ML20085F593
ML20085F593 | |
Person / Time | |
---|---|
Site: | Saxton File:GPU Nuclear icon.png |
Issue date: | 02/28/1968 |
From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
To: | |
Shared Package | |
ML20083L048 | List:
|
References | |
FOIA-91-17 PROC-680228, NUDOCS 9110220236 | |
Download: ML20085F593 (34) | |
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l li1GH RADIATION
- EVACUATIO!! PIAll i,*[,' % ,N b h ?'#;' N $ i" i -
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Q!GH TMDI ATIO!! EVACUATIO:1 PIAN %i The High Radiation Evacuation Plan will bo put into effect by count!!ng tha evacuation nlarn. This alam 10 initiated from the React.or Control Roon.
It shall be sounded af ter an investigation has been nade which shows that the causes of automatic reacter plant high radiation alams is the result of hich radiation levcis in the containment vessel and that this source of radiation produces a radiation level at or beyond the security fence in excess of 2 nr/hr.
ACTIO! BY PIANT PEIGO!PIEL STEAM PLU!T Upon hearing the evacuation alam, the steara plant control room operator will ndvise personnel in isolated plant areas of the evacuation alam.
- The steam plant will be shutdown in accordance with establinhed w- \ ,
cmergency procedures. Only those personnel necessary fcr plant shutdown (See "Energency Evacuation Procedure Saxton Station") shall remain in the plant.
These perpnnel, shall don respirators.
All other presonnel not necessary for plant shutdow- shall evacuate the plant in an orderly manner, retreating to the scale house via the macadam driveway.
.NU_CIIAR PLVIf d The nuclear plant will be shutdown in accordance with Emergency Instructions for "Ehergency Shutdown" - 501.
' Control room personnel will don respirators, begin to shutdown pl%t according to " Emergency Operating Procedures", and notify the Radiation Emergency Team. Upon coupleting shutdown they will rctreat via their privato automobiles to
- 8 1 the scale house using the macadam road.
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NUCIZAR PIN T (CONTSD)
The Radiation Energency Team will proceed to the Monitor Room. ' Ire senior member of the team will comunicate with the control room to dete m.ine what is kno concerning the status of the facility and meteorlogical conditions. The junior ccnber of the team will obtain prtable instruments and itesc of protectiva clothing and equip.ient, and will then proceed to the scab house via his private auteIbile after first measuring the radiation level at the necurity fence.
Additional ite.ns of emerCency equil nent are maintained in the uuale houeu. Tne senior membcr of the team will proceed to the scale house via his private automobile after making an esticate of the plant situation.
ALL PEPSOL'EL i All personnel will stay at the scale house anu await further instructions from the " Radiation Bnergency Team". t.11 personnel will report to their superviso.s ,
and all supenisors will report to senior man in che.rge.
ACTION BY SDUOE STAR MEGER AT SCAIR HOUSE
- 1. Notifys (ArrangedinPriorityofNotification)-
- a. Reacter Plant Superintendent - Hugh J. Williams
- Offic-t= 635 2937 Saxton Nuclear Experimental Corporation P.O. Box 99 Saxton, Pa. 16678 Hec.e: 635-3008 1101 Church Street-Saxton, Pa. .16678
- b. General Manager (Saxton Nuclear Experimental Corp.) Clayton R.
Montgomery Office: 'l- % 4-7111
-l i Pennsylvania Electric Company -
1 4C5 W. Plank Road -
Altoona, Pa. ,
Home s. 1 695-0196 616' Spruce Street - '
_ -_ Ho111davsburn_fn._______________
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- c. Industrial Health Consultar.t - Albert A. Spritr.er, M.D.
Office: 1-412-242 7520 300 Penn Center Blvd.
Pittsbur6h, Pa. 15235 Hene: 1-412-242-8553 9 Churchi13 Road 1 ,
Pittsburgh, Pa. 15235
- d. Public aclations Manager (Penelee) - Dan G. h rk office: 1-536-6611 1101 Broad Street Joitnotown, Pa. 15907 Mcco
- c. Region I, Division of Compliance, USAEC Telephone: 1-212-989-'000. (Day o: Nirht) 376 ".udson Street New York, N.Y. 10014
- f. P.r.diation Emergency Assistance, Pa. Dept. cf Health
. Telephone: 1-717-2480 (Daytirne) 1-717-3720 (Daytime)
Telephone: 1-717-233-5316 (Night) 1-717-737-5694 (Night) 1-717-545-6388 (Nir,ht)
- g. Pennsylvania State Police Telephone: 1 6234133 '
1 623 6134 Troop G Sgt. Kauffman i P.O. Box 355 Bedfcrd,-Pa.
