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| Line 256: | Line 251: | ||
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| Line 300: | Line 294: | ||
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| Line 342: | Line 335: | ||
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LCR 89-037 - U FS Rcv @ uret ne. 4.5-is sw4 i O raar | |||
* orgs ' | * orgs ' | ||
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3 / | 3 / | ||
| Line 583: | Line 572: | ||
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y I, pfG E y=t-j ElL ni | y I, pfG E y=t-j ElL ni | ||
. wJE | . wJE | ||
_, .a | _, .a Ib !< gj 4 t, | ||
Ib !< gj 4 t, | |||
l 1.Mjl 11 2 I)N . .1 l sw. .a h..e.J 5 x 4 r | l 1.Mjl 11 2 I)N . .1 l sw. .a h..e.J 5 x 4 r | ||
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| Line 595: | Line 582: | ||
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I- LCR 89-037 - U FS Rcv () uma. nr. 4.5-is sni i O or e | I- LCR 89-037 - U FS Rcv () uma. nr. 4.5-is sni i O or e | ||
; nse - | ; nse - | ||
| Line 659: | Line 645: | ||
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- w | - w | ||
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- m NE DWG EM7a-2NR- NE DWG 68021-2W8 enemaraman | - m NE DWG EM7a-2NR- NE DWG 68021-2W8 enemaraman | ||
| Line 674: | Line 659: | ||
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| Line 738: | Line 721: | ||
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| Line 749: | Line 730: | ||
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| Line 758: | Line 738: | ||
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| Line 794: | Line 771: | ||
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a LCR 89-037-UFS Revc/> uut, ne, g.s.is su i ! | a LCR 89-037-UFS Revc/> uut, ne, g.s.is su i ! | ||
lO PAGE 4 0F ' | lO PAGE 4 0F ' | ||
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| Line 999: | Line 967: | ||
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l | l Lcx 1!!a-oss-ors Rev.e ! | ||
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a 5 M.,k i 8 | a 5 M.,k i 8 | ||
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| Line 1,284: | Line 1,241: | ||
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| Line 1,685: | Line 1,635: | ||
I I I l Fors FIP-RA2-01 Att 2 P2/2 092158 DTC: File: | I I I l Fors FIP-RA2-01 Att 2 P2/2 092158 DTC: File: | ||
LC R CS - CSI ~ Uf.S . 4?cy g ) | LC R CS - CSI ~ Uf.S . 4?cy g ) | ||
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| Line 1,729: | Line 1,677: | ||
1. | 1. | ||
i | i | ||
! Fermi 2 UPDMED FINAL SAFETY ANALYSIS REPORT FIINNttSS-1~ | ! Fermi 2 UPDMED FINAL SAFETY ANALYSIS REPORT FIINNttSS-1~ | ||
FIRE FIHmlCTION SYSTERA 00VIB0001B I AND 11 i~ | FIRE FIHmlCTION SYSTERA 00VIB0001B I AND 11 i~ | ||
| Line 1,752: | Line 1,699: | ||
[ ] Other REV D) Is UFSAR change required? | [ ] Other REV D) Is UFSAR change required? | ||
[ ] Yes [ ] No LCR No. | [ ] Yes [ ] No LCR No. | ||
E) Priority NRC approval. required by (date): 4" l ~ | E) Priority NRC approval. required by (date): 4" l ~ | ||
An [ ] Emergency' [ ] Exigent condition will occur if not approved by : ' | An [ ] Emergency' [ ] Exigent condition will occur if not approved by : ' | ||
| Line 1,769: | Line 1,715: | ||
Pg.tDm sr.7ti-22oo-2. | Pg.tDm sr.7ti-22oo-2. | ||
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| Line 2,149: | Line 2,085: | ||
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| Line 2,260: | Line 2,193: | ||
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| Line 2,344: | Line 2,273: | ||
