ML20138N684
| ML20138N684 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/24/1997 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20135B565 | List: |
| References | |
| RTR-NUREG-1431 NUDOCS 9703030107 | |
| Download: ML20138N684 (600) | |
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i 4 Attachment 1 ' Byron /Braidwood Improved Technical Specifications January 23, 1997 Meeting Action Item Generic Changes versus CTS DOCS (page 2 of 4) DOC ITS CORRELATION ITS LC0 GENERIC CHANGE CTS (DIRECT OR , SECTION JFD CHANGE STATUS DOC (S) INDIRECT)(" l 3.2 C4 TSTF-097 Approved L9 Indirect 3.2 C5 TSTF-098 Approved L9 Indirect l 3.2 C6 TSTF-099 Approved L9 Indirect 3.2 C9 TSTF-110 Rev. 1 Pending LA6. Indirect 3.3 C1 TSTF-135 Item 3- Pending A6/A8 Indirect l A15/M7 3.3 C1 TSTF-135 Item 4 Pending L1/L5 Indirect 3.3 C1 TSTF-135 Item 5 Pending LA2 Indirect 3.3 C1 TSTF-135 Item 7 Pending L4/L14 Indirect J 3.3 C1 TSTF-135 Item 9 Pending L11 Indirect l 3.3 C1 TSTF-135 Item 12 Pending LA4 Indirect 3.3 C3 TSTF-091 Pending LA3/LA7 Indirect 3.3 C5 WOG-080 Pending A20 Direct 3.4 C1 TSTF-026 Approved L36 Direct 3.4 C2 TSTF-027 REV 1 Pending M9 Direct
.4 C5 - TSTF-093 Pending A13 Indirect 3.4 C6 TSTF-105 Pending LA18 Direct 3.4 C7 WOG-021 r2 Withdrawn ' A22 Direct 3.4 C8 TSTF-116 Pending L21/L22/ Indirect i
L24 3.4 C9 WOG-051 Pending L16 Indirect i 3.4 C10 TSTF-087 Pend'ing L3/L12/ Indirect L23/L26 3.4 C12 TSTF-113 REV 1 Pending L8 Direct 3.4 C13 WOG-060 Pending L27 Direct (1) A CTS Discus'sion Of Change (DOC) which is solely associated with the generic change is designated as a direct correlation. A DOC which includes more information than the generic change is des.ignated'as an indirect correlation. (2) Based on withdrawal of WOG-021. NUREG-1431 Revision 1 will be utilized for this portion of the specification. i l a
l l l Attachment 1 Byron /Braidwood. Improved T chnical Specifications January 23, 1997 M uting Action Item Generic Changes versus CTS DOCS (page 3 of 4) i, DOC ITS CORRELATION ITS LC0 GENERIC CHANGE CTS (DIRECT OR SECTION JFD CHANGE STATUS DOC (S) INDIRECT)m 3.4 C14 TSTF-153 Pending A31 Direct 3.5 C4 TSTF-117 Pending - A4 Direct 3.6 C1 TSTF-052 Pending A5 Indirect i 3.6 C2 TSTF-017 Pending L4 Direct 3.6 C3 TSTF-044 Proposed 'Pending A17 Direct l REV 1 , 3.6 C4 TSTF-030 REV 1 Pending L14 Direct , 3.6 C5 TSTF-045 Pending L11 Direct 1 3.6 C6 TSTF-046 Pending L12 Direct 3.7 C3 WOG-083 Pending A42/L1 3.7 C4 TSTF-101 Approved L28 Direct 3.7 C6 TSTF-102 Pending M2 Direct 3.7 C8 WOG-064 Pending L6/L7 Direct 3.8 C1 TSTF-002 Pending LA12 Direct 3.8 C5 TSTF-036 REV 2 Pending L14 Direct 3.8 C6 TSTF-015 Pending L18 Direct 3.8 C7 TSTF 11 5 Pending L20/L21 Direct i 3.8 C8 TSTi-115 Pending L22/L23/ Direct 1 LA9 3.8 C9 WOG-062 Pending M3 Indirect 3.8 C11 WOG-069 Pending L13/L6 Direct , 3.9 C1 TSTF 021 Proposed Pending, L11 Direct REV 1 3.9 C2 TSTF-022 Pending LA10 Indirect 4.0 None None None None None
; (1) A CTS Discussion Of Change (DOC) which is solely associated with the generic change is j designated as a direct correlation. A DOC which includes more information than the generic change is designated as an indirect correlation.
Attachment 1 Byron /Braidwood Improved Technical Specifications January 23, 1997 Meeting Action Item Generic Changes versus CTS DOCS (page 4 of 4)
- DOC ITS CORRELATION ITS LC0 GENERIC CHANGE CTS (DIRECT OR SECTION JFD CHANGE STATUS DOC (S) INDIRECT)("
5.0 C1 TSTF-065 Pending LA28 Indirect 5.0 C2 WOG-056 Withdrawn'" A28 Direct 5.0 C4 TSTF-152 Pending L5 Direct - 5.0 C5 TST' '52 Penaing LA24/ Indirect A26/A36/
- LA19 5.0 C6 TSTF-115 Pending. LA25 Direct 5.0 C8 WOG 072 Pending A37 Direct I
7 s (.1) A CTS Discussion Of Change (DOC) which is solely associated with the generic change is designated as a direct (:orrelation. A DOC which includes more information than the generic change is designated as an indirect correlation. (3) WOG-056 was withdrawn based on TSTF-121 requesting the same change. C2 will be revised to reflect TSTF-121.
1 1 1 Attachment 2 Byron /Braidwood Improved Technical Specifications January 23, 1997 Heeting Action Item Example Byron /Braidwood Plant Specific Justifications Which are Now in the Generic Process (page 1 of 2) I RECENT ! ISTS GENERIC I ITS ITS LC0 ASSOCIATED CHANGE SECTION JFD(S) ITS LC0 SUBJECT NUMBER COMMENT 3.4 P38 3.4.12 Revise SR Note to exempt WOG-087 l
" performance" of the SR rather than exempt " compliance" with the SR 3.3 P29 3.3.4 Eliminate the table in the WOG-088 Will conform Remote Shutdown System LCO to post Oct.
- 2. 1996 WOG changes 3.8 P21 3.8.1 Eliminate mode restrictions on WOG-089 Eliminates P23 the performance of SRs Beyond Scope Change 12 identified in submittal letter Attachment 5 3.1 P16 3.1.7 Correct control bank insertion WOG-092 limits action for applicable mode 3.1 P3 3.1.6 Correct shutdown bank WOG-093 Eliminates insertion limits applicability Beyond Scope Change 1
. identified in submittal letter Attachment 5 1 P7 3.1.5 Eliminate unnecessary Actions WOG-094 3,2
- 3. P5 3.2.2 to restore compliance with LCO 3.2 P14 3.2.4 Allow time for stabilization WOG-095
- after reducing power due to OPTR out of limit 3.7 P14 3.7.5 Revise the Frequency of WOG-096 SR 3.7.5.5. AFW flow path verification 3.5 P2 3.5.1 Revise accumulator boron WOG-097 concentration verification SR 3.7 P6 3.7.2 Separate closure time testing WOG-098 3.7 P6 3.7.3 and actuation signal testing for MSIVs and FWIVs 8
Attachment 2 Byron /Braidwood Improved Technical Specifications - January 23, 1997 Meeting Action Item Example Byron /Braidwood Plant Specific Justifications Which are Now in the Generic Process l (page 2 of 2) i
. 1 i
RECENT I ISTS GENERIC ITS ITS LC0 ASSOCIATED CHANGE R SECTION JFD(S) ITS LC0 SUBJECT- NUMBER COMMENT 3.4 - P3 3.4.1 Extend the time allowed to WOG-099 Eliminates ! perform the DOL precision RCS Beyond Scope ' flow rate measurement Change 5 identified in submittal letter Attachment 5 3.4 P21 3.4.12 Exempt SRs on LTOP equipment WOG-100 Will conform l not used to satisfy the LC0 to post Oct. 2, 1996 WOG changes 3.2 P1/P19 3.2.1 Clarify Completion Time and WOG-101 3.2 1 P1/P19 3.2.2 Frequency wording ' 3:2 P1 3.2.4 3.4 P14 3.4.11 Specify Separate Condition WOG-102 Entry for each pressurizer PORV block valve 3.1 . P1 3.1.6 Minor editorials to the SRs. Editorial-09 3.1 P21' 3.1.3 In SRs 3.1.3.1.and 3.'1.4.1. Editorial 10 3.1 P21 3.1.4 the word "once" was deleted. 3.1 P1 3.1.5 In SR 3.1.5.3, the word
" reactor" was' deleted.
