ML20006A754
| ML20006A754 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/20/1989 |
| From: | DETROIT EDISON CO. |
| To: | |
| References | |
| NUDOCS 9001300145 | |
| Download: ML20006A754 (130) | |
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LI(ER5ING CRANGE REQUEST
- LcR 18191 - 1012171 - IUlFISl Revision 5 Pase 1 of 23
- I
, I m m m m m eFART 1: IF5AR. PLAN. OR ruuGRAN REVISION [ ]EA A) Dooment ;
O- UFSAR
- 7) 5ection(s), Tlable(s), Figure (s), etc. Affected (Attach marked-up pages) i
__Section 9A.4.2 9.2 and Figures 9A-1. 3, 7. 8. 9. 10. 11 and 14 C) Reason for Change q9 m.m sdo au l= M L See page ,.
_ .e c,.i..*'
i CONTROLLED-D) Reference and Source Documents (Identify) l EDP 4797. Rev. 5 Test NA D r
I PDC NA Tech Spec NA %
DER b t ched) -0012 Effectiveness Review (Attached) Yes N Other. NA Drawings, Design Calculations, Correspondence, sto f- ~ ~~~~l q e ;
l####################PART 2: OPERATING LICENSE te m %.
A) Document D5n' y'16 5 E ,
] Operating License [ ] Tech Specs [ ] v na n .
[
~
l Tech Spea Clarification met i B) Section(s), Table (s), Figure (s), etc. Affected (A _
11 -
C) Reference and Source Doceents Attached ,
'[ ] Significant Hazards Consideration - E h >2
[ ] Enviromental Ispact - Categorical Exclusion O [
{
] Environmental Evaluation Other
[
l D) Is UESAR ohange required?
[ ] Yes [ ] No LCR No.
f l
i E) Priority gy ,.
NRC approval required by (date): o n. 1:
i
- An [ ] Emergency [. ] Exigent condition will occur if not approved by
(State date):
4 Explanation F) Implementation DER No. ,,
Jeeeeeeee:::::::::::#PART 3: ' APPROVAL 5;;;;;;;;;;;;;;;*;;;;;; 3;;;;;7,;;M l t, WJMM(MW41 A) Originator Sevanti Shah e- - /S&W Date / 89 B) Technical Expert S. 2. W Date2-N-Pf C) Nuclear Organization Unit Head . , Date M J Y'N D) Director. Nuclear Engineering [ ]NA [ [- A c., Date/ ~#-/f E) Plant Manager s .
Date 1-24-//
F) Director. Nuclear Licensing Date/B/kB/g C) OSRO Approval [ ] NA Date H) NSRG Approval ( NA Date l form FIP RA2 01 Att 1 F1/1 092158 DTC:-ggg, File:- f 7g
. l (INTINUATICE SEET IER 18191-1012171-lUlFISI TSC l l 1 - 1 I l l Revision S Pate 2 of 23 C) Reason for Changel Per approved document EDP-4797 and field walkdown, oorrect wireway number is RI-069 (RI stands for RITA Area). Therefore, UFSAR Section 9A.4.2.9.2 i is corrected to show the correct wireway number.
l ,
l These UFSAR figures represents Fire Hazard Analysis drawings which are updated by ABN 9941-1, Rev. O to show the fire wraps, to delete and to show the correct location of carbon dioxide fire extinguisher symbol, to correct staircase direction arrow, to add fire hose reel, to add inner sets of doors and to delete fire blanket symbols. No design change. For details, 4 see SE # 89-0012 (attached). j O
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combustibles within this sone consist of cable insulation with a -
U total 3tu content of 318,000,000. Total sone loading is 67,000~
Btu /ft3 .
9A.4.2.8.3 Conclusion l l The objective for this sono is to prevent a fire within the zone from affecting both Divisions I and II cables and to prevent a fire from crossing the boundaries of this sone. This objective is achieved through spatial separation, barriers, and the provi-sion of an early-warning detection system, an automatic Balon
]
fire suppression system, manual fusible link sprinkler systea,-
manual water hose station, and portable fire extinguishers.
9A.4.2.9 Cable Tray Area, Sone 8, El. 431 Ft 0 In.
li 9A.4.2.9.1 Description This sone, shown in Figure 9A-7,tconsists of one room. It is bounded on the north by the. steam tunnelt on the east by the turbine buildingr on the south by an outside wall; and on the 1 west by the reactor building. The sone serves primarily as a I cable routing area for Division II cable. A small amount of 4 Division I cable is routed through this zone.
I The walls, floors, and ceiling of this sone are constructed of reinforced concrete ha'ving a fire-resistance rating of 3 hr.
Penetrations through the walls, floor, and ceiling are sealed to i provide 3-hr fire-resistance ratings.- The stairwell is enclosed -
by a 2-hr-rated fire barrier with a Class 3 fire door. -
1 l Ventilation air is provided by the reactor / auxiliary building l ventilation system. Supply air is ducted directly to this sone.
Exhaust air is ducted to the auxiliary building main exhaust system.
l The alternative shutdown system is used to achieve plant safe l
zhutdown for a fire in this-sone.
! Shutdown equipment located in this sone consists of Divisions I 1
and II cables.
, Fire detection equipment in-this zone consists of an ionization j detection system. Fire suppression equipment located in this
- sone consists of an automatic CO2 system, manual water hose i etations, and portable fire estinguishers, as.shown in Figure 9A-7.
j 3 I
9A.4.2.9.2 Analysis REvlsE i
i' For-a fire in thi sone, the alternative shutdown system will be j used to bring the plant to a safe-shutdown condition. Conduit i RI 005-2P/wirewa 1-243 n ins circuits required for the alternative shutd a t . When the conduit la routed in the
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, LICENSING CB&M3 MQUEST Len 18191 - 1011191 - lUlFISl f ' Revision 0 Page 1 of 1-LI I;;;;;555euvemePART 1: WSAR, PLAN, OR rm GRAN RETISION [ ]NA eewevesel A) Doousent UFSAR B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
L Section 9A.5 Point by Point Comparison, Fire Protection C) Reason for Change To correct a discrepancy in the description of the fire hose nozzle type used at the fire hose station outride the Control Room to reflect the actual type installed. The type actually used is consistant with the description on Page 9A5 19 of Section 9A.5 which i' indicated " adjustable pattern fog nozzles are used-throughout...".
D) Reference and Source Documents (Identify)
EDP Test runrrm, PDC Tech Spec - ' ' ' ' ' ~' LED ABN Procedure DER 58-2058 SE (Attached) 89-0007 Effectiveness Review (Attached) ' i Other Drawings, Design Calculations, Correspondence, etc.
jeeeeeeeeeeeeeeeeeeeePART 2: OPF. RATING LICENSE CHANGES [II]NA weeeeeeeeI A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan
[ ] Tech Spec Clarification {
B) Section(s), Table (s), Figure (s), etc. Affected ( Attach marked-up pages).
C) Reference and Source Ibcuments Attached
[ ] Significant Ha;.ards Consideration STATUS ,
i
[ ] Enviromental lupact - Categorical Exclusion ASB bM 7Ik M
[ ] Environmental Evaluation
[ ] Other DIST*St97 M j D) is UFSAR chinge required? REV.
[ ] Yes [ ] No LCR No.
E) Priority (,
NRC approval required by (date):_
~
An [ ) Emergency [ ] Exigent condition will occur if not approved by: b. g ;
(State date): 4 Explanation QLOk' g
F) Implementation DER No.