LC.R %-Q% - UFS Rf.V. d fht 7 0F h | LC.R %-Q% - UFS Rf.V. d fht 7 0F h | ||
i t | i t | ||
i | i bioc. GM'?2.1 2.01O ( UP.%e. F 16 9.2.- I ) | ||
bioc. GM'?2.1 2.01O ( UP.%e. F 16 9.2.- I ) | |||
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r . . .p*. . . . . , . . , | r . . .p*. . . . . , . . , | ||
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| Line 2,972: | Line 2,868: | ||
y .; .', j | y .; .', j | ||
..w..... ,en y | ..w..... ,en y | ||
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| Line 3,311: | Line 3,190: | ||
/ | / | ||
D) Is UPSAR change required? - | D) Is UPSAR change required? - | ||
l I ) Yes ( ) No LCR No. | l I ) Yes ( ) No LCR No. | ||
l E) Priority b/ ' | l E) Priority b/ ' | ||
| Line 3,421: | Line 3,299: | ||
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| Line 3,596: | Line 3,468: | ||
) | ) | ||
i c:,rcuit isolation. 3E 59-0055 describes this modir;, cation. l D) Reference and source Doo ments (Identiry) b se ; | i c:,rcuit isolation. 3E 59-0055 describes this modir;, cation. l D) Reference and source Doo ments (Identiry) b se ; | ||
EDP-10117. Rev. O Test e4 i | EDP-10117. Rev. O Test e4 i | ||
J PDC Tech 5pec g cL ABN Procedure 3 E l DER s. SE (Attached) 59-0055 : | J PDC Tech 5pec g cL ABN Procedure 3 E l DER s. SE (Attached) 59-0055 : | ||
| Line 3,626: | Line 3,497: | ||
. . l q, , | . . l q, , | ||
L C R 89-098-UFSl arv. , , | |||
5 lO i | 5 lO i | ||
' UFSAR FIG. 9.2-3 PAGE 2 0F 2 f l | ' UFSAR FIG. 9.2-3 PAGE 2 0F 2 f l | ||
l l E EW SYS. DIV. I PIPI NG DWG. l W , | l l E EW SYS. DIV. I PIPI NG DWG. l W , | ||
C | C el <- > | ||
el <- > | |||
2 g 1 y . . | 2 g 1 y . . | ||
t i | t i | ||
O c - | O c - | ||
1 m | 1 m | ||
\ | \ | ||
> A900 : | > A900 : | ||
| Line 3,664: | Line 3,531: | ||
I ; | I ; | ||
; l | ; l | ||
ie | ie | ||
| Line 3,743: | Line 3,608: | ||
; .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) 3 14.1.3.2.16C7 | ; .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) 3 14.1.3.2.16C7 | ||
- C) Reason for Change: ECCS Suction line leak detection system was deleted in place, therfore the testing requirements should be also deleted from UFSAR. | - 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 D) Reference and source Dieumonts (identity) o,e 1 L C & .. . y N. | ARMS.lNFoRMAttoN SY S D) Reference and source Dieumonts (identity) o,e 1 L C & .. . y N. | ||
'- -- ~ | '- -- ~ | ||
| Line 3,914: | Line 3,778: | ||
* PAGE.. .- " EV- 2k- - | * PAGE.. .- " EV- 2k- - | ||
* P'S******* * **** | * P'S******* * **** | ||
cq$ LCR l 819 l- l111 111- 1U l F 1 SI l. | cq$ LCR l 819 l- l111 111- 1U l F 1 SI l. | ||
l Unv 2 21989 | l Unv 2 21989 | ||
| Line 3,958: | Line 3,821: | ||
* ie a se e, 3 i l o ,,,,,,,, | * ie a se e, 3 i l o ,,,,,,,, | ||
i UFSAR | i UFSAR | ||
! 7.6.1.12.2.1 System Identification | ! 7.6.1.12.2.1 System Identification | ||
} The primary containment temperature monitor subsystem uses j thermocouple detectors to measure drywell atmosphere temperature, i | } The primary containment temperature monitor subsystem uses j thermocouple detectors to measure drywell atmosphere temperature, i | ||
| Line 3,979: | Line 3,841: | ||
1 | 1 | ||
, CONTINUAT60N SNSET i . LCR l a le 1 11 1111 l- I u ir i t i I | , 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 | 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 | l | ||
$--MM-(- I i A | $--MM-(- I i A u___ _ | ||
u___ _ | |||
i - | i - | ||
,g | ,g | ||
_ S_. 'i o .. | _ S_. 'i o .. | ||
^; ~~ | ^; ~~ | ||
AbD/ , w h ,, , i REVZSE | AbD/ , w h ,, , i REVZSE | ||
^ | ^ | ||
| Line 4,013: | Line 3,869: | ||
1 | 1 | ||
