ML20005F651

Licensing Change Requests to Updated FSAR

ML20005F651
Person / Time
Site:	Fermi
Issue date:	12/20/1989
From:	Howe R DETROIT EDISON CO.
To:
References
NUDOCS 9001170099
Download: ML20005F651 (74)

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t& DDa - 10k Il -A .A2 C w.w+ C) Mal $n for ChangeTL L L 3 w _ PI A w.m J.4 s a i Pr%e RMi en mil t a l-7. e t &. x L.ii. J J -.2n24: e so t e e I M M - L., AA ,L J % M i t A4 e 'ratat bervst# km2. km*5 km4 - Kev 5% 6alkfbo6. t.c q. e< i.- D) Referbate and fource DocGments ( dentify) EDP u/A Test kl/A PDC 6mi ~ Tech spec u/A Procedure ed /A ABN M/A-DER PA-tAA '1 SE (Attached) EM M 7-. Effectiveness Rovigw (Attached) M /A Other u/A g Drawings Design Calculations, Correspondence, etc. pmc********************* * ** PART 2: OPERATING LICENSE CHANGES DGNA ****"**""*"""**) rg A) Document ( ) Operating License [ ] Tech Specs [ ] Environmental Protection Plan k i ) Tech Spec Clarification y B) Section(s), Table (s), F6gure(s), etc. Affected (Attach marked-up pages) C) Reference and Source Documents Attached STATUS i ( ) Significant Hazards Consideration ASB A J 4M ( ) Enviromental impact - Categorical Exclusion %.J U L I ) Environmental Evaluation ggg gi-sqeg ( ) other HtV. h h$ D) is UFSAR change required? m,n.L a 4 l 1Yes ( ) No LCR No. s g- ~ y l ~' '-~ ~ - E) Oriority y i NRC approval required by (date): g ( An [ ] Emergency [ ] Exigent condition will occur if not approved byT (State date)- I Explanation F) Implementation DER No. ,_.........................., ART.. A,RD AL,................. = = = = =.= =.= = =.] Date 2r2&-@ _mim A) Originator DIN Date B) Technical Expert - Date T-7/

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1 l l Figure 9 5-1 l C) Reason for Omnge UFSAR figure will be revised to change FSE N452 g l to FSE N402. This change is being made per ABN 8205-1. Rev. 5 \\ m 6 2 j D) Reference and Source Documents (Identify) i i EDP N/A Test N/A m hgM h i PDC N/A Tech Spec N/A l ABN 8205-1 Procedure-N/A g ( DER N/A SE (Attached) 89-0034 l' eq l Effectiveness Review-(Attached) E a Other h hW eMeeeeeeel{3 Drawings, Design Calculations, Correspondence, etc. j l jeeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICENSE CHANGES [s)NA g; A) Document

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[ ] Enviromental Impact - Categorical Exclusion Agg~ OM ( ) Environmental Evaluation pT - h { ] Other DIST. D) Is UFSAR change required? g" [ ] Yes [ ] No LCR No. E) Priority ~__t NRC approval required by (date): L An [ ] Emergency [ ) Exigent condition will occur if not approved by:- (State date): Explanation A F) Implementation DER No. jene m m eeneeee m eFART 3: APPR0VALSmmmummememmemm l .[ A) Originator Brett Orseno derI d%n /S&W Date 1/z /rf B) Technical Expert / [ [ e : Date J-Jf-ff S _C) Nuclear Organization Unit He 3. [. Date D E M m D) Director, Nuclear Engineering ]NA [ A Date.3 3 ki ( E) Plant Manager Date 3 % /] F) Director, Nuclear Licensing Date Y 7 l G) OSRO Approval [ ] NA Date l lH)-NSRG Approval [ ] NA Date l Foro FIP-RA2-01 A M 1 P1/1.092188 DTC: e File: e __. _,, i

