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Revision as of 23:54, 26 February 2020
| ML20023E177 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/15/1983 |
| From: | Nix H GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20023E175 | List: |
| References | |
| PROC-830415-01, NUDOCS 8306150044 | |
| Download: ML20023E177 (105) | |
Text
{{#Wiki_filter:-- GEORGIA POWER COMPANY m HATCH NUCLEAR PLANT J PROCEDURE Gamma-10 Portal Monitor Ogeration & Functional Test PROCEDURE TITLE HNP-815C, PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X.) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER r______. O New P.rocedure _ _ [ ___s ._ _/_____ _ ______.. _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ ..____ / n . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ .. _ _ _ _ _ _ _ _ . _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ .._______. i __ _ - _ .._____ ___ -_ -___--..- .---_---------. p am em e _ em .m._ _ _ .e am . . a.am -- e _. . _ e. _ .e as. ap . s. . .. _ . - _ . e__.. am g. a. e
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8306150044 830607 HNP-9
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RETURN THIS TRANSMITTAL AND ANY DOCUMENTS REGUIRED TO BE RETURNED, TO THE' DOCUMENT CONTROL DEPARTMENT. [ DESCRIPTION OF DOCUMENT (S) TO BE RETURNED: dJ/d, t l
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- it PROCEDURE CHANGES ICDE OF OPERATION OR INTENT) S DESCR1CED IN FSAR
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q .ti as exclained below ___u_es___o_n________________. _ _ _ ____ , _________________i___________ c _1,_ T_h_e_grobab il i t.y_of_.gsg.u_rrgng.q. a nd th.c_c.q.n.ssnu_cn c;s _o_f_a n__a csid_en t____ or calfunction of e_ouioment i_m.o=ortan_t_t_o safety __are _~not -- _ _ inc_rea_s_e_d___ a'bove_t.h.g.qg_a.na.1yrjtd in thg_F.Sf3 ,
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- 2. Th'e oossibility of an accident or malfunction of_a _d_ifferent_tv_ce -.
because than anall' zed in the FSAP. does not result from t_h_is_.
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the system responds and is operated as before. ._ _ g
' ~~ The marcin of safety as' de_fi_ned in the T_echnica_l_Soec_ific_ation_s_
- 3. _ _ _
-teca_use 4.k.qro_ceks does not ___ ,
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a APPHQVA( HNP-8156 E. l. HATCH NUCLEAR PLANT tv.u o g
' See Title Page O
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GeoreiaPower o il 1 of 9 See Title Page i GAMMA-10 PORTAL MONITOR OPERATION & FUNCTIONAL TEST . g i A. REFERENCES ' Instruction Manual, Gamma-10 Portal Monitor, National Nuclear j Corp., TDC #4053M, 208SM ! D. SAFETY Observe radiation protection procedures. , C. TEST EOUIPMENT CS-137 check source D. DESCRIPTION OF INSTRUMENT ' The NNC Portal Monitor Gamma-10 system utilizes a pair of large
- plastic scintillator detectors mounted vertically inLight a housing pulses which is shielded from the scintillators are detectedEach on three si' des from radiation.
by photomultiplier tubes, tube has a voltage mounted above thesupplied scintillators. a regulated source of high voltage, dividing network, Amplified pulses which-delivers an output pulse to the preamp. feed a ratemeter which responds rapidly to any variation in pulse circuits in The output from this ratemeter passes into two rate. These two circuits have radically different the time constants. alarm module.One circuit with a long time constantcounters. is used to update the background radiation level detected by the The output of the other circuit, which has a much shorter circuit.time The constant, is subtracted from the background level difference between these isvalues amplified (short andterm used count ratea less to trip high longer term background) level alarm and relay when this difference exceeds a The output of,the ratemeter also goes directly to another circuit which actuates a relay when the count rate falls below Thisarelay preset level (i.e., due to cable or instrument failure). also alarms on loss of power. R 4 O g3 ' MANUAL SEI
I
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._o , l HNP-8156 l
.E. I. HATCH NUCLEAR PLANT *vam w
^g See Title Page l O
\ _/ om Georpia Power A -
2 of 9 I See Title Page q O j i t The electronic equipment is housed in an 8 wide NIM Bin, which ' j also supplies the necessary low voltage power for the amplifiers and other electronic equipment. This NIM Bin unit houses: . High Voltage Power Supply : Amplifier and Single Channel Analyzer . Ratemeter Module Alarm Module
. Low Voltage Power" Supply The Gamma-10 system also contains two options; a solid scintillant foot monitor and carbon plastic beta transmitting
~
covers, instead of wire mesh cover. E. DESCRIPTION OF CONTROLS AND CONNECTORS O 1- Power Separate Switch on supply a.c. line power to instrument. power switch for high voltage power supply.
- 2. High Voltage Controls Two rotary switches and one potentiometer allow setting the high voltage from 0-2000 V. The applied voltage is the sum of the dial readings. These photomultiplier tubes are operated at about 1200 volts.
WARNING Never exceed 1500 V on these photomultiplier tubes. Increasing the applied.high voltage will increase the system gain and hence count rate. A SHV series connector is provided at the rear panel for connection to the photomultiplier voltage dividers o" preamplifiers.
- 3. Amplifier / Single Channel Analyzer iSCA)
- a. Amplifier Gain Controls: A rotary switch provides a coarse gain of 2, 4, 8, 16, 32 and 64. A fine gain
, .3~
control allows the gain to be varied between X1 and X10.
~/
- b. Lower Level, E: A ten turn potentiometer,that allows the lower level discriminator to be set be. tween 0-10 ~
volts. MANUAL SET
( i i PHUC4UUHF NO 64 HNP-8156 E. I. HATCH NUCLEAR PLANT -enw. no - See Title Page om O Q' Georgia Power d - See Title Page O 3 of 9
> c. Window, E: A ten turn potentiometer that allows the SCA window to be set between 0-1 volt or 0-10 volts depending upon the position of the rear panel slide switch.
- d. .Two amplifier input jacks (BNC) are located at the rear panel (marked IN) to receive pulses from the preamps.
The SCA output jack (BNC) located on the front panel is connected to the ratemeter input jack with a short cable.
- 4. Ratemeter Module
- a. Counts /Sec: A rotary switch that-adjusts the full scale range of the meter. Fixed ranges of 3,000, 10,000 and 30,000 cps. .Normally, the ratemeter should be set to LOK full scale.
b.. % Standard Deviation: Three position rotary switch that determines the statistical accuracy of the ratemeter. The % standard deviation and range {m, determine the time of response or equivalent time s/ constant of the ratemeter. Normally, the ratemeter should be_ set to 10% std. dev. to provide a relative fast. response time (S m sec.) relative to the passage time required for the door monitor. BNC input and output jacks are located on the rear panel. NOTE Ratemeter input is received from SCA output; ratemeter output is fed to alarm module input.
- 5. Alarm Module
- a. Contamination Alarm: L.E.D. lamp that indicates contaminated material has passed through the detector and triggered an alarm. This lamp may light due to a false alarm caused by the background statistical variation.
- b. Contamination / Fissile Sensitivity: Ten turn l
potentiometer that sets the magnitude of the signal fed to the alarm module. This control determines the l sensitivity of the system to special nuclear material
.- t and the false alarm rate. Increasing the dial setting
' M increases the sensitivity of the system. The centrol
~
should be adjusted to detect contaminated material r j located on a person's body while walking through the j portal monitor.- There should be one false alarm about every 10 minutes with the occupancy monito'bs , inactivated. MANUAL SET
j i l 1 l NLDUH4 W - >
-mm= HNP-8156 I E. I. HATCH NUCLEAR PLANT tmm.m O See Titi, page om ~~
GeorgiaPower d _ 4 of 9 See Title Page Fissile Time Constant: 3 position rotary switch that
- c. determines the short term integration time constant of the system. It should be adjusted to O.4 sec. which is average length of time required to pass through the '
Decreasing.the time constant will portal monitor. increase the time of response _and false alarm rate. 3 Low Limit Alarm: L.E.D. Iamp that indicates the signal d.. This may background has dropped below a preset level. be caused by loss of signal or power (high voltage or .
- a. c. line) to the detectors. s t
- e. Low Limit Sensitivity: ' Ten turn potentiometer Ten turns correspondsthat l sets the background trip point. Normally, 7 to full scale deflection on the ratemeter. If the this control ratemeter is is adjusted set at 1.0 to 10(i.e.
KCone turn). this would full scale, correspond to a trip point of 1 KC.
' f. Background Time Constant: 3 position rotary switch that determines the-long term integration time constant of the system. It should be adjusted to about 20 seconds. It determines how fast the system can respond l
to long term background changes.
- g. Reset: Pushbutton switch that resets the fissile detection system when a large signal level change occurs. It is normally only used when the system i's initially' activated.
- h. Signal Input: Rear panel BNC jack that receives signal fram ratemeter.
- i. ' Alarm Output: Rear panel connector that provides isolated NO and NC relay contacts for a remote alarm station. Relay contacts provided for special nuclear material alarm, loss of signal (or power) alarm and high background alarm.
J. Occupancy Alarm: Rear panel connector for connecting In order to SNM alarm in series with occupancy alarm.both occupancy alarm and GNM actuate SNM relay output,If occupancy alarm is not used, alarm must be closed. connector should be shorted.
- k. High Limit Alarm: L.E.D. lamp that indicates theThis signal background has exceeded a preset level.
may be caused by a large increase in the background radiation level. , MANUAL SET I l _ .,. _-
l
- .. u APPRQVAL HNP-8156 ;
m E.1. HATCH NUCLEAR PLANT %:,,e o See Title Page. O oan ~ ~o See Title Page GeorgiaPower , ,, , , l
- 1. High Limit Sensitivity: Ten turn Ten' potentiometer that turns corresponds sets the high limit trip point.
Normally, to full scale deflection on the ratemeter. This corresponds to set this control is set Fortoadditional 9.O. details on setting tnis point of 9 KC. level see AEC Regulatory Guide 5.27. F. OPERATION OF INSTRUMENT When the system is first placed in service, the following steps should be taken. Later on,only minor adjustments are necessary.
- 1. Turn off power switches to high voltage power supply and NIM Plug both power Bin. See that high voltage is set at zero.
Make sure high voltage cords to a stable source of 110 Vac. polarity is set to positive (inside of high voltage power supply).
- 2. Connect signal and SHV connectors between electronic unit
~ and detectors.
NOTE Signal connectors are BNC while HV connectors are SHV so that it is impossible to confuse signal and HV. Signal lead from preamp output is connected to amp input. Connect SCA output to ratemeter input. Connect ratemeter
- 3. Connect Amphenol output to alarm module input (rear panel).
alarm output to remote alarm system. 1
- 4. Make sure that the settings are' consistent with the specific tettings,in Section F.2. These settings are based on Normally, all the experimental test results in NNC plant.
controls'are set to perform before shipping. Turn on both power switches. Raise voltage to 1200. 5. l WARNING _ l Never exceed 1500 V on these photomultiplier tubes.
- 6. t Contamination / Fissile detection sensitivity should now be M set,for manimum sensitivity without leading to false alarms. This setting is a function of radiation background at the site. Sensitivity settings should be made soconstant the unit will detect the source with a O.4 second time setting and still be within an acceptable false' alarm rate.
- An acceptable false alarm rate can be i false alarm per 10 minute time period. MANUAL SET
~
#480L tLMJHt N83 Ai49eQvAL HNP-815G E.1. HATCH NUCLEAR PLANT mvum ~o See Title Page n, uA,.
O See Title Page 6 of 9
- 7. Set high limit alarm to 200% of background (i.e., 5 X 1000 (5000) cps for background of 2500 counts).
- 8. Set low limit alarm to 20% of background (i.e., 5 X 100 (500) cps for backgrouno of 2500)
- 9. Set update interval from 5 to 15 sec., typically 10 sec.
- 10. Set the required SNM sigmas from 1 to 8, typically 4.
- 11. Set passaga time to rate of personnel passage, typically 0.4 sec.
- 12. The factory settings are listed as follows:
- a. High voltage power supply; 1200 volts
- b. Amp /SCA; coarse gain-100, Fine gain-5.0, E (upper window)-10.0, E(lower window)-0.20, mode-normal.
- c. Ratemeter; range-3M; standard deviation 10%.
- d. Alarm; contamination alarm-3.0, high limit alarm-9.0, low limit alarm-1.0, passtime (seconds)-0.4, background update (seconds) 20.
NOTE Unit can normally be set up and operated using the NNC factory settings. If these settings do not provide satisfactory performance or if conditions at the installation site differ substantially, it may be desirable to change the settings. C. FUNCTIONAL TEST OF INSTRUMENT When the Gamma 10 Portal Monitor is in use, Data Package of this procedure should be completsd on a weekly basis. The following guidelines should be followed when filling out Data Package 1.
- 1.
Background:
The ratemeter will give an approximate value
,for the background levels. Indicate this value in the space
; provided.
4
- 2. Gree'n light check: Inspect the top frame of the portal monitor to insure that the green light (indicates passage is clear) is functional. ,
MANUAL SET
. . . .b PHottuuML w HNP-8156 E. l. HATCH NUCLEAR PLANT .
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See Title Page GeorgiaPower , ,, ,
- 3. Source check: A CS-137 check source can be used for this purpose. The source check should be done in four different ways; the source should be placed in the approximate geometric center of the portal monitor, and placed against the feet, left and right portal detectors. It is not necessary to record the actual rate when the source is placed in the portal, but to insure that the alarm is activated and there is an increase in the ratemeter.
- 4. Red light check: Insure that the red light on top of the portal monitor is activated when the source is placed inside the portal monitor. .
- 5. Reset check: After alarm has been activated, insure that the reset button (at the tcp of the portal monitor frame),
when pushed, resets the portal for the next person to enter. The red' light should go off and the green light should be on. . s e 6 l N,
-?
's e
e MANUAL SET
AP991Gvat IMgDuett NQ E.1. HATCH NUCLEAR PLANT HNP-815G See Title Page =v w w onss A O Georgia Power 2 A
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See Title Page O 8 of 9 PROCEDLRE DATA PACHACE ooCu e r No: **.9-8156-1
. SERIAL NO: ROO-
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RTYPE: C15.14
, XREF:
TUTAL SHEETS: 2 FREQUENCY:,_Weektv G., . COPPLETED BY: DATE COPPLETED: I HAVE REV!EWED THIS DATA PACHACE FOR CCMPLETEMSS ~ ' ' ' APC AGAINST ACCEPTANCE CRITERIA IN ACCORCANCE WITH HP-830. f ACCEPTABLE U4 ACCEPTABLE REVIEWED BY: DATE REVIEWED: REMARMS: l Page 1 of 2 t
.A FIGURE 1 l Page 1 of a
' MANUAL SET l
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AevoeuwAt N.u.L LMs*4 *M ) HNP-8156 See Title Page E. I. HATCH NUCLEAR PLANT at v.so. w om O See Title Page 9 of 9 DATA PAOKACD (Data Sheet 1) Cessna-10 Weekly Operational Check Portal Monitor Location Source PFL No. DATE POWolWED CREDs LICHT SACxcMLpc *1pfr esete sten L3:HT pggy SY 04D( APP 631 W.eeCETECTGI DECK OCOC FEET /L&FT/RIGHT CEDETRIC CDiTU.t l- , Vi l l
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Page 2 of 2 MANUAL SET
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DOCUMENT TRANSMITTAL TRANSMITTAL NO: MC/M3 U 9[_- '
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DATE: /C/-/S , TRANSMTTTED TO: s ,a // / M 4 dkA't dt-- [4r> A&r / /# //f I<w j's DESCRIPTION OF DOCUMENT (S) TRANGMITTED: Rn / vws si. u,
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CEORGIA POWER COMPANY HATCH NUCLE.AR PLANT .
