting cycle is initiated by the RESET - START switch. d. DISPLAY switch - Enables operator to choose which channel is displayed on the internal 4 - digit beta - gamma display. Instrument also designed for ALPHA detection, but alpha logic has been omitted. e. LINE FREGUENCY switch - Selects 50 or 60 Hz as applicable for the incoming line frecuency. . --....., ;. 4
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E.1. Hatch Nuclear Plant ~~ awawam ~ j HNP-8135 See Title Page 4 Georgia Power na c ,mo l Rao T4+10 Raqu__ 4 of 7 f. COUNT TIME switch - Selects, in the timing circuitry, f ~ the proper output of a " divided - by" counter to provide either a 6 or 30 second count time. g. TIME MULT switch - In the XI position the count time selected by the COUNT TIME switch (above) is unaffected. In the X2 position, the count time signal is put through a divide - by 2 counter and either a la or 60 second count time is provided. 4. Internal. - Channel Counter Boards (10720-00) 4 a. BETA - GAMMA ALARM digit switches - set into the counting circuitry, a number which is added to the most l recent background count. 5. Internal - Large Mother Board (10731-00) SONALERT switch - in the ENABLE position, 5 VCC is a. provided to the Sonalert so that when an alcrm l condition exists and a path to ground is established the Sonalert sounds. In the OFF position the 5 VDC I . ;,f path to the Sonalert is interrupted. l j. ~"Y ~ ~" ~ ~ ~ ~ ~. ' Int'e"r'nal - Amplifier / Discriminator Boards (10722-00) 6 ~ t " ~# ). ANTI-CON switch - In the IN position this switch a. controls the output of one section of the amplifier. b. DETA - GAMMA THLD (threshold) potentiometer - varies the reference voltage at the' beta - gamma comparator. 7. Internal - Emall Mother Board 3 a. HI VOLTAGE switch - determines whether power is { supplied to the high voltage power supply. CN or OFF. b. HI VOLTAGE ADJUST potentiometer - changas the output of the high voltage power supply. G. OPERATION CF INSTRUMENT 1. With the power switch in the DFF position and the AC switch set to the appropriate line voltage, plug the AC power cord into an outlet. l 2. Ensure.the gas flow is at least 30 cc/ min. 3. Turn HI VOLTAGE switch on small mother board to the OFF position. Turn the POWER switch to the CN position. 7.
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ta= E. I. Hatch Nuclear Plant ca=== ~o HNP-8135 ,See Title Page k atv ww uo - k.c Georgia Power em Aon Titio page 5 of 7 4. At this time, the FAIL light will come on (due to no high voltage at the detectors) if the HIGH BACKGROUNO and RECOUNT lights appear, there is no need for concern. The condition will reset itself after 34 seconds. S. Turn HI VOLTAGE switch to the CN position, FAIL light should go out. 6. . Instrument'is now ready"for use. 7. Step onto instrument, place hands in hand cavity, and press down to start count cycle. COUNTING ACTIVITY L.E.D. should be on. 8. At.the end of the count cycle, the O.K. L.E.D. will light and the Sonalert will sound. If contaminated, the "HANOS" or " FEET" L.E.D.'s will be on and the Sonalert will sound. NOTE If contaminated; call Health Physics. . -// H. Weekly Monitor Checks .f 1. Observe' gas flow and record on DATA SHuti 1. Flow rate "~7 should be approximately 30 cc/ min. 2. Remove tip cover or open cover door and place CYCLE switch to the MANUAL position. 3. Adjust TIME MULT switch for a 1 minute count time. 4. . Press RESET button on the rear of the monitor to begin background counts. 5. When the counting light goes out on the front of the monitor, turn the display swi.tch to channel 1 and record results on DSTA EHEET 1 as' background CPM for hands. Turn display switch to channel 2 and record results as background CPM for left foot. Turn display switch to channel 3 and record results as background CFM for the right foot.- 6. Adjust display switch to channel 1. Place source against the center of the outside left hand detector. Press RESET button. When the counting light goes out record results on DATA Sh:.tt 1 in the correct column. 7. Duplicate stop 6 for inside left hand, inside right hand, and outside right hand detector. B. Adjust the display switch to channel 2. Liy' the source in the conter of the left foot detector. Press RESET button. .__ q. r. _ .g . light goes out, record results in the corre ct column on DATA FHC1-T 1. P l MMUA' SET .~.....
E.1. Hatch Nuclear Plant w>= -c=== = j HNP-8135 mvmw uo Sea Title Pags Georgia Power A i i 'b m, _ Sea TI+1a P""" 6 of 7 9. Turn display switch to channel 3 and repeat step 8 for right foot detector. 10. Return CYCLE switch to AUTO position and TIME MULT switch for a 6 second count. 11. Step onto the monitor. Observe and ensure counting activity L.E.D. and 0.K. L.E.D. are operational. 12. Ensure BACMGROUND L.E.D. is operational. 13. Step onto the monitor. Lift left hand before counting time expires. Observe and insure the RECOUNT light comes on. 14. Duplicate step 13 for the right hand, right foot, and left foot. 15. Place source in left hand detector side. Activate counting mode, and ensure alarm and lights comes on for hands. Record results on DATA SHEizi 1. Perform the same procedure on the right hand detector. -fY 16. Remove protective covering from foot detectors and repeat Step 15 for each foot detector. 1 -o-17. Record alarm set points on channel boards on DATA SHEET 1. . js J 18. Install top cover or close lid and return instrument to service. 19. Replace paper covering on foot de'tectors if necessary, s 20. Complete DATA SHtti 1, calculating efficiency of the detectors. If any detector efficiencies are less than 20% or greater than 50%, repair or replace detector. Allow new detector sufficient purge time. Then repeat section H. NOTE Alarm set points will be determined by a Laboratory Foreman using 20% worst possible detector efficiency before detector would be' changed. ~. .-..--.g..,.. Mh305' SEI ..w. - c.
L ~ E.1. Hatch Nuclear Plant Y= -cao - ~o i HNP-8135 Sea Title Page f eso~ ~o Georgia Power c1 om ~o See Title Pace 7 of 7 DATA SHeti 1 HFM-4A WEEKLY MONITCR CHECK LOCATION: M.P.L. NO: SERIAL NO: . SOURCE NO: . SOURCE D.P.M. GAS FLOW: . cc/ min GAS PRESSURE: BACMGROUNO CHECKS: HANDS cpm; LEFT FOOT cpm; RIGHT FOOT cpm SOURCE CHECKS: SOURCE CPM-BMG DIVIDE SOURCE DPM X 100 + EFF. LEI,ECIER 1500ECE_CK _ CPM ' EliG _CEtt.50UECE_QEU__DEIECICE_EEE !_6L650_5EI_ERILI.. .., -, ~ "b,* ' Y2th3 i i -d*,-tN3th5 j " "-?.t-9hYL, . Y~.h l ~~ \\ -- = = - = = - r u,p p uGT NOTE IF OETECTOR EFFICIENCY IS LESS THAN 20% OR GREATER THAN 50%, REPAIR OR REPLACE DETECTOR. ALARM CHECKS: LEFT HAND: ACCEPTABLE UNACCEPTABLE RIGHT HANO: ACCEPTABLE UNACCEPTABLE LEFT FOOT: ACCEPTABLE UNACCEPTABLE RIGHT FOOT: ACCEPTABLE UNACCEPTABLE COMPLETED BY: DATE e 0 ..:~... .g.....----..~..--- .-.2 e M**M o' S ET ~ .~.... .}}