..... es*enepART 3: AppRoyALS.......eeeeeeeeeeeeeeeeeeeeeeeeesent- g ;E.
ie....e '
A) Originator l D. S. Eason # g - m Date2.mr.sy g
B) Technical Expert D. S. Eason [ M : _ e b , Date 8-2P-f{ g C) Nuclear Organization Unit Head ) k. & U1 DateMMT7 '#
D) Director, Nuclear Engineering [ ]NA Date Jf/N h E) Plant Manager
__. Date 1 /.77 F) Director, Nuclear Licensing I A_ - Date R /'?/ p G) OSRO Approval ['><1 N A _h , ,_ DateJ-/-d g g IH)-NSRC Approval Ckd NA D6te l Form P1P.RA2-01 Att 1 P1/1 092188 - ~- ~ - DTC yc g File: / 735
~
- ~ . - , - .. . . .
l I
WFBCTIVEMESS REVIEN l i Reference LCR 18191 - 1011191 - lUlFISl l Revision 0 Page 2 of 1Y g = p u p u e u u = = ; = = PART 1, wsAR i isA wouwwweuun i ;
A) Quality Assurance Program l
[ )Yes ( ) No Does the change (s) ocase to satisfy the criteria of 10CFR50, Appendix B and the UFSAR progran commitments previously accepted by the NRC?
Provide the basis for each change on Attachment 2. Page 2. ;
B) Fire Protection Progras. l
[ )Yes (XX) No Does the change (s) significantly decrease the level of fire protection in the plant?
[ 3Yes (XX) No Does the change (s) result in failure to complete Fire
, Protection Program approved by the NRC prior to license issue?
Provide the basis for each change on Attachment 2, Page 2.
TIM PART 2: RADIOLOGICAL a ,ERuemCx nrarumor. PREPae--a PLAN [IIJNA "Ml A) [ ] Yes- [ ] No Does the change (s) decrease the effectiveness of the RERP Plan?
. ( ) Yes '[ ] No Does the RERP Plan, as changed, cease to meet the-l standards of 10CFR50.47(b) and 10CFR50 Appendix E?-
Provide the basis for each change on Attachment 2, Page 2.
leepeee neveseee neePART 3: 5ta;URITY PLANS [IIJNA n euweepe = = =:ej A) Document A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training bO and Qualification Plan prepared pursuant to 10CFR50 34(c) or 10CFR737
[ ] Yes ( ) No Does the change (s) decrease the effectiveness of the first four categories of Informational Background, Generic Planning Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan prepared pursuant to 10CFR50 34(d) or 10CFR737 Provide the basis for each change on Attachment 2, Pare 2.
lennenanne **** esePART 4: PROCESS CONTROL PROGRAM [XX; NAH " " H H H'l A) [ ] Yes [ ] No Does the change (s) reduce the overall conformance of the solidified waste product to existing criteria for solid wastes in accordance with Technical Specification 6.13?
Provide the basis for each change on Attachment 2, Page 2.
Inununnennup**unuPART 5: ODCM [IIJNA enunpuunnununa j
! A) [ ] Yes [ ] No Does the change (s) reduce the accuracy or reliability I
of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.147 Provide the basis for each chan ge on Attachment 2, Page 2.
- juup***m*** nee *PART 6
- APPROVAL 3' M'######H'H######H i A) C-fginator D. S. Eason [ea yW,.
r DateMf7 l
- B) Technical Expert D. S. Eason [e Date 2-##f C) Quality Assurance (For Security Plans only) Date ID) OSRO (Not required for UFSAR-QA Changes) M v Date 3-1-f l l
l r r r., e . s a w w _ ~ azzia- -
a- - - - -- --
j grygcTITENESS REVIEN DOCU W rFATION l RafGr:nna LCR 8191 - 1011191 - IUlFISI l Reviston 0 Page 3 of 1 4 Dooment UFSAR
-O Listed below is each change, by section and page, the reason for the change and the basis for corcluding that the revised plan or program continues to satisfy the criteria for that plan or program.
Section/Page I (hange l Basis I
l I 9A.5/Pg. 9A.5-22 l Delete word "0NLY" in ITo correct this Section ]
I 1 lparagraph response to iten lto be consistent with l I l(b) on this page such that lpage 9A.5-19 which states l I lit reads " adjustable lall areas use "aa.Justable
! I Ipattern, fog nozzles are Ipattern fog nozzles l I lprovided". Also revise lexcept 5th floor Reactor I I I"WILL BE" to "ARE" to IBuilding....".
I I lindicate existing lThere is no requirement i I l configuration. Ito use fog only nozzles l I I lfor this area. The type O l I
I lused is considered the l I I laost appropriate for the i I I lhazards involved. Fire 1 l l l Brigade members are -
1 I I ltrained in the proper use l I I lhazards and capabilities l I l lof adjustable pattern fog I I I Inozzles. Additionally, I I I Ithis hose station serves i I l lareas where reach of a l l l lhose stream may be l l l Irequired and fog only I i I l nozzles could reduce fire I lfighting capabilities.
' I IUsing fog only nozzles l lcould reduce fire fighting j i capabilities to address i various fires potentially I expected.
t .- n o ne.vu .i c;_ _ _ . _ _ _ _ _ _ _ mm __ __am
n u m. 4c4'ff-#/f-4Xr
-oiti.a ,or p,. ate .n..r enastructies and coerattaa riante ar=2 22:1:e
- rpMV (a) pire originating withis s'embleet er senseles and (b) Seposure fire involving eenheetibles la the general rose area.
Bees stations adfaseet to the sontrol reos & hose station le provided adjesent to with portable estinguishere in the sentret the oestrel rees. Fire eettaguishore reos are seeeptable. are provided adjaeost to er la the een-trol rees.
se.amlee het are esapatiste a, e and equi,es.t 1. th. es.t wi.th e1 ,. the
. .asFad han ==pmetabIpo.ttera, e kWy 8 ed. perse fog'::fra,a'asstee eheu14 he provided ges the assoal hose e tratand a their safe eso.-
ties. Se esseles choses should satisfy actual fire fightaat asede, eatiety slee= %
trieel safety and afsteine test damage to eteetrieel equipment free e strena teplegament. s.
Fire deteettaa la the oestret reos ombi. Semination deteeters are provided la mete, and eeneeles should be provided by the setties of the rose as we11 se la seeks and heat detectore la each fire the aestrel reos sabinete and senseles.
area. Mars and annussiettee should be Additteest preteeties is est11aed la 1
provided la the sentrol rees. Fire alares the fire hasards amanysis. Fire alares ;
la ether parte of the plant should also la ether plaat leestiene are sasunei-he 41eroes and anneneisted la the sentrel sted and seteate alaras la the sentro!
, rees. rees.
3 Breathlag apparates for eestrel reos oper- Sreathing apparates for the sentrol !
atore sheeld ha read!!y available. Centrol reos operators will be readily avata=
resa fleers, esillage, supporting strue- able la the sentret rees. Osattel reen
, tures, and walle, taeludtag penetrations fleers, esillas, sepperting streetuses, and deers, should be designed to a etsimas and walle, imeloding penetrattene and fire rattag of three heure. All penetra- doore, are fire rated as disemesed in tien seale should be air tight. Seetten gh.d. All penetratten seele i will be airtight.
~
Manuelty operated ventilation systees are he weatilaties erstem will esteenti-acceptable. eally be placed la the seeke purge sede i
'sy eentireed setivatten of the salen systee la the sable spreading reos er !
relay rosa. Se smoke purge mode saa also be esaualty lettiat Cables should met he leested la asocealed h e eensealed space honeath the see-fleer and esiling spaces. If seeh een- poter reos subf aeor will be provided
~
sealed synees are used, herever, they with a Balen erstem.
eheuld have fleed automatie total fleedlag halen preteetten. All sables that enter the sentrol teos should terstaats in the .
l eentrol rees. That is, ao sab11aq enould i be etaply routed through the sentrol resa
- free one area to another.
