|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos ML20212A0661986-12-19019 December 1986 Proposed Tech Specs Re Steam Line Rupture Detection/ Isolation Sys 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] |
Text
- , - , - - , - - , -
O O
O
/
ATTACIDENT 1 l
l
\
8008050l88* '
1 m
Revise AC 7.4. as follows:
- 1) Part . (d) - Replace the second paragraph as indicated on page 7.4-2, and
[ delete steps 1,.2, and 3 on pages 7.4-2 and 7.4-3.
I
- 2) Part (e) - Delete in. its entirety (pages 7.4-3 and 7.4-4) .
i
- 3) Table 1 - Delete in its entirety (page 7.4-5).
i
- 4) Table Notation - Delete in its entirety (pages 7.4-6 and 7.4-7) .
{ Reason for Change:
Eliminate any disparities between the Fort St. Vrain Technical Specifications
. and 10CFR20.103 and eliminate the need for any future revisions to AC 7.4 as a result of revisions to 10CFR20.103.
i 4
4 i
4 s
k S 4
1 T
i I.
i t v - ,y y a -- .-,r , -,.=w- v - .- u-~,- -,re -, ----p-t. -er .
-.m- w -.T- . .-~,
7.4-2
- c. Temporary changes to procedures of a. above may be made provided:
- 1. The intent of the original procedure is not altered.
- 2. The change is approved by two members of the plant manage-ment staff, at least one of whom holds a Senior Reactor Oper-ators License.
- 3. The change is documented, reviewed by the PORC and approved by the appropriate Superintendent within 15 days of implementation.
- d. Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20, and shall be ap-proved,. maintained, and adhered to for all operations involving personnel radiation exposure.
Respiratory protective equipment shall be provided in accordance with 10 CFR 20.103.
i 1
- , . . , -. .m ,wv.-
- DELETE THIS PAGE Fort St. Vrain #1 Technical Specifica icus A=end=en
- 16 - 11/24/76 page 7.4-3 l
1 I
i f ca M m?isg such radioac:ive =a:erial for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> a:
de parti =ent concentration values provided 6 Appe= dix 3, l l
Table I, cole n 1, of 10 Cya 20. I
- 1. Tor radicactive mater'al a designated "Sub" in de "!so pe" column of Appendiz 3, Table I, Col- 1 of 10 C7120, .he concen estica value specified is ~:ased upc= exposurt. Oc de =aterds' as an ex:er=al radiatien scurce. :divid *'
exposures to dese =a:era shall be accou=:ed fer as part of the l'~'tatics on individual dese 6 20.101.
- a. Is all opers:1cus in Pich adequate l' # stien of . he '
- *-a' a:1:n of radioactive =atert by da use of p;ccess or other engineeri:g
. con::cis is i= practicable, the lice =see =27 pe=1: an i=dividual -
is a re.*::icted area a use respi:2::r7 p c active equip =e== :o l'~#: de #-b' m:'_m of airbo=a 'd' active ester d o' , p;cvided:
- 1. The l' ':s specified is d. above a:s so: exceeded.
- 1. laspi:20=:f procac.dve equip =en: is selected a=d used so that de peak conce==2:1:ns of airbone : adicactive matar'*' i=halei ~:y an #-d' ridual wearing de equip =en:
does so: creeed da per-'--: cenes==2_'~ values specified 1: Apped'r 3, Table T, Col- 1, of 10 C7120.
yo: da pc: poses of -' 'a subparag 17' n , de c= ce==stice of :ndicac.ive enza.ial .ha: is '-%' ed . ten respi:2:::s c
are vers may :e deram' ed ~:7 div'd' T the a=~ien:
at: borne cecce= Cat'. n by de p;ctec ics fac c; specified in Table I, appe=ded := **d* specif'ca.icn f:: .ie respiratory p ctac:'ve equip =e== vo=. If ie i=:sie of l radicactiv1Lis M:Q- doW M7 mms arge-gen-m
DELETE THIS PAGE ,' '
Fort St. Vrain #1 Technical Specifications
. Acend=en: 16 - 11/24/76 Page 7.4-4 to have been differe== dan :ha: 1:i:1,1117 esti=ated , de latar pa=:1:7 shall "ce used is evd.crd-e -la excesures.
- 3. n e licenses advises each resp kater user tha: he =ay leave the area at a=y time for relief from respira:or use is case of equipment =aliuse ion, physical or psychological disccm- .
forr, or any o:her condi. ion da: sigh: cause reduction 1:
the protection afforded the wearer. .,,
4 ne licensee =ain"'-= a respiratory pro:ec ive p cgram adequate to assura dat de requirs=e :s above are =et.
- 5. n a lice =see uses equip =ent approved by de U. S. Sureau of Mines u= der its appropria:a Approval Schedules as se:
forth i= Tabla I.
nose speed fica:1cus, win respect :o the previsions of 10 C.3.