/ :.: *;,' .. | / :.: *;,' .. | ||
I '- : | I '- : | ||
i m | i m | ||
Latest revision as of 14:47, 15 March 2020
| 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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'D) Reference and Bource Doom ents (Identify)
EDP-8040 Test ll/A .- be d ) PDC-5040 Tech spec I/A g , ABN N/A Procedure L/A fg 1 DER 57-0424 SE (Attached) 9-0021 , Effectiveness Review (Attached) N/A C4 Other N/A # Drawi g4 l ! l******************}'PART2:s, Design Calculations, Correspondence, etc. OPERATING LI(MISE (BANES RMl3NA *********l g g, v l l A) r-:-:r:nt [ ] Operating License ( ) Tech Specs ( ) Environmental Protection Ed b Plan V l [ ] Tech Spec Clarification l B) 3ection(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) gg C) Reference and Source Documents Attached BTATLIS ( ) Significant Hasards Consideration ( ) Environental Impact - Categorical Exclusion 80 7 $g/g f [ [
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D) Is UFSAR change required? titV. [ ] Yes ( ) No LCR No. _ B) Priority NRC approval required by (date): An [ JEnergency ( ) Exigent condition will occur if not approved by: (State date): Explanation i F) Implementation l DER No. l p;;;;;;;;;;;;;;;;;;;PART 3: APPRDTAL5;;;; ; ;;;;;;_;;;;;;;W ,;E;;;;;;I A) Originator 41EEy0C>LPd () iorMVemm# // 2 A7#t#d W J/7/M R. L. Howe /S&W Date.R/f g B) Technical Expert IF
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-"- T&scM h{.47. t.11.jp A) Originator John M. Witchard f'7 /S&W Date #2 (1 B) Technical Expert On. e 411 Gr % < s n. H l d a Date g ?
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_C) Nuclear Organization Unit He 3. [. m Date D E 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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[ )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
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- 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~
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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 i B) Technical Expert y Date.2dN C) Quality Assurance (For Security Plans only) Date l lD) OSRO (Not required for UFSAR-QA Changes)t Date l l' /wt a.cdecf &
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l, , LISBING (RAME MNEST 3 MR 18til - l#141/l - lAllflSI y 4 CONTROLLED Revision I Pane 1 of 2 l y.mmm.mPART 1: WSAR. PLAN. OR ruuunAN RETISION [ ]EA ;;;;;;;#, A) Doo ment UFSAR
- 5) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
UFSAR Fig. 9.2.-4 amai $8 5'l 2 C) Reason for Giange Delete instrument P44K505B which is no lonaer reautred. B) Reference and Source Documents (Identify) EDP 9331 R gv. 6 Test : PDC Toch Spec- . ABN Procedure l DER SE (Attached) 59-0042 ; Effectiveness Review (Attached) ; i Other l i Drawings, Design Calculations, Correspondence, etc. ; jeeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICENSE GIANGES [I ]NA #########l j A) Document 1 [ ] Operating License ( ) Tech Specs [ ] Environmental Protection I i Plan ( ) Teen Spec Clarification
- 5) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) l C) Reference and Source Documents Attachet 6TATUS '
( ) Significant Hazards Consideration ASB # A d 1/ 4 O ( [
) Enviromental Impact - Categorical Exclusion
] Environmental Evaluation DIST. M M :
( ) Other eo
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D) Is UPSAR change required? - l I ) Yes ( ) No LCR No. l E) Priority b/ '
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NRC approval required by (date): 2 , An [ ]Energency [ ] Exigent condition will occur if not approved by: (State date): ..