- 3. Cable Screadine * -
p (a) h e preferred aseeptable methode tres (1) Auteestle water systes such as h e sable spreading rose is protected eleoed head sprinklere, eyes head by an automatie Balen syetes.
delete, or open direettenal spray messies.
Deluge and open spray systems In addition, a manually actuated auto-should have prev &olone for esaual entic sprinkler systes la imetalled for operation at a remote staties haetup espability. ,
however, there should slee be pro-eleiene to operation. preclude Imeeticatsadvertent of sprinkler heado er spray nesslee should eensider eable tray staing and I 1 s
-\
9A.5-22 e
~
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~
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L
LICRMSING OIANGE W lUEST AcR -18191 - 1010111 - luirlSi Revision d Page 1'of 3 I m . m w w m PART 1: WSAR. FLAN. OR FIEMNIAN WTI5 ION [ ]NA wwme l A) Dooment UFSAR
- 5) Bection(s), Table (s), Figure (s), etc. Affected ( Attach marked-up pages) l Figures 5.5-19 and 5.2-1 l C) Reason for Diange The above UFSAR figures are prepared based on P&ID l 6N721-2046 and 6N721-5007 respectively. 'mese P& ids are being revised I
per ABN-5441-1. As a result, the above UFSAR figures require a revision
! to agree its P&ID. None of the text of the U5FAR is affected by ABN-5441-1 D) Reference and Sourue Documents (Identify)
EDP Test- CONToniLED ~ ~ ' -
PDC Tech Spec ABN 5441-1 Procedure DER SE (Attached)56-125 & 59-001 Effectiveness Review (Attached)
Other Tech Spec la)rovement Progras l ,
l Drawings, Dsig1 Calculations, Correspondence, etc.
leeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICENSE CHANGES [I]NA eseeeeeeeel A) Document
[ ] Operating License [- ] Tech Specs [ ] Environmental Protection Plan l [ ] Tech Spec Clarification
~ "
B) Section(s), Table (s), Figure (s), etc. Affected ( Attach an. - ~
i ;s^TAfus l
C) Reference and Source Documents Attached g ,,h s g . c;$
i [ ] Significant Hazards Consideration
[ ] Enviromental Impact - Categorical Exclusion Ol$T, $#'MT ba
] Environmental Evaluation
[ .
[ ] Other REV D) Is UFSAR change required?
I ) Yes [ ] No LCR No.
- ~
E) Priority
- ' NRC approval required by (date)
- h.
l An [ ] Emergency [ ] Exigent condition will occur if not approved by: y l (State date): 4c l ,
w /-
. Explanation b ((
M F) laplementation DER No. y e '
i....................,AR,3, A,,,o m S..... ....... .. .... .......i ,
,e A> origina w , R. W. Haupt 4 M S A #
Date a u Q g B) Technical Expert Date -
88h - ~
i C) Nuclear Organization Unit Head / d C , Date M [ g g D) Director, Nuclear Engineering [ ]NA / Date2!2.
E) Plant Manager # Date /
F) Director, Nuclear Lice ing Date M M w SS' <
l G) OSRO Approval [ ] NA Date lH) NSRG Approval [ ] NA Date l Fra n FTP-RAP n1 A r.t i P1/1 n021RR ntr ? ,e , e o Pilar -r s e
LC R
- 89- OOl-UF5 . 4
- PAGE- 2 O F 3 "'.
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'y . PAGE. 3 OF 3 . P"*' "
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loLll l - lOlFl l
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Revision h Page 1 cf.32.
u . . . P A RT 1 : UFSAR. PLAN. OR PROGRAM REVISION I IN A ""**"******"**J .
_ i Document Js=u o \
B) Section(s), Table (s). Figure (s), etc Affected (Attach marked-up pages) klGO2Es 7,4 -I SMEET i Tk4c2O Garrt 6 /
C) Reason for Change cr:c nnu us:n 5;.ws:s5- C'OPd*TcD Al I E*D
~ ' ~ ~ ~
F I
/
I D) Re rence and Source Documents (identify) I
<cuecmL t'c.s=c ATTewenc rs Th Test /
PDC Tech Spec '
i ABN Procedure DER SE (Attached)-w sw A (ce., a h t. .k_cac evN l
' Effectiveness Review (Attached)
Other kCc d QS ose, Drawings. Desi Calculations. Correspondence. etc.
p ...u.....o..*******"gn A) Document
"* PART 2: OPERATING LICENSE CHANGES I INA *******"*"*"l
( ) Operating License [ ] Tech Specs [ ] Environmental Protection Plan I ) Tech Spec Clarification
- 3) Section(s). Table (s). Figure (s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached r g#gT (,,'. 'c3 LE
[ ] Significant Hazards Consideration
~ '
M .W i..' I ] Enviromental impact - Categorical Exclusion I ] Environmental Evaluation goj a A_' d g
_ ,4 M wg,e W(
- c -
- ' A I ) Other Ulbl S' -
D) is UFSAR change required) -
( )Yes [ ] No LCR No Ny' S) Priority a g[
NRC approval required by (date): p NCPY/ $cen An [ ) Emergency [ } Exigent condition will occur if not approved by:
_ (State date): ARMS DfDEEED 7 DTC:veM &qrt 9-R-6'9 Explanation DSN: FF.M,/ upS 4e gj F) Implementation DER No.
p . . ... . . . . . . . . . . . . . . . . . . . . . . . P A R T 3 : A P P R O V A L S- * " " " * " """"" * "" " * " * *" * "" * " * " * " * * " l A) Originator /b ,, [ dd Date 1 lh9/sA
- 9) Technical Expert h Date fz//9/R C) Nuclear Organization Unit Head w' Date / 89 i
D) Director. Nuclear Engineering i ]NA [. [. h__ __m Date //# /7
- ) Plant Manager Date /-/ /-/7 irector. Nuclear Licensing W Date
//ZYh
- 9) OSRO Approval [)tt ,, , ,, Date lH) NSRG Approval I ] NA Date l f orm FP-RA2-01 Att 1 P1 1 052it!. OTC; gg File. Jrj3y
_. -__ =_ _ _ _ _ _ _ _ _ . - _ _ _ _ , _,
1 CCNTINUATION SHEET 1 1
LCR 1818l-1016111-lulFlSl .i l
TSC l l l -l l l l l Revision f Page 2 of 22 A) Document u s=po I Reason for Change ,
o Change documents were written that identified changes to plant drawings, These ,
drawings are the source documents for the UFSAR figures; however, when the drawings were revised, subsequent changes to the UFSAR were not mada. The change documents have supporting Safety Evaluations (identified below) that were previously written. The following UFSAR figures should be revised to incorporate these changes.
Safety UFSAR Plant Drawing Change Document Evaluation 7.4-1 Sheet 1 61721-2230-1 EDP-7645,Rev8= 87-191 A%
EDP-6937, Rev A 88-032 oec- >
7.4-1 Sheet 2 61721-2230-2 EDP-7645,Rev B 87-191 65d EDP-6937, Rev A 88-032 -a W EDP-7718, Rev A 87-200 IM 6 l 7.4-1 Sheet 3 61721-2230-3 EDP-7814, Rev 0 87-326 c&
D V 7.4-1 Sheet 4 61721-2230-4 EDP-7645,Rev B EDP-7609, Rev A 87-191,A A%
87-169 n d EDP-7748, Rev A 87-217 AG 6 7.4-1 Sheet 5 61721-2230-5 EDP-7609, Rev A 87-0169 A56 -
7.4-1 Sheet 6 61721-2230-6 EDP-7814, Rev B 87-326 e o Changes to the UFSAR are being made to incorporate previous equipment , changes that were the subject of previous FSAR revisions, but in which portions of the FSAR >
requiring revision were inadvertantly not identified. The specific changes to be made are:
- 1. UFSAR Section 5.5.6.2.2.4 describes the operation of the Steam Supply Line Bypass Valve (E51-F095). This section states that the valve should open or close against full pressure within 15 seconds. The E51-F095 valve function was effectively removed from the RCIC system by adding a blank flange upstream of the valve by Minor Modification 8511, and was supported by Safety Evaluation 88-0033. The UFSAR will be revised to delete reference to E51-F095 in section 5.5.6.2.2.4. UFCN 88-030 was previously submitted; '
however, this section was not identified as requiring a change. This change will reflect the As-Built condition of the plant. I l
- 2. UFSAR Figure 7.4-1 sheet 2 shows the operation of Steam Bypass Valve
/~ E51-F095. Because this valve function is no-longer part of the plant design, f\ '
per Minor Mod 8511 and Safety Evaluation 88-0033, Figure 7.4-1, sheet 2 will be revised to remove all references to the E51-F095 valve Form FIP-RA2-01 Att 5 P1/1092188 DTC: File:
~
l l
, in/ &222.
mm o6t. Os=s y
- PRELIMINARY EVALUATISN Pg 1 of 1 ;
ooo.......................................................................................................