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l EPFECTITENESS WTIEN-ReforenceLCRlEl1-l l l 0 l - lU f Slgg 2. 4 Revision 4 Page 1 of 1 ImmmmennunuweewePART 1: W5AR. [ ]EA w m m *********u l A) Quality Assurance Program [ )Yes [X) No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B and the UFSAR progran comaltaents previously accepted by the NRC? Provide the basis for eacn change on Attachment 2. Page 2. B) Pire Protection Prograa [ )Yes [X) No Does the change (s) significantly decrease the level of fire protection-in the plant? _ [ )Yes [ K) 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. I m PART 2: RADIGAGICAL BERGENCY HESPONSE PREPAnr.uura PLAN LXJNA em j. A), [ ] Yes i j No Does the change (s) decrease the effectiveness of the RERP Plan? [ ] Yes [ ] No Does the RERP Plan, as changed, cease to meet the. j standards of 10CFR50.47(b) and 10CFR50 Appendix E? Provide the basis for each change on Attachment 2. Page 2. geomeoneemumePART 3: SECURITY PLANS [X JNA M M M M M #####ee***l A) Document A) [ ] Yes [ j No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security-Personnel Training. .O and Qualification Plan prepared pursuant to 10CFR50 34(c) or 10CFR737 L [ ] 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 I responsiblity matrix of the Safeguards Contingency-Plan prapared pursuant to 10CFR50 34(d) or 10CFR737 Provide the basis for each change on Attachment 2. Page 2. leeueemmeneneePART 4: PROCESS UGnHuk, PROGRAM LX JNAmmmem l _ A) [ ] Yes [ ] No Does the change (s) reduce the overall conformance of l the solidified waste product to existing criteria for l solid wastes in accordance with Technical i Specification 6.137~ Provide the basis for each change on Attachment 2 Page 2. jeeemenemeemumeeenePART 5: ODCM LX JNA emumunnennune j [ A) [ J 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 6.14? i Provide the basis for each change on Attachment 2. Page~2. 4: jummmunnenPART 6: APPR0VALSemmmmmmmememum l' A) Originator SENAWTl SH AH Date 2-/6-27 Date.2dN i B) Technical Expert y C) Quality Assurance (For Security Plans only) Date l lD) OSRO (Not required for UFSAR-QA Changes)t Date l /wt a.cdecf &

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1 1 LICENSING (EAME MNEST 14R 189 l - 1015121 - IUlFISI CONTROLLED ~ 4 Revision SI Page 1 of 3 I m m m e m,PART 1: UF5AR, PLAN, OR PROGRAN REVISION [ ]MA ***mH l l A) Document EDP-9969 B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) UFSAR Flaure 7 3-9 sheets 2 and 7-crut-m.Dd9 C) Reason for (hange 'the reason for this chante is t'o add throttlina capability to valves E1150F017A and E1150F017B in the manual openina mode. D) Reference and Source Doctments (Identify) EDP 9969 Test PDC 9969 Tech Spec ABN Procedure DER 89-0160 .SE (Attached) 89-0035 Effectiveness Review (Attached) Other Drawings, Design Calculations, Correspondence, etc. leeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICENSE MA N [ ]MA #########l A) Document ( ) Operating License [ ] Tech Specs [ ] Environmental Protection-Plan [ ] Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected ( Attas n rg g C) Reference and Source Documents Attached gg w, 1 lody ( ) Significant Hazards Consideration ( ) Enviromental Impact - Categorical Exclusion DIST. NT M l [ ] Environmental Evaluation [ ] Other REV D) Is UFSAR change required? [ ] Yes [ ] No LCR No. E) Priority 4" NRC approval. required by (date): l An [ ] Emergency' [ ] Exigent condition will occur if not approved by Q, ~ (State date): C-Explanation E !9 F) laplementation l 'h DER No. m Tesussususnusne:: =PART 3: ArracvALs* - ** = = =**= === = = = ===1 g5 - s22 A) Originator C. M. Corso /N/ M /S&N Date &