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9 H. Notify Hospital (J.C. Blair Mmorial) llur.tinr< ion, Pa.
Hospital: 1 4 43-2290 hichard E. Cummincs - Ai~inistretor 1-643-2290 (Day) 1443 2298 (Hight) or
- Robert J. Ayella, M.D.
L ray Dupartrrxnt 1-643-2299(Day) 1443-3783 (Night) 2 Personnel monitoring and decontamination (postible use of fire track).
- 3. Barricado of roads by stat,e police.
- 4. Continuous raonitoring of radiation levels. ;
- 5. Erwironmer.tal samples.
- 6. Wacuation of residents if necessa;;<
- 7. Tal:e action as required or possible to remedy cause of high radation levels.
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f>AX70!1 !!UCU' Art EXPERl!4E!A AL CORPOIMTIOil 4 ' .;.
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00!!TAltM2 T VESSPL PVACUATIO!i PIAt1 N
This evacuation plan is to be used to ovacuate the containment vnc.scl when the evacur." n alam(s) is sounded daring fuel removal from the reactor coro, fuel i loading into the reactor core, and the initial entry of each ner or u.a.ed fuel 3
aosemb3y into the fuel otortgo racn.
I I Pactrictions Durine Hand}$nn I
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(1) llo more than 15 persons are allowed in the C.V. during fuel removal from I the reactor core, fuel loading into the reactor core, ar.d the initial
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ontry of each new or uned fuel aseembly into the fuel otorage rack, l except as authorir.od by the Reactor P3nnt Superintendent.
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, (2) No poroonnel are n11 owed below the lower operating floor (oxcept to i unload 3x3 fuel box) during fuol raa. oval from the reactor corn, fun 1 l loading into the reactor core, and the initial entry of each new or used fuel noncmbly into the funi ntorado rnck, except no authorized by tho '
ouporviolon in ch'trge of the fuel handling werk.
!!onitorine Equiement on Ihnd in the Containment Vescel (1) Criticality Monitoring System: This system consists of a neutron detector and neutron source located in the fuel otorage rack. The system win be in operation whenever fuel lo loaded into the storace rack. An audiblu
,.3 oignal will warn all personnel of an increasing count rate. :
i (2) Gc=a Radiation Monitoring System: This system consists of a detector connected to a count rato meter located on the operating deck. An audibl9 eignal will be connected to the count rate meter and will cound when the ga"=a radiation level reaches a preset- alarm point between 5 mr/hr and 20 nr/hr.
(3) Source Range Alam Panel: This system consists of the two existing source range BF3 detectora located around tho-reactor vessel. The count level signal from the EF3 detectors thru the Source Range Alam Panel will
' ' initinto an alam in thp control room and the C.V. whon a prodotertraneo count lovel is reachnd. The predetemined count icvel will'be not in-j accordance with existing-Standing Orders. '
Evneuntion Proendure: :
(1) Upon hearing the evacuation alam, all pe sonnel within the C.V. will
', 'q' place any equipment in his possession (with the _ exception of radiation C
. monitoring equipment) on '.he floor or other convenient location 'ind .
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proceed to evacuate the C.V. by the personnel accese door. The concrete c,
.V elabs (reactor compartment cover blocks) stored on the upper operating floor shall be used as a shield for personnel while waiting to enter the air lock.
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'. '(2) - The inner air lockloor will not be closed until .nll personnel hhva !.
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w i 5 ' entered the area between the air lock doors. '
Ij f.y ",; wy I(3) The Radiation Protection Enginner on duty will mensure the radintion N . , .- ' levels at the e.ir lock while rareonnel are ansembling theroin. ,
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() T!.c su;.:cr >i.nr in cMrce vill- ascertain the a:: ;<rv ,
hwa aca c-bled in the c.ir lock.
(S) /.11 3 erronnel tril: exit the air lock togdhor. "de in# -
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t:.e c.ir lock u;11 re:ure the door.
(6) Tw : ire-ion of travel, by all personnel will b- 'c.", 't. :- --
t:m J. J. : the .c ni tor room. The rn li n '. '.c* r-t o e t ' , ' * ---
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si) If it it nec e rar, to scun 1 the evacuation clnric., tJi<; : :c., " Hi, . !M . . ' ! <,n Eva uation Tlar" will be followed.