. PART 1: DESCRIPTION OF CHANGE (Preparer) ]
A) Document identification l B) Revision C) Pts Number i e t2 ag . emt. opw I c6 u/A D) Description of Change 6EEVE12.AL. Gfli: 4. mom cf THE OPSA9 A2e ed is.y::, s yPDATED T o 19 Col 2.pcztATEE Ct16 TM AT *J EEEE iWNY mis 6ED iM AlteL'v1005:, uvesAst REVistCNEi .
Au we -m mvous samy wwmwas.
f 4
s.
uoo......................................................................................................
l PART 2: PRELIMINARY EVALUATION (Preparer) l A) Review of Commitments M No commitments
[ } Commitments exist. (list) _
( ) (.,ommitments met - None negated
[ ] Commitments need changing. (explain)
B) Impact on License, Plans, or Programs
[ ] No change to Operating License (TS EPP). TS Bases. UFSAR, or NRC approved plans or programs required p1 License Change Request (LCR) recuire:: LCR 16I BI-!Ok>l ll-lOlFlSI 1 C) Effect on Environment
~
$4 No effect on environment
[ ] Environment affected Contact Fermi Environmental Programs Coordinator and indicate resolution D) Need for Safety Evaluation (check appropriate answer)
Yes No Y PQ [] 1. Is this a change to the facility, including assumptions, as described in the UFSAR?
[] M 2. Is this a change to a procedure, including assumptions, as described in the UFSAR?
[] M 3. Does this change constitute a Special Test? ,
if any are 'Yes
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- -(TYPICAL FOR ALL WOV'5) VALVE FN8 HAS ADDITIONAL INDII.
i~ INDICATING LIGHTS (NOT AS A PART OF PB) i INDICATING LIGHTS LOCATED AT IS0LATION STATUS
- DISPLAY WIMIC-VALVES FN7,FN 8,Fele,F812,F813 l F829,F831,F845'AND F859 ONLY. /
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- 4. Valve Operation Requirements (Cont'd) 267'F.. Physically located as close to the containment as practical.
Vacuum pump discharge opens-and/or closes against 50 psi dif-isolation (F002) forential pressure at temperature of 267'F. Physically located as close to the containment as practical. ,
Ot::: ::;;1" id : typ :: 0;: ; iret fill ;;rrrer?
. . . . . . _ ,.m .f .2 <2_ _/.::__cler:
-r-; - - . ,
check valve turbine Located at a high point in the line on a horisontal run, with adjacent piping exhaust (F040),
arranged to provide a continuous down-ward slope, from the upstream side of DELETE the check valve to the turbine exhaust drain pot.
Vacuun breaker isolation open and/or close against a differen-valves (F062 and F084) tial pressure of 50 psi at a nominal rate of 12 in. per minute.
Vacuum breaker check open with a minimum pressure drop (less i
valves (F063 and F064) than or equal to 0. 5 psi) across the -
valve ~ seat. , ,,,j
- 5. Rupture Disk Assemblies (D001 and D002)
Used for turbine casing protections includes a mated vacuum sup-port to prevent rupture disk reversing under vacuum condit. ions.
Rupture pressure 150 psig i 10 psig Flow capacity 60,000 lb/hr at.165 psig
- 6. Condensate Storage Requirements 70,000 to 111,000 gal (Total reserve storage for both HPCI and RCIC' systems.)
- 7. Piping RCIC Water Temperature The maximum water temperature range for continuous system opera-tion does not exceed 140*F. However, due' to potential short-term operation at higher temperatures, piping expansion calculations were based on 170*F.
- 8. Turbine Exhaust Vertical Reaction Force Unbalanced pressure due to discharge under the suppression pool-l water level is described in Reference- 6.
I 5.5-18
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, V FWuSE ~7.4-1 SWEET 2 DETROIT BOISON COMPANY DRAWING NO.817217130 2.MEV.0
. LIENSING CHANCR Rf4UEST e LCR 18181 - 1015191 - IUlrlsi Revision 0 l JRmunnH.PART 1:~{TFSAH. PLAH, OR PROGP1.M RETISION [ Page ]NA 1 .H of 3.MH l !
A) Document UFSAR B) Section(s), Table (s), Figure (s), etc. Affected ( Attach marked-up pages)
UFSAR FIGURES 7.6-11 and 11.4-1 c 10t. E vi.i C) Reason for Change The above UFSAR figures ~are prepared based on PalD 61721-2679-1. This P&lD is being_ revised per ABN-5434-1. As a result, the above sentioned UFSAR TTgures require a revision to agree with its P&lD.
None of the text of the UFSAR is affected by ABN-5434-1.
D) Reference and Source Documents (Identify)
EDP Test CONTROLLED PDC Tech Spec l ABN 8434-1 REV. O Procedure 1 DER SE (Attached) 55-0240 REV. O Effectiveness Review ( Attached)
Other Technical S>ecification laprovement Program item Drawings, )esign Calculations, Correspondence, etc.
leHeressessemaneeensPART 2: OPERATING LICENSE CHANGES [I ]NA es.e eene l A) Document
[ ] Operating License [ ] Tech Specs ( ) Environmental Protection Plan
( ) Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
~
C) Reference and Source Documents Attached
] Significant Hazards Cons!cterstion STATUS
[
O [
[
] Enviromental Impact - Catego ical Exclusion
] Environmental Evaluation O ^, ^ "I . N'M glgy,h M '
( ) Other D) Is UFSAR change required? btV.
[ ] Yes [ ] No LCR No.
. E) Priority NRC approval required by (date):
_ An ( ) Emergency [ ] Exigent condition will occur if not approved by:
(State date): ft]
Explanation E I
% p9 F) Implementat. ion k l
DER No.
,....................,,R1 3, A,,, ems...................................,
- g A) Originator R. N. }{aupt f/' Date /h/[8$ '
B) Technical Expert 4. Jt. Date3/27h C) Nuclear Organization Unit Head h$b .
Date </f D) Director, Nuclear Engineering [ ]NA / _
Date J/N E) Plant Manager MC . dono h Date .I//[
j F) Director, Nuclear icensing % Date 't h l
G) OSRO Approval [ ] NA Date IH) NSRG Approval [ ] NA Date l l ,
l Fora FIP-RA2-01 Att 1 P1/1 092188 DTC: gpa_ga File: g s- J
~
~
3
, y . g; y; -g; ..
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- PAGE 2 OF 5 !
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- f il
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o6 PRIMARY CONTAINMENT MONITORING SYSTEM .
viam DETROIT EDISON COMPANY DR AWING NO. 61721-2679-1, REV. R .