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l 4 C1 l A) Dooment g l Q 4t*k*etc.Affected(Attachmarked-uppages) h M) ) (a) T i B) Bection(s), Table (s), F1 l W3\\ sal *4al UFSAR Fia. 9.2 # 2 I j C) Reason for Giange Delete Auto-:,solator F44K505A Whinh is no ;,onner roeuired in loop boosuse replacemenS recorder possenses ;,nheren';;,nout ) i c:,rcuit isolation. 3E 59-0055 describes this modir;, cation. l b D) Reference and source Doo ments (Identiry) se EDP-10117. Rev. O Test e4 J i cL PDC Tech 5pec g ABN Procedure 3 E $ l SE (Attached) 59-0055 DER s. Effectiveness Review (Attached) Other j Drawings, Design Calculations, Correspondence, etc. h jeeeeeeeeeeeeeeeeeeeePART 2: OPERATING LI(ENSE (EAEES [I ]BA *******#el gf gl A) Dooment [ ] Operating License ( ) Tech Specs [ ] Environmental Protectior Plan [ ] Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up panes) i me Ava 13 C) Reference and Source Doo ments Attached b' b -- [ ] Significant Hazards Consideration ggg et M 1 [ ] Envirosental !apact - Categorical Exclusion OlST.py gG' 4 ( ) Environmental Evaluation [ ' Other .o D) Is W3AR change required? [ ] Yes ( ) No LCR No. E) Priority NRC approval required by (date): 4 4 l An [ ]Energency [ ] Exigent condition will occur if not approved by: (State date): f Explanation F) Implementation DER No. {eeeeeeeeeeeeeeeeeeeePART}: APPICTAL5HHHMMMMMMMMM'MMMMH l A) Originator G. M. Maher EM /S&W Dated 3M 3 &[f7 7<S. Date 3-3149 B) Technical Expert C) Nuclear Orge.nization Unit Head M Date 4f)l2f e D) Director. Nuclear Engineering ( )NA Date ) V)~ (( L E) Plant Manager p // Date ()- 6 /7 F) Director. Nuclear Licensing MA Date f////G G) OSRO Approval ( ) NA Date lH) NSRG Approval ( l WA Date l Fors FIP-RA2-01 Att 1 P1/1 092155 DTC: g File: f 7g

q, L C R 89-098-UFSl arv., 5lO PAGE 2 0F 2 f i UFSAR FIG. 9.2-3 l E EW SYS. DIV. I PIPI NG DWG. W C e 2 l 1 g i t y O c \\ 1 m ]) 6,~ A900 v l %^) i Gi ,6vst ^ i yn } l 4 {.. g O u m ? b. n um ee M '1 K e n PS ( > 4 b ~ ) M. d h L ... c ;;w g i e i i O ' " i " g I m" /, z I

ie uCENSING CHANCE RECUEST

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• i)

Revision d PaDe 1 of f .nu...nu... .* PART 1: UFSAR. PLAN. OR PROGPAM REVISION [ IN A "* """ ; "" " " * ""l A) Document l UFS AR B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) .See.rlan //. 3 1. 6 C) Reason for Change s1. e/nm*/w arvum / Ja e n * >'an a f r a af*a :m m .*. - e s'n vAm o c.r. a z svsea-.. 1 e no e,%'w /M ma=> --~- w :.1 rw- -= = de :- uren .sen (Ann /L er. 3. 2. 2.1 desu/aeAn m 2 .' 4 e < Umad e h - ='m 'em I I Teen rm . 3/4, t/ 2.9 as 'A m. > 'Jo e' > 'n Arth - itt - a n s a." D) Referehte and Source Documents (Identify) EDP Test PDC Tech Spec Ph a,.# ruee -as-errr ) l i ASN Procedure i DER pp-ta34 SE (Attached) #9-annr Effectiveness Review (Attached) i Other 4M'rt / - t o / 7 - 2 Drawings, Design Calculations, Correspondence, etc. p .n........... u.......... PA R7 2 : OPERATING LICENSE CHANGES t>dNA *""""""**"**"l A) Document 1 [ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan ) Tech Spec Clarification h) bection(s) Table (s), Figure (s), etc. Affected (Attach marked-up pages) W I M 8 W a* J.. $) m 1 C) Reference and Source Documents Attached N [ ] Significant Hazards Consideration [)lST.If#I kr i [ ] Enviremental Impact - Categorical Exclusion [ ] Environmental Evaluation REV._ i [ ] Other D)is UFSAR change required? [ ) Yes [ INo LCR No ) E) Priority NRC approval required by (date): An [ ) Emergency [ ) Exigent condition will occur if n,i.ypivvett,gS*lNFoRMATON sYSTE $ (State date): -rn, e r __ g,j g, -"-- -,PIS. Explanation c4 een o c icon m v i. i se v wvs _ j' g4 F) Implementation / /d E.-3', Pas DER No. w W nampm p n.......................... P A RT 3 : AP P R O V AL $* * """ * *7*"**.W.* 98P**J '"*** ""_* **"* **4tf * ** * "