$pL: :'
Explanation 5 ( . a l $ F) Implement.ation ' i
- DER No. g i ..................,A,7 3, A,,,om ...... .............. .- i n A) Originator J. Lakin Lb [M Date2Adh')
U I B) Technical Expert 0 6 7&x //O@@ Date t 17 99 7, , i C) Nuclear Organization Unit Head tr//. rw co., c. Date .3 / 19 h sn 3 D) Director. Nuclear Engineering ( ]NA 8 [. h w Date .3-/P [ E)PlantManagerM d/27 @[w Date.3/J W 79 F) Director. Nuclear Licensing C) OSRO Approval ( ) NA Date Date tI E I lH) NSRG Approval ( NA Date l ' Form FIP-RA2-01 Att 1 11/1 092188 DTC: g File: j73y
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.- , [ UCENSIN3 CHANGE REEUEST
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*# Revision 8 Page 1 of 4
/***"* "* * *"*"* *
- PART 1 : UFSAR, PLAN, OR PROGRAM REVISION [ JN A **" * * * * ** * * * * * * * " * * * *l l
Ud) Document i UFSAR l B) Sect 6on(s), Toble(s), Figure (s), etc. Affected (Attach marked-up pages) Figure 3.8-40 l C) Reason for Change: Changes due to EDP-3152 have not been made to UFSAR Figure 3.8-40. D) Reference end Source Documents (identify) i . EDP-3152 Test PDC Tech Spec l ABN Procedure 1 , DER SE (Attached) 85-3152 for EDP-3152 l Effectiveness Review (Attached) No ; Other 6C721-2315 j Drawings, Design Calculations, Correspondence, etc. ' p ee. . . . . . . . . . . . * * * * " * * * * * * *
- PAR T 2 : OPERATING LICENSE CHANGES [m) N A "*"*"* ***""" * *" l A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan [ ] Tech Spec Clarification
- 3) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
BTATUS C [ ] Significant Hazards Consideration ASB A d U(, 9 O ) Reference and Source DocumentsDIST [ ] Enviromental impact - Categorical Exclusion [ ] Environmental Evaluation Attached 4EPT AY < - [ ] Other REV l D) is UFSAR change required? [ ] Yes [ ]No LCR No. i
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l A) Dooment g C1 l l Q B) Bection(s), Table (s), F1 (a) 4t*k*etc.Affected(Attachmarked-uppages) h M) T ) i UFSAR Fia. 9.2 # 2 l W3\ sal *4al , C) Reason for Giange Delete Auto-:,solator F44K505A Whinh is no ;,onner I j roeuired in loop boosuse replacemenS recorder possenses ; ,nheren';; ,nout '
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i c:,rcuit isolation. 3E 59-0055 describes this modir;, cation. l D) Reference and source Doo ments (Identiry) b se ; EDP-10117. Rev. O Test e4 i J PDC Tech 5pec g cL ABN Procedure 3 E l DER s. SE (Attached) 59-0055 : Effectiveness Review (Attached) ! Other ! j Drawings, Design Calculations, Correspondence, etc. h
- jeeeeeeeeeeeeeeeeeeeePART 2
- OPERATING LI(ENSE (EAEES [I ]BA *******#el . ;
A) Dooment
] Operating License ( ) Tech Specs [ ] Environmental Protectior gf gl -
. [ 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 , [ ] Significant Hazards Consideration ggg et M 1 b' b --
[ ] Envirosental !apact - Categorical Exclusion 4 ( ) Environmental Evaluation OlST.py gG' __ [ Other .o -_ D) Is W3AR change required? [ ] Yes ( ) No LCR No. E) Priority 4 NRC approval required by (date): 4 l An [ ]Energency [ ] Exigent condition will occur if not approved by: ! (State date): ! Explanation f F) Implementation DER No. {eeeeeeeeeeeeeeeeeeeePART}: APPICTAL5HHHMMMMMMMMM'MMMMH l A) Originator G. M. Maher EM <
/S&W Dated ,..
3M 3 &[f7 B) Technical Expert 7<S. Date 3-3149 C) Nuclear Orge.nization Unit Head M ', e Date 4f)l2f 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
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L C R 89-098-UFSl arv. , , 5 lO i ' UFSAR FIG. 9.2-3 PAGE 2 0F 2 f l l l E EW SYS. DIV. I PIPI NG DWG. l W , C el <- > 2 g 1 y . . t i O c - 1 m
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D) Referehte and Source Documents (Identify) EDP Test l PDC Tech Spec Ph a,.# ruee -as-errr ) 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 l ! ) Tech Spec Clarification , _ , _ , . , , , l h) bection(s) Table (s), Figure (s), etc. Affected (Attach marked-up pages) W I M 8 W a* m J .. $) 1 C) Reference and Source Documents Attached N [ ] Significant Hazards Consideration i [ ] Enviremental Impact - Categorical Exclusion [)lST.If#I kr < [ ] Environmental Evaluation REV._ i [ ] Other l D)is UFSAR change required? [ ) Yes [ INo LCR No -
)
E) Priority NRC approval required by (date): i An [ ) Emergency [ ) Exigent condition will occur if n,i .ypivvett,gS*lNFoRMATON sYSTE $ (State date): -rn, e r __ , g ,j g , Explanation ""'""""" "- -"-- -,PIS . een o c icon v i. i se v wvs m g4 _ c4j' F) Implementation " / Pas ' DER No. nampm /d E.-3', w W 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 B) Technical Expert 17 UbeAOt>7ll .Al.M-->>
Date_M&B/I 7 C) Nuclear Organlaation Unit Head Date NU D) Director, Nuclear Engineering [ ] g [. 2A n Date Uf-d E) Plant Manager [ /J7 m Jh , [, h,5, o Date f/f/#9
/) Director, Nuclear Licensing _ 4* Date M P) OSMO Approval N NA g.'e s st. t5.' ' ~ Date
'H) NSRG Approval t<] NA Date l Jorm FIP-RA2-01 Att 1 P1/1092188 DTC: TC,q File: fy
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!i. b*VO8 'Y E j 1 it is impossible to perform any service on the operating chain. Thus, upon malfunction, operation can be shifted to the standby ' 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-a cation is presented in subsection 3.2.2.