C 3 -
___m.m_-
l 1h'NSE-iY$5^7 ARMS INDEXED LIMNSING CRANGE REQUEST DTC: rL4M Mn, f/W/
LCR 18181 - 1015181 - IUlFISl
>' DSN: SY r$& u r.S A'u <f Revisiond Page 1 of 2 I :::::;99999 u PART in UFSAR PLAN. OR PROGRAN REVISION [ ]NA m eT Hej A) Document UFSAR B) Section(s), Table (s), Figure (s), etc. Affected ( Attach marked-up pages) f Table C) Ranson for Change 9A.6.2-1 To change Fermi 2 diesel driven fire pump / CFE,iv' w e*
(PIS No. P80000001 starting 24V batteries specific gravity requirement from 1.200 to 1.235 and the overall bank battery voltage from 24V to 26.2V.
l l
D) Reference and Source Documents (Identify)
EDP Test CONIMULLED i PDC 5523 Rev. K B M t' Tech Spec Section 4.7.7.1 3 ABN Procedure 42 501.01 l DER 57-0330 SE ( Attached) SE-58-0239
) Effectiveness Review (At.Lached) *^f. LO OC wrW-ZwSi Other Memorandum NE-PJ-88-0628- Dated October 13, 1955
- Drawings, Design Calculations, Correspondence, etc.
j leeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICENSE CHANGES (II)WA #HHHHl l A) Document
( ) Operating License ( ) Tech Specs ( ) Environmental Protection i Plan 1
( ) Tech Spec Clarification
! B) Section(s), Table (s), Figure (s), etc. Affected (Attach
~ . .BTXTUdi C) Reference and Source Documents Attached ggg og q fg g l O (
[
) Significant Hazards Consideration
] Environmental Impact - Categorical Exclusion DIST. $ EFT B7
[ .) Environmental Evaluation
( ( ) Other REV.
i D) Is UFSAR change required?
i -
( ) Yes ( ) No LCR No.
j E) Priority i
NRC approval required by (date):
An ( ) Emergency ( ) Exigent condition will occur if not approved by:
(State date): '
Explanation F) Implement.ation DER No.
inuunun muuPART 3: APPROVALSmtmmp9munneme mmen l A) Originator Q v 'T' Ma Date dit/By B) Technical Expert _ es _
Date /-/f-Pf PN C) Nuclear Organization Unit Head %,4- .
Date / I@
D) Director, Nuclear Engir.cering [ INA Date J f E) Plant Mar.ager d,-- Date l d ,[/
F) Director, Nuclear Licensing ,
Dat[/[fyr
.pa g wi G) OSRO Apt
- oval (Y) NA Date gyptn -
lH) NSRG Approval ((]NA Datt Fora FIP-RA2-01 Att 1 P1/1 092188 DTC:gp File: /Qf
I
~
L ck. 89 058.W1 <
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l LICDISING CRANCE RElUEST i
IIR 18181 - 1015111 - IUlFlSl !
. ]
- Revision F Page 1 of M l - PART 1
- UPSAR. PLAN. OR rhuGRAN IETISION I ]BA --- ;;;;l A) Document UFSAR _ CONTRotLED N N B) Section(s). Table (s), Figara(s), etc. Affected ( Attach marked-up pages) V See Page 2 for list of affected figures and tables, k) fly $
C) Reason for Diange 'Ihe listed figures and tables are revised as shown 3 to document changes made to the plant process sampling systen as a result
~
si k of EDP-7516.
D) Reference and Source Documents (Identify) f E
W(,q}p MG -
EDP-7816 (2e/.c. Test N/A RN
"' [
PDC N/A Tech Spec N/A
'nf ABN N/A Procedure N/A '
DER N/A SE (Attached) 55-0235 co i Effectiveness Review (Attached) N/A J e4 i;
- Other 144 ECR-7t/6 2.etyW Ect1rs.3 teus F
> e i
d',p9 C'M Drawings, Design Calculations, Correspondence, etc. E
- lSQ',b $ !
6 l********************PART 2: OPERATING LICENSE CHANGES [ I]NA .
A) Document tu
- [ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan p'
[ ] Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-un n==a a p
-..,7,.9 ~~
C) Reference and Source Documents Attached
( ) Significant Hazards Consideration J .' "" as a-J "IM
( ) Enviromental Impact - Categorical Exclusion^ ', n , . , jf,g pq .
( ) Environmental Evaluation
[ ] Other ipu ,
D) Is UFSAR change required?
( ) Yes ( ) No LCR No. l Y ^- ' # ~ g .
4 E) Priority u-NRC approval required by (date):
An ( ) Emergency ( ) Exigent condition will occur if not approved by:
(State date):
Explanation i F) Implementation
! DER No.
i IH m m " m m m 'PART 3: APPROVALS l g g g.) IT A) Originator G. N. Eide a /M66 ll,[)/h B) Technical Expert 'kd d Date // ,
, n-r g C) Nuclear Organization Unit Head d 3 ) . b un us' Date II-b N '
D) Director, Nuclear Engineering ( NA Date // jr#
E) Plant Manager Date //,-[p F) Director, Nuclear Licensing -- # Date ,lf [/f M I C L OSRO Approval ( ) NA Date W
fby g roval ( ) NA ,
1 - ^* Sei 1 p1/1 OQ2155 N
T $4 @ _ _ _..E&cr e._.___
I 00IlTIllUATICII SEET l 14R 18181 - 1015l11 - IUlFISI TSC l l1-IllI Revision # Page 2 of J1 A) Document UFSAR l l
Part IB) (Cont'd) l The following UFSAR Figures and Tables require revision as a result of EDP-7816. '
EDP 72.ib aosoO U FSAg ig pact- eg op, ,150 uo. bw ta . uo.
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- 1. Table 9 3-1
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j TABLE 9.3-1 TURBINE BdILDING PROCESS SAMPLING SYSTEM i
Seerce.eperetlas -
senple ve , per m er type of analyele % ,eretore creusere Item me. ee.ert ,tlen te,eetion senple anearete =>de e*rs feelst i
1 TDCtw 12) t and w heet eschenger Twbe teste Conductlelty & ecol gretr 95/13e 33 outlet 1.shoretory 2 Condenser Condenser leet semple reteen ^-
100 -14 '
teoughe 1Ine _
, 3 Condenoote 13) Condenoste puoyo Condemoete Swity Crob stetten 94 213 i discherge north- equellty and to ory ;
center-south tube techo t 4 condenoote Condeneete pumpe Condenoote I. Dioeelved Os Ctpattaueen 94 213 diocharge heeder geelity and 2. Condwet twit y grott etetton
- tube leone Laboratory Condenser (6) space tape - 100 S Condenser test -le 4
treeghe inlet and not used
, cetlet each #
- J egoodrant turbine g 6 Condenser Condeneer feelt treogh Seegrie pum, y pr i- :s 7 condoneer elecoleting WE and SE ester boe Water enelyele pW. chlorinetten Cret> etetten 99 SS
' p.e ester system 12) Influent lotoretory '
- e AM B {,
o Condenser elecoletin, ester system 12) e and w seter teses effluent noter enetrole Chlorine, eendse-tivity, pW, and Cret,etetson- sie se ll
- I
, A er 3 total sellde laterotory .
9 condonoste polishing deelnerelleer petishing deelnerelleet Intet heeder Condemoete geellty and 1.