3.9 P1 3.9.1 In SR 3.9.1.1 the word "once" Editorial-11 was added. 3.4 P1 3.4.16 The LCO was revised to reflect E0itorial '.2 W11'l conform P45 the specific activity limits to post Oct. directly in the LCO. 2, 1996 editorial changes
f i . Attachment 3 Byron /Braidwood Improved Technical Specifications l . January 23, 1997 Meeting Action Item ITS LC0 versus CTS Page (page 1 of.7) , ITS LCO Braidwood CTS Page Byron CTS Page 1.1 1-1 1-2 1-3 1-4 1-1 1-2 1-2a 1-3 1-5 1-6 1-9 3/4 1-1 1-4 1-5 1-6 1-9 3/4 1-3 3/4 4-31 3/4 1-1 3/4 1-3 3/4 4-31 1.2 1-9 1-9 1.3 1-9 1-9
- 1.4 1-9 1-9 0 1-7 1-8 1-7 1-8 2.1.1 2-1 2-2a 2-1 2-2 2.1.2 2-1 2-1 2.2.1 2-1 2-1 2.2.2 2-1 2-1 o 2-2
, 2-2a 3.0.1 3/4 0-1 3/4 0-1 3.0.2 3/4 0 1 3/4'0-1 3.0.3 3/4 0-1 3/4 0-1 3.0.4 3/4 0-1 3/4 0-1 3.0.5 3/4 0-1 3/4 0-1 3.0.6 3/4 0-1 3/4 0-1 3.0.7 3/4 0-1 3/4 0-1 SR 3.0.1 3/4 0-2 3/4 0-2 SR 3.0.2 3/4 0-2 3/4 0-2 SR 3.0.3 '3/4 0-2 3/4 0-2 SR 3.0.4 3/4 0-2 3/4 0-2 6 3/4 0-3 3/4 0-3 3.1.1 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-1 3/4 1-2 3/4 1-3 3.1.2 3/4 1-1 3/4 1-2 3/4 1-1 3/4 1-2 1 3.1.3 3/4 1-4 3/4 1-5 3/4 1-Sa 3/4 1-4 3/4 1-5 3/4 1-Sa i
. CTS pages listed do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted or relocated.
l
1 l l Attachment 3 Byron /Braidwood Improved Technical Specifications ; January 23, 1997 Heeting Action Item l ITS LC0 versus CTS Page a (~page 2 of 7) ' 4 ITS LCO Braidwood CTS Page Byron CTS Page i ' 3.1.4 3/4 1 14 3/4 1-15 3/4 1-16 3/4 1-14 3/4 1-15 3/4 1-16 1 3/4 1-17 3/4 1-19 3/4 1-17 3/4 1-19 l 3.1.5 3/4 1-20 3/4 1-20
- 3.1.6 3/4 1-1 3/4 1-21 3/4 1-1 3/4 1 21
- 3.1.7 3/4 1-17 3/4 1-18 3/4 1-17 3/411 18 1 3.1.8 3/4 10-3 3/4 10-3
- 3/4 1-7 3/4 1-8 3/4 1-9 3/4 1-10 3/4 1-7 3/4 1-8 3/4 1-9 3/4 1-10 3/4 1 11 3/4 1-12 3/4 1-13 3/4 1-22 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-16
- 3/4 10-1 3/4 10 2 3/4 10-5 3/4 1-22 3/4 10-1 3/4 10-2 3/4 10-5 1 3.2.1 3/4 2-4 3/4 2-6 3/4 2-7 3/4 2-4 3/4 2-6 3/4 2-7 l l
3.2.2 3/4 2-8 3/4 2-9 3/4 2-8 3/4 2-9 3.2.3 3/4 2-1 3/4 2-2 3/4 2-1 3/4 2-2 3.2.4 1-5 3/4 2-10 3/4 2-11 3/4 2-12 1-5 3/4 2-10 3/4 2-11 3/4 2-12 i 3/4 3-5 3/43 I
- 3/4 2-3 3/4 2-5 3/4 2-3 3/4 2-5 3.3.1 2-3 2-4 '2-5 2-6 2-3 2-4 2-5 2-6 2-7 2-8 2-9 2-10 2-7 2-8 2-9 2-10 3/4 3-1 3/4 3-2 3/4 3-3 3/4 3 3/4 3-1 3/4 3-2 3/4 3-3 3/4 3-4 3/4 3-5 3/4 3-6 3/4~3-6a 3/4 3-9 3/4 3-5 3/4 3-6 3/4 3-6a 3/4 3-9 3/4 3-10 3/4 3-11 3/4 3-12' 3/4 3-12a 3/4 3-10 3/4 3-11 3/4 3-12 3/4 3-12a i 3.3.2 3/4 3-13 3/4 3-14 3/4 3-15 3/4 3-16 3/4 3-13 3/4 3-14 3/4 3-15 3/4 3-16 l 3/4 3-17 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-17 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-21 3/4 3-22 3/4 3-23 3/4 3-24 3/4 3-21 3/4 3-22 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 3/4 3-27 3/4 3-28 3/4 3-25 3/4 3-26 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-34 3/4 3-35 3/4 3-36 3/4 3-29 3/4 3-34 3/4 3-35 3/4 3 36 3/4 3-37 3/4 3-37 3.3.3 3/4 3-53 3/4 3-54 3/4 3-55 3/4 6-25 3/4 3-53 3/4 3-54 3/4 3-55 3/4 6-25 l
3.3.4 3/4 3-50 3/4 3-51 3/4 3-52 3/4 3-50 3/4 3-51 3/4 3-52 3.3.5 3/4 3 19 3/4 3-22 3/4 3-28 3/4 3-37 3/4 3-19 3/4 3-22 3/4 3-28 3/4 3-37 3.3.6 3/4 3 16 3/4 3-21 3/4 3-24 3/4 3-35 3/4 3-16 3/4 3-21 3/4 3-24 3/4 3-35 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3.3.7 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42 3.3.8 3/4 3-39 #4 3-40 3/4 3-41 3/4 3-42 3/4 3-39 3/4 3-40 3/4 3-41 3/4 3-42
- 3/4 9-14 , 3/4 9-14 CTS pages listto do not have c)rresponding ITS requirements but are provided for completeness. The CTS pages conta r n.'quirements which are deleted or relocated.
9
i l 1 Attachment 3 , Byron /Braidwood Improved Technical Specifications : January 23, 1997 Meeting Action Item , ITS LC0 versus CTS Page j (page 3 of 7) l 1 ITS LCO Braidwood CTS Page Byron CTS Page 3.3.9 3/4 1-13a 3/4 1-13b 3/4 3-2 3/4 3-6 3/4 1-13a 3/4 1-13b 3/4 3-2 3/4 3-6 3/4 3-9 3/4 3 12 3/4 3-9 3/4 3-12 i o 3/4 3-7 3/4 3-8
\
3/4 3:30 3/4 3-31 3/4 3-7 3/4 3-8 '3/4 3-30 3/4 3 31 3/4 3-32 3/4 3-33 3/4 3-38 3/4 3-43 3/4 3-32 3/4 3-33 3/4 3-38 3/4 3-43 ! l . 3/4 3-44 3/4 3-45 3/4 3-46 3/4 3-47 3/4 3-44 3/4 3-45 3/4 3-46 3/4 3-47 l . 3/4 3 48 3/4 4-49 3/4 3-56 3/4 3-57 3/4 3-48 3/4 4-49 3/4 3-56 3/4 3-57 1 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-58 3/4 3 59 3/4 3-60 3/4 3-61 3/4 3-62 3/4 3-63 3/4 3 64 3/4 3-65 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 l 3.4.1 3/4 2-8 3/4 2-9 3/4 2-13 3/4 2-14 3/4 2-8 3/4 2-9 3/4 2-13 3/4 2-14 3.4.2 3/4 1-6 3/4 1-6
- 3.4.3 3/4 4-32 3/4 4-32 3.4.4 3/4 4-1 3/4 4-1 3.4.5 3/4 4-2 3/4 4-2 3.4.6 3/4 4-3 3/4 4-4~ 3/4 4-3 3/4 4-4
, 3.4.7 3/4 4-5 3/4 4-5 3.4.8 3/4 4-6 3/4 4-6 3.4.9 3/4 4-11 3/4 4-l'1 3.4.10 3/4 4-10 3/4 4 10 .1 3:4.11 3/4 4-12 3/4 4-12 3.4.12 3/4 4-39 3/4 4 41 3/4 5-7 3/4 5-8 3/4 4-39 3/4 4-41 3/4 5-7 3/4 5-8 3/4 5-9 3/4 5-10 3/4 5-9 3/4 5-10 -
- 3.4.13 3/4 4-13 3/4 4-21 3/4 4-22 3/4 4-13 3/4 4-21 3/4 4-22 3.4.14 3/4 4-21 3/4 4-22 3/4 4-23 3/4 5-5 3/4 4-21 3/4 4-22 3/4 4-23 '3/4 5-5 3.4.15 3/4 3-40 3/4 3-41 3/4 3-42 3/4 4-20 3/4 3-40 3/4 3 41 3/4 3-42 3/4 4-20 3/4 4-20a
~
3.4.16 3/4 4-27 3/4 4-28 3/4 4-29 3/4 4-30 3/4 4-27 3/4 4-28 3/4 4-29 3/4 4-30 3/4 4-31 3/4 4-31 3.4.17 3/4 4-7 3/4 4-7 3.4.18 3/4 4-8 3/4 4-8 o 3/4 4 9 3/4 4-24 3/4 4-25 3/4 4-26 3/4 4-9 3/4 4-24 3/4 4-25 3/4 4-26 3/4 4-38 3/4 4-42 3/4 4-43 3/4 10-4 3/4 4-38' 3/4 4-42 3/4 4-43 3/4 10-4 3.5.1 3/4 5-1 3/4 5-2 3/4 5-1 3/4 5-2. CTS pages listed do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted or relocated.