• l A) Originator [O. h Date 7
• F * *8 9

.Al.M-->> Date_M&B/I 7 B) Technical Expert 17 UbeAOt>7ll C) Nuclear Organlaation Unit Head Date NU D) Director, Nuclear Engineering [ ] g [. 2A n Date Uf-d E) Plant Manager [ /J7 Jh, [, h,5, o Date f/f/#9 m /) Director, Nuclear Licensing _ 4* Date M P) OSMO Approval N NA g.'e st. t5.' ' ~ s Date 'H) NSRG Approval t<] NA Date l Jorm FIP-RA2-01 Att 1 P1/1092188 DTC: TC,q File: fy

j i da 0 9 - to.r - os i* panu a UFSAR M !i. b*VO8 'Y E

'j

Thus, upon malfunction, operation can be shifted to the standby it is impossible to perform any service on the operating chain. 1 chain without interrupting plant operation. Because both chains are isolated, service can be performed on one chain while the other operates. 11.3.3.4 Quality Grouo Classification The Regulatory Guide 1.26 classification of components iri the of fgas system is Quality Group D except valves, pipe, and water ring pump, Which are Group C. This classification meets the criterion of Regulatory Guide 1.26 since the single failure of i any component does not result in an offsite. dose in excess of 0.17 res. This is demonstrated in Subsection 15.11, Where the i analysis of the ofigas system failure is presented. The analysis assumes 100 percent of the iodine in the system'is released and { 10 percent of the noble gas is released. The offsite doses due to whole failure of the of fgas system are 20' area to the thyroid and 4.20 area to the Whole bodyr therefore, no single equipment failure can exceed the recommended dose limit'of Regulatory Guide l 1.26. A detailed discussion of equipment Quality Group classifi-cation is presented in subsection 3.2.2. a i 11.3.3.5 Seismic Classification since an assumed seismically induced total failure of the offgas system would not result in an offsite dose in excess of 0.5 rea I. as specified in Regulatory Guide 1 29, the of fgas system does not N require Category I design. The analysis of the offgas system 4 failure is provided in section 15 11. The calculated doses ni $ }f resulting from total failure of the offgas system are 20 area to e the thyroid and 4.2 area to the Whole body. li 11.3.3 6 Offaas system Instrumentation and Control !vP ( The offgas system is monitored for radiation level at two loca- - J r tionsis f:n.;;;;;.; ef ;;.; delay pipe and in the pipe line i d upstress of the reactor building ventilation exhaust. The radia-y tion monitor".p; u;;.; e: ;t.; delay pipe continuously monitors radioactivity release from the reactor and therefore continuously y monitors the degree of fuel leakage. This radiation monitor is. used to ovide an alara on high radiation in the offgas. The monitor e no control function. The radiation monitor for the reactor building vent continuously monitors the of fluents released from the charcoal beds. If high radiation levels should occur in the discharge of the offgas system, this monitor would alarm in the main control room. Upon receipt of a high radiation alarm, the plant operator can evaluate the situation and initiate the proper action. ( O delay pipe is also monitored.The discharge from the mechanical vacuum pump downst Upon detection of a high radiation l A level by this monitor, the mechanical vacuum pumps are tripped. 11.3-16

i ,i i. UCENSING CHANGE REEUEST s LCR 89-107-UFS j CONTROLLED Revision / P goaet > i .mmmm.m.PART 1: UFSAR. PLAN, OR =-2=^* REvislON [ ' lNA "* **""* * *"l Document UFSAR I B) sect 6en(s), Table (s), F63ure(s), etc. Affected (Attach marked-up pages) 14.1.3.2.16C7 3 C) Reason for Change: ECCS Suction line leak detection system was deleted in place, therfore the testing requirements should be also deleted from UFSAR. ARMS.lNFoRMAttoN SY S o,e 1 L C &... y N...]D48 D) Reference and source Dieumonts (identity) ~ ~ ~ ~~ G;2,6 EDP Toch Spec