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. PROCEDURE Site Area Emergency - Shi f t Supervisor PROCEDURE TITLE
-HNP-4M3 PROCEDURE NUMBER Lab i
RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )
,_----.--__--____-_--_-----.F. __----__--_-_ F---_------------ .-----__.
APPROVED APPROVED 4 REV. DESCRIPTION DEPT. PLANT DATE EAD MANAGER
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.. . . ......:.. .. . . . . . i
.. . . , . . . . . . ~ . . . .
- 2. The cessibility of an accide-t or malfunction of a different tyce ?
s..,...... . . . . , - - _w : .- - = . . . . - . . . . . . . . , . . . . . _ . , . "_ 'than a'nalv:=d - - - in the FS.2.P. .- d:rt - not resu.lt frem this chance because
. . ' * , " ' ' " ' ' ' the system rescorids'and is cerated as before the chance.
~~ -
u-------- - r
- 3. The marcin of safety as de#i ed in the Technical Scecificat.i,qn_s r
is not re_duc_ed due to th_is revi_sion because the revision does not
- - - -- ----- - ------ ---_ s chance anv limited safety syste t settines which would allow a s
safet'y limit to be exceeded er to allow a limitine condition for _ ooerations to b_e
- -- -- -ex_ce_eded.__a_s
- -- _ stated in' Technical. Soecificat_ ions. - - --
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1 of't yl, Su p E .- I SITE AREA QERGENCY - SHIFT FOREMMt
* . NQ3 Thir, procedure supercedes HNP-4GO2, Revision 6 dated 8-1-80.
A. CONDITION Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. Il B. R__FFERENC_g 1 FNP-4620 l HNP-4853 C. ACTION .
- 1. Proceed to control room immediately.
- 2. Classify and declare emergency using FNP-4620, ensure .that l correct operator action has been tal<en to bring emergency under control.
- 3. Evaluate conditions and findingt, of the control room operator to see if a General Emergency should be declared, based on performance of HNP-4853 and criteria in HNP-4720. l ,
- 4. Assure call list for Site Area Emergency has been initiated.
- 5. Activate Internal Survey Team by contacting Operations Support Center when staffed. Direct Internal Survey Teams
- to arnag to be survoyed as appropriate.
t
- 6. Activate Rescue Team as necessary by contacting Operations l
l Support Center Manager when staffed.
- 7. Establish communications with the Secur.ity Force, Technical Support Center and the Emergency Director as soon as possitale and discuss declaring a General Emergency and/or
- the need for outside assistance for tise Site Area Emergency.
8., Direct on site actions to bring emergency under control. Openh .s 9d Assume the duties and responsiliilities of the Shif i.-- f Sopervisor, if he does not report to the Control Room or is i ; incapacitated, as per HNP-4630. i. MANUAL SET i
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT m PROCEDURE Site Ar,q,a Emergency - Rally Point Leader PROCEDURE TITLE HNP_ 4626 l PROCEDURE NUMBER . Lab RESPONSIBLE SECTICN . I NON-SAFETY RELATED ( ) SAFETY RELATED ( X) APPROVED APPROVED DEPT. -PLANT DATE REV. DESCRIPTION LEAD MANAGER ______ r_ _ _ _ _ _ _ - _ _ _ - - - _ _ . - _ . . 2 Pages 1,2, & 3 Deletions on f
,,. ; g fg II Pages 1 & 3 __?
e /____ _ _ - .G 3 /_ _ _ _ . ._ _ _ _ _ I _O,W ._ 4_ _ _ _...__f1_.. _
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a9 H P-9 . t llANUAL SE1
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. . REVISICr! Clu.r:GEG MOCE 0 .CPERATIOtt OR INTENT AG CEGCRIDED IN FSAR:
( )gYes . ()() No -
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- CHANGE INVOL.VES:- [
J. ( ') An unreviewed Safety Guestion ( ) Tech. Specs. ( >< ) Neither -
-, (See back for Safety Evaluation if required). :. :
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. . . . , - . . . . . . . , . . . .. .. a . --
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REASON FOR RECUEST - - -
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. _unreview '
q _-.u.e_s t_i_on _a_s e xc_l_a_i n_e_d__b_e l_c_w . l - 1 Th_e_grob _-- a.b.il_i_ty o f gg.u --re.s.- a.* .*<_nd._th3_e_qn. 5a_uen ac ---c_es_r o.f.__a n__a_cc_i d_e_n t__ or mal----_-- fua.: tion _o_f- _ec_uf: --. - --_-
.e_.t_h : rt_a_n.t _to__safet.y are not increased __-.
abon_t.h.m._a.uly.u.d i.n__i'i.:JN_d.y.e_10 Ibss.e..cbacsas_her. usa - - -
.. _ _ - the revis_io_n does not ch'a .:e th_e. ourcos_e_
-. or c_e_r_f_orman_ce_of
- --- - --= the ---
sy_ stem.
- 2. The cossibility of an aceits,t or malfunc_t_ ion of a differe_nt tvce .
_ . . , . . . . . . -.. - _. - -. ....-.w _ _ . . . . . ......-.......... . , .~ "
; than analyzed in the FSP. d:ss not result frem, this, chance because
.. u.... . . . , .
the syste: resconds. and is i:erated as before the chance.
- .. 3. The rt:arcin_of safet_y as de#' .ed_in the Technical Scecifica_tions
-- -- _-_= -- -
~
(/'
~~
.< is not _redu_c_e_d due to this re.v._ision because th_e_ revision does not_--
-- . chance _an'y li..ited safety sys.ta t settines which would al_1p;t_,a safet'y lim _it_'to be exceedef __
_---_ r__to__ allow a limiti_ne co_ndition for ocerations t_o_be exc_e_ed_e_d_is state __d_ in'- -Technic _al Scecifications.
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i~ E. l.' Hatch Nuclear Plant =m-=
. g HNP. 4M6 Sao Titio Page d/ C / an v~o= ~of Ge( rgiiPower s ,_ ' #
S e Title Page , 1 of.3 ( SITE AREA EMERGENCY - RALLY POINT LEADER NQTE This procedure supercedes HNP-4E.05 Revision 6 dated 1-2-81. A. CObOITION Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases ar not expected to exceed PAG exposure levels, except near the site boundary. - B. REFERENCE H P-4620 HNP-4621 C. GENERAL INFORMATION & INSTRUCTIONS
- 1. The primary cally point for personnel inside the primary protected area is gate 16.
( . 2. The primary rally point.for personnel outside the primary protected area is gate 1.
- 3. The alternate rally points are: -
a .. Environmental Building .
- b. Skills Training Building or The Outage Training Building.
~
- 4. The criteria for rally point habitability are:
j a. Area dose rate less than 0.5 mr/hr, and
- b. contamination level less than 100 cpm above cally point i background.
i 5. The locations of decontamination showers outside.the primary j protected area are: -
- a. Environmental Building i
i b. Outage Training Building I. j ,
$ .. F
} , . .
- ilANUAL SET l
. - ~ . ~. - _- _ . . . - . . _ - _
- 1
-4 E. l. Hatch Nuclear Plant ra* w a o HNP<4A26 a<v*oa a'o Uce Title Page #,
Georgia Power d . See Title Page
, ~
2 of M ! (~~ Do not release any person who has received greater than 25 6. rem whole body dose or is suspected to have ingested significant amounts of radioactive materials. Such persons are to be taken to the hospital for examination and further evaluation of exposure. ,
- 7. Confer with the Emergency Director before releasing any personnel involved in the incident.
- 8. Check with the Security Force, general contractors, and Georgia Power Construction Department to determine those persons remaining in the plant. If any person (s) is (are) '
unaccounted for, report this to the Shift-F ans If the t Shift % emen cannot account for the missing person (s), form i a rescuel, team (s) and initiate,HNP-4628, Site Area Emergency (
- Rescue Team. ,
D. 6CTION
- 1. After the RET assembles in the OSC, the OSC manager will appoint a Rally Point Leader to take charge of the cally point.
( 2. The Rally Point Leader should instruct all RET members not assigned a specific function ~to report with him to gate 16. M Leave enough RET members in the OSC to comprise an internal
- - - . survey team and a rescue team (approximately seven . . . . _. . individuals).
- 3. Determine if the primary cally points are habitable using the- criteria in Section C.4
- 4. If conditions at the primary cally points do not satisfy the criteria,in Section C.4, proceed to an alternate cally point. Determine if the alternate cally point is habitable using the criteria in Section C.A.
- 5. Dispatch an appropriate number of> RET members to.the
- selected cally points to monitor personnel for contamination..
- 6. Assure personnel gather at the designated rally points for frisking by RET members and collect all personnel dosimetry.
- a. Attempt to separate those individuals who were involved
,' in the incident, who were working in< contaminated
.J areas, and those wearing protective clothing from other
( ~ personnel at the rally point. lt I - s l . MMUAL SET l i
- . , - - --n--
1 E.1. Hatch Nuclear Plant - am> ~ W4 HNPo 4626 ave * =o See Title Page '4 7 Georgia Power c , k . 3 of 3 i (S jic o ,,T i t l e Fac e i I
^
. b. Attempt to survey those individuals with emergency ;
response assignments as soon as practical. ,
- c. Instruct individuals who were involved in the incident, those found contaminated (greater than 100 cpm above i the Rally Point background), and those with personnel dosimeters off scale to remain at the cally point, separated from the others, and notify the Health Physics Supervisor in the TSC.
- d. Forward these individuals personnel dosimetry to the EOF and instruct these personnel to report to the EOF (after checking through the rally point) for further
' . evaluation of dose re,ceived.
- e. Dispatch an RET member (s) to accompany contaminated individuals to a decontamination shower (see C.5) and supervise the decontami'ation n procedure.
1
- f. Release uncontaminated individuals to evacuate the site on U.S. Hwy. 1 in the direction specified by the Control' Room.
( Report status of the evacuation to the Emergency
~
g. Operations Facility. ,
- h. Do not release members of the Radiological Emergency Team, except to go to the EOF, unless directed to do so by the Emcgency Director or Shift Foreman if the 1 Emergency Director cannot-be-contacted. ($,74,ya , - .- . .
- i. Assist in routing ambulance to pick up any injured personnel. Assure ambulance driver and attendant are provided with TLD badge and pocket dosimeter on entry.
J. Assist Emergency Director in bringing emergency under
- . control. .
9,
..~
S I I l l ! . l
- 1 1
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- EANUAL SET I
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- \
GEORGIA POWER COMPANY !' t
. HATCH NUCLEAR PLANT !
p PROCEDURE - l s.. i-l SITE AREA EMERGENCY - OPERATIOSS SUPERVISOR . PROCEDURE TITLE HNP-4630 PROCEDURE NUMBER
- LAB RESPONSIBLE SECTION 8
SAFETY RELATED ( X) bCN-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE EAD MANAGER -
^
2 Page 1 ,,, 8
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Date: { .I 1 ~) E3
,' REVISICt! CHANGES MOCE OF .CPERATION OR INTENT A3 CEGCRIOED Iri FSAR:
( (X") No 1
. . - . )gYes .
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.. .CHANGF. INVCt.VES:- - *
(.) An unreviewed Safety Guestic.n t ( ) Tech. Specs. (X) Neither ;
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REASON FCR REGL'EST - __- ']Mde._ [ M&. - cd 5N ouh rdg[/<e oIX o Pod [[ws __ _$N' . 0. Y n kt(b. -[DieVrit,- Old rNO((as uilh- pcvnker. .N
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- -- _an_t to s_afety are not -__ increas_ed l
aboV2 th51L_8.D.1]27Ad 1.2. 2 2 ].51 Lt ZQ b2St t CbL02.RS b.t.C.U59. -- the _ revision does not c,h'an:s the ourcose or oerformance of the -- it
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. , p' than analv:sd in the FSA*'._diss not resu_lt frcn _this chance because
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. the syst_s_: resconds. and.is i:sr_at_ed as before the chance. - --
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- 3. The marcin of-- sa_ fety as de#'n.e.d in the Technical Scecifications
.(.'
( c is not reduced __du_e to this r_e_ vision because the revision d_ces not -- _ _ -
-- . chanc_e_a_nv_ li:.ite_d__ safety sys'ag settines__which would all_ow - -- a __
1 safety li_mit 'to be exceeded o_r to allow 'a limitine condition for 1_ - '
~~~
ooerations to_be exceeded as stated in Technical Soecifications.
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- am5am Sao Title Paga ,
[ Georgi $ Power s . j See Title Page , 1 of 1 j operad e l SITE AREA EMFRGENC -SHYFT SUPERVISOR l A. CONDITION Events are in process or have occurred which involve actual or likely major. failures of plant functions needed for protectio'n of the public. Any releases are not expected to exceed PAG exposure levels, except near the site boundary. B. REFERENCE FbP-4620. FNP-4720. HNP-4740. HNP-1. . C. ACTION
- 1. Proceed to control room.
- 2. Take control of all activitie,s in the control room, ensuring that proper coordination of all activities is carried out.
j- 3. a. Assume the duties of the Emergency Director until- [ ( ' relieved. Assure ~that those actions in HNP-4640.which
.can b,e performed from the control room are accomplished.
- b. Assure correct emergency classification has been declared as per HNP-4620.e
. O pmo. -
- 4. Evaluate actions of Shift Fcremea and operator to bring l emergency under control. .
opedes
- 5. The Ght+t Supervisor is responsible for notification of !
Plant Management and NRC as per emergency call list and other offsite agencies in accordance with notification procedure HNP-4861. The actual nofitication process may be d,elegated to other, specifically trained, shift personnel. 9,
- 6. Consult with the Technical Support Center and Emergency Director to determine any outside assistance nee,ded.
- 7. Assure that personnel are assigned to maintain an open line to NRC, T.S.C. and E.O.F. and inform these groups of significant plant changes.
- 8. Escalate to general emergency class (refer to HNP-4720 and 4853), if appropriate.
( , 9.2 Provide information to the Emergency Director to assist in his determination of close out or reduction of the emergency class. .. MANUAL SET h .seos .