Attachment 3 Byron /Braidwood Improved Technical Specifications January 23, 1997 Heeting Action Item ITS LC0 versus CTS Page (page 4 of 7) i ITS LCO Braidwood CTS Page Byron CTS Page 3.5.2 3/4 5-3 3/4 5-4 3/4 5-5 3/4 5-6 3/4 5-3 3/4 5-4 3/4 5-5 3/4 5-6a 3/4 5-6 3/4 5-6a 3.5.3 3/4 5-7 3/4 5-8 3/4 5-7 3/4 5-8
- 3.5.4 3/4 5-11 3/4 5-11 ,
3.5.5 3/4 4 21 3/4 4-22 3/4 4-21 3/4 4-22
- o 3/4 5-10 3/4 5-10 3.6.1 1-2 3/4 6-1 3/4 6-2 1-2 3/4 6-1 3/4 6 2
, 3.6.2 3/4 6-4 3/4 6-5 3/4 6-4 3/4 6-5 3.6.3 3/4 6-1 3/4 6 11 3/4 6-12 3/4 6-16 3/4 6-1 3/4 6 11 3/4 6-12 3/4 6-17 3/4 6-16 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6 24 3.6.4 3/4 6-6 3/4 6-6
- 3.6.5 3/4 6-7 3/4 6-7 !
I O 3.6.6 3/4 6-13 3/4 6-15 3/4 6-13 3/4 6-15 3.6.7 3/4 6-14 3/4 6-14' 3.6.8 3/4 6-26 3/4 6-26 3.7.1 3/4 7-1 3/4 7-2 3/4 7-3 3/4 7-1 3/4 7-2 3/4 7-3 , 3.7.2 3/4 7-9 3/4 7-9 ! 1 3.7.3 3/4 6-1 3/4 6-16 3/4 6-17 3/4 6-21 3/4 6-1 '3/4 6 16 3/4 6-17 3/4 6-21 3.7.4 3/4 7-9 3/4 7-9 I 3.7.5 3/4 7-4 3/4 7-5 3/4 7-4 3/4 7-5
- 3.7.6 3/4 7-6 3/4 7 6 1 3.7.7 3/4 7-11 3/4 7-11
, 3.7.8 3/4 7-12 3/4 7 12a 3/4 7-12b 3/4 7-12 3/4 7-12a 3/4 7-12b 3.7.9 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14a 3/4 7-15 3.7.10 3/4 7-14 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-17 - 3.7.11 3/4 7-14 3/4 7-16a 3/4 7-16 3/4 7-18 3.7.12 3/4 7-17 3/4 7-18 3/4 7-19 3/4 7-20 CTS pages listed do not have corresponding ITS requirements but are provided for completenest The CTS pages contain requirements which are deleted or relocated. 4 8
Attachment 3 Byron /Braidwood Improved Technical Specifications January 23, 1997 Meeting Action Item ITS LC0 versus CTS Page. (page 5 of 7) l ITS LC0 Braidwood CTS Page Byron CTS Page 3.7.13 3/4 9-4 3/4 9-5 3/4 9-14 3/4 9-15 3/4 9-4 3/4 9-5 3/4 9-14 3/4 9-15 3/4 9-16 3/4 9-16 3.7.14 3/4 9-13 3/4 9-13 3.7.15 3/4 9-13 3/4 9-13 3'.7.16 Open item Open item 3.7.17 3/4 7-7 3/4 7-8 3/4 7-7 3/4 7-8 0 3/4 7-10 3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-10 3/4 7 22 3/4 7-23 3/4.7-24 3/4 7-23 3/4 7-24 3/4 7-25 3/4 7-25a 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-27a 3/4 7-25b 3/4 7-26 3/4 7-27 3/4 7-28 3/4 7-27b 3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-31 3.8.1 3/4 8-1 3/4 8-2 3/4 8-3 3/4 8-4 3/4 8-1 3/4 8 2. 3/4 8-3 3/4 8-4 3/4 8-5 3/4 8-6 3/4 8-7 3/4 8-5 3/4 8-6 3/4 8-7 3.8.2 3/4 8-9 3/4 8 9 ' 3.8.3 3/4 8-1 3/4 8-3 3/4 8-4 3/4 8-9 3/4 8-1 3/4 8-3 3/4 8-4 3/4 8-9 3.8.4 3/4 8-10' 3/4 8-11 3/4 8-11a 3/4 8-13 3/4 8-10 3/4 8 11 3/4 8-11a 3/4 8-13 I 3.8.5 3/4 8-13 3/4 8-13 3.8.6 314 8-11 3/4 8-12 3/4 8-12a 3/4 8-13 3/4 8-11 3/4 8-12 3/4 8-12a 3/4 8-13 3.8.7 3/4 8-14 3/4 8-15 3/4 8-14 3/4 8-15 3.8.8 3/4 8-16 3/4 8-16 3.8.9 3/4 8-10 3/4 8-14 3/4 8-15 3/4 8-10 3/4 8-14 3/4 8-15 3.8.10 3/4 8-13 3/4 8 3/4 8-13 3/4 8-16 0 3/4 8-8 '3/4 8-17-47 3/4 8-8 3/4 8-17-47 3.9.1 3/4 9-1 3/4 9-1 3.9.2 3/4 9-1 3/4 9 1 3.9.3 ' 3/4 9-2 3/4 9-2 3.9.4 3/4 9-4 3/4 9-11 3/4 9-4 3/4 9-11 3.9.5 3/4 9-9 3/4 9-9 3.9.6 3/4 9-10 3/4 9-10 3.9.7 3/4 9-12 . 3/4 9-12 CTS pages listed do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted or relocated.
i d
. Attachment 3 ,
Byron /Braidwood Improved Tt.chnical Specifications January 23, 1997 Meeting Action Item 4 ITS LC0 versus CTS Page - , (page 6 of 7) 4 ITS LC0 Braidwood CTS Page Byron CTS Page
- 3/4 9-3 3/4 9-6 3/4 9-7 3/4 9-8 3/4 9-3 3/4 9-6 3/4 9-7 3/4 9-8 4.1.1 5-1 5-1 4.1.2 5-1 5-2 51. 5-2 4
4.1.3 6-1 5-3 51 53 ! i 4 .4.2.1 54 5-4 ! g 4.2.2 5-4 5-4 ! 4.3.1 5-5 5-5b 5-5 5-5b i 4.3.2 5-5 5-5 4 4.3.3 5-5 5-5 5.1.1 6-1 6-1 5.1.2 61 6-5 6-1 6-5 l 4 5.2.1 6-1 6-1
, 5.2.2 6-1 6-2 6-2a 6-5 6-2 6-2a 6-5 i
4 5.3.1 6-6 6-6 , 5.4.1 6-16 6-16 J 4 5.5.1 1-4 6-26 6-27 1-4 6-26 6-27 5.5.2 6-17. 6 17 5.5.3 6-18 6-18 5.5.4 6-18 6-19 6-18 6-19 5.5.5 5-Sa 5-6 5-Sa 5-6 5.5.6 3/4 6-8 3/4 6-9 3/4 6-10 3/4 6-8 3/4 6-9 3/4 6-10 5.5.7 3/4 4-42 3/4 4-42 5.5.8 3/4 0-2 3/4 0-3 3/4 0-2 3/4 0-3 5.5.9 3/4 4-13 3/4 4-14 3/4 4-14a 3/4 4-15 3/4 4-13 3/4 4-14 3/4 4-15 3/4 4-16 3/4 4-16 3/4 4-17 3/4 4-17a 3/4 4-17b 3/4 4-17 3/4 4-17a 3/4 4-17b 3/4 4-17c 3/4 4-18 3/4 4-19 3/4 4-18 3/4 4-19 5.5.10 6-17 6-18 6-17 6-18 4 CTS pages listea do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted or relocated.
i Attachment 3 Byron /Braidwood Improved Technical Specifications January 23, 1997 Meeting Action Item , ITS LC0 versus CTS Page l l (page 7 of 7) ' l l ITS LC0 Braidwood CTS Page Byron CTS Page l 5.5.11 3/4 7-14' 3/4 7-15 3/4 7-16 3/4 7-16a 3/4 7-16 3/4 7-17 3/4 7-18 3/4 7-19 i 3/4 7-17 3/4 7-18 3/4 7-19 3/4 9-14 3/4 7-20 3/4 7-21 3/4 9-14 3/4 9-15 3/4 9-15 3/4 9-16 3/4 9-16 5.5.12 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-1 3/4 11-2 3/4 11-3 5.5.13 3/4 8-4 3/4 8-4 5.5.14 6-27 6-27 5.5.15 6 27 6-27 5.5.16 1-2 1-3 1-4 3/4 6-1 12 1-3 1-4 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-2 3/4 6 3 3/4 6-4 3/4 6-5 5.5.17 3/4 8-11 3/4 8-12 3/4 8-11 3/4 8e12a 5.6.1 6-20 6-21 6-20 6-21 5.6.2 6-22 6-22 5.6.3 6-22 6-22 5.6.4 6-22 6-22 5.6.5 6-22 6-22a 6-22 6-22a 5.6.6 3/4 4-32-37 3/4 4-39 3/4 4-40 3/4 4-40a 3/4 4-32-37 3/4 4-39 3/4 4-40a 3/4'4-40b 5.6.7 3/4 3-53 3/4 3-53 5.6.8 3/4 6-8 3/4 6-9 3/4 6-10 3/4 6-8 3/4 6-9 3/4 6-10 5 6.9
. 3/4 4-17c 3/4 4-17d 3/4 4-17c '3/4 4-17d 5.7.1 6-25 6-25 5.7.2 6-25 6-26 6-25 6-26
- 6-3 6-4 6-7 6 15 6-3 64 6-7 6-15 6-23 6-24 6-23 6-24 CTS pages listed do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted or relocated.