2 wigI sedlee centlassee gest > otetten 94 213 tube leeke I.eteratory j 10 Cendonoste polishing pellehlag deelnerelleet Treeted conden- 1. condsettetty costlesome 94 21 3
, domincealleer outlet heeder sete erselity 2. Sleoglyed Oy groep stetten
' r-rc FOLREvlydriroTI+ecs . >
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TABLE 9.3-1 TtmBINE BUILDING PROCESS SAM 5 LING SYSTEM (Cont'd) i Source Operettne Semple top Purpose of Type of Anelfele 9*nperatore Pr'esere Item Do. Descriptlen 14eation Sample Analyels 8eede (*FI 198999 i
i 11 Feedseter Secotere sno. 2 FWR effluent teater snelycie 1.aboratory Crab stetten I67 4 74 i
- 14) lie IIA. 119, header 2w. 2C. 25 IIC 12 Weectog feedseter After Iest feester lest ce one1yeIe beConductt,Ity CentSnoose 429 999 system (2) A and 9 6A and 6ft (2) I 29 Turbidity T greb stetten IA Dissolved Op l ,
2A Conductivity '
( taboratory - [
, 13 mester feed Wester feedpump die- teater snelyste Dissolved Oy Continueue 94 799 charge header I.eboratory greb etetton ;
2 ;
14 seeln etese feeln etese line Steen conditione Condwettetty Continuous S42 997 ,
(2) (A or 9) 1.eboratory greb stat ton 15 prelne cooler Drain dieeterge esoter snelyele 1.aboratory Recol greb to conde,,er 194 -12 pele ,
en 3 >
16 Demereting see. 5 Ino. Ser f SS deeln Diesolved osygen 1.aborat ory 792 to heater (2) deeln outltt Crab stetton 239 E W Feedseter leeetere
(
17 112) c h e inlet and outlet to tocaters tieter emelyele laboratory Spore tape - 195-499 999 k o jg not used 634 g ye,dester teeetere Dreine inlet and tanter enelyelo 3 '
(12) outlet to locaters I.eboratory Spore tape - [195-499 -13.5-345 seet used
}
19 Condenoote pollening Polishing deelnerelleet Condenoote conductlet t r:a_ ,
94 213 deelnerelleer inlet heeder geelity l
- 29 Condeneste p liehlseg polletting deelnerelleet Beelnerelleet tlwity Continueue 94 213 j
.I deelnerelleer effloent teceder efficiency -
(
- 21 Ceneral serelee Effluent tereder tester snelyste Chlertnetten Recol greb 95 ISO i i
ester heeder to circulatin9 ester j 22 peector feedester 36 in. 9eceder efter
' (e) (e) (e) 499 127S 2 system hester 6A and 69 '
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TABLE 9.3-1 TURBINE BUILDING PROCESS SAMPLING SYSTEM (Cont'd)
~~
Sample Top purpose of
_ Seorte Gueretten Item esp. Type of Analyelo troperatore Preeeere DeeerIptien tecet Ion Sempte oneIyeIe stede f*F) IpeIg3 23 Condenoste 84) leetwell discharge pipe coch geodrent, Tube leste { Laboratory sr mmW c1.7 -9 t j condeneer N ,
24 Ciresteting Ciresteting water Proportional Laboratory proportlenel 95 90 water decent decent Ilne semple of esepter with and eseple decent to Leere gree,etetten return 82) Erle 25 Peedseter heater Hester deeln peepe feelesting Diesoleed 03 Contineses MS P
deelne discharge heeder 791 heater deeln Turbldlt contribution to feedveter 26 Citeeletlag Discherge of decent smoter enelyele Laborotory 1,ecel groep 95 Se unter decent pumpe before redueste 27 sessicey deelnerelleer Top on tenet Tent ester Laborotory tecol grote Astylent Tenet heed storage tank perity 29
%i Condensete storage Top on tenet Tant seter laboratory Recol grote Amapleet ga , tent petity Test lieed f g l>ee*F) -
M. 29 Condeneste reture se ,r Top on tenet Tant water Laboratory p* tenet perIty Imcel grote Went Test Steed C,I 895*F) *!
w ..iet u - to C.,reter. u . C., es,,,,i y condeneste reterm perity i.eterator , teesi , ret, ,, ,. ,,!
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- P A RT 1 : UFSAR, PLAN, OR PROGRAM REVi$lON [ ]NA *"*******************l A) Document UFSAR Section 11.4.3.8.2.15 CONTROLLED
- 8) UFSAR Section(s), Section Table (s), Figure (s),
11.4.3.8.2.15: etc. Affected UFSAR Table 11.4.1, (Attach Fig raarked-up 11.4-2 : Fin pages)4-5it. crvoi-or,a.1 4 3 C) Reason for Change The plant does not intend to use station air for breathing purposes? D) Reference and Source Documents (identify) EDP Test PDC Tech Spec ABN QS *T7 - l Procedure DER SE (Anached) 88-0232 Effectiveness Review (Attached) Other RACTS 5654 Le%r A/ F-4.C-f r - O /0 9 Drawings, Design Calculations, Correspondence, etc. ' P ** * * * * * * * * * * * * * * * * * * * * * * * "
- P A R T 2 : OPERATING LICENSE CHANGES [ X]NA *********"*"******** l A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protectio n [ ] Tech Spec Clarification _ B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up p Cjq C) Reference and Source Documents Attached O/g7 [ ] Significant Hazards Consideration PSQ [ ] Enviromental Impact - Categorical Exclusion kk /9e l [] ironmental Evaluation D) is UFSAR change required? 'l N f. [ ]Yes [ ] No LCR No. / E) Priority NRC approval required by (date): NQ An [ ] Emergency [ ] Exigent condition will occur if not approved by: ! (State date): ARMS INDEXED Explanation
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f u mt pg. g g.p p5 f(c.. G Og l /C v: p V.gr /M~O .' F) Implementation 4 DER No. r............................,AR13, A,,RD,A<S__........._...__...~._._......._.._..., A) Orininator AAAAA-- f (n K SM A A M A ) Date it ~ ~E - SS B) Technical Expert [] (da'#*IMANMA) Date (f. 88 C) Nuclear Orga t Date // f D) Director, Nuclear Engineering [ ]NA m Date
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l E) Plant Manager Date t) Director, Nuclear Licensing Dated //W l G) OSRO Approval [ ] NA /)) _e s Date *2/7/M lH) NSRG Approval [ ]NA Date l I Form FIP-RA2-01 Att 1 P1/1092188 f g p(,gs m e,,,wg DTC: rt.t.cq, File: l16E ombgewAme . _ - - - --
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aswing tho 20dictien eslocco, uoing tho radiotiCn iconithra TS
. 'dotormino which in10t has tho 16 wast radiction lovelo AOk
- This systcm is Quality Levol I and Catogary I. F8rrodundancy,Og UFS two detectors are provided for each intake (north and south). O Arrangement details are shown in Figures 11.4-2, 11.4-5, and 9.4-2.