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE General I~meroency PROCEDURE TITLE HNP-4720 PROCEDURE NU.'13ER Lab RESPONSIBLE SECTION SAFETY RELATED ( X) NON-SAFETY RELATED ( )
- - - _ - . , _ - _ - - - - _ _ _ - - - - - - - - _ - . , - - _ - - - - - - - _ _ _ - - - . . _ - - - - - - - - - - - - - - - . r--------
APPROVED APPROVED REV. DESCRIPTION - DEPT. PLANT DATE HEAD MANAGER 1 Page 2 & 4 p
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it Page 1
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.-5________________--. . - _ _ - - _ _ _ _ _ - - _ - - . . - - - _ _ - _ _ - - _ _ - _ _ _ . .--_--_--
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. 1/re' '2 7 f 7
.. REVISICil CH.*,t:CCG MOCE OF .CP!.RATIOtt OR INTENT AS DEGCRIDED IN FSAR: . i
( )gYes . (X ) No - [ l l
. CHANGE I?WOL.VES*-
( *) An unreviewed Safety Guestion (- ) Tech. Specs. (X) Neither t[
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t. REASON FCR REGtEST
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PhD Decretary j8 3 _____.___ 48* __ __ _.3._.n__.j3__ ____ .__ _ _ _ .
*PRU Numtoer Date -
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- _ ques ti_o_n_a_s__ex_c_l_a_i.ne_d__b_el ow._.____
b.- ; i 1, The grobability of .gsqurr.*._- =, _a_ndv._t.bg tg.n.i.
. q ouences, of an acci. dent ____ !
. . g or__m_al_f_u_n_c_t i_o_n__o _f __e_c_u_i __=__' _'_- _o r_t_a_n_t_to_.s._a _ __ f_e_ty a_re _no t i n.c._r_e a_s_e_d_ !. ! ,
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' * *I the revision does not ch'a . S the ourcose or oerform_a.n._c_e o_f__the - - - - -
-- _ s i
. system. - . ;
... s . ._ _ .. .. .. ,
- 2. The oossibility of an acci s't or_m.a.lfunction of a different' tyce 7 4
_,. . . . . _ -s:- :. 2 . - = = . . _ . _ . . . . . . . . . . , . ,
; than a_nalyzed in the FSAP. d:es not result frem this chance b_ecause
- - 'i
__...p.:... . .. e! the svsta u resconds_..and_.is ::e 3
....._r_at.e_d as.. before the chance.
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. 3. The marcin of safe _t_y_as_ de## ed in the Technica_1_Scecificati.o_n_s A, , is _not reduced __du_e to th_i_s_r_e_v_ision because the__revi_s.i.on does not
- - - _ s 1
--.. . chance __anv li .ited_ _ safety svst.a.[settines which would a11eit_a
- - a l
s a fet*'L.imit to be exceeded or to allest a limitine condition for
= - -
I ooerations_to be exceedef as stated in' Technical Soecifications. i +
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..h _E. l. Hatch Nuclear Plant
' HNP. 47Pn jd {
g See Title Pego Get gaPower n m. M El 1 of '9 f _See Title Pane CENERAL EijERCFNCY A. CLASS _ DESCRIPTION Events are in process or have occurred which involved actual o'r imminent substantial core degradation or melting with potential Release for loss of containment integrity. Refer to Table 1. can be reasonably expected to exceed PAG exposure levels offsite , for more than the immediate site area. . B. PURPOSE i j Purpose of the general emergency declaration is to(2)(1)provide initiate ' predetermined protective actions for the public, continuous assessment of information from licensee and offsite organization measurements, (3) initiate additional measures as indicated by actual or potential releases, (4) provide consultation with offsite authorities and (5) provide updates for the public through offsite authorities. 9
, C. PLANT ACTIONS'
.." NOTE I upro:Hm Supen.se
,' I The Shift cere=== or Eh+ft Supervisor (or higher ranking licensed or certified person present) in consultation with the STA, if feasible, recognizes and declares that the plant
' is in a state of emergency of the general clasification. I
" Tht Supervisor assumes the -cole of emergency dire.ctor Ofmf. until relieved by the F4an-t Mer.ager or his designee. l bount MA9
- 1. Promptly inform State and local offsite authorities of general emergency status and reason for emergency (parallel notification of State / local).
I
- 2. . Augment resources by activating TSC, Operations Support
- Center ,and ECF.
- 3. Assess and respond. l, Dispatch onsite and offsi+ monitoring teams with associated l
i 1 l
- 4. l communications. I i 5. Dedicate an individual for plant status updates to offsite authorities and periodic press briefings (perhaps joint with offsite authorities). l i-i~ 6.d Make senior technical and management staff onsite available
for consultation with NRC and State on a periodic basis.
i l 1 . 2 e a MANUAL SET 1
~ < = =
G ia E.1. Hatch Nucicar Plant
.. HNP. 472n
' * = ' * ,e t See Tif.le Pago ~p ? l
.... Georm).albwer d as .. . -
f 2 of 9 Gee Title Pace
- 7. Provide meteorological data and dose estimates to offsite ,
authorities for actual releases via a dedicated individual or automated data transmission. j
- 8. Provide release and dose projections based on available plant condition information and foreseeable contingencies.
- 9. Close out or reduce emergency class by briefing of offsite authorities followed by written summary within 8 hours of closecut or class reduction.
D. STATE ANO/OR LOCAL OFFSITE AUTHORTTY ACTIObG
- 1. Provide any assistance reguested.
- 2. Activate public notification system promptly,' inform public of emergency status and provide updates periodically.
- 3. Consider sheltering for 2 mile radius and 5 miles downwind and assess need to extend distances. Consider advisability of evacuation (projected time available vs. estimated
, evacuation times).
( A. Augment resources by activating primary respond centers.
- 5. Dispatch key emergenty personnel including monitoring teams with associated communications.
- 6. Dispatch other emergency personnel to duty stations within 5 mile radius and alert all others to standby status. -- -
- 7. Provide offsite monitoring results to GPC, DOE and others and jointly assess them.
~
- 8. Continuously assess information from GPC and offsite monitoring teams with regard to changes to protective actions eatready initiated for public and mobilizing evacuatjon resources.
- 9. Consider placing milk animals within 10 miles on stored feed i and assess nand to extend distance.
-10. Provide press briefings, perhaps with GPC.
- 11. Maintain general emergency status until closecut or -
reduction of emergency class. , 1 . l . .t. l NANUAL SET 9 434
-. _.., , . . . . . . . . - .- .. ~ .
.) ,.
C # 4
!! ! . I
.3 -
TABLE 1 GENERAL EMERGENCY f,. I .7 t
~
frl!TIATING CONDITTON EQUIPMENT STATUS PARAMETER VALUE Yl7 "i i 1.a. Effluent monf tors detect levels Mpin Stack and/or Reactor Bldg. Vent $ $* corresponding to i rem /hr W.B. monitors Hi Hi alarms plus monttc:a
- j or 5 rem /hr thyroid at the site ' reading plus dose rate projection boundary under actual meteoro .. calculations. Dose measurements off- .
l j . logical conditions. site using portable instruments or environnental m6nitoring stations. - .-
-i l.b.
Projected dose rates as above ' Dose rate projections will be bas ~ed
~
i based on other plant parameters. - on the following: Contalanent Post - - ' r LOCA Radiation monitors, analysis of . . S O ? drywell air sample. ARM monitors in Reactor Building, plus possible con-
!It 9 N
0 l .j firmation from effluent monitors or rg rf. g [- offsite measurements. .. mr -
~
1\m a <. 2.a. Failure of cladding and contain-containment with potential loss See Table 1-a. '
'Reactorpressure>l325psig'.fla with failure of safety h
r5 [i c! l of primary coolant boundary. 3
$ relief valves to open.
3
E' j 416J volts undervoltage. .i< ) t
[
- 600 volts undervoltage. iE .
I L Analysis of activity in : J . i . steam and coolant. Reactor e
' water level 5352.5 inches. ,
j Failure of ECCS to auto or manuat initiate. Indicated loss of primary containment. g ' 1}g i l
= .
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TA8tF 1 -GENERALEMERGENCY(Continued)' W - id!NITIATlNG CONDITION -
. E00fPMENT STATLG PARAMETER VAttlE 5 1 7 g
, 2.b. Failure of cladding and primary See Table 1-b. Containnent pressure >25 psig coolant boundary with potential * ? 2 Containnent temperature j j loss of containment ' >3000F Inalysis of activity in
' , steam and reactor coolant .
* - Reactor water levels L/64f ,
inches 3
. Containment Post LOCA Monitor Readings )g F
. Containment High Range Radia- .
Q --
- L
- tion Monitor Readings n, r: r
~
Main Steam Line Flow >120 psid 3 Q E
- - Containment atmospheric mH ry: g
, anal,ysis S$ ET 7 l
2Jc. Failure of primary coolant Mm - 2 See Table 1-c. .' containment pressure >25 psig $ i boundary and containment with . Containnent temperature p R
- potential loss of cladding
>3000F 2 E m
S
. Rain Steam Line Flow >120 psid 5 y Indicated loss of primary : i;P Q containnent -"
3' Failure of ECCS to auto or $
~
manual initiate - 4160 volt undervoltage 600 volt undervoltage Reactor water level <_/lg.f n . 'e - inches and decreasing E - q, . . . i , . i
=
j O3: 3= Loss of physical control of the Observation Shif t Supervisor's judge-E l ?j
'~ 8 plant -
i M ment based on advice.of i s aj-
- Security Shif t Supervisor s N S5 m 2 O b*%
~
~
p . . . - - - ~ . . . . . . . _ _
~
8 -. l .
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( < i _ u N .-e TABL51 GENERAL EMERGENCY (Continued) - n ~ INITfATING CONDITION EQUIPMENT STATUS PARAMETER VAttlE i crer-h 'o 2 .9. 4.' dtfler plant conditions exist Judgement of Shif t 0 from whatever source that make Supervisor and STA * = release of large amounts of ' i .a radioactivity in a short time j j periodpossible(e.g.,anycore - 2 e melt situation). Example of - ' sequences: , ,
- a. Transient (e.g., loss of offsite . '
m . power) plus failure of ' requisite Ijm coreshutdownsystems(e.g..
- I.
scram). Could lead to core . p i melt in several hours with contain- ' - C) - l ment failure likely. More severe ' . '. ~
- - ' O -
l f consequences if pumps trip does not , . Ihg , 5 function. -
.m > .:. .E s -
m:n z sr-
. c.: .
- b. Small or large LOCA's with failure ,.
qm cy g of ECCS to perform leading to core :
,y ;:- . c.
? melt degradation or melt in minutes -
n r5 c-to hours. Loss of containment in- - - 3 ' 5 i "
' ~ ' '
tagrity may be inminent. 3 t- [D i' . E Ei
- c. Small or large LOCA occurs and con- -
esi E tainment performance is unsuccessful , j9 . affecting longer term success of the y ECCS. Could lead to core degradation'. or melt in several hours without con- - is . .i tainment boundary. .. E A x 3: j z3 E d. Shutdown occurs but requisite decay 2 [ heat renoval systems (e.g., RilR) or
,E 3
'" ?" l m nonsafety systems heat removal means I
> I.
are rendered unavailable. Core de- S 3 O$ gradation or melt could occur in about ten h'ours with subsequent containment
, o y failure. -
1
- ..a -
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TABLE I N GENERAL EMERGENCY (Continued) - - INITIATING CONDITION EQUIPMENT STATUS _
~
PARAMETER vat.UE !" j . b O -- i 5. Any major internal or external events -
@ 2 I
, which could cause massive comon . m M E damage to plant systems resulting
$'Y # :.J.
o in any of the above.
@f om E o Z Fires Massive damage to ECCS System Loss of ECCS Systen [- h E.
n t;
~
o l Earthquake Massive damage to ECCS System . Loss of ECCS Systen j R, ! d 3 u i a w R O e M - a R s 1 z$
$ h 7h
. 5 ,a Q o M t45 v'
4 0
i m: 4 ' i 0 - o i -
- 1 - -
TABLE 1.a 5,,)-}5g ; EnUIPMEll{JTATUS FOR FA! LURE OF CLADDING AND CONTAINMENT WITH POTENTIAL LOSS O Ll 3 3
. n m
= c,
. . : a o 1 3 GAP ACTIVITY IN .
. .'~ -
STATUS INDICATES All. t Pdli%RY COOLNIT *
. CONTAlHFENT PENETRATIOrls NOT VALVED OFF OR CLOSED s
~g Am OR
]q(
! CORE UllCOVERED _
q OR c3 , l -
\,% . - . %. .
j ' e p aA..~s ,4 C' 'E M. l '
-SHIFT SUPERVISOR,S &.m O
.- i> :.
^
- j [-
. OPINION e
GAP ACTIVITY IN STEAM - Q O c,
- . y R 9.
'.- o a
~
R LOSS OF AC
. 1 o FN Ei
- 2. '
LOSS OF ECCS -
.I OR -
i AND . -
\ 1 .
m .i - l Ell!Gil REACTOR PRESSURE k.' -
,, j .,-
i j IA RilTil l%LFuriCTI0lllNG - . ' . 8 9 ?E
" tdLIEF i NS SAFETY - -
- 4 5 ,3 EVALVES
- o
+
h 4o N
. GENERAL 04ERGENCY - o
, 3 sy
.~~'- ~ ~~~ ~~ ~~~~" s ....... .. +...- ...... .. ....... _. ,......... _,.,. _ _ _ -_ _ _ _ _===* ~--~ .se. .eso.e e ~
4 4 I - I TABLE 1-b '
; ,~ -
i s i EQUIPflErli STATUS FOR FAILURE OF CLADDING AND.Pll!HARY C0OLANT B00tIDARY u!TH POTENTIAL p ..; -- p. L i?I 9 ; 3 $ i. J GAP ACTIVITY IN j g
/.111G1 DRYkFLL PRES $1M * ,<-
i FRIIWitt00LANT ,
/ IIIGl DRYhELL TEMPEMTURE E 2 l CORE (I COVERED OR H AND ' 9 OR I l
~' -
*Y -
gtP j ,jtTIVlW IN 4 CAP ACTIVITY IN IXMELL ' P CONTAINENT C) PRESSURE
~
C 2
/ t 1 TS : .
,d pD g
Ang .. o CONTAINrENT h A 5 v STEAli LINE BREAK PRESSURE c c OR l /' N ' g o_ dETr.'EErl
< If1 CREASING CO:lTAll!! tint AND 3
. G Q i tASiv
)1'( AND 1 LOSS OF , 7-CONTAINMENT .
' OR COOLING STtWi LillE BREAK /' . J
. j .
D0.tlSTRERi 0F'- e4siv
'/* '
AND ! SillFT SUPERVISOR l ~
-' OPINION ! .
1 [l m liSIV FAILURE N . . 6pvJ.w . , a 2 E f' ; ,A 2
#1D OR CORE UilCO'!ERED r
3 s 7(
.A m-Nf . ./ s .. . .. ./
/ -
.N 5 3; d*
CAP ACTIVITY IN 7 o aTElli __, OR W v
. G*iP ACTIVITY IN ,- - -
J 4. PI(ItNty fo?!.qL GENERALEljERGENCY _
; . m 4
]:;.
fL ( :
* '4 TABLE 1,-c .