& 0
._ ._- - . . . . = . - . . _ _ - -- -
1 4 Attachment 4 Byron /Braidwood Improved Technical Specifications Anticipated License Amendment Requests versus Affected ITS LC0 (page 1 of 1) I i 4 AMENDMENT IMPACTED REQUEST SUBJECT CHANGE DESCRIPTION DESCRIPTION OF ITS IMPACT ITS LCO* PTLR** Relocate RCS heatup and cooldown 4 limits and curves, coupon removal ITS submittal reflects the 5.6.6
; relocation of this ' schedule, and LTOP figures to an information with owner controlled report which appropriate discussions.
includes methodology. Throttle l Revise throttle and governor valve None None Valve / Governor surveillance frequency from monthly j Valve to quarterly. - Byron only- Revise battery specifications to Value changes and addition Battery reflect new purchased batteries. 3.8.4 of battery specific i Replacement 3.8.5 ' discharge test. 3.8.6 Byron only - Decrease RCS Dose Equivalent Iodine Value change only. Dose Equivalent 3.4.16 allowable value to allow continued
- Iodine operation prior to SG replacement.
allowable value
- Byron only - Revise UHS basin requirements based Value changes only.
Ultimate Heat 3.7.9 SG replacement and recent design
- Sink evaluations.
Boraflex** Provide ITS Specifications which Specification development 3.7.14 ! reflect the Technical Specifications involved. 3.7.15 ', associated with the spent fuel pool 3.7.16 and racks which will be in effect at 4.0 the time of implementation. Steam Generator Revise CIV table to reflect single Affects the listing of 3.6.3 (SG) feedwater penetration for the new Feedwater (FW) Isolation 3.7.3 i Replacement #1 Unit 1 SGs. Valves subject to closure (CIV) time testing and background description of FW flow paths. SG Replacement Revise specifications to reflect Value changes only. 5.0
#2 (P,) analyses changes associated with B 3.6.5 steam generator replacement.
including revision to P,. maximum peak containment temperature. SG Replacement Revise Instrumentation and RCS Value changes only. ' 3.3.1 ' #3 (SG Levels) Section Steam Generator level values 3.3.2 to reflect the new Unit 1 steam 3.4.5 generators. 3.4.6 3.4.7 SG Replacement Revise SG Inspection Program to Program will be revised to 3.4.16
#4 (SG reflect new Unit 1 SGs and revise reflect Unit 1 inspection 5.5.9 Inspection Dose Equivalent Iodine allowable requirements. No 5.6.9 Program) value to standard value, additional conversion 1ssues involved. Dose Equivalent Iodine change is a value only change (affects Figure also).
o , Bases associated with the identified LC0(s) will also be revised. Any Bases which are
" impacted other than those directly associated with an impacted LCO are identified separately.
Identified as open item in Improved Technical Specification submittal.
. . . . . . - . . . . - - - . - - - - . - . -.- - - - - - _ . . . .. - - - . . ~ .
Defide M m I.I
- l. 0 USE AND APPLl(A7loM
- 1.## DEFINITIONS i i i --
I i ______.norc-------------- ,
@ The defined terms of this section appear in capitalized type and are applicable hroughout these Technical Specifications
)
f . ._ ona Sa3 ______,_ ACT% Required Ach 6 be 4.kQ I
%d
, e O ACTI0h.. M -- hall be that part of a taaha!tsap Specification deh prescribes under designated conditionsO( e . oc A l W e b T. Q i ACTUATION LOGIC TEST
- O An ACTUATION LOGIC TEST shall be the application of various k r_m simulated b hi+ !
input combinations in conjunction with each possible interlock logic state and i verification of the required locic output. include a continuity checkC as a minimum.) of output devices.The ACTUAT 996%90 CHANNEL OPERATIONAL TEST '
@ cril-lh $
@ EESAs"AlWGDCHANNELOPERATIONALTESThhallbethe'injectionofasimulated/
4 signal into the_ channel as close to the/ sensor as practicable to verify ) OPERA 8ILITY & _ _. . ....... m ...,.z..
.ri: functi ff.a The SIMRID CHANNEL OPERATIONAL TEST shall include adjustments, as necessaiy, of the alarm, inter-1a9 ed@ 91; Estpir.t, ' d,a t .a ti e ~,si.i,vinto . are wicnin 1nehrequirea range and accuracy. .
% egr w 6. perke,..J b wee d ow (rewire AXIAL FLUX DIFFERENCE sedes oc speMar, wertsppi.,9, ne M.J q % ,, , y 3. u n ,,,y ,y ,,,,, g ,d.
O AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signa.ls between the top and bottom halves of a two section excore neutron detector. CHANNEL CALIBRATION O A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that L responds within the required range and accuracy to known
- "- e inpu@ JThe C"^~5L c=LIPa= th::' :::r- :n .n; ;nn r g g fr-Ndiaa &e trice r rd eh- , %te '::S : 1':r tri; funnM nM: :aay bem_ i.g performed bysany series or sT(Utnr.ial, overlapping, or total channel steps such that the' entire channel is calibrated. / gh ggg Q wm .o CHANNEL CHECK a.g -- -
& A CHANNEL CHECK shall be the qualitative assessment,of channel behavior !
g during operation.(by observatioriI This determination shall include, where O possible, comparison of the channel indication and@ status with other ( l indications @r status derived from independent instrument channels 1 measuring the same parameter. i i i l l
\
BRAIDWOOD UNITS 1 & 2 1-1 - 1 I
..- - . .. . ~ -. .- - .
CTS INSERT (S) SECTION 1.0 9 Definitions l'.1 1 INSERT 1 1A (A3 and A4) {
-The CHANNEL CALIBRATION shall encompass those components, such as sensors. I alarms, displays, and trip functions, required to perform the specified safety l function (s). Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative l assessment of sensor behavior and normal calibration of the remaining -
l adjustable devices in the channel, j i INSERT 1-1B (A3 )
... . including all components in the channel, such as alarms, interlocks.
displays. and trip functions. required to perform the specified safety function (s). I 4 Revision A
i Debnebens eI
- Lco wm 36\
n s.o hDEFINITIONS [Addrewdh 5dhea 34 ( N ba & Suho.4 5. 6 ) TONTA'INMENT~ INTEGRITY ' % 1
\"^ ~~ ^
1.7 CONTAINMENT INTEGRITY shall exist when; a. All penetrations are either: required to be closed during accident conditions, 1) Capable of being closed by an OPERABLE containment automatic isolation valve syste.a, or
- 2) 1 Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as p'rovided in Table 3.6-1 of Specification 3.6.3.
b. ' All equipment hatches are closed and sealed, c. Each air lock is in compliance with the requirements of Specification 3.6.1.3, ' d. The containment 3.6.1.2, and leakage rates are within the limits of SpecificatioIseon &
- e. T= 0% '
The sealing hallnwc. mechanism m 0-rings) associated with each penetration (e.g., welds, is OPERABLE. CONTR6LLEDLEAKAGE(
- 1. 8 CONTRO _
co antpum/LEDLEA
)
p seals. shallbe[tatsealwat/rflowsu[liedtot/ereacto)
/
; CORE ALTERATION'
([od, s , ,
-4v4y reably
@ CORE ALTERATION shall be the movementan.aanipe:tetfitp of anykompone within Suspension the reactor of CORE vessel with ALTERATI0@shall not the precludevessel completion head of mov'ement removed of a and fue component to a safibusumulitum position.
fCRITICALITYANALYSISOF84RONANDBRAIDWOODSTATIONEUEL/TOR
- 1. 9a Th CRITICALITYA/ALYSISOFBYRONDBRAIDWOODSJTIONFUELSTOR d RACKS, i a document t at provides the E storag ximum allowab These limit shall be date ned and subai ed in accordan with e fuel. enrichme for a Specif cation 6'.9.1. 0.