Dn(2 TE THlS SECTIOtd. 11.4 3.9.2.15 Breathine Air Wadiation Monitor 8vhtem This onitor system measures t activity in the be thing air prior o the control air isolat on valve. The norma air proc-essing nit takes the air from t e station air system. q is then cleaned, filtered, and a itored for grade B a The air quality, before ing su through a hose,pplied breathin air to individual wo kors as regulator complies pressure and mask or suit. e system th Regulatory Guide 8.15 A represent tive air sample is extra ted from the manifold f the station air pstream of the control a isolation valve. A stainless at el sample line is used to rocess a sample the gh a gas monitor, low-flow switch, and a a sple pump, before th - sample is ret ned to the manifold. The sampling as embly is made of one off- ine gas monitor, a local beta-sens tive scintillation detecto acunted on top of a h l1 11.4-22 - i
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PERW 3 UPsAR stain 1 ss steel chaab r, a preamplifier, and a diation analyser locate on the relay on anel. One hi O tow-<1-room. i==F recorder is ti , p<1 ovided. ovih-radiae a ia ion and i one === 1 The range no sensitivit of this detector are list in . Table 11.44 The system is Quality Level III and nesismic. Arrangement details are a wn in Figures 11 4-1, 11. -2, and 9.4-2. The monitor i installed an will be functional prior the irst refuelin . Use of sta on air as a supply for br athing rposes will t be permitte until the monitor is fun ional. ernate respirgtory protecti asasures will be used the i erim. 11.4.3.8.2.16 Onsite storage Facility Ventilation Eshaust . Radiation Monitor System This monitor subsystem seasures the radioactivity in the radwaste O ' onsite storage facility exhaust prior to its discharge to.the environment _and,.in doing so, complies with Regulat.ory Guide 1.21, Revision 1, and GDC 23 and 64. The activity this monitor e detects is a result of the storage and handling of radwaste and equipment in the building. Resultant radioactivity is normally expected to be below detectable levels. The particulate and iodine activity is accumulated on filters viewed by solid-state, e be.ta scintillati,on,and
, __.... gamma scintilla. tion' dete.ctors. . ,,se The
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. . DSN: W.W& t#S O'l(t Revision /
Page i of 18
~9'jn.n.9....s..PART1: UFSAR. PLAN. OR iFh0 GRAM REVISION [ ]NA M# ..e#l A) Document UFSAR B) maation(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
(See Continuation Sheet) C) Reason for Change Installation of a Sample Drain Collection / Recovery : System. y D) Reference an,d Source Documents (Identify) EDP 1080 Test N/A CONTROLLED PDC N/A Tech Spec N/A ABN N/A Procedure N/A DER N/A SE (Attached) 55-0224 Effectiveness Review (Attached) N/A 1 Other N/A Dr ~ leeeeeeeeeeeee.awings, Design Calculations, Correspondence, etc.
.e.eeePART 2: OPERATING LICENSE CRANGES [I ]NA seeeeeeeel ,
rating License [ ] Tech Specs ( )E [ ] Tech Spec Clarification km M1 B) Section(s), Table (s), Figure (s), etc. Affected (A 04 Y -
. Ten g C) Reference and Source Documents Attached -
[ ] Significant Hazards Consideration RC 9 [ [
] Enviromental Impact - Categorical Exclusion ronmental Evaluation "
J D) la UFSAR change required? [ ] Yes [ ] No LCR No.
., E) Priority NRC approval required by (date):
An [ 3 Emergency [ ] Exigent condition will occur if not approved by: ' (State date): Explanation F) Implementation DER No. i .................., m 3, A,,Ro m S................ m = = = = ,....si A) Originator L. Hitchell h /S&W 4 S B) Technical Expert /[ ag . , , ,. Date ,/Z[/6k C) Nuclear Organization Unit Head AC/ti -_d- suc- Date E/7/G D) Director, Nuclear Engineering ( INA Date /d E) Plant Manager 4/ .d. DateJ//48f F) Director. Nuclear Licensing
/G Date C) OSRO Approval [ ] NA Date H) NSRG Approval ( ) NA Date l
? Fors FIP-RA2-01 Att 1 P1/1 092158 ) DTC: h_liletin=_--- a
a e corrINUATION SHEET
.. .. IAR 18181 - 1014161 - IUlFlSl I O Wl l-l l l l Revision AI Page 2 of 18 !
A) Document UFSAR l Sect. 9.3.2.2 " System Description" See pages 2 & 3 Fig. 10.4-8 Sht. 1 See Pages 4=thru 6 GW40l.sk Fig. 10.4-8 Sht. 2 See Pages 7 thru 10 6 nut . mM .l Fig. 10.4-9 .bt. 1 See Pages 11 and 12 6 m e t. my 10.4-9 Sht. 2 Fig. See Pages 13 and 14 6 m C \.,0cc4 - I f Table 9 3-1 See Pages 18 thru 17 F/Anafef-85-87 Fig. 9 3-1 See Page 18 (Full Size Blue Line 6,TU . WCo.3 Drawing) INSERT "A" r- 2 3 A special Sample Drain Collection / Recovery System has been designed to reduce radwaste burden by collecting and recovering certain sample drains which are of sufficient water Quality to allow recovery into the condensate process flow without radwaste processing. The system s consists primarily of a single tank with 240 gallon working volume and 20 GPM pump. Normally this system discharges to the condensate puup - suction header but defaults to Turbine Building floor drains. N
/
l O Form FIP-RA2-01 Att 5 P1/1 092188 DTC: File: _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ - . . . . . , . _ . . . _ , . _ - _ , ._...,,,,__..,,._m..,v.. . ,. ,-.,.. . . , - . , - - . _ . , . . . . .
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LCR SS-b46-0F5 nya i pawn a UrsAn N # f 7t h Y k ht h ()g After sample conditioning,Athe samples'ilow unrough the analysis instrument ion to the radwsste floor drain system, (DtMTA"XEK 2) , Central and sampling reactor stations are located in the redweste, turbine, buildings. This is done to minimise the length of the sample lines and therefore shorten the transport time for the samples. Each central sampling station contains the remote and continuous samples as discussed in previous paragraphs, grab and the temperature conditioning equipment tion. The central sampling stations are and analysis instrumenta- , l hoods to draw air from the sample sinks. ptovided Airflow with is 100 exhaust to 150 l linear ft per minute. i All remote sample lines, where possible, are pitched 1/4 in./f t ' in direction of flow. The sample line lengths are es short as possible and the routing avoids tra upstream from the sample discharge.ps, deadlegs, Sample flow and is in dips the turbulent-flow sentative region to minimize deposition and to ensure repre-samples. accessible areas. Local samples are located in well-ventilated streams to the floorDrain drain funnels syst are provided to carry sample 9.3.2. h MidiAG M 7 Al!Wff#6l Safety Evaluation =*s- - Samples that require special handling, and all sample lines that flow continuously, lead to central sampling stations in the - reactor ing. building, the turbine building, or the radwaste build-The central sampling stations are equipped with ventilation I hoods, backflushing facilities, and pressure and temperature controls. Remote air-operated sample valves are controlled from I these central sampling stations. l High-pressure sample lines are required to pass hydrostatic tests with the process units they serve and must conform to the same j , construction standards. i All sample lines have a shutoff valve located as close as possi-ble to the sample source connection. This valve is manually i operated if accessible, and solenoid operated where inaccessible. Solenoid valves are designed to fail closed. Soft-seated sole-noid valves are provided to ensure minimum leakage because leak-age could go undetected for long periods of time. Since all samples have a potential for becoming radioactive, the following special precautions are taken to minimize radiation hazards to plant personnels
- a. Sample lines are routed wherever possible in shielded areas where plant personnel have little or no access l
- b. Equipment that tends to trap activated " crud" is kept
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E. bt 121- 2400 RLACTOR BLO6. SAMPLIN6. - - 61721-2400-1s-S PLANT SAMPLING REGul ENTS. DE91GN INSTRUCTION Non , 9 WATER 9 EQUIPMENT DIVI 9 ION DWG'*: l A. S7326 DE Co FILE No.Cl-637 TURBINE BLDG.SA4Pl. 9BMIONS. . -
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14R 18181 - 1013141 - IUlFIS! Revision F Page 1 of 19 Os I - PART 1: UFSAR. PLAN. OR ruivunAN RETI5 ION [ ]EA r-- ;;:1 r h.I A) Document to! (y UFSAR B) 5ection(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) h'S See Page 2 5 L EQ ! C) Reason for thange The addition of the corrosion product sample panel O has revised several Figures and Tables in the UFSAR. % p! I oD b r'ANTROLL t:.C k' . E D) Reference and Source Documents (Identify) EDP-1809 Rev. B Test N/A h i $ E l 1 PDC N/A ABN N/A Tech Spec Procedure N/A N/A f< 'N ^ l DER 55-1311 Effectiveness Review (Attached) SE (Attached) 55-0070 N/A Other ECR-1809-1 Rev. A, ECR-1809-2. Rev. # lg'N$> w i tz Drawings, Design Calculations, Correspondence, etc.