r. r. n n 3 snon PDC PI ocedure m '" '~

tached) SN- [_ ABN Sl ! h'techD6)~"~u A irmeeisec 'pu (A DER 89-0287 Pl L l Test iD?RDVAt REQ'D: YN...... No.. ~ Effectivenet.s Review (Attached) [ JYes [ ]No 1 Other FCN 86-069, RACTS 4527, VP-85-0207, QA-89-1037 Drawings, Design Calculations, Corres >ondence. etc. p...u.uu u.un..u......* PART 2: OPERATih 0 LICENSE CHANGES [XlNA *"""""*"*"l A) Document ( ) Operating License ( ) Tech Specs ( ) Environmental Protection Plan ) Tech Spec Clarification j B) bestion(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) j 0 ([eference and Source Documents Attached 1R ] Significant Hazards Consideration [ ] Environmental Evaluation ) Enviromental Impact / Categorical Exclusion [ ]Other D) is UFSAR change rectu6ted? )Yes [ ]No LCR No STATUS E) I'riority ASB kfMrb NRC approval required by (date): An [ ) Emergency [ ) Exigent condition will occur if not approved by: Ul5T. FL Y 7' PSM (State date): j i m,... ) i n. v. Explanation F) implementation DER No pmun.........u....*"* PART 3: AP P R O VA L S* " "" * "" * * * " * * * """ * "" * * " *""" * *

• l A) Originator: A. Klemptner 24[/12)

/4-Date 0gf4 B) Technical Expert .k Date f 4

• IT, C) Nuclear Generation Unit Head b6 N Date 8!/

i D) General Director, Nuclear Engineering ( )NA [. N m Date J N/)T E) Plant Manager dN Date @//.4 0 ~ ) Other Date f) Director, Nuclear Licensing A Date [/7f H) O_SRD Approval (Tech Spec Amendments) [ ] NA Date e 91 NSRO Approval (Operating License Amendments) i ) NA _ Date l Form FtP-RA2-01 Att 1 P1/1030189 DTC: Nyor UFSAR File: 1735

ag .9 LW 09-non-Urs RW o lg rem a waan n p g,f g, ~* !O i 4. RCIC 5 BPCI 6. Radwaste systen - _ _ _ : rlir; c;:ter (rd :::;ir. pipi.4. I i i d. Acceptance Criteria - he leak detection features of the I nuclear systems must be verified for proper operation and shown to be within their respective engineering design specifications. .i l e

4.132.17 Liquid and solid Radwaste systen Prooperational Test a.

Test objective - To verify the operation of the radweste ' l i system, including pumps, filters and desineralisers,- I l, centrifuge, and solid-handling equipment i i ) b. Prerequisites - The checkout and initial operations j tests have been completed and the TRC has reviewed and i approved the test procedure and the initiation of test-1 ing. Additionally, laboratory facilities must be avail-l able to perform water quality tests c. General Test Method - Verification of the radwaste sys-tea capability is demonstrated by the proper, integrated operation of the followings l 1. System pumps under all normal possible flow paths and component operation l l 2. Isolation valve operation, including valve logic and leak detection sensors and related 1, annunciators l-l 3. Filters and domineralizers and related controls l 4. Centrifuges and solid-handling equipment 5. Phase separator and waste sludge subsystems 6. Chemical waste and spent resin subsystems. d. Acceptance Criteria - All system and subsystem com-t ponents must be either verified for proper operation or demonstrated to be within their respective engineering design specifications. 14132.18 Reactor Protection System Preoperational Test Test objective - To verify the proper operation of the a. reactor protection system (RPS), including sensors, logic channels, scram relays, reset logic, and motor-generator power supplies 14 1-21