[ndiv dual Specific ions.Plant opera on within thes limits is addr sed i DIGITALCHA6MELOPERATIONA TEST ! l'.10. A D ITAL CHANNEL 0 ERATIONAL TEST hall consist of exercising the igital computer ardware using ata base manip ation and injec ing simulated ocess ptato erify OPERABI TY of alarm an or trip functi s. 4 DOSE EQUIVALENT I-131 6which DOSE EQUIWLENT I-131 shall be that concentration of I-131 (microcurie / gr alone would produce the same. thyroid dose as the quantity and isotopic mixture of I-131,.I-132, I-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." l I BRAIDWOOD UNITS 1 & 2 1-2 AMENDMENT NO.18 l
)
De 6 n ,t,,3 ,, , L- c-o ?. . (, . l-DEFINITIONS U"#5 'l ' )k CONTAINMENT INTEGRITY Y$ " D CONTAINMENT INTEGRITY shall exist when: i a. enetrations required to be closed during accident 1tions i are e r: , 1) Capable ing closed by an.0PER containment automatic { isolation valv tem, or I 2) Closed by manual val , ind flanges. or deactivated automatic
- valves secured eir close itions, except as provided in j
~ Table 3. - Specification 3.6.3. '
- b. All nt hatches are closed and sealed, ach air lock is in compliance with the requirements of 4
Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of Specification '
3.6.1.2, and i e. The sealing mechanism associated with each penetration (e.g., welds, - bellows, or 0 rings) is OPERABLE. - CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement'of a component to a safe conservative position. CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACKS 1.9a The CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACXS, is a doc'ument that provides the maximum allowable fuel enrichment for storage. These limits shall be determined and submitted in accordance with Specification 6.9.1.10. Plant operation within these limits-is addressed in individual ~ Specifications.
. DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.
DOSE EQUIVALENT I-131 1.11 DDSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the cuantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation 'of Distance Factors for Power and Test Reactor Sites." hadtessed sn D& ,4; ,s s I
- BRAIDWOOD. UNITS 1 & 2 h Docs 1-2 for Sn.4.ea I.c AMENDMENT NO.18
. ~ . -. - . - .- -. -. . - . . . . .
- De ft a.4 3 3,3 i
- L c o 3. (, . I Sec+;en s.o DEFINITIONS
\:u ^ GO :., cc +.v &
CONTAINMENT INTEGRITY % >#> # ~ 1.7 ' CONTAINMENT INTEGRITY shall exist when:
- a. All penetrations required to be closed during accident conditions j
are either:
- 1) Capable _of being closed by an OPERABLE containment automatic i ,
isolation valve' system, or '
- 2) Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.
- b. All equipment hatches are closed and sealed,
} c. Each air lock is in compliance with the requirements of i-Specification 3.6.1.3, i
"dNeT5ntai * * ~
o pecification 1
- e. Th; ;;;lin =W j 5:ll: :, :g-:::h:0 ' ;:)i::i: :::::i:ted 0"ERf."LE. "ith ::9 peae+ @ = N O
- CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
! CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION 'shall not preclude completion of movement of a component to a safe conservative position. CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACKS
- 1. 9a The CRITICALITY ANALYSIS OF BYR'ON AND BRAIDWOOD STATION FUEL STORAGE RACKS, is a document that provides the maximum allowable fuel enrichment for storage. These limits'shall be determined and submitted in accordance with -
Specification 6.9.1.10. Plant operation within these limits is addressed in individual Specifications. DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY'of alarm and/or trip functions. DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for. Power and Test-Reactor Sites." Maress J in De(; a,.n, i,; - BRAIDWOOD UNITS 1 & 2 se. D oc 3 6.1-2 W on i,o AMENDMENT tl0.18 . u -_
feAw&m t. t j i 6 ped =4in fD
@ DEFINITIONS j E -' AVERAGE DISIKTEGRATION ENERGY w caw a.m a m.e>
j h @ E shall'be the average edinproportiontotheconcentiationof i each radionuclide in the(senem of,the sum of the average beta and ganna i energies per disintegration tr;/m for - : r :- re n::: A mv ) '- the :----1:q { , ENGINEERED SAFETY FEATURES RESPONSE TIME ,jyg[,9 i
@ G The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its j safety function i.e.
di'scharge pressur(es re,ach their required values, etc.).the Times valves travel t shall include diesel generator starting and sequence loading delays where applicable.g fFRE00ENCY NOTATION (** ! .4 The FREQ CY NOTATION spicified for e perform equirements e of Surv lance j all correspond"to the int als defin in Table .. l GUENIHEIP) LEAKAGE 8BENYIME!P)LEAXAGE shall be: '
- a. IJa.a.G.4A. Laakat.c ~
akane f:::::t :""""2LLir .trre.;;; 9 : :::::: :/:t-3 such tas C-+w=) pump sea @or valve packing L;;;; r- r y aptured and conducted to sump or collecting tank, @ f cm.e rua.euaw m w u o .v.e s u m o n U msesuya;w or wuA %umisaysen) Q /eak e into'the containment atmosphere from sources that are both spec " cally located and known either not to interfere with the g operationofgeakagegetectionfystemsornottobe/RE55URE JOURUKRTLEAKAGE,or 3 ReactorCoolantSystem/eakaaethroughasteamgeneratortothe Secondary (EetrtantfSystem.
/b,M4en%
s { f 1, W. Pre *+= sea L4hkuc rs. %duy LE4xur. deh9in dea %waver mevdhere:.. kre.) I 1.15.a The maximum allowable primary containment . leakage rate, L , shall be i 0.10% of the primary containment air weight per day at the calcul'sted oeak ; tcontainment pressure (Pa). / 4adeegaA hs %Adoggo MASTER RELAY TEST - .w. * ,4 e m a; w See 'poc 4 - 6ecM 60 s hM ( >:r"
. y ver.w w & c.), A MASTER REl.AY TEST shall ^- "- ----'--"-- -* each
- t ter, en0PERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
MEMBER (S) 0F THVPUBLIC 1.17 MEMB 0F THE PUB shall inclu all persons o are not occupati ally associate with the plan . This categ \ employ s of the licen e, its contr does not in ude ) ors or vendo and persons o enter the te to service uipment or t ke deliveri . This cate' y does in ude' persons w use. portions f the site fo recreational occupational.) other purpos not associat with the pl .I
~
BRAIDWOOD - UNITS 1 & 2 1-3 AMENDMENT NO. 73
. , - , - ...n - , - -
2 B
. CTS INSERT (S) l SECTION 1.0 Definitions 1.1 INSERT 1 3A (L2 )
The response time may be measured by means of any series of sequential. ;
- overlapping, or total steps so that the entire response time is measured.
l i i l i I Revision A O rr
_ - .-.- - . - . . ~ - . . . . . - . - _ . - . . . . _ _ . - . - . - - - . - - . - . . . . . . - - - - DEFINITIONS De%:4<eed.I Sec+. e a 5.0 4 . t _E - AVERAGE DISINTEGRATION ENERGY i 1.12 E shall be the average (weighted in proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gamma ! energies per disintegration (MeV/d) for the radionuclides in the' sample. ENGINEERED SAFETY FEATURES RESPONSE TIME t 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time ! i interval from when the monitored parameter exceeds its ESF Actuation Setpo. int 4 at the channel safety functionsensor until the ESF equipment,is capable of performing its i.e. { discharge pressur(es re,ach their required values, etc.).the Times valves travel shall include diesel generator starting and sequence loading delays where applicable. s , FREQUENCY NOTATION i 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance i Requirements shall correspond to the intervals defined in Table 1.1. j IDENTIFIED LEAKAGE i i 1.15 IDENTIFIED LEAKAGE shall be: 1 ! a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as i pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or 4
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the 1-operation of Leakage Detection Systems or not to be PRESSURE j BOUNDARY LEAKAGE, or j
.c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant' System.
b l S.54, h . 1.15.a The maximum allowable primary containment . leakage rate, L , shall be 0.10% of the primary containment air weight per day at the calculated peak containment pressure (Pa). Adecssed in Sec4.o.,I.O MASTER RELAY TEST su pocs (.,5 9 # i 1.16 A MASTER RELAY TEST.shall be the energization of each master relay and ' verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
- MEMBER (S) 0F THE PUBLIC 1.17 MEMBER (S) 0F THE PUBLIC shall include all persons who are not i
occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter j the site to service equipment or to make deliveries. This category does
, include persons who use portions of the site for recreational, occupational, l or other purposes not associated with the plant.
BRAIDWOOD - UNITS 1 & 2 1-3 AMENDMENT NO. 73 .