- l####################PART 2: OPERATING LICENSE CHANGES [I ]NA eteeeeees l ;
A) Document l l ( ) Operating License ( ) Tech Specs [ ] Environmental Protection Plan lw [ ] Tech Spec Clarification S$ e E B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages i C) Reference and Source Documents Attached m.
'~~"'ga r-O. [
[ [
] Significant Hazards Consideration
] Enviromental Impact - Categorical Exclusion
] Environmental Evaluation
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B) Technical Expert W.V/.MC Ad?iLY d Date //!$ 9 C) Nuclear Organization Unit Head / d. curoui Date ll'bM D) Director, Nuclear Engineering ( NA Date # /[F E) Plant Manager dh Date // f..har F) Director, Nuclear Lice sing Date / /// G) OSRO Approval [ ] NA _ Date
'Hi NSPF ia-' L,ffprs- '.a1 u._/v
[ ] NA Mn=" < wifW- J. ___ _ _ . . . _ms _ _ o som_ Date I
ODNTINDATION M ulm 18181 - 1013141 - lUlFISI Tsc I I I - 1 I I I Revision W Page 2 or 19 A) Document , UFSAR l B) Section(s) Table (s), Figure (s), etc. affected Table 9 3-1, Page 9.3-20 Figure 9 2-12, Sht. 2 LMn eu I Figure 9 3-3 < Tm cre 'm Figure 10.4-8, Sht. 2 r. m% \ *w ,4 t Figure 10.4-9, Sht. 2 G m .am L u z. I Figure 10.4-9, Sht. 1 f.r n m. sv <: j Figure 10.4-10 OcA9s :,ect O l l [ ... l l ., _____3 i I __ -._ i - _ o _ Fors FIP-RA2-01 Att 5 P1/1 092185 DTC: File:
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- 1. GE FEEDWATER CONTRDL SYSTEM $1721-2125-185 733E153-R1-155
- 2. CONDENSATE SYSTEM
- 3. FEEDWATER EATER. DRAINS SYSTEM
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- 4) Document- PART 1: W N M. PLAN. OR m -MAR REVISIM L , BA ;;;;;;;e]
UrSAR B) CONTRO Mtion(s), Mble(s), Figure (s), etc. Affected (Attach marked-up pages)LLED Section 8.3.2.1.1 Figures 8.3-9. Sh #s 1. 2. Fiaure 8.3-11 i C) h e for change Increase the low voltaae (undervoltage) alarm for Division I & II ESS and BOP battery chargers from 124.5V to 125.5V. D) Reference and Source h uments (Identify) EDP Test f.M PDC 9695 Tech Spec Table 4.5.2.1-1/i ABN Procedure ~ DER 55-1923 ! SE (Attached).. 55-0219 ) Effectiveness Review (Attached) Other 6SD721-2530-10, ii & 12. DC-0539 \/oLIt bed Drawings, Design Calculations, Correspondence, etc. ( VJ-c o - % . cAQ jeeeeeeeeeeeeeeeeeeeePART 2: A) Document OPERATING LICENSE CBANGES [II]NA #########l ! [ ] Operating License ( ) Tech Specs ( , Plan ) Environmental Protection ' ( ) Tech Spec Clarification B) htion(s), Table (s), Figure (s), etc. Affected (AHa* -----,,,,)
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t ied.m '.w and Source Documents Attached BTAids O (
) ..gnificant Hazards Consideration 3 'aviromental Impact - Categorical Exclusion ASB r ' ' y "
Bnvironmental Evaluation ()}gy 6ef7' 93 ( ) Other REV. D) Is UFSAR nhange required?
- [ ] Yes [ ] No LCR No.
E) Priority . i NRC approval required by (date): An [ ]Energency [ ] Exigent condition will occur if not approved by: (State date): Explanation F) laplementation DER No. gee::::: :cce==::::::PART 3-APPROVA15 ;;:::::::;;::GMl A) Originator F. T. Konja G 'T Met Date 12./S/8 6 B) Technical Expert ih h. =,.T 1 d Date /fd/N' C) Nuclear Organization Unit Head . h/ e/Mh88 D) Director. Nuclear Engineering ( NA Date / //f E) Plant Manager k O s- Dates.t.A9 F) Director. Nuclear censing _- 6 Date //2.5 /$ 7
- 0) OSRO Approval (XX) NA Date lH) NSRG Approval (IX NA
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l, certain positions on the ESF 480-V buses supply non-safety-related loads. The control logic power for these positions as O well as the safety-related battery systems. Non-safety-related de power loads, such as positions is supplied by the class lE
- emergency oil pumpe, are normally supplied by the 20P battery i
system. Where non-safety-related power loads exist on the Class lE battery systems, a Class 1E isolation device will dis-connect the non-safety-related load from the Class 1E battery system on receipt of a LOCA signal. i i The ESF and BOP systems are protected from voltage variation by an undervoltage and two overvoltage circuits at the charger. overvoltage circuit deactivates the rectifier bridge When the One voltage exceeds 138.5 V, while the other alaras to the main control room any voltage surpassing 136 V. The undervoltage relay alarms in the' main control room 3f the voltage at the main distribution panel drops below _ J '1-gg
- 8. 3. 2.1. 2 260/130-V DC Class ir Fower System -
Two loads. center-tapped 260-V batteries are provided for Class lE They are designated as 2PA for Division I and 2PB for Division II, and are shown in Figure 8.3-9. The batteries are located in separate rooms in the auxiliary building. The chargers and related equipment for the Class 1E batteries are located outside the battery rooms, in accordance with the separa-9 tion criteria required for redundant systems. 4 i Each in series. 260-V battery is divided into two 130-V batteries connected battery charger. Each 130-V battery section has an adequately sized These chargers are connected in parallel through fusing to their respective battery. For each 260-V battery, a 130-V spare battery charger is provided that can replace either of the normal 130-V connected chargers. The replacement can be made manually When it has been verified that the Figure charger 8. 3-9.is connected to the proper 130-V battery, as shown in
- Each. division's two 130-V batteries and their j chargers division. are the source of de control power for that respective 4 To maximize the reliability of system control power, the following. philosophy is applied
- a. Control power for each of the two load groups within a I' division ~is supplied from a separate 130-V de section of that division's battery
- b. I Power for control of each division's two diesel i generators and their associated switchgear. is supplied from the 130-V de battery section supplied from their respective load group.
The 260-V during shutdownsources conditions.furnish power for the de motors necessary l For 260-V use, the battery is 8.3-40
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- 3. PROVICE SOLAvesse SARAIOR$ A40ufe0 C588TS A PUSE CL F 9WITOMES.
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- 7. FA0887AL SLEVATIOfS O9 0STASUTION CAssestT5 0Mous selTCH Aste UPDATED FINAL SAFETY ANALYSIS REPORT '
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-T f RE PER TO DETROIT EOlBON SPECIFICATION 3071138 STD.EJ POR PUSE SIZE, TYPE AND RELATED DATA,
= f i ' l 2. BATTERY CHARGER M10H VOLTAGE ALARM AND TRIP SET AT 135.0V AND 138.SV v s s . . y
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- 5. ALL CABLES SHAL L BE 2/C 813 UNLEM OTHERWISE l- .. . .
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- 6. "8P" DENOTES "WPACE".
- 7. FRONTAL ELEVATIONS OF DISTRIBUTION CABINETS TvecL can w u maa% sen+va, SHOW SWITCH AND FUBE CLIP SIZES,RQI FUSE SIZES.
REFER TO NOTE 8'1 FOR PUBE SIZES. S. FOR DETAILS OF HI & LO VOLTAGE AND LOSB OF FOWER i ALARMS AT MAIN CONTROL ROOM ANNUNCIATOR CABINET, SEE DWG,800731 3531-13. TABLES 3 & 4. l 8'
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