.(
w w I Equir!!ENT. STATUS FOR FAILilRE OF PRIMARY C'00LANT BOUNDARY AND CONTAINijENT )lITH POTENTIAL. LOSS Of CLAD 0!!!G ; ;. L a e o
. 8 - f =
. j j
~.:.,e.
,., HIGH DRYWELL PRESSURE STATUS IrlDICATES
~ g ALL C0tlTAllt1ENT O -
PErlETRATiotis TDT - . HIGH DRYWELL TEMPERATURE 9 I
; VALVED OFF OR m - ,
M. E g OR S Q) Y N -
$NT '
NillFTSUPERVISOR'S OPilligH
]
- f?N (
a E R [ p STEAM LINE BREAK Imi- E og /m n== ns astv MSIV HALFUNCTION . ECCSFAILURE - [*
' E WATER LEVdl LDH i OR LJ AND '
STEAM LilE BREAK BETWEEN i ! !! gAi!ODECIWAstilG { ? l ? C0flTAIMiENT AtlD MSIV d o 8 ,;j tu -J o l , -* LO3S OF AC POWER GENERAL EMERGENCY .
, e V; $
1 - i I
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT
- PROCEDURE GEbEEAL_ EMERGENCY - SHF T SUPERVISOR PROCEDURE TITLE HNP-4723 PROCEDURE NUMBER (AB RESPONSIBLE SECTION q i
1 SAFETY RELATED ( X) NON-SAFETY RELATED ( ) 1, t APPROVED APPROVED - I REV. DESCRIPTION DEPT. PLANT DATE : HEAD MANAGER l 2 Page 1 (~C 3l1f8.2. p / s' o # ~ _ _ _3 _ _ -.______P_a_ge_ 1 - - _ - - - _ - - - _ -_ . 72 _ _ _ _ _ .. _# .c'_n. cy., _[ 4_- ./_/ -Et_
- 9
**a_L. !
( __-___- 4
-____-_--__1 Page
[
._ _/f p. f
- _ly_ _ - _,
- -_____- .____-_______L______-. . _ _ _ - _ - _ _ - _ _ _ _ - - - .. _ - _ - - _ . , - _ _ _ _ - - - - ..___--_..
9, l
-__---- - . _ _ _ - - - _ _ _ _ _ _ - _ - _ _ _ -. _ - _ _ _ _ _ _ _ _ _ - _ _ _ . ._----_---_.--___.._-_-_--- I l
I
+_,--_______-__-_____-
._-_---__________ y__-_______-_____. .._-____.
-_---_(--___-__-___-___-_-_.-_--____________3-_-_---______ --. .___-__-.
HNP-9
. MANUAL SET s
. . l
- , . . _ - _ - ~ . _ , . - .
({,W ' . . .j e .. . 8
. Cf.10'.'TO. ! r.!.q Rf T.' f G t ~et alf Ot r. :~.T J
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- l PROCCOL'nE Nb. HNP- - /- i1
- r. -
/;. .. . . . .
N . l
- Revision No. -
_ . I.) .
.( RFC'L'::.ST.FD RY _.
Of..P R_Trf..D._1.T._1_6_
. . _. O .P P: r_t.'.:.:.
Date:
. Name- Datn; Signature: ..
Y' ~I O l [h(e, -
~1 v
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)
I i REVIGICt! CHAT:GES MOCE OF.CPF.RATICPI OR INTENT AG DEGCRIDED IN FSAR;. ( -)gYes - ( )O No
. l' , 1
g cHAncs nuot.vEs:-
.. **( ) An unreviewed Sefety Guestion ( ) Tech. Specs. (X') Neither f:
- . , ,. . (See back for Safetv ..
Evaluation if required). ...: n. .. ...~~.e .. . * . - .. s
. .... a...<.
_ ...Saf.ety Related '@)
-~
..' N._on.. S..a . .f et - _y .R. . e . l. a. t e.d.,.w..(. .> .).
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. . . . i. ~ . . .. . =. = 6. ah-i.% . .; .& a. '.'.. . .. .. w a..:.:w. s a.p. _ a.< u ... .. - - ...- . 1.s-( _) Yes N . - e. .-
.- ..,. =. .Safety /Non-safety Status Change. . ..'..,
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Attach marked up copy.o f procedure to this f.orm. 7.9.D.-'.p . j
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.e........ . . , . .. . . . . . . . . . ,. . . . . . . - . , .
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- REASON FOR REGL'EST
&G6 f- ~ hb*.h.htTlYhQ1(YIYhQQ U(N S $tX41sor,
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. . The ' e_vis i_o_n o_f t_h_is o.r. aced.u. re _d :
E J
--_s _ e_t_ con __t i _tu te_.a.n__u_n_rev i ewed s_a_
q ~ _ ,. _ ues t i_on _a_s__e x_p l_a.i.n e d__b_e _l o_w .__-_______ _____ _ _ _ _ .i -___ *
- 1. I The Erobability_o..f qsgy_r_e_=._- =m.3_n;i_t_hs ranycuences"of an accident i or ma _l f_u.n..c._t i_o_n_o _f.e..c_u_i _ .e_.t i__:o rt_a_n_t - -- -
-- .I
_' a_'bo_v.a. .2. t.h aL=._a_n.=
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%._ d_ i3_d.un._.to._th.eua n .cbac.a =J_b.e.ua . - a__
_
- I
_th_e__r.evis._ ion _d_o_es__n_ot ch'z__e._the ournose or oerfo.r.. i sys.t.em.
. c. . . t
,3, . . . . . .- . . . . . . . .
t
- _ . - . . . 2. . . .
The_ cossibility ,w. of an accide-t or malfunction of. a differ.ent tvoe ? __
- .. ---'_~ :~......w........am...:....... .
w ' . . ::.m . . . than .analyze - - . - _d in the FS.U. c es_not result from .t.his chanc_e because .
".,l the _sys_t_e_m m -
resconds..and.is :.:erated as before the chance. - n
. . . . .~ _ . ,.._ . . ;. ...
i
.. 3_.- - - The car.ci.n o_f__s.a.fe.t.y as_ de"-_ed in the _T_echnical Scecific_at. ions
-=-
t
/
is.n._ot_r_e_d_uc_e_d_.due to th s revision because the revision does not b N chan.ce _a.n..y l_i_._.i_ted__ safety s'. ste 1 settines which .w.ould allow a i ,
- --- 4
, .. safet'y l.i_mit 'to be exceeded or to allos a_limitine condition for 1I _ f-'_ - ~
.I.
ooe.ra*.icn._s_t_o_ b._e e_x_c_e_ede_d_.a._s s_tated in' Technical Soe I y....+ ;s ~ . .
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E. l. Hatch Nuclear Plant =m~~
. HNP. 4723
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L ows$o-7 CGNERAl EMERGENCY - SHIFT. FOREMAN
. tLO.IE I Ylin. procedure supercedes HNP-4702, Revision.4 dated 5-13-78.
.b CIf?)l.IlOfl -
I t. vents are in process or have occurred which involve actual or
- ineni nen t e.uhstantial core degradation or melting with potential f o r- to..s of containment integrity. Release can be reasonably l
i - c a s.e s. t i d to exceed PAG exposure levels offsite for more than the j inr.ma t.3 t'e site area. - t ' j
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. FNP-47dO FNP-4730 l N 3-4115 3 C. /C T Ir*J _
(, ' 1. Proceed to Control Room immediately.
-(
- 2. Classify and declare emergency using HNP-4720, ensure that l correct operator action has been taken to bring emergency under control.
; 3. . th ing HNP-4853, perform dose assessment calculations, report results to Chift-Supervisor.
eyva.hons l
. 4 Assure call list for General Emergency has been initiated.
% Acttvate Internal Survey Team by contacting Operations
; Gupport,Conter Manager when staffed. Direct Internal Survey
- Icam. t, areas to be surveyed as appropriate.
; (. . At t avate Rescue Team as necessary by contacting Operations Guppnet Center Manager when staf fed. } '? . I' .t.it,t ish communications with the Security Force, Techni_c.rl ; 'iupport Center and the Emergency Director as soon as
- . . Ls'. s c h 10 and discuss the need for outside assistance. .
I U-j ~85'ect onsite actions to bring emergency under control. -
; - c. (pf rsh .s
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- C e the duties and responsibilities of the Ghift l
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. t '.. r r v i sor if he does not report to the Control Room or is g
'"8apacitated, as por HNP-4730. .,
. MANUAL SET f-
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4 1 GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE ^ General Emergency - Rally Poi'nt Leador PROCEDURE TITLE - HNP- 4~12E. PROCEDURE NUMBER Lab RESPONSIBLE SECTION l 1 SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED DESCRIPTION DEPT. PLANT DATE REV. HEAD MANAGER _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________ r-______. 2 Page 1,2, & 3 fy d //
/^ W OI// O Deletions 1 & 3 e_______.
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.____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________ p_______.
______. .____________________.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________________ p_______.
.____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________ p_______.
______. .____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ..________________ y_______. I
.__-________u,_ _ _ _ _ _ _ _ .. - - - _ _ _ _ _ _ _ _ _ _ _ _ . .________________ y_______.
.____________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .________________ p--____--
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- MANUAL SdNP-9
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OFPART G.' t T t-iF.- O AP P: .'O'_.'._:. . Natw; De-t e ; Signature: .. Date:
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.. REVISICN CHANGES MOCE OF .CPERATION 03 INTENT A3 DESCRIDED IN FSAR:
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REASON FOR REGUEST-h6- ~2. 'M ~ 4 4 t. ff kl UI SufC1 VIS (2 ' 86)
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-_._ The_grob_a.b._il_i_ty _ of .gsgure.=..- s _a.n.dw._t._h.e._gny.auences - .of an accid _e_n_t - _.
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- 3. The marcin of safety as de#f. ed in the Technical Scecifications
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_ safet;L_l,imit ~to be_ _excesisi er _to allow.a limitinc condition for -- ooerations to be exce=ded . 2 as stated in' Technica.l. Scecificati_on_s_. -
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== E 1. Hatch Nuclear Plant "= rva ~o
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o... . Ge rya Power i .. _ 1 of 3 See Title Page GENERAL EMERGENCY - RALLY POINT LEADER NOTE This procedure supercedes HNP-4705, Rev. 5 dated 1-2-81. A. CONDITION Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release can be reasonably expected to exceed PAG exposure levels offsite fo'r more than the immediate site area. B. REFtHENCE HNP-4720 HNP-4721 C. GENERAL INFORMATION & INSTRUCTIONS
'9
- 1. The primary rally point for personnel inside the primary
(- protected area is Gate 16.
- 2. The primary cally point for personnel outside the primary protected area is Gate 1.
- 3. The alternate cally points are:
- a. Environmental Building
- b. - Skills Training Building or the Outage Training Building
- 4. The criteria for rally point habitability are:
- a. Area dose rate less than 0.5 MR/HR and
- b. contamination level less 'them 100 CPM abov'e rally point i background.
- 5. The locations of decontamination showers outside the primary protected area are:
- a. Environmental Building Outage Training Building c i b.
9 5
- MANUAL SET
HNP.4726
- 'Sta Title Page Georgia Powerkn
; mve m 4=o ' I ;
m -- : See-Title Page 2 of 3
- 6. Do not release any person wh'o has received greater than 25
- rem whole body dose or is suspeited to have ingested significant amounts of radioactive materials. Such persons i are to be taken to the hospital for examination and further evaluation of exposure.
- 7. Confer with the Emergency Director before releasing any personnel involved in the incident. $vp rus.c
/
- 8. Check with the Security Force, general contractors and Georgia Power Construction Department to determine those persons remaining in the plant. If any person (s) is (are) unaccounted for, report this to the Shift Foreman. If the i Shift Foreman cannot account for the missing person (s), form a rescue: team (s) and initiate HNP-4728, GENERAL EMERGENCY -
RESCUE TEAM. , D. ACTION
- 1. After the RET assembles in the OSC, the OSC manager will appoint a Rally Point Leader to take charge of the rally point. ,
- 2. The Rally Point Leader should instruct all RET members not
- assigned a specific function to report with him to Gate 16.
(s> . g Leave enough RET members in the OSC to comprise an internal survey team and a rescue team (approximately seven individuals).
- 3. Determine if the primary rally points are habitable using the_ criteria in section C.4.
- 4. If conditions at the primary cally points do not satisfy the criteria in section C.4, proceed to an alternate rally Qetermine if the alternate rally point is habitable point.
using the criteria in section C.4.
- 5. Dispatch.an appropriate number of RET members to the
- selected rally points to monitor personnel for contamination.
~
- 6. Assure personnel gather at the designated rally points for f risking by RET members and collect all personnel dosimetry.
- a. Attempt to separate those individuals who were involved i in the incident, who were working in contaminated areas, and those wearing protective clothing from other personnel at the rally point.
7
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- MANUAL SET
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HNP.4726 f av o= ~o -
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3 of 3 l See Title Page .
- b. Attempt to survey those_ individuals with emergency response assignments as soon as practical.
- c. Instruct individuals who were involved in the incident, ,
those found contaminated (greater than 100 CPM above the cally point background), and those with personnel ' dosimeters offscale to remain at the rally point, + separated from the others and notify the Health Physics Supervisor in the TSC. d.- -Forward these individuals personnel dosimetry to the EOF and instruct these. personnel to report to the EOF (after checking through the rally point) for further evaluation of dose received.
- e. Dispatch an RET member (s) to accompany contaminated individuals to a decontamination shower (see C.5) and supervise the decontamination procedure.
t
- f. Release uncontaminated individuals to evacuate the site on U.S. Hwy. 1 in the direction specified by the Control Room. .
- g. Report status of the evacuation to the Emergency Operations Facility.
- h. Do not release members of the Radiological Emergency Team, except to go to the EOF unless directed to do so by the Emergency Director or Shift Foreman if the j Emergency Director cannot be con,tacted. LS.p,w3,
- i. Assist in routing ambulance to pick up any injured personnel. Assure ambulance driver and attendant are
- provided with TLD badge and pocket dosimeter on entry.
- j. Assist Emergency Director in bringing emergency under control.
l I . '4, l 4 's l l 1 i 1 1 . 1 : t . i . S * . . a
- MANUAL SET .
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GEORGIA POWER COMPANY
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HATCH NUCLEAR PLANT . PROCEDURE General Emergency Operations Supervisor PROCEDURE TITLE HNP-4730 _ PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 2 Page 1 f_ - - _ ---- _ - _ _[- f~ g _ _ _ - _ - _ _ _ . alglg). c ------ 3
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Tdme;-~~~~~~~~~ Date SIMEI5ce: -~~~~~'~ 63te: . Z 7 (h O ? E3 f) . ) ' t sw (... , REVISIC:t CH .r:CES MCCE OF .CPERATIO?! OR INTENT AS OF.GCRIDED IN FSAP.: ( )gYes . O(') No . 1 k
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- t' The marcin of safety-------- as d e## .e d in the Technical Scecifications __' -
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e . is not re_duced due to this revision because the revisien does not - - - - = - chance an.v. li..ited .s._afstv - - _ . -systs, settines_.w.hich would all_ow a
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safet'y l,imit 'to be exceedsf or to allost a limitine condition for
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_ _ . . . ^ E.1. Hatch Nuclear Plant mar "v ca /
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Ge x3i aPower a . 1 of 1- h{ [See Title Pace o,<nk } G_ENERAL EMERGENCY - -SHIFT SUPERVISOR A. CONDITION involve actualtial or , Events are in process or have occurred Release can be reasonably whichimminen than the [ for loss of containment integrity. expected to exceed PAG e immediate site area. B. RLFER_Eb'CE ' I
. i FNP-4720. t' HNP-4740.