j* LIMING CEARE MIORBT j l a 18191 - lilil01 - lUlFl51 Revis:on i Paae 1 of f. 1.- = n ; " x " PART 1: wear. FLAN. (3t ruumsdH ev.,5IEN I BA... sue l ATBooment 1 EDP "838. Rev. O B) soot:,on(s), thble(s), rigure(s), etc. Arrested ( Attach marked-up pages) i WSAR Fia. 7.3-13. Sh. 3 (See Pase 2 of this LCR) GTri m -> c) Reason for Emange EDP-7535 modified the aknual control circuits of N51Ts. MR F;,a. 7.3-13 neee< Hi revision 'e re. ' lect i se o, ' 1stehlu gw relay (w th e;,ectric reset) ;a the annus;, ogn'Lrol c;,rcui'L of each DJ mererence and source Dooments (Isentiry) EDP "838. Rev. 9 Test PON 42.610.01 PDC "535 i Rev. 5 Tech spec pot a. ':'ected 'ABN. l/A Procedure rwi 4 !.510.01 l DER 42-277 SE (Attached) 5' +0059 i Effectiveness Review (Attached) N/A l Other Drawings, Design Calculations, correspondence, etc. l leeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICW5E (EARES [I )MA *********l r A) Document [ ] Operating License ( ) Tech Specs [ ] Environmental Protection Plan i [ ] Tech Spec Clarification l B) 5ect. ion (s), Table (s), Figure (s), etc. Arrested (Attach marked-up pages) C) Reference and 5ource Documents At,tached [ ] Significant Hazards Consideration STATUS t ( ) Enviromental !apact - Categorical Exclusion I ( ) Environmental Evaluation gg m, g/n g l [ ' Other-Olgt M T i D) Is Ut3AR ohange required? i [ ] Yes [ ] No LCR No. RN E) Priorit,y k ~ NRC approval required by (date): I An ( ) Emergency [ ) Exigent condition will occur if not approved by "f (State date): 6k (y {j Explanation m ..,.n ni L.c v x, ti N wrS 6 m k' , h }h F) Implementation f l DER No. g l 1;;;;;;; n n;;;;;;;e5PART 3: APPM)TA13emwmpemqmwgmmmmw l ]. O ( A) Originator A. G. Reyes [M P W4(pr4 / f"fr1 /S&W Date /d k SD B) Technical Expert /cs G, Ts44uma .4Ar 4Nn Date 6/27M eq l C) Nuclear Oraanization Unit Hoa d PJ3fl//_sDate M fe/A4 hb / V> s D) Director. Nuclear Engineering [ INA M h Date 7'# E) Plant Manager Date 7-D-M F) Director. Nuclear Licensing Date M d &7 g! G) OSRO Approval [ ] WA Date lH) NSRG Approval I NA Date l Fora _F_I_P_,RA2 01 Att 1 01/1 DQ21RR n'rri. -.. rai-. l

o l 4 1 3 1 2 l 43 8%//0-thc5 Rev'o y,z /uss e ** 2 E M. .... ~... lOI E r g-REYlSE PER a EDP 7838 I-U-\\ /-5-\\ (EAi) (4 *. 4) "F" W IB \\ /4BfT \\W -/ \\ W team / ,. g 6 1 i iM. \\ leW.\\ .-k 5 \\W

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1HIS 11 AN 13D5 PRODJ tD Draw W/ CHANGES DR MtVISIONS TO T Daav1ws MJst et emD;faM1 10 is ATTENilDN OF THE IGDS CDDRD154-ENSt*t 1Mai THE 3GD5 Fl.E !$ 1 NUCLEA8t SAFE 1Y RELATED 1 m LQ

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• l PAGE...-

cq$ LCR l 819 l-l111 111-1U l F 1 SI l. Unv 2 21989 l -?tn:-7a,FM Revlolon A Pese 1 et 3 l

p.......m......m. PART 1 : UF5AR. PLAN. DR PRL""_^V REVl510 4 I N6A ="*;;;; ;;;;;;**l A) Desument UFSAR

^ j B) Section(e). Table (s). Figure (s). etc. Affected (Attach marked-up pages) Section 7.6.1.12.2.1 Sys".em Identification and UFSAR Fioure 9.2-11 6m % i C) Reason for Change Replacement o" Recorder T23-R800. l I D) Reference and seurse Desuments (6dentify) EDP 847? Tech Spec l PDC B472 Procedure l ABN SE (Attache 6) 89-0060. Rev. 1 DER PE (Attached) l Test Effectiveness Rev6ew (Attached) ( JYes [ Xpvo l Other Drawings. Des 6cn Calculations. Correspondence. etc. p............................ PAR T 2 : OPERATING LICENSE CHANGE 5 I XINA ******""*l A) Document ( ) Operating License [ ] Tech Specs ( ). Environmental Protection Plan i 1 Tech Spec Clarification .) no. tion (e). To.ie(.). Figu,e(s). eic. Aff..ted (Atisch marked-u,,eges) C) Reference and Source Documents Attached .i ( ) Significant Herords Consideration ( ) Environmental Evaluation ( ) Enviromental impact / Categorical Exclusion [ ]Other l' D) is UF5AR shenge required? I' l ' O ] i ' ]Yes ( ) No LCR No t l E) trierity "M i NRC approval reevired by (date): I"4 ' An ( ) Emergency ( ) Exigent condition will occur of not approved byg ;, //-do-B ) (State date)- i.. v. ., wOst[ Explanation e e-I F) implementation 4 DER No. ,............................,A,1,.A,,,,,A,,...............,......................................, A) 0,i.inet., n. s. nunninos/impei, @k--V- .s,e vdr .)ve.hni.eiE..e.,,. M 244 L S. e os,e #W47 MM.'ies, oene,etion mit Need v.a.e - rwt s~~- De,e dsn c D)..ne,sioi..te,.=u.i.e,En.in.e,in t iN. M s/u4 ost. ' ~ p oste fo.u.,e, $),ieni mene.e, F) Other Date [vd + Date ////% .) Director. Nuclear Licensine H) OSRO Approval (Tech Spec Amendments) [ ] N. Date N) NSRO Approval (Operatine License Amendments) NA Date l l Form F8P-RA2-01 Att 1 P1/1030189 DTC:JIMR for UFEAR File: 1735