20.103 shall be supersedes by adoption of proposed cha=ges :o 10 C72, 20.103, which asuld =ake -lis specifiestion 0.==ecessary. -
l - ,! t i .
$N'" a5v u,,S s
- "o E. v". gp$ y i
Y {ref o pg1 gi j n
l0$$"
I ,m a pggy
@% ub&.
A y _
T t N e -
E f p H a i P S u I q I
I l e Q ar , )
E l nar KK .JJJJJ l 1 1 i1 1 1 aoA o (
F ni( f t t t t t.t t t t t 3 O ot rr r rrr r r r r 6 i asg aa pp_ a aa a a aa a N t pl n i i ii i p pppp ppp 1 O auai l iil l l l l l i i i l l l 1 I Ncvd) uu uuuuu uuu T c oed Si f SSSlif i SSS 5 C uO r u e }-
e prt E.
l E i nrpea oA pl 1 1 1 1 1 1 1 1 1 1 1 1 1{
1 1 1 1 1 1 1 ,1 1
S Hf ul t t t L t t t t t t t rr rr rr r rrr r O
T f et ot t ep l
i s 'u PP aa aaaaa PPPPP aaa PPP P a
ual y s
I
! i t eut RR RR: RR: RRR R S E ai ll l e FF FFFFF FFF F t
l i
l et ct_ CC CCCCC CCC C o l r udl n i T l l unnc e 00 00000 000 0 A C BI as m 33 33333 3 33 3 R
I )
P 2 S (
E S re R t l od 0 l in t oa I O R T C
nu aaa cmn a
F A ai n )) fd na E. S F s gt e t 5 5
((
nov l nat n H R N tdi 50 0000 000 o ti i A O O anr 0 0000 000 i ean
. T T I l at) 1 1,o 1 0 1 01 t pr C i .
T !
u } ! l j./ l c y yd,
' A C c at.( 1 1 1 e$ p e.
F E i rpo or ot a
, t T t oed N O rpci rof I O R aaxx Pf o1
! P P veo f
l C.
t Ie 'j l T )
O I H (
P S
E D PP a FF0OyF niRn CC PCC P
- i. ! ; :,
O H Nj i g
, n i
a l i
k u r9 o
t( r a u
t a
c r i- ei
- r
) a o se r a l l 7 r k g t - l i
) t apr
( u n a fI 1 l A l l a i
i p a u m i
y r ll l l auuu d H l l e C J
l r "foma u u os l i uuu i n o - l p
plifff n I
! fff p t r I R fl s i ( u nai
- T l l p e ,, ,; a ,,, e o p P g aa i u t i eeea t a eee H id u I n I I f S cccc n u ccc t ne R i _ - e eeec o t eee n i u ar
_ C y ,, e r n l l l i c a lll o lu i
f ee o i pppp - i,i i p gg l
E l
I i
r ee cc l
gt a l eeeedL r cccco!
f l
t a
pccc eee f
t u mii l
i nn u l i gr i aaaaou e paaa noyy P pp ui A FFFFI S l i
! aFFF i cfl
- ee n p l i
i p r cc m _a u u yrp
_ i aa t e . . a nuis A FF A R 1 2 C A pu
- 1 I 1 I I
(
2 '
kl.ETE THIS PAGE Fort St. Vrain #1 Technical Specifications A=end ent 16 - 11/24/76 Page 7.4-6 TE27Z NOT1*2N 1
Sea da.following sy=bols:
C7: continuous flev D: demand 37: negativa p sssura G.a., negativa phase during f4miacie:1
?D: pressura dama=d C1.a., always positive pressural 3.: recirc.:lat':g (closed circuhl 4 " Cal For purposes of +'= specifhat'c= da p;ctactic= fac c is a reasurs of da degraa of p ctac 'au afforded by a respirator, defined as de rat'.o of the conce==stice of at:5c :a radicactive =aterial cu:sida de resp'ratory p ccective equipman: to that hside the equipman: Cusually i=sida tha faceptacal cedar condi: ices of use. It is applied cc da ambient at:'orna: ecuca==ation to esticata de conce==ation i= haled by tha waarer accordhg =c de fc11cwi=g for=ula:
Concent:stics Inhaled - A=Lient Airborne Coneset= ache P:ccactice Fac:c C51 Tha procaccion fac:c s apply:
, (11 cely for tra1=ed d-d'viduals weart=g properly fh tad respirators used a d ~='--s' ed under supervisics is a well-pt =-=A raspirs=:7 p ccactive p cg:ss.