,, -, , - ~
DeC n1&c t.1 l Spexb% 5:0
- DEFINITIONS -
'pfFSITE DDSE CALCULATION MANUAL d'y l [
- 1.18 t The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the metnocology j and parameters used in the calculation of offsite doses resulting from radio- } .
active gaseous and liquid affluents, in the calculation of gaseous and liquid ' effluent monitoring Alars/ Trip Setpoints, and in the conduct of the Environ-
- mental Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environimental Monitoring i
Programs required by Sections 6.8.4.e and f, and (2) descriptions of the
'infomation that should be included in the Anriual Radiological Environmental 4 * ' ( Operating and Radioactive Effluent Release Reports required by Specifications , \6.9.1.6 and 6.9.1.7. /
OPERABLE - OPERABILITY An tem m,pw gga l
@ G A system, subsystem, train, component or device sh 11 be ERABLE or
! have OPERABILITY when it is capable of performing its spe ified function (s), i O anri when all necessary attendant instrumentation, controls, electrical power, coolingMS seal water, lubricationE other auxiliary equipment that are j required for the system, subsystem, train, component, or d.evice to perfom its function (s) are also capable of performing their related support function (s). G2ED OPERATING LIMITS REPORT G5E _cW.JtApee'i r4c. f Mtrume+ea9 8 D'""Dl g" 4 h G=PEprovide B TheC^"F"^ m r LI"ITE """^" h s-specific the un document that I 7 : = r.Z 11mits for the currentt=:r:::nc reload cycle. These. i cycle-specific <=aerattnelimits shall be determined for each reload cycle in ification 0' .0.1.01 { j accordance limits is addressedl with Spe(in individua1Qs ecifMons" operation within the ( Parsmaksv) @ qy ( g4,w ) l c~ e.v:'= L necE 2 MODE i h 6 2 '"""aTI'"= ".=r " n .) MOD [shall correspond to any one inclusive combinktion of core reactivity condition power level', @ average reactor ! coolant temperaturegspecified in Table
/
,,,,, , m m , , , % )
(g4neu.4*rve*<.1LM
'Mmre W+ htW '
@\ , .
u wh,,,h, g,, %g p 1.20.a P shall be the maximum cali:ulated primary containment pressure! j ((44.4 psig) for the design basis loss of coolant accident. J PHYSICS TESTS # 4 (z w w w +.Vrw. a &**" ) 4 Q PHYSICS
@ nuclear charact STS shall be t ose tests performed to measure the fundamental in Chapter 14 fistics of the core and related instrumentation.
the@SAR, /e' scribed 50.59,or,@ herwiseappro@edbytheIbthorized ommission. . under the provisions o 10 CFR (PRET5URY r y v BOUNDARY r \ LEAKAGE \ Y g ,m ,,. ,. . - -
-~...~ LEAXAGE 6he++-be-+eekene) (except steam generator 6 kbody, pipe wall', or vessel wall./_bbad) through a nonisolable fault in a 1 w w _ w wm
___1 BRAIDWOOD - UNITS 1 & 2 1-4 AMENDMENT NO. 73
D eh6 % i. Spn M s.o . i DEFINITIONS OFFSITE DOSE CALCULATION MANUAL 5.5.1.. hit The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodol and parameters used in the calculation of offsite doses resulting from radio- . active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alars/ Trip Setpointy and in the conduct of the Environ- , i mental Radiological Monitoring Procram. The ODCM shall also contain (1) the 7 Radioactive Effluent Controls and Fadiological Environmental Monitoring Programs required by Sections 6.8.4.e and f, and 2) descriptions of the E 'information that should be included in the Annual (Radiological Environmental Operating and Radioacti>e Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7. OPERABLE - OPERABILITY I 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perfom its function (s) are also capable of performing their related support function (s).. '
' OPERATING LIMITS REPORT 1.19.a The OPERATING LIMITS REPORT is the unit-specific document that provides operating limits for the current operating reload cycle. These cycle-specific operating limits shall be determin6d for each reload cycle in accordance with Specification 6.9.1.9.
limits is addressed in individual specifications. Plant operation within these operating OPERATIONAL MODE - MODE 1;20 An OPERATIONAL MODE (i.e., MODE) shall correspond. to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 E, . Asans,a :n su% -mn.o S.3,l6 . S u oo w S a k .,to f. 1.20.a P (44.4 psi,) PHYSICS TESTS g for the design basis' loss of coolant accident.shall be the maxim F '[ # 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR- ~ 50.59, or (3) otherwise approved by the Comission. PRESSURE BOUNDARY LEAXAGE . 1.22 PRESSURE BOUNDARY LEAXAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. BRAIDWOOD - UNITS 1 & 2 1-4 AMENDMENT NO. 73
Def m be 1. l
@ DEFINITIONS
" PROCESS CONTAQL PROGRAM (
1.23 The PROCESS CONTROL (PCP) shall contain the current. formulas d sampling, analyses, tests, and de rs Rtions to be made to en ! processing and packaging of solid radioactlus on demonstrated processing of actual or simulated wet s sWJe accomplished in such a way as to assure with 10 CFR Parts 20, 61 M nd 71, State ; regulations round require'aents, and other requirements iioTem o the o solid radioactive waste. . PURGE-PURgkNG / 1.24 PU E or PURGING sha be any contro11e process of disc ing air or gas from a nfinement to mai in temperature, ssure, humidity concentration INSERT, or oth operating condi ion, in suci,a man r that replaceae air or gas is tl gA grequi d to purify the onfinement.) OUADRANT POWER TILT RATIO
@ QUADRANT POWER TILT RATIO shall be the ratio of the maximum. upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum ' lower execre detector calibrated output to the_ average of the lower excore detector calibrated outnuts. whichever is_creater. /With one excore detector inoperable, the remaining three detectory
[shallbeusedforcomputingtheaverage.j _ g4 d dre w d b S ee
- 3. 2 . se RATED THERMAL POWER do s A Sub 2.2 f.JM*at4or)
RATED THERMAL POWER shall be a totallcore heat transfer rate to the h @ reactor coolant of 3411 MWt. REACTOR TRIP SYSTEM' RESPONSE TIME E D The REACTOR TRIP SYSTEM RESPONSE IME shall be the time interval from when the monitored parameter exceeds its ipgetpointatthechannelsensor until loss of stationary gripper coil voltage. REPORTMLEEVENT( 1.28 A REPORT LE EVENTMall be any pf those condi/ ions specified in ) Sec ion 50.73 of 10 CFR rart 50. / / / J SNUTDOWN MARGIN 4 (Canho)) CRCCAs) G SH RGIN shall be the instantaneous amount of reactivity by which the react r is suberitical or yould 1 from its present condition
/B'/
v assumin@d11 GBEH5pEh /od fluste [e subcriti ssemblies _utdown-end'd=r:M are fully inserted except for the single r== :rrt:r :::-- g of highest reactivity worth which is assumed to be fully withdrawn.
.. lM
@_{reca.r i-sc 7 BRAIDWOOD UNITS 1 & 2 1-5 AMENDMENT NO. 35
. . - - -_ = -. -- - -- _ . . . - .
CTS INSERT (S) SECTION 1.0 Definitions 1.1 1 INSERT 1 5A (Au ) PRESSURE AND The PTLR is the unit specific docament that provides TEMPERATURE LIMITS the reactor vessel pressure and temperature limits REPORT (PTLR) including heatup and cooldown rates, and the pressurizer Power Operated Relief Valve (PORV) lift settings for the current reactor vessel fluence seriod. These pressure and temperature limits shdll 3e determined for each fluence period in accordance l with Spcification 5.6.6. Plant operation within l these limits is addressed in individual Specifications. I INSERT 1 5B (L2 ) The response time may be measured by means of any series of sequential, l overlapping. or total steps so that the entire response time is measured. INSERT 1 5C (M3 ) b. In MODES 1 and 2. the fuel and moderator temperatures are changed to the hot zero power temperature. 1 9 6 Revision A
O d n,0.o, i, , E SP *d e.4,ca 3.a.4 i j DEFINITIONS y PROCESS CONTROL PROGRAM , [o$$$ [#.$ . 1.23 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, i ] sampling, analyses, tests, and determinations to be made to ensure that l ! processing and packaging of solid radioactive wastes based on demonstrated j i processing of actual.or simulated wet solid wastes will be accomplished in
- such a way as to assure compliance with 10'CFR Parts 20, 61, and 71, State i regulations, burial ground requirements, and other requirements governing the
- disposal of solid radioactive waste.
i PURGE - PURGING ' i 1.24 PURGE or PURGING shall be any controlled girocess of discharging air or gas i from a confinement to maintain temperature, pressure, humidity, concentration i or other operating condition, in such a manner that replacement air or gas is
- required to purify the confinement.
l ! QUADRANT POWER TILT RATIO 1.25 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore l Ln detector calibrated. output to the average of the upper excore detector cali-
- brated outputs, or the ratio of the maximum lower excore detector calibrated j
W output to tre averace of the lower excore detector calibrated out>uts, whichever V s areater. With one excore detector inoperable, the remaining tiree detectors
$lg/ TafstD be used for computing the average.
- RATED THERMAL POWER
- l i
1.26 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MWt. j
. . l . REACTOR TRIP SYSTEM RESPONSE TIME 1
l 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from ! when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss' of stationary gripper coil voltage.
- REPORTABLE EVENT ,
1.28 A REPORTABLE NEVE'T shall' be any of those conditions specified in !' Section 50.73 of 10 CFR Part 50. SHUTDOWN MARGIN ! 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which ! the reactor is subcritical or would be subcritical from its present condition 1 assuming all full-length rod cluster assemblies (shutdown and control) are i fully inserted except for the. single rod cluster assembly of highest reactivity l worth which is assumed to be fully withdrawn. Qpn--
- kddressedis Sec4,y g,o l ,
f Q ( S'e D%s for Sec4, o, i.o BRAIDWOOD UNITS 1 & 2 - l-P' AMENDMENT NO. 35 i
4 Deb. bas 1.1 . 1 I l hDEFINITIONS l 1
'SITEBQDNDARY}
1.30 he SITE B00 ARY shall that line be nd which the and is neith Wnet,norleasedfnorotherv e controlled b the license SLAVE RELAY TEST enN.a *e) u s.s+ .i .... - G:3B A SLAVE ELAY TEST shall h e each slave relay and eve-"r r :: :: PERABILITY of eachtrelay. The SLAVE RELAY TEST shall include
,a_continu<ty checkf as a minimum,) o yassociated testable actuation devices.