CONT 8NUAT60N SNttY LCR l 819 l-11ltilI-1 Ulr i s I TSC L. I l-1 1 1 1 j l

a.

• ie a se e, 3 o,,,,,,,,

i UFSAR 7.6.1.12.2.1 System Identification } The primary containment temperature monitor subsystem uses thermocouple detectors to measure drywell atmosphere temperature, i j pressure suppression pool chamber atmospheric temperature, and pressure suppression pool water temperature. % achieve repre-sentative temperature seasurements in the primary containment, 16 i sensors in the drywell, four sensors for suppression pool atmos-phere, and four sensors for suppression pool water are used. The monitored temperatures are contin'.*ously recorded on two strip-chart recorders. The primary containment temperature monitor l subsysten has no control functions its purpose is that of data acquisition. Because of the importance of securing these temperature data on occurrence of abnormal plant conditions, two l redundant temperature monitors are provided. In parallel with the primary containment temperature monitor subsystem (PCTMS), and in response to additional design requirements, two additional O temperature monitoring systems have been installed to monitor the drywell air temperature and the suppression pool temperature, as discussed below. The additional drywell air temperature monitoring subsystem uses i 24 thermocouples (which are independent of the PCms) installed at ein elevations. We temperature information is recorded in i the main control room and is used by the operators to compute the j volumetric average temperature for determination of the Technical j specifications operating limit. The additional suppression pool ] temperature monitoring subsysten uses a recorder and eight thermocouples (which are all independent of the PCMS).. The i thermocouples are placed so. that each thermocouple monitors the discharge of two SRVs. The recorder is located in the main con-I trol room and will alara on bulk average water temperature 195.0'F or detection of an open T/C. The technical specifications allow the maximum average temperature of the suppression pool to be 95'F during operational conditions 1 or.2 unless the thermal power is Q less than or equal to 14, or a test is being performed which adds. heat to the suppression chamber. To alert an operator of this limit, an alarm will be set a_t approximately 95.0*F-(increasing). b Farm F4P-RA2-01 Att 6 P1/1030189 DTC: [ ] TCLCR for UFSAR File: 1735 WMUUTureruntr#rv

1 CONTINUAT60N SNSET i LCR l a le 1 11 1111 l-I u ir i t i I TSC 1 1 l-I l 1 l I Revision A Pese 3 of 3 l A) Desument UFSAR, Figure 9.2-13 I \\ l $--MM-(- i A i S_.'i AbD/ ^; ~~ ,g o u___ REVZSE ^ h,,, i w i t a.., sa r

• 4 i

l $ r-@ en7ei /m !$A bg% j J ! E' ''' l0 ~~~ + n' g , ;.....$ ' - g,...,.in.....,' agg;w :.'. *"*' i t tr 1 ,,l ' :'.... / :.: *;,' I i m l' sre i W;;... /,'g($.A l ] (ns:""* 1 h l g*g \\ g w ) eLi!< h a! m ./ -. ;TT 3J w;,. [ ,.y ~ ' A'WlUg"'* 1 g, Fstm FAP-RA2-01 Att 5 P1/1030189 DTC: ( ) TCLCR for UFSAR F60s: 1735 _.._ DTC: [ ) TDLCR,for other ___y _ _ _ _ _,, _, _}}