P n -t elo Rvli nt i s - Msn' te - in ~ Inc' r: f r.t s an5. L,ne ier s :
Tre follcwi ,- li-; cf yertable radiation monitorinr, iratrumen will he c', r.ila: 2.. for 23e citi -r i n '.h
- C. 'i. or the CU Baildi'.c ~i-- t':e :P.n M 11r.r. o f Ne? .
('1 T. A. ad : . 1- y '.. n n i n .h er;) ,
( .~. ) ".C. Datic P;e (J-250,000 nr/nt)
(3) G.!:. St.rvey !!et'r (0-20 r.r/nr)
(4) Dn3 !;c;tren Prate a C3 (0-600 mren/hr N; and 0-30 r.rcn 'hr lit )
( f.) AP Alpi,.a Frobe ' J21 (0-150,000 d/m k r,'
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SAXTO:1 ITgFAR EXPETtIlOIITAL C0;tPoilATId:1 Fnercenev Fire Procedure:,
- 1. Person locating fire vill announce to entire plant thru pagine. 3. nte t tne 1. cat;or.,
type, intenoit; of the fire, and will then attempt to extinguich t:.e fire wcle help in being sent to the fire area.
Ere,nle : Attention all Personnel! Small electrical fire beated in Gau Co:prounor Room of the R.U.D.F.
Repeat name.
- 2. All -perconnel vill irrtediately ev..cuate fire arer. except for thoce p<.. connel trying to ccatrol the . fire.
3 Control roon peraonnel will sound fire alam.
4 Reactor Unift Supervisor will notify " Radiation Fcergency Tean.
- 5. Reactor Plant Technician will proceed to fire location, with approprht e fire fighting aat protm tive equijnent, and utart ouppreanion of fire.
- 6. Steret plant peraonnel, upon hear.ing S!!10 and/or ut.eles phnt fire alamn, ulll initiat e proecdurco for aupplying fire hydrants with wat :r.
- 7. Ihrint; weekday daylicht uhift, all available "S:iEC" personnel in plant will proceed to area near fire and ausiat as necessarv. l
- 8. D : ring weekend i or :!v ing weekday nightino shifts the stmaa plant control roon operator will dispatch available personnel to fire area to ancitt.
- 9. On recuring of fire, "'i.;diation Ihergency Tean" will eva]uate and clear area for renn . a of nomal w;rk routine.
See attached list of fire equipment locations.
Kenneth E. Beale Radiation Protection Engineer E
- - - - ., - - - . _ - - - - - - -.--_---,._._.---_.-----.__---._____--_--_--.---__-_-.--.--_-n- _ __ _
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SAX"'011:UCI2AR MPF2.Ir1TAL ColPORATIGJ e
Fire B:tir.mishers and Apnaratus Incations HTIUGUIS:TEftS[
km location 002 (201)
- 1. C&A DuRM.nc - Cu wall outside Health Physics Offico door.
- 2. C4A Billding - Ato:iliary Equipacnt Room on west wall nr.xt Dr/ Chunici1 (30J) to I?or.itor Room door.
3'.
C&.A bilding - Instrument Repair Shop on cast wall inside
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CO2 (00) door.
- 4. C M Dailding - In corridor on second floor inside door Dry Chanical (20//)
entranco from west stair tower.
- 5. C&A Inilding - Reactor Control Room on north wall behind 002 (208) control panels.
- 6. 04/. Nildin" - E:perimental Instmmentation Room on east 002 (208) wall at corner near corridor.
7 CM Ihilding - Ir /estibulo on north wt.11 outside chmical Dry Chetn.ical (20lj preparation laboratorf door.
- 8. C. V. - In upper operating level at stair inside air lock Dry Chemical (30/t entrance.
Dry Chemical (30!,
9 Sewcge Tncatinent Duilding - Insido u .or on richt uall..
y CO2 (20")
- 10. E*DF - Control 'Roca - On west wall inside door entrance.
Dr/ Ch =ical (20, I
- 11. IGDP - Drum shipping room on south wall inside door entrance.
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- 12. ElDF - Evaporator and Gas Stripper Room at lower level insido 002 (20,7) door entrance on south wall.
Drj Chenical (20
- 13. Fork lift truck. ,
APPARATUS
. Tyne Ioention s
!!ydrant
- 1. Approximately 50 feet sooth and in front of the CLA Duilding.
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2 02teide the south-east corner of the C&A Duilding between , lydrant
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Monitor Tank #2 and fence,
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!!ose cart with Scale and Storage Room. 300ft.of11"'
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2cm locatica Pire hose rec:1c and
- 4. ICDF - Evapor:.t* and Gas Stripper roo:a at gratin; hose cc:uwetion level incide ve a entrance, Fire hoco reels and
- 5. WDF - Scale and St.arage P.com in north- zast corner hoce ccrdNetion of roo:n by cact entrance.