SOLIDIFICAI C D tSOURC/ CHECK (
@ O 1.3 A SOURC CHECK sh 1 be the qu itative a essment o channel re onse the cha el senso is exposed a source increas radioactiv .y STAGGERED TEST BASIS GD A STAGGERED TEST BASIS shall consist of[ T.*((
fa. A test schedule for systems, subsysteins, trains, other desi isted' f components obtained b ' dividing t specified te t interval i on equal intervals, d
\
- b. The t sting of one ystem, subsy tem, train, r other designat como nent at the ginning of ch subinter 1. -
THERMAL POWER - is eneven g G2EP THERMAL POWER shall be the tota 14 core heat transfer rate to the reactor coolant. Ime e g a bA TRIP ACTUATING DEVICE OPE L TEST EiEB A TRIP ACTUAT DEVICE OPERATIONAL TEST shall consist of aaaratina the Q ~ frip Attuating A6vfce and verifying OPERABILITY Of al-w ;m. riou ...a2 Gr.1; ^=rtune.14he TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment,asnecessary,oftheAip,Attuatinggevicesuchthatitactuates at the required getpoint within the required accuracy. bead
] UNIDENTIFIEF LEAKAGE QtQPgeo l watte m3e4 t'EB GmfFNHADfLEAKAGE dHEBh @dustapnMich is not JDENTIFIEf LEAKAGE Q L _ . -
[UNRESTRICTEdAREA( 1.38 An NRESTRICTED REA shall be a area at or be nd the SITE B01)dDARY access which is no controlled by he licensee fo purposes of pr ection of indi iduals fros' posure to radi tion and radio' tive materials or any thin the SIT BOUNDARY used or residential uartersorforindustrial,) karea c cial, instit ional.'and/or ecreational pu oses. _1 BRAIDWOODUNITS1k2 1-6 AMENDMENT NO. 35
1 P CTS INSERT (S) : SECTION 1.0 1 Definitions .l.1 INSERT 1 6A (Ag )- the testing of one of the systens subsystems, channels, or other designated canponents during the interval specified by the Surveillance Frequency, so that all systems. subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of. systems, subsystems, channels, or other designated components in the associated function. INSERT 1 6B (A3 and L3) -
. . . . . including all components in the channel, such as alarms, interlocks.
displays, and trip functions, required to perform the specified safety
. function (s). The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire trip actuating-device is tested.
6 j Revision A
Dek%ks \.8 j l ((() DEFINITIONS i l t N EXHAUST TREATMENT SYSTEM ( 1.39 A VENTILATION EATMENT SYSTEM shall be any system j installed to reduce gaseous ra and 1 e or radioactive ' n particulate form in effluents by passing ventilatio n st gases through charcoal l Ag adsorbers and/or HEPA filters for th l j ulates from the gaseous exh o oving iodines or partic- l team prior to the r to the environment.
- Such a system is no ered to have any effect on noble )
- Engineered effluents.
eatures Atmospheric Cleanup Systems.are not co red . to ILATION EXHAUST TREATMENT SYSTEM components. I VENTING / f ~ 6 1.40 VENTING hall be any con olled process of ischarging air o gas from a
- confinement maintain tempe ture, pressure, idity, concentr tion or other opera ing condition, i such a manner th. replacemen.t air or gas is not
! provided o required during ENTING. Vent, u d in system na , does not I imply a V NTING process. i M HOLDUP SYSTEM i i 1.41 A WASTE GAS HOL A hall be an' esigned and installed to i reouce radioactive gaseous'efflue ., eting Reactor Coolant System off-l gases from the Reactor ystem and prov i the purpose delay or holdup for
- en ng the total radioactivity prior to to the e
i i 4 l. BRAIDWOOD UNITS 1 & 2 1-7
D36ndini 1.1 5 ! TABLE 1.1 FREQUENCY NOTATION
/
\
NOTATION \ FREQUENCY , l 5 '\ At least once per 12 i \ urs. 1 W D
\ At least once per 4 hours.
At least onc er 7 days. M At east ce per 31 days. Q At 1 (onceper92 days. .
.SA least o per 184 days.
R At least once p 18 months. j S/U Prior to each react startup. N.A. Not applicable, e completed prior to each rel se. 1 As 4 BRAIDWOOD UNITS 1 & 2 1-8 .
t Deb'.4Jons 1. I '
- l. )- l TABLE O F)
SahAT:0NA0 MODES li C.TDR) ' REACTIVITY MODE CONDITION, K % RATED (a) AVERAGE 00iANT b' TLE] eff THERMAL POWER # TEMPERATURE @
- 1. POWER OPERATION > 0.99 > S[ (1. r#U NA '
- 2. STARTUP V
> 0.99 < 55 d MO n NA ,
- 3. HOT STANDBY < 0.99
- 4. HOT SHUTD0 < 0.99 E NA
] >3507 l R NA / 350[>T A.
> 200 Q ,y9
- 5. COLD SHUT 00 < 0.99 $ NA
<2007 6.
REFUELI k (Ch Q NA @^ 1L N A
@ )JA @
).
A. la) 7Exelvoing decay heet. (08sel ..,tr.; ree; tor =;;e; NW*"S vessel head closure bolts less than fully tens oned.p r . tt, ti+ ::: .__:-= Q Q h6A&vguie/reache vessel heus) closure bol4 s fully de n tion *{
^W kN E (see T.nsecl.1-94)
Ses % 1.2. - L.3 de.l Cverben See L 17 - Crpi,L E,i 5ec L l.4 - l~reye-< y BRAIDWOOD UNITS 1 & 2 1-9
, 'Iicer+ 1- 9 A LogicalConnectorg, hoc) e. Iof 21 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of l logical connectors. Lcgical connectors are used in Technical Specifi. cations (TS) to discriminate between, and yet connect, discrete Conditions. Required Actions. Completion Times. Surveillances, and Frequencies. The on1 logical connectors that appear in TS are AND and DR. The p sical arrangement of these connectors constitutes logical conventions with pecific meanings. 4 e BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified b the placement (or nesting) of the logical connectors and the number assigned to each Required Action. The first lev'l e of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector ' in the first level of nesting (i.e.. left justified with the number of the Required Action). The successive levels of j logic are identified by additional digits of the Required i Action number and by successive indentations of the logical connectors. When logical connectors are used to state a Condition.
' Completion Time. Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition. Completion Time. Surveillance, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors. (continued) BRAIDWOOD - UNITS 1 & 2 1.2-1 Revision A ,
TN9E.Ar Logical Connectors, l-44
- 1.2 Fw)e.
1.2 Logical Connectors @## Al ; EXAMPLES EXAMPLE 1:2-1 LOGICAL CONNECTORS (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Veri fy . . . 8HQ A.2 Restore . . . - In this example the logical connector eEQ is used to- ) indicate that when in Condition A. both Required' Actions A.1
~
and A.2 must be completed. O i
. l i
.(continued)
BRAIDWOOD - UNITS 1 & 2 1,2-2 Revision A .
I n e.x r f 44 An Logical Connectors, 1.2 , Pq,_ 1.2 Logical Connectors #I J EXAMPLES EXAMPLE 1.2-2 MULTIPLE LOGICAL' CONNECTORS (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LC0 not met. A.1 Trip . .
@ l . i A.2.1 Veri fy . . .
l A.2.2.1 Reduce . . . 2 A.2.2.2 Perform . . . I A.3 Align .'. . This example represents a more complicated use of logical
~
connectors. Required Actions A.1. A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector @ and the left justified may be chosen.Ifplacement.A.2 is chosen, Anythen one both of these A.2.1 three and Actions A.2.2 must be performed as indicated by the logical connector MD. Required Action. A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector
@ indicates that A.2.2.1.and A.2.2.2 are alternative choices, only one of which must.be. performed.
BRAIDWOOD - UNITS 1 & 2 1.2-3 Revision A .
Q 3 Completion T1 , 1-44 m Pe.y. t>5 1.0 USE AND APPLICATION (q g g J . 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance.for its use. 9 BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LC0 state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action (s) and Completion Time (s). DESCRIPTION The Completion Time is the amount of time allowed for completing a. Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the~LCO. Required Actions must be c leted prior to the expiration of the specified C letion Time. An ACTIONS Condition remains in effect and th Required Actions apply until the Condition no longer exists or the. unit is not within the LCO Applicability.