FNP-1. C. ACTION
- 1. Procede to control room. ensuring t
- 2. Take control of all activities in the control room, l s Assume the duties of the Emergency Assure that those Director actions until in the
- 3. a.
is established. E.O.F. HNP-4740 which can be performed from the control room are accomplished. b, Assure that correct emergency classification has been -i
- declared as per HNP-4720. -
Svytenne l 4. Evaluate actions of Shift -Fort-emaTr and operators to bring emergency under control, l epiruhens is responsible for notification of list and
- 5. The -Stritt Supervisor T'lant Management and NRC as per emergencyfication call other offsite agencies in accordance with shift notiThe actual noti personnel.
procedures HNP-48G1. specifically trained, delegated to other, Consult with the Technical Support Center and Emergency
- 6. Director to determine any outside assistance needed. line to Assure that personnel are assigned to maintain open 7.
NRC, T.S.C. and E.O.F. and inform these groups of , significant plant changes. in Provide information to the Emergency Director to rgency assist { . ' his determination of close out or reduction of the em class, as per HNP-4720. . (
- r .
1 i MANUAL SET j
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GEORGIA POWER COMPANY HATCH NUCLEAR PLANT - PROCEDUME Handlin2_ Exposed And/Or Contaminated Casualties PROCEDURE TITLE HNP-4801 PROCEDURE NUMBER Lab RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 6 Pages 3-7, 9-13 - _.. g_ p___ __ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _ ___y .________ _ __ __ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .r________________. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..________ __ _ _ _ _ ..____________________ r________________. .________________ .________ e HNP-9
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HANOLING E XPOCED AND/OR CONTAMINr.TCD CAGttALTICS A. (yJ!'t.f,35 To provtde procedures for assuring that prompt and effective ftrst atd. m.edical attention and health physics evaluation is afforded to excessively exposed and/or contaminated casualties. D. SaECTy Under all circumstances, unnecessary esposure to radiation should be avoided. Under emergency conditions, the risk of exposure (usually slight) to the rescuer, the first-aid man, or the health physicist, should be balanced against the contribution (usually great) he is making toward the health and safety of the casualty. C. REFER?NCES HNP-4810 HNP-8006 FSAR, Section 13.7.5 10 CFR 20.103. 10 CFR 20.405.
. D. DEFINITIONS For the purposes of this procedure, the following definitions will apply:
~
- 1. Serious Injury - Injury warranting off-site medical support.
- 2. . Acute Exposure - Exposure received over a period of 12 censecutive hours or less.
v,
- 3. Excessive Radiation Exposure - Acute exposure known or suspected to have exceeded the following limits-
- a. Whole body; head and +.unk; active' blood farming organs; lens of e:e; or gonads - 3 rems.
- b. Hands and forearms; feet and ankles 3/4 rems;
- c. Skin of whole body - 7 1/2 rems.
- .2
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- MANUAL SET
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- 4. Excessive Radioactive Contamination - Any of the following:
- a. Detectable radioactivity on or near a wound;
- b. Radioactivity on exposed skin of individual, maasured with beta detecting GM survey meter, shows greater than 10 "mR"/hr at 1" from' radioactivity;
- c. Radioactivity on clothing of individual, measured with beta detecting GM survey meter, shows greater than 160 "mR"/hr. at 1" from radioactivity;
- d. For purposes of admission to Appling General Hospital -
Any external contamination detectable witfi a beta detecting G.M. survey meter;
- e. Inhalation.or ingestion of radioactivity in quantities known or suspected to exceed those allowed by 10 CFR 20.103;
- f. Inhalation or ingestion of unt.nown quantitler of radioactivity.
' ~
5'. Off-site Medical Support - Care, treatment and/or consulation provided by Company Medical Consultant, staff of Appling General Hospital, or Radiatien Management Corporation. E. APPLING GENERAL HOSPITAL CONTAMINATION CONIROL_ POLICY
- 1. Policy Appling General Hospital is prepared to provide care and treatment for patients who are externally contaminated with i radioactivity in their Radiation Emergency Area oni_r. The l hospital defines " external radioactive contamination" as any
! detectabl.e radioactivity deposited on the outer surface of l the patient's body or apparel. [ 2. Procedure l l In conformance with the Appling General Hospital policy, all
- patients considered for transfer from the plant to the
! hospital will be monitored by a momber of the flealth Physics sta f f. - If detectable contamination remains on the patient's body or apparel, the Nurse Shift Supervisor at the horpital l , will be informed that the incoming patient is " contaminated". , t , s-
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- 1. Excessive Radiation Exposure - No serious injury (See Section H) (Normal Hospital Admission *) .
- 2. Excessive Radioactive Contamination - No serious injury (See Section I) (Admission through Radiation Emergency Area, Except if contamination is Exclusively Internal Deposition).
- 3. Excessive Radiation Exposure and Radioactive' Contamination -
No Serious Injury (See Section J) . (Admission through Radiation Emergency Area, Except if
- Contamination is Exclusively In'ternal Deposition)
- 4. Excessive Radiation Exposure - With Serious Injury (See Section K) (Normal Hospital Admission *)
Excessive Radioactive Contamination - With Serious Injury 5. (See Section L) (Admission through Radiation Emergency Area, Except if contamination is Exclusively Internal Deposition).
- 6. Excessive Radiation Exposure and RadEoactive Contamination
( with Serious Injury (See Section M).
' (AdmitJion through Radiation Emergency Area, Except if Contamination is Exclusively Internal Deposition)
G. GENERAL ,PROCEDtIRES
'~
- 1. -In any accident, incident, or unusual! occurrance, when there-is a reasonable probability that an Endividual may have been seriously injured, exposed and/or custtaminated, provide first aid, then make immediate contact with the Company (if radiation Physician and Radiation Managernent Carporation is involved) in the event that an ind'ividual is known or suspected to have been seriously injutr e d , summon the ambulancs needlessly than to jeopardiire a man's life.
'4
- 2. All exposure, contamination, or inj ury incidents, or combinations coming within the scope of this procedure, warrant off-site medical support. Im some instances (e.g.,
a 4 rem whole body exposure) the suivort may simply consist of telephone consulation with the Canpany Physician and(e.g., Radiation Management Corporation. .Im other instances j a burn case), the need for support uny be Far more urgent. Accordingly, Shift 5pr4 man will obtalin a prompt evaluation ' l of the urgency for ob'f f-site medical suppor.t. ) vf<fvuo-
- Monitor the patient for incidental,, but detectable contamination. If contamination is detected, he will be C
admitted through Radiation Emergene,y Area. ,
- 14ANtlAL SET
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- 3. In all cases covered by this procedure, first priori ty will
~
always be given to serious injury. After a victim has been removed From a hazardous araa, care and treatment for excessive raediation or contamination exposure can be deferred without significant harm to the victim, but failure to administer prompt first aid may jeopardize his life.
. 4. The Plant Manager will assure that each accident / incident is investigated, its causes determined, and action taken to prevent its recurrence.
- 5. After each a:cident or incident in which first aid or Medical Room supplies were used, the Laboratory Foreman will assure that these supplies are replenished.
H. EXCESSIVE RADIATION EXPOSURE _- NOT SERTOUS INJURY
- 1. Immediate Action
- a. Exposed individual wi)' take immediate action to
- protect himself from further exposure.
(^ b. Exposed individual will notify S'ift. h Foreman without \ delay. - -
$Prvisw 69pervss.v
- c. Shif t-Focemerr will alert member of the Health Physics
~
I staff and direct him to exposed individual.
- d. Member of Health Physics staff will:
~
(1) Attempt to determine nature and degree of radiation exposure by: (a) Discussion with exposed individual;
' .# (b) Surv'y e of accident / incident area;
'A
,,, (c) Read exposed individual's pocket dosimeter.
(2) Advise Shif t -Ftrreman of the urgency for medical } support. Si e ntar (3) Allay fear and relax the exposed individual.
- 2. Follow-up Action Sqew httyrdflh"j't
- a. Shi f t 50eemarr will noti f y -P+nnt-Mana9ac. Operations {
Supervisor and Health Physics Superin tenden t. l ;
- b. The Plant Manager will: ,.
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Georgia Power d ~~ 4 o r 14 93n Pa,a 1 (1) Notify or authorize notification of Company and
- - Plent. Medical Consultants and Radiation Management Corporation.
(2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if: (a) Personnel whole body exposures suspected to be 25 rem or more; (b) Personnel skin exposure is 150 rem or more; . (c) Personnel e*xtremity exposure is 275 rem or , more.
. (3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph within 24 hours if exposures are 2C% of the above values.
(4) Assure report required by 10 CFR 20.405 is sent to
" NRC within 30 days of accident.
b) ,
- c. Exposed individual will be observed for symptoms, such as nausea, vomiting, fatigue, skin redness, or diarrhea, while awaiting results of consultation between Health Physics staff, P' ant and Company Medical Consultants and Radiation Management Corporation.
- d. Health Physics staff will send exposed individual's TLD l
badge to vendor for EMERGENCY proce,ssing.
- NOTE There is no need for first aid or for urgent transfer of exposed individual to hospital. If determined by med,ical consultation that hospitalization is indicated, individual will be transfered to Appling General Hospital. Unless exposed individual has incidental l
' detectable contamination, he will not be admitted through Radiation Emergency Area. Refer to HNP-424 and HNP-4420 for one hour notification to authorities. I. EXCES9IVE RADIOACTIVE CONTAMINATION - NO SERIOUS INJURY Immediate Action 1.
,a.'
Contaminated individual will withdraw from the 4 immediate area of contamination, take elementary steps
.\ to decontaminate himself (e.g. remove clothes and wash exposed skin), notify the' Shift Foiemen and await {
member o f, Health Physics staf f. S*p"'wr
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- b. Shif t -Foeeman will alert member of the Health Physics k staff and will direct him to contaminated individual.
- c. Member of Health Physics staff will:
(1) Determine the level of external contamination using a G.M. survey meter.
'(2). Initiate personnel decontamination procedures (Refer to HNP-8006).
e (3) Estimate extent of internal contamination by assaying noseblow sa.mple. Soynvoo < (4) Advise Shif t -Foreman of the urgency of need for j off-site medical support. (5) Recover contaminated individual's personnel dosimeters. , 4 2. Follow-Up Action. ggyd Syurvior
- a. Shift Foreman will notify 411ent Manager, Operations l
' (' bepervisor and Health Physicist Radiochemist.
- b. Plant Manager will:
(1) Notify or authorize notification of Company and - Plant Consultants and Radiation Management Corporation.
- (2) Assure that report required by 10 CFR 20.405 (if any) is sent to NRC within 30 days.
- c. Health Physics staff will assure contaminated indi'vidual's TLD badge is sent to the vendor for EMERGENCY processing. .
- d. Heal'th Physics personnel will perform analyses of contamination to determine its isotopic composition (if internally deposited).
- e. The Health Physics staff, with assistance from Radiation Management Corporation, will initiate bioassy program to help determine level of internal contamination and to follow its reduction.
,' f . Subsequent treatment to accelerate reduction of
.J internal contemination may result from consultation be' tween Plant and Company Mndt ral Cc,nsultants and
- Radiation Management Corporation. . .
. MANUAL SET
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If contaminated individual is evacuated to hospital, he will be admitted through the Radiation Emergency Area. Refer to UNP-424 and HMo-4420 for notification to authorities within one hour. J. EXCES3pg_R_ADIATION EXPOSURE ANO RADICACTI'JC CONTAMINATTONlr'g 2 SgijIOt_t3 INJURY
- 1. Immediate Action
- a. Exposed / contaminated individual will protect himself from further exposure /contaminaticn by leaving the hazardous area. .
- b. Exposed / contaminated individual will notify Shift k f:orema by m.g" without j $9mw-delay.
- c. Shift Fo mmen will alert member of Health Physics staff l and will direct him to exposed / contaminated individual.
- d. Member of Health Physics staff will-( 1 )~ Determine the level of external contamination using a G.M. survey meter.
(2)' Estimate extent of internal contamintion by assaying noseblow sample. (3) Determine nature and. degree..of radiation exposure, by:
- (a) Discussion with exposed individual; (b) Survey of accident / incident area;
, (c) Read exposed individual's pocket dosimeter.
hupt da'ur (4 T' Advise Shif t for-eman of the urgency for of f-site l j
,. medical support.
(5) Initiate personnel decontamination procedures (Refer to HNP-SOO6).
- 2. Follow-Up Action .
Sqrasee &cMvoA
- a. Shif t 4:oremstr will notif y P-lent Manager, Operations }
Supervisor and Health Physics Superintendent. 6t., ud d
- b. Plant Manager will: g MANUAL SET
, , _ - ~ _
- m. m , .
m::' 4001 E. I. HATCH NUCLEAR PLANT cawa 'o See Paqo 1 .q'Y, . om Q ~~ GeorgiaPower ch 3 nr 14 Gee-Pana 1 i (1) Notify or authorize notification of Company and
, Plant Consultants and Radiation Management Corporation.
(2) Immediately notify NRC Regulatory Operations,. Region II, by telephone and telegraph if: , I (a) Personnel whole body exposure is 25 rem or 2
- more; (b) Personnel skin exposure is 150 rem or more; (c) Personnel extremity exposure is.375 rem or more. .
~
(3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph if exposures are 20% of the above values. .
. (4) Assure report required by 10 CFR 20.405 is sent to
- NRC within 30 days of accident.
Exposed individual will be observed for symptoms, such f - c. as nausea, vomiting, fatigue, skin redness, or diarrhea, while awaiting results of consultation between Health Physics staff, Piant and Company Medical-Consultants and Radiation Management Corporation.
- d. Health Physics staff will send exposed individual's TLD badge to vendor for EMERGENCY processing.
- e. ~ Health Physics personnel will perform analyses of centamination to determine its isotopic composition (if internally deposited).
- f. The!H ealth Physics staff, with assistance from
- Radiation Management Corporation, will initiate bionssay program to help determine level of internal contamination and to follow its reduction.
- g. Subsequent treatment to accelerate reduction of
= internal contamination may result from consultation between Plant and Company Medical Consultants and Radiation Management Corporation.
- h. If exposed / contaminated individual is evacuated to hospital, he will be admitted through the Radiation Emergency Area. Refer to HNP-4400 for notification to authorities within one hour.