Piro hose rcela and
Fire houe connection 7
C. V. - Prhary Compart:acnt on north wall behind heat cxchanger above elevation 795 i Fire hoce connection
- 8. C. V. - Auxiliary Conpartraent - storace well heat exchance level along wall at pu:aps above stairwell to lower level. <
3 Pi 9 hose connection s C. V. - Auxiliary Coapartncnt - Componcnt Cooling jj 9.
heat exchange lovel - alota',, wall at pumps.
Firo hone connection
-l bottom of veccel
- 10. C. V. - Au::iliary Compr.rtacnt along wall at etairway.
Pire hose connection
. 11. C. V. - Auriliary Compartncnt - botto:a of vessel along wall at discharge pumps.
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' SAXT0!l NUCLEAR EXPERIMENTAL CORPORATION 9
406A Date_ 7/16/65 406A Scheduled Ro. actor Stratdown Check off List A. Pre Shutdown Check- off 1 Secondary syste:n ehutdown (O.I. 440 ccenpleted).
2 Special instructions for the shutdown, if applicable, cave been
. reviewed by operations personnel.
- 3. 'riestinghouse Re-ident Engineer or his designce notified of impending shutdown.
- 4. Main c.,clant systen being naintained at 2000 psi and 530 F.
- 5. Operations cleasance.
6 Services clearance.
B. Shutdown Check -off
- 1. Establish a suberitica' reactor condition by running in or dropping control rods to zero inches.
> 2 Source ange detectors high voltage on.
- 3. Safety rods cocked at approxi:nate4-inches.
- 4. Source chamel readings: Ch. A cps Ch. B cpo
- 5. Entretnce to containment vessel Scheduloi Yes No Note: If entrance is scheduled purge contain:nent vessel alsr approval received frca Services (Sea O.I. 425).
Ccr:pleted by Licensed Reactor Operator h
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- CI SAXTON !iJCLEMi EXPERT!MTAL C0!tPORATION 4b7A:1 Date Wa%k='.s S/13/bc
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ic7A Main t'nolant Synt em Cooldown Cneck-of f List
- 1. Reactor nr.intained in the "Het Shutdown" conditien (0! 406). ,,
2 nydrogen removal initiated: PST at 0 psi, level nornal, vents open to _ _
gas canifolc. ( Ref er t o 0.'I . i.L8). '
- 3. Ali pressuricer heat ers off.
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- 4. Re%t the nain coolant flow alam. and scram setpoints to 1.2x10 and 1.0x100 lbc/hr respe:.ively. Transfer the main coolant pump to the variable frequency generat or, reduce generator output to 30 cps and 220 volts. ,
- 5. Increase the service water flow to the component cooling heat ext:.ar *ers to above 250 gpt. _
N;te: 1. A de:c.ineralicer nay be placed into service as authoriced by the SOAT or his designee.
2 At the next available opportunity enter the containment vessel and reace TIC-21V setpoint on the non-regenerative neat exananger cutlet to minimum.
- 3. 22 denydrcgenation, purification, and boration of the r.ain f
i coolant systen; all of which require charging and letdown flow, are to be accomplisheC simultaneously with the cooldown.
- 6. Charging and letdour. initiated at approximately 30 gpm and the regenerative
- r. eat exchanger by-pass TIC-247 adjusted f cr maximum heat renoval.
Sanple pump on ,f required.
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- 7. Denineraliced wat er nake up adjusted by HO-22Y/ to maintain level in the pt.rification surge tank. ]
- 8. Spray valve on nanual and maintairang 175 to 2000 F differential between the pressuricer and the main coo 3 ant.
.10. Syste: pressure 1200 poi - safety injection bloc 1:ed. Gags placed in FIC 22V and 23V.
- 11. Boron determined and adequate for shutdown prior to MC temperature of
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4300F. (See S.O. #20).
- 12. Syste= pressure 400 psi - steam bubble collapsed.
13 Spray valve full open. -
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ur til the systcm f d l aj'e!. Concentration is ic'sS th:An
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15, iTne:. L:.s . in . coinn; te:.perature in reau:ed to less than 200 F, cre.vny fi2] tnestum -.oratcr as follcws: cpen vent s on S3 . operat e DA feed pun" tc s u; ,: ;, ..ter r DFP eductor - open BFP suction i na c;n ::.rge
.<.1ver .- open :'e nat.at er f. o' control (7-1121) to fill EU - reset ull r ena:t lou w:.on E'? ; : ru12 but leave E3 vents open. .