i 11.3.3.5 Seismic Classification since an assumed seismically induced total failure of the offgas I. system would not result in an offsite dose in excess of 0.5 rea as specified in Regulatory Guide 1 29, the of fgas system does not 4 N require Category I design. The analysis of the offgas system ni failure is provided in section 15 11. The calculated doses
- e resulting from total failure of the offgas system are 20 area to
$ }f 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- - i J r tionsis f:n.;;;;;.; ef ;;.; delay pipe and in the pipe line yd upstress of the reactor building ventilation exhaust. The radia-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 A from the mechanical Upon detection vacuum pump downst of a high radiation l level by this monitor, the mechanical vacuum pumps are tripped.
, 11.3-16
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- 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 D) Reference and source Dieumonts (identity) o,e 1 L C & .. . y N.
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1 Effectivenet.s Review (Attached) [ JYes [ ]No , 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 l , ) Tech Spec Clarification j B) bestion(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) j 1R
] Significant Hazards Consideration [ ] Environmental Evaluation
, 0 D)([eference and
) Enviromental Impact is UFSAR change rectu6ted?
Source
/ Categorical Exclusion Documents Attached
[ ]Other
)Yes [ ]No LCR No STATUS E) I'riority NRC approval required by (date): _ ASB kfMrb _ ,
An [ ) Emergency [ ) Exigent condition will occur if not approved by: Ul5T. FL Y 7' PSM ' j (State date): m ,. . . i i n. v.
)
Explanation ! I F) implementation l 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 0 dN Date @//.4
~
) 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 I rem a waan lg n p g ,f g,
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,, _ _ , _ . - _ _ _ : rlir; c;:ter (rd :::;ir. pipi.4. I
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- 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 e l
;4.132.17 Liquid and solid Radwaste systen Prooperational Test l a. Test objective - To verify the operation of the radweste ' i system, including pumps, filters and desineralisers,- ;
l, centrifuge, and solid-handling equipment i I
- i
)
- b. Prerequisites - The checkout and initial operations 1 tests have been completed and the TRC has reviewed and i j 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 -
l and component operation l 2. Isolation valve operation, including valve logic ; and leak detection sensors and related : 1, annunciators , l- . Filters and domineralizers and related controls l 3. 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
- a. Test objective - To verify the proper operation of the ,
reactor protection system (RPS), including sensors, logic channels, scram relays, reset logic, and motor-generator power supplies 14 1-21
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'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
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[ ] 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 gg m, g/n g I ( ) Environmental Evaluation l [ Other- Olgt M T __ i D) Is Ut3AR ohange required? i [ ] Yes [ ] No LCR No. RN
~
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A) Desument ; UFSAR ^ j B) Section(e). Table (s). Figure (s). etc. Affected (Attach marked-up pages) I 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) l EDP 847? Tech Spec l PDC B472 Procedure l ABN SE (Attache 6) 89-0060. Rev. 1 l 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 ' ]Yes ( ) No LCR No I' l ' O 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.
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Date ////% ) H) OSRO Approval (Tech Spec Amendments) [ ] N. Date l N) NSRO Approval (Operatine License Amendments) NA Date l l Form F8P-RA2-01 Att 1 P1/1030189 File: 1735 DTC:JIMR for UFEAR ;
CONT 8NUAT60N SNttY LCR l 819 l-11ltilI- 1 Ulr i s I j TSC L. I l- 1 1 1 1
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i UFSAR ! 7.6.1.12.2.1 System Identification } The primary containment temperature monitor subsystem uses j thermocouple detectors to measure drywell atmosphere temperature, i
- pressure suppression pool chamber atmospheric temperature, and pressure suppression pool water temperature. % achieve repre-sentative temperature seasurements in the primary containment, 16 l sensors in the drywell, four sensors for suppression pool atmos-i 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
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, 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
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