.~
~
MANUAL SET
. . . . . . = - - - . - - - - -.- -
~ ~,. , , - ~
~
E. l. HATCH NUCLEAR PLANT HNP-4801 See Page 1 "t***
' ~~
Sco Paqe 1 GeorgiaPower 9 of 14 i K. EXCESSWE RAOI ATION EXPOSURE _-_ WIT!j SERIQUS INJURY
- 1. Immediate Action
- a. First person who becomes aware of a serious injury will notify Shif t -Foreman. -
{ f Suprvtwv /
- b. Shift Foceman will alert individual trained in first I aid.and member of the Health Physics staff and direct
,them to injured. _
- c. Individual trained in first aid and member of Health ,
Physics staff will: , (1) Administer first aid consistent with nature and extent of injuries. (Refer to HNP-4810). Lgme-(2) Advise Shift Foreman of urgency of need for [ off-site medical support. (3) Recover injured's personnel dosimetry. o (4) Remove injured from area of risk in accordance
. with HNP-4802.
5 9 .cw- . I
- d. Shift Foremen will summon Plant Medical Consultant (Company Physician) and ambulance or, on the advice of the Plant Medical Consultant, will arrange to transport injured to hospital via company or personal vehicle.
Supern w
- e. Shift Foreman will inform Nurse Shift Supervisor at l
- Appling General Hospital that an injured individual will be sent to the hospital for treatnent.
NOTE i Unless injured has incidental detectable contamination, he hill not be admitted though the Radiation Emergency Area. Refer to HNP-424 and HNP-4420 for one hour notification to authorities.
- 2. Follow-Up Action
( p.m, INd 7
- a. Shif t Foeeman will notify P-1-ant Manager, Operations .
( Supervisor and Health Physics Superintendent. c 6oud - i
- b. P-1-ant Manager will: l i, '. d (1) Notify or authorize notification of Company and
', Plant Consultants and Radiation Management Corporation. .-
MANUAL SET
- c. .- .- -_ _ - - - _-_ . _. -. _ _ - - -.a.._ _ _ _ _
* % 4
i E. l. HATCH NUCLEAR PLANT. - , un'-^not Con Pnqa 1
***w ev.s
' K -~
[d Ca* Pane i Georgia Power cs 10 of 14 (2) Immediately notify NRC Regulatory Operations,
- Region II, by telephone and telegraph if:-
Personnel whole body exposure ik 25 rem or (a) more; ., f (b) Personnel skin exposure is 150 rem or more; a (c) Personnel extremity exposure is 3*/5 rem,or more. ,
. (3) Notify NRC Regulatory Operations, Region II, by telephone and telegraph within'24 hours ~if exposures are 20% of the above. values.
. (4) Assure report required by 10 CFR 20.405 is sent to NRC within 30 days of accident". ) ,
^
c. The Health Physics staff will: Determine nature and deg ee of. radiation expos'ure-
., (1) by:
(a) Discussion with injured; f (b) Survey of accident / incident area;,r j [
'l i (c)
Read exposed individual's pocket dosimetec. .- (2) Sent the injured's TLD badge to fthe v9ndor for - EMERGENCY processing. _./ ;
/
L. EXCESSIVk RAOJ,OACTIVE CONTAtjINATION - NITd'SERICUS INJURY,
/
k_e,
- 1. Immediate Action:
- a. Fir.ht person who becomes aware of a serious injury will l
notify Shif t Foremam ' j f Sqervboc7
- b. Shift Focemen wil'1 alert individual trained in first l aid and member of the Health Physics staff and direct them to injured.
- c. Individual trained in first aid and member of Health )-
Rhysics staff will: (1) Administer first aid consistent with nature and f , extent of injuries. (Refer to HNP-4810). ,
.~
MANUAL SET
. ~ ..- - _ ._
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$'- HNP -4no t E. l. HATCH NUCLEAR PLANT **=***'u
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GeorgiaPower A ~~ Cee Pnqn 1 11 of 14 a (2) In accordance with HNP-4302, move injured to
- Madical Room in Control Building and initiate decontamination procedures (Refer to HNP-8000,)
while continuing first aid. IF-injured cannot be i moved safely make him comfortable and await arrival of Plant Medical Consultant or ambulance. Supm.- (3) Advise shif t -Focemen of urgency of need f or { off-site medical support. j } , i Recover injured's personnel dosimel:ry.
-(4)
. (5) Estimate extent of internal contamination by ,
s eassaying a nose blow' sample.
! 5.p mv
- d. Shif t Foceman will summon the (Company Physician), {
ambulance.or, on the advice of the Physician will arrange'to' transport injured to Appling General Hospital via company or personal vehicle.
$.gwyn.r r ,, .
- e. Shift Eopeman will inform Nurse Shif t Supervisor at {
i Appling General Hospital.
- yi !
(" -
, NOTE Emphasize that the injury do_e3 involve radioacti.ve contamination and that injured ss to be admitted to j -
Radiation Emergency Area accordsng to special hospital
" Procedures for Handling Radiatson Accidents". Refer to HNP-424 and HNP-4420 f or one hour notification to authorities.
P l 2. Foll'ow-Up Action: l
. $q gynev-l' a. Shift 4:oceman will: {
(1)'b, Assign member of the Hea18. Physict '*f to [i ' l 3 accompany the injured and grovide cow." a'.e health l A fr
,* physics support to ambulawre and 'hospt cal staff.
' GenenA
(
> (2) No t i f y FLlen-t Manage r , Opemation Supervisor and Health Physics Superintenernt.
ty , '
' b. The Plant Manager will:
- (1) Notif y or authorize notifucationiof Company t Physician and Radiation Management Corporation;
. (2) Assure report required by to CFR 20.405 is sent to MRC within 30 days. ,.,
- MANUAL SET
_ , _ - - - _ _ _ _ - . - . _ _ _ _ _ _ _. ~ _ _ . . 3- __
m,- .,o.. . HNP 41;nt E. l. HATCH NUCLEAR PLANT ww see Paqa 1 , f, wt - 5 4+ g,, p, ,i a 1 12 o f 14 _
- c. The Health Physics staff will:
(1) Assure injured's film badge is sent to vendor for EMERGENCY processing. (2') Initiate analysis of samples of contamination to determine its isoltopic composition (if internally deposited). (3) De responsible for recovery of all radioactive waste from " Radiation Emergency Area" at Appling
. General Hospital. ,
- d. When injured's condition has been stabilized, decontamination efforts will be re-initiated so that patient can be moved to conventional part of hospital.
- e. Subsequent treatment for internal radioactive contamination will result.from consultation between Company Physician and Radiation Management Corporation.
. NOTE Any radioactive material (shrapnel) removed from ~
injured will be recovered, if feasible, and used as aid in determining ultimate exposure suffered by injured.
,M. EXCESSIVE RADTATION EXPOSURE AND RADIOACTIVE CONTAMINATION WITH 5ERIOUS_ INJURY
- 1. Immediate Action
- a. First person who becomes aware of accident / incident will notify Shift Fbrem,an. (
b. J9-4 %p,< = n.- Shift Eoreman will alert individual trained in first ( aidand member of the Health Physics staff and direct l them to injured.
. c. Individual trained in first aid and. member of Health Physics staff will:
(1) Administer first aid consistent with nature and extent of injuries. (Refer to HNP-4810). (2) In accordance with HNP-4802, move injured to j Medical Room and initiate decontamination 4 proceduroc (Refer to HNP-ROOC.) while continuing first aid. If injured cannot be moved safely, make him comfortable and await arriva1 of Plant l
- i Medical Consultant or ambulance.
\ . MANUAL SET
-- . - - . ~ . - _ m--. _ _ - _ _
l
\
l
-.. .mu - ~ i E. l. HATCH NUCLEAR PLANT im- Ano t !
Soo Psiqa t "tna w vus <g { Cae Paca 1 GeorgiaPower d ~~ 13 of 14
$afu vr>ee (3) Advise Shift _Foceman of urgency of need for i off-site medical support groups.
(4) Recover injured's personnel dosimstry. (5) Estimate extent of internal contamination by
. assaying a nose blow sample.
tEIE
. Emphasize that the injury _does involve radioactive contamination and that injured is to be admitted to Radiation Emergency Area according to special hospital " Procedures for Handling Radiation Accidents". Ref er to FWP-240 and HNP-4420 f or one hour notification to authorities.
- 2. Follow-Up Action:
% peakse
- a. Shif t -Foreman will:
m
}
(1) Assign member of the Health Physics staff to accompany the injured and provide complete health physics support to ambulance and hospital staff. 6onsl (2) Notify P4 ant Manager, Operation Supervisor and l Health Physics Superintendent.
- b. The Plant Manager will:
(1) Notify or authorize notification of Company Physician and Radiation Management Corporation; (2) Immediately notify NRC Regulatory Operations, Region II, by telephone and telegraph if:
. v, (a) Personnel whole. body exposure is 25 rem or more; (b) Personnel skin exposure is 150 rem or more; (c) Personnel extremity exposure is 375 rem or more. ,
(3) Notify PRC Regulatory Operations, Region II, by - telephone and telegraph within 24 hours if
. exposures are 20% of the above values.
t (4) Assure report required by 10 CFR 20.405 is sent to NRC within 30 days. .- 4 MANUAL SET , . - ~ - . . _ ._ .-_ -.
. ,,.. 4 E.1. HATCH NUCLEAR PLANT e -^90t
'""M#'"'
F, e. as P .3 et rn 1
, c, (.~
v.,, 4 ~~ ct.4 P a .,a 1 GeorgiaPower ca 14 of- 14
- c. The Health Physics staff will:
(1) Assure injured's TLD badge is sent to vendor for EMERGENCY processing. (2) Initiate analysis of samples of contamination to determine its isoltopic composition. (3) Be responsible for recovery of all radioactive waste from " Radiation Emergency Area" at Appling General Hospital. (4) Determine nature.and' degree of radiation exposure by: (a) Discussion with injured; (b) Survey of accident / incident area;
(c) Read exposed individual's pocket dosimeter.
, d. When injured's condition has been satbilized,
. decontamination efforts will be re-initiated so that patient can be moved to conventional part of hospital.
- e. Subsequent treatment for internal radioactive contamination will result from consulation between Company Physician and Radiation Management Corporation.
- f. Any radioactive material (shrapnel) removed from
- injured will be recovered, if feasible, and used as aid
- 'in determining ultimate exposure suffered by injured.
l l 1 o
- w t
l l - l .2 MANUAL SET
...,_ . - ~ __ _ __.- . .
GEORGIA POWER COMPANY ! HATCH NUCLEAR PLANT . l PROCEDURE Naturally Occurring Phenomenon PROCEDURE TITLE HNP-4858 PROCEDURE NUMBER Lab. RESPONSI LE SECTION SAFETY RFLATED ( X) NON-SAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAC R
/
Page 1,2,6,9 & 10 o s 1
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PROCED, URE. .t/O. Hr.:P- ( W) s. t' - s Revision No. *-
- _- _ e
_ _ - _ . -- - _J RFC'_ C.TFD__G_Y -- -- OfPART GIT t-6,10 ..PPrict.'.:.t. Name; Dest e
- Si gn.. t u ra: .. Date:
_ _ . , [l b' - I_--_e_s_ '. 8 i
.'. REVISICM CH.".r:GCS MOCE CI.CPERATION 03 INTENT AS DEGCRI'OED IN FSAR: .
i ( )gYes . ()() No -
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- ___ue_s_t_i_o_n _a.s. _e x_o_l_a_i n_e_d_ _b _e l c_w ._ _ ____ ________________' __ ____________
I 1_.__Th_e__o_ro_S _a)._il_i_t_y_ o f .gsc.u_r_r.=..~2,._a.n.ds.t.h.e rAny.,o_u_e_n_c_es__.o f__a n__a_c_c_i d_e_n_t____ i
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_o_r__ mal _f_u_n_:ti_o_n_o__f _e__e.S_u_i _t _f_ :._o r.t_a_n_t__to _s_a f_e_ty -__ a _re__n_o_t _i_n.c._r_e a_s_e_d__ --.
. I, abo
-= =_v.a_t.h.aL=. v. a. n.=_1' 1. u.d_i n'r.$u . :C_.3_(u.a._.t0._tia
,a S.a - .rt_a 0na.S_hi_cusa_ _ _ _ - - - _
. the revis.i.on__does
_ _ _ _ n_o_t_ch'a_._:e__the ourcos_ e_ or oe_r.f._o_r _a_n_c_e_o_f__the a system. __
~. -
.. . . . . . .. .. .... . ~
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The nossibility of an actifs _t__o_r_nalfunction of a different tvoe ? _ - . . . . ...e,_.._- ._ : . _ . . . . . . .~.m.........,.. .
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't
- .. than an_a_lv_:ed in the FSA_S. d:es__not . .
_ result from_ this chan_c_e__because
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the sys_t_e_ u rescon_ds..and _is .. .::e.r.ated as before the chan.ce. -- i
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- I
<i u - 3. The ma_r_ci_n_o_f__s_afe_t.y ._
as_d_e_#f_r_.e_d_in the Technical Scecifica_t_i_on_s -- - -- is not _r_educ_ed due to th_i_s_r_e_v_i.s. ion because the_ revision does not . ( .
-- . chance __a_nv limited safity s st_e t sett'inos which_wo_u_ld__al_l_ow a __
. . f
- safet*v- _1,.*ni_ t to be exc==_'=' er to allow a-l.i.mitine. co_n_d.i. tion fo__r__ _ .
6
._ . - ooerations to be exceeds' a_s _ stat._.ed in Technical Scecifications.
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H N P-Spe' Ti.tle Page d .p Georgas Power c_: .. . 1 of 12 {( _. She Title Pana_ NATURAL.LY OCCURRTNG PHENQtjFJOrj NOTE (This procedure supersedes: HNP-43OO, Revision 4 approved
- 7/25/80; HNP-4301, Revision 4 approved 9/18/79; HNP-4302, Revision 1 approved 9/18/79.) .
A. CONDITION: ear 4THGUAKE : seismic activity, and ground j, ; The plant accelerographs indicate:or outside sources report ground motion. motion is felt, lf B. OPERATOR _ ACTIONS , i
- 1. For a seismic shock with only annunciator D076 (Seismic Instrumentation Triggered) in panel H11-P657 and the RED INDICATOR LIGHT (L51-OSOO1) on the TIME HISTORY ACCELERGRAPH (L51-RGOO) in panel H11-P701 which is less than OBE (0.08g),
continue to operate and proceed with plant inspection. Follow Figure 1. Declare a NOTIFICATION OF UNU5UAL EVENT m EMERGENCY and refer to the applicable HNP-4400 series procedures for the appropriate response. (.
- 2. For a seismic shock with annunciation as stated in B-1 and any of the following:
- a. Unit I (1) Seismic peak shock recorder _high G 1evel alarms.
(D070 in panel H11-P657 is set to actuate when 100% OBE of 0.089 vertical has been exceeded).
~
NJO Dne or more ambar_ lights on peak shock j annunciator panel (L51-RGEO on panel H11-P701) will be on. These annunciator lights are set for 100% OBE level at 4
- frequencies and 3 directions (North /
South, East / West, Vertical). This info will be recorded in C.1.A.