2 .,. s:cr age ue;;,
Ac. a t:; tre ;ncreated to re.,ueling .,.evel, ceterrane :om..-
le.el and bo c;. nn:entra:ic:.. If necessary, fill EST to 80,000 ca_ ons. -
- 17. Prmsrir.er te .perature : s 1EO F or less. _
- 18. C re rogen icss +.nrr. c:!Ec. ,cr.plete H2 reno;ai check-r,ff ! EA.
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pressure to lesu than 2 50 p52.
- 20. Snu:Jewa crohn.; .. ;&t er (91 i.23 and component eco ing node selector in Sna nd wW' pon t. cn, . . . _
- 21. 'h e f e u e r_ r. c 2,J.: 4e = caters "ra hed out" and tagged with operators mo 1"' pam norns feed ~~
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Prensri:.er heaters _ .
m e-it ..... '.p m _ea ..t ~:e w r. : ca; .on su; .ce tane.
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- 23. Onarg...c pat;i .<_. s:.: fR tagged or. - _ _ . -
%. D. '. ; r..: ed ircn S.I. pr.p breakerc and tagged. _ _ _ _
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I Completed by j la ar. sed Reactor Operator
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EMERGENCY INSTRUCTION 510 HIGH RADIOACTIVITY LEVEL i
A high radioactivity level will be indicated by an alarm of 'cr.o or .cre } of radiation manitoring ch natcls. i i 1
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' Any one of the following symptoms may be an indication of the emerces y condition: -*
- 1. . Containment Vescel air-.pa.rticle (RIC-1) and/or radio-gas.(RIC 2) alam is actuated.
- 2. Stack car (RIC-3) alarm is actuated.
- 3. Cornponent cooling (RIC-4) alam in netonto.
- 4. Utcam concratur blev. lown (RIC-5) nlam in netunted.
5 RWDF liquid effluent (RIC 6) alam is actuated.
6.- Site air particle (RIC 8,9) alam is actuated.
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- II. Immediate Action:
2 A. Automtic Action:
4, -
Steam generator bicudown is discontinued.
B. Manual Action:-
i
' For all alarms, advance filter paper (if applicable) and attempt to reset the alam. . Check the instrument for proper operation and C
, verify with a portable monitor or air sample.
' . l.-
If the centainment-vessel air particulate (RIC-1) activity.is
. hbhi
-t
- a. Initiate reactor hot shutdown (See 0.I. 406).-
Allow-containment vessel ventilation system to function for j
b.
one (1) hour.
j c.- If step "b" reduces or returns radioactivity level discharge
- 25) (if the stack to nomal,.
i start purge operation (seo 0.I.
1, ~
activitywillnotexceed2x10-_uc/ccwhenaveragedever q~ one year),- then' enter containment vessel to locato and -
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reduce cause of airborne activity.
d.- -Iflevel step .L"-and "c" does not reduce or return radioactivity
}
. -j -. to r.omal,- start purge op'eration (see 0 I. 425) (if
,. 1 A the stack discharge activity will not exceed 2 x 10-7 uc/n
- d : ,% > when averaged over one year) and initiate reactor cooldown.
.- _( neo Q I.-407).
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l Initiate proceduren to n11rdnate cw.o o r a l r;,n nt et','ty e.
in containment vennel.
2 If the con + Mnment vecr,el radio can (111C 2j net;vity it. Lech;
- a. Initiate reactor hot shutdown (see 0.I. 406).
- b. Start containment vessel purge operation (see C.I. .M; (if the stack di scharge activity will not exceed 2 x l-? ue 'ec when averaged over cne year).
- c. If step "b" is not possibic or does not retre or ret ;rn radioactivity 1cvel to nornal, initiate re t9.r coolt/e.. 9+ ' ', t; t
1 - d. In',t hta nroceduren tu nlM: mt e cau .r. of ai rt rr.a in c. id ainment vm nel.