(111 for af -purif7 i ng respira:crs only *4an high afficiancy (abava 99.9% re:mval eff hiancy by U.S. 3urazu of Mises type diccc71 phthalata CCPl tast] par '~ $ a fil:ars a=d/or sor5snes appropriata :c he hasard are used i=
atacspheres :ac def'-'=c La cz7sen.
l l ("' l for a==csphar; agyl7icg raspirators cely ' den supplied 1 with adequa:a respirabia air I '
l 3 l Ixclud1=g radioac ive ec *-ats hac prese c an absorpth= or sub-esice l hazard. For =1-'- czida apprezi=acaly half of de 1=.aia occ==s by absorptic: 1 through ,.ha ski: so that an overall p:ccac ica fac:c: of sec sc:a ha=
approx 1=a:aly 2 is appropria:a when ac=osphera-supply 1=g :sspira:crs ars used to proeact agai=se =i-' - Mde. A1:-pu 1f71=g :sspfra: cts are toe :sec== ended for use against ::1:1== o*de. See also fcoc= cts 5, 3 12,, cone ,4 ? supphed-air sui:s and hoods.
Por: St. Vrain #1 DELETE THIS PAGE Technical Specifications A=end=en: 15 - 11/24/76
? age 7.4-7 T.A31.2 NO"ATION 4
Under c'd- cype only. No: recc= mended for use icere 1: =1ght be possible for the ambient at:bor=a ecuces=ation to reach instantaneous values greater than 50 times the pertinen values in Appendix 3, Table I, Cel"--- 1 of 10 C7R Par: 20.
5 Appropriata pro:ec.ics fac:c:s =ust be dera:=ined <'ag acccu== of the, design of the suit or hcod and i:s pe=eabdT * :7 Oc de ceu-' d-=-: under cceditices of use. No protectica fae:c: greats: dan 1,000 shall be used e= cap: as authoriced by the Cc= mission.
6 No app:cval schedules cu=S=:17 availabla for this equip =ent. Iquip=en =us:
be evalcated by *esting or on basis cf available cas: i=fc =atien.
7 Culy for shaven faces and whera =cH d g interferes with da se.al of tight-ft:-' facapiaces ap.1=s the skin. (Ecods and Suits are e=:ep:Sd.)
NOTZ 1: ?:ccactice fac:crs for respira crs, as =ay be =77 :--ed by de U.S.
3ureau of #-as or the Na- M' !ss-d:::a for Occupa:1ccal Safety and ?.Aald acOcrd**g cr approval schedules for respirators to protact aga1=s airbone radiccuclides, may be used to is exte==
. :ha: they do =c: exceed da protactice fac:crs listed i= -"- Tabla.
The protactics fac:c:s is dis Tabla =ay set be app;cpriata :=
circumstances where ch s - T- or oder respirator 7 ~m-=-ds exis:
~
is addi dcn to radicactive ha ards. The selectics and use of
- sspirators for such ci ==msez=cas shculd taka i=:c accou== app cvals of the U. S. Sureau of Minas or the Naciccal I=sti:::a for Cecupa.icnal Safety and ~aald is acec:da=ca vid its appt'-abla schedules.
NOT2 2: Radicac '_ve cou '"' ="ts for which da ecces=m-d-- values 1: Appa-d'~
3, Table I of 10 C71 Far: 20 are based on 12:a=al dose due :o ' 5 mi s-
.ica =ay, 6 addition, prasen: ex:a=al exposure hasards at hipar c=ncan=2:1cus. Cedar such cir==s:2=cas, ':ations on occupanc7
=sy have to be gove==ed by er:s=al dose ' .s.
+ 4 e m 4 Awa .-.J A A > --- J.e--, e Lm+ m -
me-- - 2 j
e .
1 O
+
I 5
b
,l -
h 1
t i
S J
l l
d I
i ATTACHMENT 2 l.
J d
'?
4 4
i e
i i
r 4
1 l
J_
t i
l 4
i I
t i.
-wer<wri+,y -m , .-,-- ,-- r- ..,_.-,---r-,---. - ,--.e-.-- - - , , e r . . _ - -- - - - - m - - - - --- --ee. - , , . , ~. - - + .-n, e---i,e n--w-pm -- ~ , - -w- ..v-e-
., Revise Table 5.4-1, MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTING OF SCRA!! SYSTEM
" Method" of Channel Description 10, Function c. to cead:
Compare _-each thers couple output to a NBS traceable standard.
Internal test signal _ to adjust trips and indicators.
" Method" of Channel Description 15, Function c. to read:
Compare each thermocouple output to a NBS tracea'ule standard to adjust temperature trip point.
Revise Table 5.4-2, MINIMUM FREQUENCIES FOR CHECKS , CALIBRATIONS AND TESTING OF LOOP SHUTDOWN SYSTEM
":tethod" of Channel Description 7, Function d. to read:
Compare each thermocouple output to a NBS traceable standard.
Internal test signal to adj ust ~ trips and indicators.
, Reason for changes: P reviously, the stated method was to compare each thermo-couple output to a calibrated RTD. The necessity to calibrate the subject thermocouples in plant environments which do not permit use of a laboratory standard requires a change in the =ethod of calibration. The proposed method
- assures an acceptable calibration will be performed without direct use of a laboratory _ standard i the plant environments.