+ b. Unit II
. (1)
Seismic peak shock recorder high G 1evel alarms.
. (DO68 in panel 2H11-P657 is set to actuate when 100% OGE (.03g) vertical has been exceeded.
a d 9 MANUAL SET 5
'i .. . - . . .
e-. m p .
._ __ _~ -. __ ._
"a a ~"' ~
1:r;;5. E. I. Hatch Nuclear Plant llNP. 4Rr,g
'u+o= w Sne Title Page 7'
- '1
... Georg. ia Power a@.g ~.<~ l 2 of 12 i See Title Paqe NOTE One or more red lights on peak shock j annunciator panel (L51-R620 on penal H11-P701) will be on. These annunciators are set for 100% OBE level for 4 frequen-cies by 3 directions (12 total) (North / .
South, East / West, Vertical) This info will be recorded in C.1.A. (2) " Seismic switch tripped" alarm (D069 on panel 2H11-P657) which is set at OBE level of .08g. Shut down the affected unit (s) and declare an " Alert" emergency. Follow Figure.1. , Refer to the appli cable HNP-4500 series procedures for appropriate response. NOTE If any of the situations-in section 2 occur, the operator should play back the Time History Recorder tapes to determine the actual maximum g acceleration magnitude. (For
- instructions on retrieval of seismic data, see HNP-1-3980 M
- section G.2.)
' 43) For a seismic shock with annunciation as stated in B.1 and B.2 above and the maximum g level measured by the time / history accellograph recorders is greater than OBE le'vels (0.159), shut down the affected unit (s) and declare a site area -
emergency. Follow Figure 1. Refer to the applicable HNP-4600 series procedure for appropriate response. (4) For a seismic shock resulting in massivo damage to the ECCS system, refer to the applicable HNP-4700 series procedures for appropriate response. (5) Notify Plant Management. . C. SUBSEGtENT OPERATGR ACTION l
- 1. A post earthquake instrumentation review will be conducted l as follows:
- a. Record the Peak Acceleration recorder lights (Rad and Yellow) on Data Package 1. Have three qualified operators verify the lights before n? setting the panel.
b .. Check the feedwater to steam flow for a mismatch. ' s MANUAL SET
--. ~ E. l. Hatch Nuclear Plant h== sh HN P- 48GU
's ww w 2, p See Title Page ccorgias rower s .. _
Gee Title P.'qe 3 of f2
., c. Check the applicable neutron range monitors for abnormal readings.
- d. Check all systems for abnormal power changes. {
- e. Check the drywell for temperaturas, humidity, pr, essure and the sample system for abnormal activity levels.
- f. Check the drywell sumps for high level and/or flow.
- g. Check all other equipment drains and sumps for high i level and/or high flow rates. .
- h. Check th.e torus water level recorder for high or low level.
- 1. ' Check all area radiation monitors for excessive activity levels.
J. Check tNe 4160 volt and 600 volt auxilliary equipment for trip 3.
- k. Check the turbine generator instrumentation. .
(
.2. Notify the Test Shop to do,each of the following as required by Figure 1.
- a. Retrieve record plates from the Peak Shock Recorder (L51-N105) per HNP-1-5631 and record data. Install new record plates to record after.. shocks.
- b. Retrieve record plates and tapes from the Teledyne PRA-103 Peak Recording Accelerometers per HNP-1-5625 and Engdahl PAR 400 Peak Acceleration Recorders per HNP-2-5G26. Install new , record plates and tapes to record after shocks.
- c. RekrievemagnetictapesfromtheTimeHistory Ac'celerograph recorder, L51-R600, per HNP-1-3980. Make hard copy records and install new tapes.
- d. Restore all instrumentation to operable status with 24 hours. (Unit 2 Tech. Specs. 4.3.6.2.2).
- e. Recalibrate all seismic monitoring instruments actuated during a seismic event within 30 days. Notify Kinemetrics, Inc. (telephone 213-795-2220) to perform calibration of the Time-History Accelerograph System t
and the Peak Shock Annunciator System (Unit 2 Tech.
*- . Specs. 4.3.6.2.2).
9 y e
' MANUAL SET
._ ~3
.. 4h E.1. Hatch Nuclear Plant HN P- 4H9R See Ti.tle Page A 7 M '
i.... CCOlylaPOWCI'UA r.c.t o 4 of 12 __S,ep Title Paqa
- 3. A plant inspection should include but not be limited to the following:
- a. In's'pect the main steam lines and turbine ertraction steam lines for damage.
- b. Inspect the condensate piping and pumps for leaks and damage.
c ., Inspect the feedwater piping and pumps for leaks and damage,
- d. Inspect the turbine oil system for leaks or damage. .
- e. Inspect the RWCCW and ser'vice water for external leaks. Check for an internal leak by mon'itoring the l j
RBCCW surge tank level. I
~
- f. Inspect the intake structure and associated equipment for damage. l
- g. Inspect the off-gas stack and equipment for leaks. I 4
- h. Visually inspect the diesel generators and their switchgear to assure the units are intact. Perform the routine surveillance test to prove the system is operable. Tie bach diesel generator onto its bus and Isolate its bus from the syster.,one at a time.
Minimize operation of the diesel generator in parallel with the system because a major transmission line fault, which is probable during this event, could cause - damage to a parallel diesel generator. i." Inspect the switchyard for damage. 1
- J. Inspect the turbine pedestal for damage.
- k. Inspect instrument racks and control panels for damage.
9,
- 1. Inspect CSCS components -for damage.
i m. Inspect fuel pool for damage. I
- n. Inspect all plant batteries for damage.
i : 4 o. Inspect instrument and service air system.
- p. Inspect plant communications for damage.
[ 45 Evaluate the post earthquate instrumentation review and , }( l { plant inspection,
~
I i . - \ i l 1 . i e MANUAL SET
- i i ... -
l , -
== E. l. Hatch Nuclear Plant Ms e ~'
HNP- 48G8 ~ S2e Ti tie Page m v~om w Georgia Power k
't * ,
o... n- .. - See Title Paqe 5 of 12 _.
/
- 5. Completer analysis of seismic data.
NOTE-The results of the plant inspection will immediately be reviewed by the Plant Review Board and appropriate surveillance testing will be specified. A special report must be submitted to the NRC within 10 days. D. REFERENCES
- 1. S-40827 Seismic Instrumentation Earthquake Response Manual
- 2. Unit 2 Technical, Specifications - para. 3.3.6.2
- 3. HNP-1-3980 Seismic Instrumentation F.T.txC. , Section G.
Restoration of Seismic Instrumentaticn and Data Retrieval
- 4. HNP-1-5625 Calibration of Teledyne-GeoTech PRA-103 Peak-Recording Accelerometers
- 5. HNP-1-5631 Peak Shock Recorder Calibration
.6. INP-2-5626 Calibration.of Engdahl PAR 400 Peak
^
..cceleration Recorders.
'4 s-l t
.a l ..
MANUAL SET
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".PN % =o ,oin e s.gm m .c= =
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==>6 E. l. Hatch Nuclear Plant ---
HNP- 4R5R Gee Title Pago m vem. w Georgia PowerQs
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See Title Pace 6 of 12 E. q_OWITlW: TGRNADO The plant shall normally be alerted by outside communications and/or local indications of a tornado condition in the area which may disrupt the transmission system or present a hazard to-the station facilities. The plant will remain at full availability unless dictated to be otherwise by deteriorating conditions. As evaluated by supervision.
. F. OPERATOR ACTION
- 1. Thoroughly inspect the plant for loose materials which may be blown about.
- 2. Instruct contractor personnel of the event and advise them to commence preparations for the securing of construction materials and equipment.
- 3. Remove or secure all outside scaffolding and swinging stages.
- 4. Close and secure all Reactor, Turbine Building, Switchyard and Off-Gas Filter Building doors.
l
- 5. Plant personnel,shall seek refuge within buildings and
. report to their supervisors for specific instructions. ,
- 6. Perform routine surveillance test of the standby Diesel-Generators in anticipation or a potential off site i power failure, if a tornado has been sighted in immediate area or known to be headed in direction of site. -
- 7. Arrange for additional assistance to provide continuous inpections of buildings and roofs.
- 8. Install door braces on all roll-up doors equipped for braces.
- 9. Notify p,lant management. .
- 10. For any' tornado onsite causing significant damage affecting plant operations, refer to applicable HNP-4400 series procedures for appropriate response.
- 11. For any tornado striking the facility incurring damage affecting safety systems, refer to applicable HNP-4500 series procedures for appropriate response. .
I
- 12. For any tornado or sustained winds in excess of design level r
(300 mph), refer to applicable HNP-4600 series procedures
; for appropriate response.
.i l
l l MANUAL SET
-, i
"~~~' E, l. Hatch Nuclear Plant aw =. -
HNP- 4R58 S2e Titto Page mrma m Georgia PowerQs x3-See Title Page . 7 of.12 G. SUBSEGUENT OPERATION ACTIOiJ
- 1. In the event buildings have been damaged or the reactor power level has become abnormal, internal damage to the process systen may be. suspected. Proceed with an instrumentation review and plant inspection per HNP-4858.
section C.
- 2. Perform continuous building inspections.
- 3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow the-applicable annunciator response or emergency procedure.
. 4. If the plant is not damag,ed and is operationally intact following an alert, resume normal operations and inform Load Dispatcher.
. H. CONDITION: HIGH WTNOS (HURRICANE)
The plant shall normally be alerted by outside communications and/or local indication of high wind conditions which may disrupt the transmission system, or present a hazard to the plant facilities. The plant personnel shall prepare for plant load
, reduction as may be required. In the event winds reach hurricane
( velocitiet (sustained wind speed greater than 75 mph) near'the plant site and/or a plant load rejection is imminent, notify the load dispatcher and reduct to load as directed. NOTE After a hurricane warning is received, dispatch an operator to the plant meteorological station and place the wind speed transmitter speed selector switch in 100 MPH. Note that the control room recorder indication will have to be multiplied by two. Notify the Laboratory personnel of time change is made. I. OPERATOR ACTIONS Thoroughly inspect the plant for loose materials which may 1. be blown about.
- 2. Instruct contractor personnel of the event and advise them to commence preparations for the securing of construction equipment and materials.
- 3. Remove or secure all outside scaffolding and swinging stages.
; e 4.. Close and secure all reactor, turbine building, switchyard . and off gas filter building doors.
4 MANUAL SET m ...
.* _ . , , = , _ _ _ ,
m emae=. * ~ _ _ __ ,__ _ __ l
ia ->< E. l. Hatch Nuclear Plant ~ ~ ~ < = HNP. 489R atwoa ao Sao Title Page L
- 4 'l'
,... Georgia Power s{ m..
See Title Pace 8 of 12
- 5. Plant personnel shall seek refuge within the plant buildings
< and report'to their supervisors for specific instructions. f I-
- 6. Perform the routine surveillance test of the standby emergency diesel generators in anticipation of a potential ,
off-site power failure when winds reach hurricane velocities - j near the site. l t
- 7. Arrange for additional assistance to provide continuous ,
inspection of buildings and roofs. Ofcc0lt.%
- 8. At the direction of plant management or the -Stuf4 Supervi sor l i
reduce power to 25% rated when winds reach hurricane velocities near the site and a plant load rejection is imminent. .
- 9. Install door braces on all roll-up doors equipped for braces.
- 10. Notify plant management.
- 11. For any hurricane (wind speed greater than 75 mph) onsite causing significant damage affecting plant operations, refer
- to applicable HNP-4400 series procedures for appropriate response.
- 12. For hurricane winds near design basis level (300 mph), refer to applicable HNP-4500 series procedure for appropriate response.
- 13. For hurricane winds greater than design level, refer to applicable HNP-4600 series procedures for appropriate response.
J. SUBSEGUENT OPERATOR ACTION
- 1. In the event buildings have been damaged or the reactor power level has become abnormal, internal damage to the process system may be suspected. Proceed with an instrumentation review and plant inspection per HNP-4858 section ,C.
- 2. Perform continuous building inspections.
- 3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow the applicable annunciator response or emergency procedure.
- 4. , If the plant is not damaged and is operationally intact
; following an alert, resume normal operations and inform Load Dispatcher.
l l
.i MANUAL SET l -- -.
eA E. I. Hatch Nucicar Plant *cwire o !4 HNP- 4858 . li u v~e% ~o See Title Pege Powerka
~1 'h'
... Georoia O
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See Title Pago 9 of 12 _ K. CONDITIOril_EL_OQO_ The plant shall normally be alerted by outside communications !
- and/or local indications of river elevation greater than or equal to 88.6 ft Mean Sea Level which may present a hazard to the plant .,
facilities. The plant personnel shall prepare for plant load - ! reduction as may be required. L. OPERATOR ACTIONS
- 1. For (50 year)' flood causing significant damage affecting plant operations, refer to applicable HNP-4400 series '
procedures for appropriate response.
- 2. For flood near design level (greater than 100 ft. Mean Sea
- Level), refer to Applicable HNP-4500 series procedures for appropriate response. l
- 3. For flood or hurricane surge greater than design levels (greater than 120 ft. Mean Sea Level), refer to applicable
'IflP-4600 series procedure for appropriate response.
M. SUBSEGUENT GPERATOR ACTION ( In the event bu'ildings have been damaged or the reactor 1. power level has become abnormal, internal damese to the < process system may be suspected. Proceed with an instrumentation review and plant inepection per HNP-4858 section C.
- 2. Perform continuous building inspecti[3ns.
- 3. If the plant instrumentation review and plant inspection evaluation indicates damage to the process system, follow l the applicable annunciator response or emergency procedure.
- 4. If the plant is not damaged and is operationally intact followirig an alert, resume normal operations and inform Load Dispatcher.
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a GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE
. REPAIR
------- A. ND CORRECTIVE ACTIOP_J FOLLOWING A RADIOt OGICAL_FMFRGFNCY PROCEDURE TITLE HNP-4RE.6 ~
PROCEDUii5 AU555R LAB RESPONSIBLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
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74 G ' 7/n " - - 3 ,, v. _ _ _ ll g REVISICM CHANGCS MCCE C' .CPERATION OR INTENT AS DEGCRIGEO IN F3AR:
. ( ) \Yes GC ) No -
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CHANGE ItNCtNES: . l ' ,
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is not reduced due to this revision because the revis.i.on does_n.o_t___ --
. chance _a_n_v li:nited safety svsta ' settines which would allow a i
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C.1. F1dLUll INUUlUaf t'1801 M'octovat ko . HNP. 4RG6 Smo Title Pego mmio= =o rb S 't 's' om Georg.a Power n ,m See Titto Page 1 of 7 fp REPATR AND CORRFCTTVE ACTTON FOLLOWING A RADIG1,0GTCAL EMFRGENCY A. PURPOSE The purpose of this procedure is to provide guidance to enspre that doses to workers performing repair and corrective action functions during an emergency situation are maintained as low as is reasonably achievable,
- s. BgEgegNCES
- 1. NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power PIants."