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- 3. 1r t.he nt em r,an (illG-)) i netm ted :
- a. Temport.ril; place fresh air dr.per to " Cal" positicn. .f the ecunts do not decrease, this is evidence of increared btek-ground. If the counts do decreue locate cource of hich actizity by sequentin11y perfoming the following c,arnim:. t (note: Operate on1; those cyatecc thtt were in operation 't time of high activity alam).
j
' c. Shutm wn the r. tack fan (thic action should 9 t'. Jm 1. *11 ve:.t11ation nn 1 tank ga role an y atemd. o
- c. denfir::. th 6t all vent.ilatl < a nod gr, rolonso yn'm chu Lewn, t
l d. Start up stack fan. If high lavcl er.1-t: M."i:
Integrity of rupture dic es coinci":en' c %J.~J :- 'r:1 i
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board alam.
l 3 Lenerater vent or air ejector vcnt ceincident ith .T J-f l high level er alam, er
- e. Start-up the containment vessel ventilation anl prce F:'
if the reactor is not operating.
- f. Start-up the ElDF ventilation system.
' g. Open the gas decay tank effluent valve.
- h. initiate procedurea to-eliminate eunne or high a;rb.rv activity,
- i. If the above steps do not :cmedy the nit % tion inititte.
ienetor shutdown (cea 0.1. 406) and if dermad nece;rary reactor cooldewn (see 0.I. 407).
- 4. If the component coolinC (RIC-4) alam is actuated:
- a. Sample and analyze component cooling water.
, b. If activity of the component cooling water is above tolerance, and the condition cannot be corrected, initiate reactor fi chutdown (cce 0.I. 406).
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- 5. '.f the steam generator blowdown (RIC-5) alarm in actuated:
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- a. Verify that the blowdown in dincontinued automatically.
4 t b. Poni tion 3-.way valve to direct tho flow of blowdown in E outlet line of blowdown tank to the 161DF.
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( c. Sample and analyze the blowdown water.
- d. If Lich activity level is confimed initiate rea:t:r shutdown (sec 0.I. 406) and reactor :coldown (c.<e C.;. 407,.
- 6. If the liquid effluent (IIIC 6) alam is actuated:
' c. Stop IGDF effluent discharge to the river (see 0.1. 430,.
- b. Deterr.ine and correct cause of high activity, t
' 7. If onn or more site air particuhte deteco.r (h ,- r ,9; C u- .
are nctu tvd:
- a. ClN.r filter rarer rapidly by using the p*.per drive switch
- switched to " fast" for 20 seconds, 4
- b. If high activity level rer.ains, verify the stack gas
' activity is nomal. If not noms 1 follow prred.;re :,f II, D, 3 in there emergency instractions.
- c. Survey respective area and check for possible enifunctia.
of detector.
III. Subse,uent Action:
Action must be taken m uonn an t.he rauloactivity levnl L:s below 1
I tolerance.
- 1. Investigate the cause of excessive radioactivity level.
c.s Make necessary repairs and perform deconte.mination, as requirca.
2.
4 i IV. Action Su-ary:
Complete a survey of the plant equipe.cnt. Note action (s) taken and a
status of the system after ecmpletion of this in:truction.
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- a 4 PLi!TT OPERATJ!J3 SAXTOM GTATf o:l E!U0CE!CY !WACU ATION PROCEDU lE Personn Involved : 1211 8 A!! - 3 to 7; 8 AM - 4 Di - 3 to 57; 4 M; to 12 ti - 3 t ; 7
- 1. Inercane to naxinun load on operating generators.
- 2. Reduce speed and ctop all ctokers feeding coal.
- 3. Shutdmm forced craft fanc on all boilers.
4 Open;.1 L boiler fire doorn. ,
!> . Open uuperheater blowdown valven on each boiler.
- 6. O,,en uide all auh pit sprinkler valven.
- 7. 11oce down boiler fires through fire doors.
- 8. Open and feed valves on service water to surge tanks.
9 Start #5 steam boiler feed punp and leave on.
- 10. Shutdown electric boiler feed punpn when flow decremen.
I 11. Bring load down with stean prennure on each turbine governor, chut #1 down first, then d3 at or near 150 poig.
l 12. Close turbine throttle valven and check auxiliary oil pumps.
1 13 Clone nain otean to air ejectors.
V
- 14. Shutdowh cir3ulating uater, condensate and air wanher puwas.
15 Shut d2 turbine down on orders from SURC operator.
Switchboard operatora, utility bay operators, turbine operators: ha /e 16.
ntation - approximately 45 minutes after alam.
17 Firenen: Re.ain until certain boilera do not require any more water, shutdown I.D. fans and //5 Br F. pump before leaving, approxinately 13Jhourc af ter,alam.
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. P. W. Stewart ,
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' PL41JT U1 STA!n)BY SAXTG STATIO:1 KGt00;CY EVACUATIG1 PROCEDURE If the plant hno only one boiler on with no concrator on #1 or #3 turbines at the tine of alarn, the following steps are to be undertaken at once:
- 1. All personnel other than operators and supervisors leave at once.
- 2. Firemen fill unt<r bottic full on the boiler on line.
J. Oyulnith flr. d.v.wa, renove all fans and open anh pit nprink ler wirlo, nt,op at.oher if running.
4 Contral root operators and turbine operators take s/2 turbine out of unrvice as directed h" S:;40 operators.
5 All operatorn should be out of the station in 15 ninutes dependin;' on when the onier in received to take t!2 turbine off.
P. U. Stewart
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January 23, 1968
- a. 5 To: All Employees Sa : ton Stem. Station
Subject:
SIEC Evacuation Alam Uith the present warning nyaten enployeca in certisin arean af the Pene]o':
In order to correct thin condi tion Stean Stati.on do not henr the Evacuation Alam. is uuunded the follo; ring proceoure shall be used in all canon, wnun the altm.:
includini: the 10 Al; tant each Friday, lhrinc the hourn 7 Mi to 3:30 MI the Plant Clerk imediately on hearing the alam nhall c.11 the followini; dttpartnents and tell then the alam is belnr,In the e soun:kd an:.imhc uhother these'itcalls is a test at the or timeactual thealam.Production Er.gineer will do ro.
not able +.o Darin ; hourn other thail thone liuted above the only call noccanary would be to the Dailer ;heon an.
1.h'tn will be thn reiaponnihility of the Shi f t Foreman on duty.
P!uno 11 0 . '7 - Niler Roon 1:achino Shop Phone 110. !8 .
Electric Shop Paonc Ilv. 21 -
Phone '!o. 33 - Store Roon Pnonc Ilo. 635-2041 - Operating Departnent Procedure to be followed in the event an actual evacuatio:,- In planned has already been given each departacnt.
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A. At.e..:c .Co.r.r:.v Cor:d un.i on Hagion I, Divicion of Conpliance, USAEO, 376 Hrtuon Street, Au York, He. York 10014 (1 '?l2 9$1-1000) chall be noti icd in tho follauirc nanner whenever an ine.: tent involving radioactivo nnterial occurn.
- 1. In& !! ate 1;W f4 cati on
; r t el ,-hone a:tt toler.raph of gny :ine lout i.nvo i v ; v i, f .
ro+,q t , m.open:
~in ny"".:tl nuc lea" interial po33enned by D*W.C an'l wh i eb u 0 hw stoneel or threatens to cauce; c::pocure of an individual to 25 rens or nore of
. " diation, e:;ponure of skin of whole body to 150 rens or nore, or of the e:;trene -ins to 3Pi rcns or nore.
' it" lean c- af r uiloactive naterlals which if averaced over a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.1 wou 1.! c.;eend ', nUO t i v.cn t.he 1ini,Ln unne' r i n;i for noch rtateriain io i
Appe:. iin ", 'lable II, 10 CFil 20.
Drtare to nreport" in excesu of 100,000 dollars, or loca of cnu workini:
week or nare cf the operation of any facilities affe::ted.
- 2. 2:eng Fuur : bur Motification f+/ telr. : hone and telegraph ' any incident involving licensed n'.ter al ponncbsed by S!!E0 which may have caused or threatens to caunu; expacure of any individual to 5 rens or nore of radiation, exposure of ukin of uhole body to 30 rcas or nore, or of the extrenetien to 75 renn or rare.
The release of radioactive natorials in concentrationr which, if averaged over n period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 tinc.1 the linits specified for cuch unterials in Appendix B, Table II,10 'Fil 20.
D:ela n'.c to proporty 1n excoon of S1,0m, or loan or oon oay or wero of the operation of any facilitica affected, i
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T e i REPORTING - STATE GOVERNMH1T A. Penneylvania Department of Health SNEC is directed to notify innediately the Pennsylvania Department of Health whenever thero is a spill or an accidental discharge of radioactive material and shall advise that department promptly concerning the pertinent facts and probable danger. SNEC ,s, hall maintain rosters of Pennsylvania Department of Health personnel and downstream users of river water who shall ,
be notified. In the event of any such accidental discharge the Department of Health shall determine whether or not downstream users shall be notified, and by whaci. '
B. P1 nnsylvania Denartment of Hsalth Roster (arranged in priority of notification)
RHIIONAL OFFICE l
f Telephone: b717-248 6785 (all daytime calls) 29 Chestnut Street lewistown, Pa. 17044
- a. Regional Sanitary Engineer - Elvin F. Hoover Homo L717-899-7175 Box 176 McVeytown, Pa. 17044
- b. Assistant Regional Sanitary Engineer Daniel B. Drawbaugh Hame: L717-248-5632 '
723 B Highland Avenue High]And Park Iewistown, Pa. 17044
- c. Sanitary Eh61neer II - Gerald C. A11 ender '
Home L717-248-7272'
., 841 South Main Street
'y ,
Iewistown, Pa. 17044 ,
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ItEPORTIHT - _STATJ: C'J 7FJtulEJT C.