- 2. EPA-520/1-75 001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents."
- 3. NCRP #39, " Basic Radiation Protection Criteria."
- 4. HNP-8002, " Radiation Exposure Limits." '
- 5. HNP-4812 " Emergency Exposure Guidelines" C. ACCg@SJONTROL -
L
- 1. During an emergency, access to the protected area will be controlled. In addition, access to all areas beyond C-52 will require specific authorization and will be limited to personnel who are needed to provide specific functions in the Turbine and/or Reactor Buildings. An example of the ,
personnel who will receive authorized clearance to these l areas are: Control Room personnel, personnel on the fire l I brigade, RET members for the purpose of internal surveys and personnel required for repair and corrective action functions. A list of Control Room pe'rsonnel requiring access shall be provided by the TSC manager or his , designee. . All other personnel shall require authorization from the OSC manager or his designee after consultation with the TSC manager. Access.for personnel to High Radiation Areas shall have more stringent requirements to be discussed in a later section of this procedure. l t t ( -? v l **
.1 MANUAL SET l
--------m: _
-t E.1. Hatch Nucicar Plant r=umac ao HNP. 4866 anis.o= ~o Sao Titic Pago Georgia Power d . .,
See Title Page . E of 7- .
- I t 6 D. EXPOSURE LIMITS AND AUTHORT7ATION i
- 1. All exposures to personnel are to be kept as low as is !
reasonably achievable. This pertains to all personnel who are required to remain on site during an emergency situation
- for the purposes of accident recovery. i
- 2. Exposure to the whole body shall be limited to 300 mrem / week. Any expected whole body radiation eFposur.e above 300 mrem in any one week shall necessitate the completion of HNP-8002 Form 2 " Authorization to Exceed Administrative !
Exposure Guides" by the indicated parties.
- 3. Exposure to the whole body shall also be limited to 1,250 mrem / quarter. Any expected.whole body exposure in excess of 1,250 mrem in any one quarter shall also necessitate the completion of HNP-8002, Form 2 " Authorization to Exceed Administrative Exposure Guides" by the indicated parties. ;
a I
- 4. In some instances during emergency conditions it may be
~
necessary to exceed 10CFREO Exposure limits. In such instances, refer to HNP-4812, " Emergency Exposure , t
~ Guidelines" for guidance. The Emergency Director, or his designee, are given the authority to permit these exposures.
t
- 5. Cxposure of emergency workers to any level is justified ;
only if it is determined that benefits to society are being achieved and efforts are being made to keep exposures ALARA. E. CONDITIONS OF EYPOSfEE t
- 1. Persons performing the planned actions should be volunteers '
broadly familiar with exposure consequences.
- 2. Women. capable of reproduction shall not take part in these actions. j
- 3. Internal dxposures shall be minimized by respiratory 6 protection., and contamination controlled by use of ;
l protective clothing. . t l
- 4. Workers that are to perform the required actions should be l
well trained in the jobs that they will be performing to cut down on the amount of time they need to spend in the area (s). i F. RAOIATION WORK PERMTTS ; ! 1. Whenever practical, an RWP should be initiated before any work is performed. 7 4
.. i l
MANUAL SET l u.... i >w_ _- 2__ _ _ _ _ _ . _ . _ _ . ~ . , - .--..--.-# . -w . = ~- .e 1 .-
c, . . Aa iiUCIUdr Mant %"i w , HNP. 41W.6 l
. . , S2a Title Pag 2 atws'o= =o - - '
... .... Georgia Power d .. See Title Page - 3 of 7 ' '
- 2. The most current survey information available for the area in which the work is to be performed is to be used unless conditions exist or there are indications that the radiation levels in the area have increased significantly. '
- 3. Area Radiation Monitors (ARM's) are to be used to the exten't possible in predicting general area radiation levels.
- 4. If there is not enough information regarding the radiation levels in the areas (s) to be entered or new up-to-date information is deemed necessary, the TSC Manager, after consultation with HP Supervision, may elect to send an Internal Survey Team, comprised of RET members, into the area to determine the radiation levels.-
t
- 5. All survey information should be placed on the appropriate Routine or Special Survey Map (See HNP-8012), whenever practical. The use of these maps will aid in the routing of workers in the area, determining stay times and making man-rem estimates.
- 6. All areas that are surveyed are to be surveyed for Beta dose 4
rates in addition to Gamma dose rates. All smears that are taken are to be counted for Beta activity as well as Gamma activity. kw
- 7. It may be necessary, in some instances, that the work needs '
to be done immediately. In such instances, the TSC manager, i
~
after consultation with H. P. Supervision, may elect to ! appoint an internal survey team, or member, to accompany the ', . repair and corrective action team, to survey the area while the work is being performed. In such instances, it may also be necessary to complete all documentation at a later time.
- 8. " Low volume and/or High volume air samplers are to be used to the extent practical in determining airborne
, concentrations. In addition to these air samplers, CAM's '
and CIM CAM's will be used where appropriate in airborne concentration determinations. Isotopic compositions should also be per, formed to evaluate radiciodine concentrations. G. EXPOSLJE CONTROL
- 1. No personnel, other than Internal Survey Team members, may enter an area where dose rates are not known, except as stated in F.7 above.
- 2. Personnel shall not enter areas where dose rates are beyond the range of instruments being used. '
^
4 . ,
' ~
MANUAL SET I m =- _:_ __ -- m
HNP. 4HG6 Sao Title Pcgs u m.o= ~o J "/ '" om Georma 0 Power is ~ ~ . = See Title Page 4 of 7
- 3. Personnel shall be equipped.with dosimeters capable of
. measuring anticipated doses. This shall include, but not be limited to:
- a. Two direct reading pencil dosimeters for whole body exposure: ,
- 1. O-200 mR and/or 0-5 R; and
- 2. O-20 R
- b. A Thermoluminescent Dosimeter (TLD) to permanently record whole body exposure.
- c. Extremity dosimeters when the extremity exposure rate is likely to be four (4) times the whole body exposure rate and the extremity. exposure rate is likely to be 400 mrem /hr or greater. The extremity dosimeter (s) is/are to be worn on that part of the body that is likely to receive the exposure.
- d. A digital alarming dosimeter (0-10 R) with a predetermined alarm set po. int. The digital readout and
, the alarm will enhance the worker's knowledge of his accrued dose.
(' 4. Protective clothing shall always be worn by workers entering areas for,the purposes of repair and corrective action. The minimum dress requirements shall be:
- a. One pair of cotton gloves
- b. One pair of rubber gic.ges
- c. One pair of cloth bootteh
- d. One pair of rubber booties In the event that more stringent requirements are specified on the RWP, or by H. P. Supervision, then those requirements shall prevail.
i
- 5. Respirators shall be worn as appropriate. In all cases where airborne contamination is anticipated, personnel shall be fitted with pressure / demand Self Contained Breathing Apparatus (SCBA) as a minimum.
~
- 6. Potassium Iodine (MI) tablets should be administered to all personnel who are likely to inhale 20.0 uCi'O.E. I-131 oc l greater. This decision is to be based on the-results of previous Whole Body Counts and the projected exposure. HP Supervision shall make the final determination on wheihar or not K1 should be issued.
( . MANUAL SET w ...
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O a Power n I See Title Page 5 of 7' l ( 7. All workers upon leaving a high airborne radioactivity area will be decontaminated as necessary and then given a whole body count. If indicated, other bioassay methods may be ' used in addition to the whole body count.sY fH. ALARA CONSIDERATTONS , 1. In order to maintain radiation exposures to personnel performing repair and corrective action functions during
. emergency conditions as low as is reasonably achievable, the following steps should be performed, whenever practical:
- a. Prebriefing-All workers that are to be sent into High
) Radiation Areas should.be made aware of the dose cates in the area, stay times, and airborne concentrations.
All workers should be familiar with exposure I consequences. An attempt should be made to estimate the total man-rem exposure of the prescribed action, based on radiation levels and man-hour estimates, and all attempts should be'made to keep exposures below this estimate. Some of the methods that may be used to
, accomplish this are as follows: ;
(1) The workers should be informed of the magnitudes and loc'ations of significant radiation sources at ( ,
.the task location or accesses, and should also be informed of low exposure waiting areas, if any,
'that are to be used when necessary. Using the most current survey information or anticipated levels, the workers should be informed of the best way to reach their destination (i.e., the route that would result in the lowest exposures). Since the workers will most likely be wearing SCBA equipment, consideration should'be given to reducing the amount of time needed to reach their destination since they will only have 30 minutes fof supplied air. .
The personnel in attendance at the pre-briefing
should be; the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor or Foreman; the n
OSC Manager; cnd a Shif t Supervisor or I:oeTuss. Opcoc ,.,a uye'!du. , (2) A tool list should be developed prior to entry, such that a worker is well equipped to perform the , required actions. Since a lot of time will probably be used in reaching the destination, care p should be taken to reduce the number of trips
;W g needed. ,
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.tf (3) Consideration should be given to the use of special tools that may reduce the amount of time , ;
spent in the area, orLtdqt will enable the worker to handle " hot" pipes or" valves remotely. These
~
should only be used, however, by workers who are f familiar with their operation. l a , 7 (4) -Consideration should be given to the prefabrication of systems outside to the High Radiation Areas which would result in less time 'i being spent for the required, action. ,
~s f (5) Consideration should be given to the removal of systems to be worked on from highiexposure rate areas to low exposdre ratefareas, if practical, to further reduce exposures td. workers.
l e Y. . (6) Consideration should'be given to the use of 4-communication systems (such as walkie-talkies, headsets, etc.) so tnat any prob' gems or f difficulties that are. (pcountered may be related l
- back to supervisory' personnel for '
discussion or : comment. -
; f e
- (7) Workers that~aresto perform the required actione. '
.should be well trained;in the job (s) that they W / .
will be performing in^ order to. cut down on the r ,f j amount of time-they need to: spend in the area (s'). i Job Execution-Although prebr,iefing is an essentiab t)ep b. in maintaining radiation exposures-to station personnel, ALARA, implementation of exposure controls duringithe,#,.u execution of a job is the primary rpechanism for , ,,% maintaining radiation exposures as ilow as is reasonably" achievable. Some e xmpl6s'cof exposure controls methods that should be utilized are'as follows!. j 1 (1)>,In order to reduce internal doses, the proper - respiratory protection equipment must be worn by 1 all persons who have the potential of inhaling airborne radioactive materials. . (2) Protective clothing needs to be worn to reduce V the liklihood of skin contamination. (3) Time, distance, and shielding are the most effective ways of - reducing exposures and must be . utilized where- and whenever possible. p 1 s e Y
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. (4) Proper communication between workers in high
, j radiation areas and supervisory personnel who are i
fY monitoring the operations from other locations is essential in identifying problems' incurred auring execution of the required actions. This will be o enhanced through the use of communication systems such as walkie-talkies or heatsets. .
- c. Post-briefing-Performance of this stop will help in
' planning futu're jobs.by using a type of " lessons
. learned" approach.
.The personnel in attendance at the post-briefing should
~L be: the work crew; a Lab Supervisor or Foreman; a Maintenance Supervisor,or Foreman; the OSC Manager; and lb
- a Shif t Supervisor or -Foreman.-
Cp4%%3 F 7a.~.W. (1) The importance of this step stems from the possibility that it may become necessary to perform subsequent.similar actions during
. emergency conditions.
4
., (2) Any problem or recommendations that arise should be dc.cumented for the purposes of planning and p . execution of subsequent actions. _ These recommendations should be expressed by anyone
. involved in the opirration.
(3) The degree of success.or failure should be reviewed upon completion of each job and should also be documented for further use.
-? !
- I. EFFLUENT RESEASES ,
f NOTE < f Due to the increased likelihood of fuel failure during an accident condition particular care must be taken in !
, analyzing.all releases. In addition to performing isotopics _
on a GeLi detector, all gaseous effluent' filters must be O f measured for Beta emitters,particularly Sr-90. Refer to i i appropriate HNP-7000 series procedures for analysis. l* s lt l. A .t , 'j gt .
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l l GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE S e c u,r.,i t y Alert - 02 erating Personnel _ PROCEDURE TITLE HNP-4901 PROCEDURE NUMBER Lab RESPONSIDLE SECTION SAiETY RELATED ( X) NON-GAFETY RELATED ( ) APPROVED APPROVED REV. DESCRIPTION DEPT. PLANT DATE HEAD MANAGER 4 Pages 1 & 2 , ______.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _t . ______, [ /_ M___ ___,J_..[ (f ... m HNP-9 , MANUAL SET t _ y e
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Name; Dete; Signature: .. Date: j lh- r h IY Gp F~A
. . REVISIC! CH.",NGCC MCCE OF.CP!.RATICtl DR INTENT AS CEGCRIDED IN FSAR: . !
( ) ,Yes . (X) No --
.. CHANGE INVCt.VES:. ,
. ' . ( ) An unreviewed Safety Guer. tion (- .) Tech. Specs. - (b ) Neither
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or malfun: tion of ecui: ar.t 3 :Ortant to safety are not in.c.reased
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- * ' " * ~ than analyzed in the FSA. d:ss not result frem this chance because e.,.... .
the systs: resconds and is ::srated as before the chance. s.---- ___ m' 3. The marcin of safety as_ dsfi_ sd in the' Technical _Scecifica_t_i_on_s r .
,' is not reduce _d due to th'_s_ revision because the revision does not
_ 1 I chance anv li..ited safaty restan settines which would allow a -- - . safet'y_ l,imit to be excs=dsf er to allow a limitine condition for ooerations to be exceedsf_ as__ stated in' Te_chnical S_o_ecifications_.__----_--
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SECURITY ALERT - OPERATING PERSONNEL
~
A. PURPOSE Notification has been received of a security alert involving: A bomb or other overt threats or A c.ivil disturbance B. . ACTION
- 1. Bomb or other overt threats
- a. The operator will initiate the securith alert signal over announcing:
the public address system and then follow up by THIS IS A REACTOR STATUS ALERT *
% evtw 4 b. The Shift For-eman will institute an immediate I dispersion of available personnel to search and inspect vital areas within the operating buildings. If
. required, personnel to aid in the search. .
the Shift -Foretan will call in addi tional ;
' 5qe n ts,-
- c. The operating personnel will make a thorough search of
~
the vital areas and report any , findings to the Shift
-Foreman . g Squvise
- 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. f--unauthor i ze d intrusion is discovered or suspected, the 'Shif t Foreman will be notified immediately. The h"" y Shift Eoreman will then have the main control room i
ccess' doors locked and notify security headquarters, op a.be
- f. Shi f-t Supervisor refer to HNP-4420, 4520, 4620, and l 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 ** -
* ~
MANilAl. SET
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' HNP-4901 E. l. HATCH NUCLEAR PLANT s See Pa9e 1 . . ~ ~
3' V. See Page 1 Georgia Poweri ~~ 2 oe 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.
C7 etace
- d. Shift Supervisor refer to HNP-4420, 4520, 4620, and l
.4720 procedures to determine if emergency should be declared.
l - v,
*i MANUAL SET}}