RADIATION 2 JGNCY ASSISTANCE (arranced in priority of notif3 cation)
Radiological Health Section Office Telephone: 1-717-787 2400 Gr,r.nonucalth of Pennsylvania Departnent of !!calth lladiological Health Section
- P.O. Box 90 Hartir> burn, Pa. $120
- n. Chief Radiological Health Section - Thomas M. Gerusky Office: 1-717-7d7-2480 (day) limw : 1&717-23b5p6(nicht)
- b. Itmiintion it. alth Phynieint - ilod O. Inchenau Office: 1-717-787-3720 (day)
Hone: 1-717-545 6388 (n_. a,)
Director Division of Occupational Health Jan Lielien, M.D.
c.
Office: 1-717-787 6525 (day)
Hone: 1-717-737-5694 (nicht)
Wesley E. Gilbertson
- d. Director alreau Environmental Health Offico: 1-717-787-5027 (day)
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' Ifoue : 1-717-761-3456 (night)
L e. Secretary of Health - Thomas M. Georges, Jr. M.D.
j Office: 1-717-.707-6436 (day)
Hone: 1-717-236-4853 (night)
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4 IhDIONAL OFFICE (Continued) ,
Jamcc J. VanGurdy
- d. IhtEr' Pollution Control Special.iet I Herno: 2-717.248-5727 112 South Main Street Icwistown, Pa. 17044 Water Pollution Control Specialist II Richard L. Morris c.
Home: 1 717-248-5659 fiD 62 Box 57B lawietown, Pa. 17064 E
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. Y llIGli RADIATION EVACUATION PIAN DIERGENCY B)UIPIT.NT SCAIS liOUSE - STEAff PINIT Anount it_en j 6 Half Face Respirators 6 Plastic Shoc & Ankle Cuvera 2 Doz. Pair Pallbearers Gloves 1 Doz. Pair Industrial Gloves 3 Hoods
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Surgeon Caps 6 Doxon Sneae Paper 4 Coverallo (Size 53) 2 Coveralls (Size 48) 2 labcoats (Dize 48) 1 Inbcoat (Size 56) 1 Roll Macking Tape 1 Doc. Plastic Gloves 1 ; Iot of !!iscellaneous Signs and Tags 1 Iot of Itisec11aneous Plastic Bags 1 High Radiation Evacuation Plan 2aoh (All equipment stored in sui'. cases located in scale house) a
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S7C Operatiente Report f or
,J u1L1l{G,9_. . . . . . . #2 -
3.
T.5PEltIET/1 PROGR'.'1 ,
1 The Core III rero power physics racacurements were compicted durihC the-month and the following pararaters rrasured:
All Rods Out Just critical Boron Concentration -
1082 ppm B Modcrator Temperature Coefficient All Rods Out - 0.Sx10-4 ok/h/Or at 505 r.1052 ppm B Control Rod 2 at 7.cro Inches - 1.4x10-4 ok/k/ r at 5030F, 788 ppm B Boron Worth - 100 ppa /% Ak/h at 920 and 603 ppm B Control Rods 2 and 5 Integral Ucrth Control Rod 2 - 3.20% Ak/k - 320 ppm B Control Rod 5 - 3.23% Ak/k - 323 ppm B The in-core flux mapping system was operationally tested and flux maps made at reactor power levels of 0.47 Wt and 0.51 MWL.
The rai]ed Fuel Monitor System was operationn1 during the zero power physics measuredente and data was obtained at low power levels.
- 4. OPEKATIONil TESTS The SNEC fire and evacuation alarms were tested on July 4, 11, 38 and 25.
The monthly- test of the radiation monitoring system was completed on July 4.
The monthly test of- the safety injection and recirculation systetu was '
conducted on July a. .
Scram circuit response times were measuredo 'n July'3. The rainimum time recorded was 0.043 seconds and the maximum time was 0.240 seconds. Control rod-drop times , hot with flow, were measured on July ' 7. Five drop times were measured f8r each~ rod and the minimum time was 0.798 seconds the maximum time was 0.972 seconds.
Thh pressurizer safety valve tests were completed on; July 15. -
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