, If situations are discovered that require entry into more than one Condition at a time within a single LC0 (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in -
multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition. Once a Condition has been entered. subsequent trains, subsystems components or variables expressed in the Condition.. discovered to be inoperable or not within limits, will nD1 result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. (continued) BRAIDWOOD - UNITS 1 & 2 1.3-1 Revision A e,- . , . - _ . , - , , -.--r y . - _ _
,_ _. . . . . . . - _ __ .&_ um ~. m.-..m_ . m ..a . _ m . _m.____2 _.. m m.
r 3 MM ' Completion Times 1.3 Completion Times [#f AI; 1 i DESCRIPTION However, when a subseauent train, subsystem, component, or (continued) variable expressed in the Condition is discovered to be ; inoperable or not within limits. the Completion Time (s) may 1 be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
- a. Must exist' concurrent with the .ficit inoperability:
and
- b. Must remain inoperable or not within limits after .the first inoperability is resolved.
The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:
- a. The stated Completion Time. as measured from the initial entry into the Condition. plus an additional 24 hours: or
- b. The stated Completion Time as measured from discovery i of the subsequent inoperability. l The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, i subsystem, component, or variable expressed in the l Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.
The above Completion Time extension does not ap)ly to a Completion Time with a modified " time zero." T11s modified
" time zero" may be expressed as a repetitive time (i .e. , "once per 8 hours." where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.
(continued) BRAIDWOOD - UNITS 1 & 2 1.G-2 Revision A .
Completion Times 1-Th Pye Q 1. 3 ' 1.3 Completion Times (continued) d #f M J
- EXAMPLES The following examples illustrate'the use of Completion Times with different types of Conditions and changing
, Conditions. I EXAMPLE 1.3-1 COMPLETION TIMES ACTIONS I i CONDITION REQUIRED ACTION COMPLETION TIME i B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours i met. Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered. The Required Actions of Condition B are to'be in MODE 3 ; within 6 hours AND in MODE 5 within 36 hours. A total of ' 6 hours is allowed for reaching MODE 3 and a total of 36 hours (not 42 hours) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours, the time allowed for reaching MODE 5 is the next 33 hours because the total time allowed for reaching MODE 5 is 36 hours. If Condition B is entered while in MODE 3. the time allowed for reaching MODE 5 is the next 36 hours. I l
)
(continued) BRAIDWOOD - UNITS 1 & 2 1.3-3 Revision A .
krue.g.T j qg Completion Times , Pqe_ h . 3 1.3 Completion Times 'T of xl > EXAMPLES EXAMPLE 1.3-2 DEFAULTED CONDITIONS / LCO 3.0.3 ENTR'Y /- (continued) COMPL ETION TIMES ACTIONS ! CONDITION REQUIRED ACTION COMPLETION TIME 1 A. One pum) A.1 Restore pump to 7 days inopera)le. OPERABLE status. B. Required B,.1 Be in MODE 3. 6 hours Action and associated .A_NQ
, . Completion Time not B.2 Be in MODE 5. 36 hours met.
i When a pump is declared inoperable. Condition A is entered. ! If the l 7 days. Condition pump is not B isrestored to OPERABLE also~ entered and the Completion status withinTime I clocks for~ Required Actions B.1 and B.2 start. If the
- inoperable pump is restored to OPERABLE status after Condition B is entered. Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
When a second pump is declared inoperable while the first pump is.still ino the second pump. LCO perable. 3.0.3 is Condition entered, since A is thenot re-entered ACTIONS do for not include a Condition for rare than one inoperable pump.
- The Completion Time clock for adition A does not stop after LCO 3.0.3 is. entered, but continues to be tracked from the time Condition A was initially entered.
- While in LC0 3.0.3. if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for
- Condition A has not expired. LCO 3.0.3 may be exited and i operation continued in accordance with Condition A.
i . l (continued) BRAIDWOOD-- UNITS 1 & 2' 1.3-4 Revision A . Y
'1Nsu.T f.44 Completion Times, 1.3
?qe 1.3 Completion Times >
- EXAMPLES EXAMPLE 1.3-2 (continued) #
While in LC0 3.0.3. if one of the inoperable pumps is 4 restored to OPERABLE status and the Com)letion Time for Condition A has expired. LCO 3.0.3 may ae exited and 4 operation continued in accordance with Condition B. The Completion Time ~for Condition B is tracked from the time the Condition A Completion Time expired. On restoring one of the pumps to OPERABLE status, the s ' Condition A Completion Time is not reset but continues'from - { the time the first pump was declared inoperable.. This Com]letion Time may be extended if the pump restored to
- OPEMBLE status was the first inoperable pump. A 24 hour extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for i > 7 days.
I (continued) BRAIDWOOD - UNITS 1 & 2 1.3-5 - Revision A ,
J ( 3
"# Completion Times 9
1.3 Completion Times d c,4 W j ' I EXAMPLES EXAMPLE 1.3-3 MULTIPLE FUNCTION COMPLETION TIMES ' (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i ~ A. One A.1 Restore - 7 days Function X Function X train train ~ to OPERABLE E - inoperable. ' status. 10 days from discovery of failure to meet the LC0 i B. dne B.1 Restore 72 hours I Function Y i Function Y train
- train to OPERABLE M inoperable. status.
10 days from discovery of failure to meet
- the LCO 3
i C. One C.1 Restore 72. hours Function X Function X train
- train to OPERABLE i
inoperable. status, i M gg One C.2 Restore 72 hours
; Function Y Function Y train train to OPERABLE i'
. inoperable, status.
3 1 . (continued) i BRAIDWOOD - UNITS 1 & 2 1.3-6 Revision A 4 .
- . = . . - .
- Completion Times 1-4 & 1.3' fhy d. '
1.3 Completion Times _ (IO #f 21;
' ~
EXAMPLES EXAMPLE 1.3-3 (continued) When one Function X train and one Function Y train are inoperable. Condition A and Condition B are concurrently . applicable. The Com)letion Times for Condition A and I Condition B are tracted separately for each train starting ' from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e.. the time the I situation described in Condition C was discovered). l If Required Action C.2 is completed within the specified l Completion Time. Conditions B and C are exited. If the l Completion Time for' Required Action A.1 has not expired, operation may continue in accordance with Condition A. The l remaining Completion Time in Condition A'is measured from the time the affected train was declared inoperable (i.e.. , . initial entry into Condition A). The Completion Times of Conditions A and'B are modified by a logical connector with a separate 10 day Completion Time measured from the time it was discovered the LC0 was not met. In this example, without the separate Completion Time, it would be aossible to alternate between Conditions A. B. and C in suc1 a manner that operation could continue i indefinitely without ever restoring systems to meet the LCO. 3 The separate Completion Time modified by the phrase "from discovery of failure to meet the LC0" is designed to 3revent e indefinite continued operation while not meeting the CO. This Completion Time allows for an exception to the normal
" time zero" for beginning the Completion Time " clock". In this instance, the Completion Time " time zero" is specified as commencing at the time the LC0 was initially not met, instead of at the time the associated Condition was entered.
(continued) . BRAIDWOOD - UNITS 1 & 2 1.3-7 Revision A ,
r 3 MC# Completion Times e 14+ 1. 3 ' i Qe. !_ 1.3 Completion Times d P4 % l l EXAMPLES EXAMPLE 1.3-4 MULTIPLE FUNCTION COMPLETION TIMES (continued) e ACTIONS i CONDITION ~ REQUIRED ACTION COMPLETION TIME i )i A. One or more A.1 Restore valve (s) 4 hours valves to OPERABLE
- j. .
inoperable, status. l' I.
- B. Required B.1 Be in MODE 3. 6 hours Action and 4
associated e@ t . Completion i Time not B.2 Be in MODE 4. 12 hours met. l-A single Completion Time is used for any number of valves ino wrable at the same time. The Completion Time associated
- witi Condition A is based on the initial entry into
} Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable. while Condition A is . still in effect does not trigger the tracking of separate
. Completion Times.
1-Once"one of the valves has been restored to OPERABLE status. . 4 the Condition A Completion Time is not reset. but c6ntinues i ! from the time' the first valve was declared inoperable. The 1 Completion Time may be extended if the valve restored to ' j OPERABLE status was the first inoperable valve. The . Condition A Completion Time may be extended for up to 4 hours provided this does not result in any subsequent valve being inoperable for >'4 hours. i
- If the Completion Time of 4 hours (plus the extension)
L expires while one or more valves are still inoperable.. a Condition B is entered. y i (continued) i l' BRAIDWOOD - UNITS 1 & 2 1.3-8 Revision A .
r 3 MN Completion Times 1-TA- 1.3 fa34-1.3 Completion Times (I53 (Edl ) EXAMPLES EXAMPLE 1.3-5 SEPARATE ENTRY CONDITION (continued) ACTIONS NOTE - Separate Condition entry is allowed for each inoperable valve. d CONDITION REQUIRED AC' TION ' COMPLETION TIME ~ A. One or more A.1 Restore valve to 4 hours i valves OPERABLE -status, inoperable. 1 B. Required B.1 Be in'HODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours met. The Note above the ACTIONS Table is a method of modifying ' how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table. The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable. 4 Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable. Condition A is entered for each valve and separate Completion Times start and are tracked for each valve. (continued) BRAIDWOOD - UNITS 1 & 2 1.3-9 Revision A
Completion Ti , Pqt 1.'3 Completion Times 84% EXAMPLES EXAMPLE 1:3-5 (continued) If the Completion Time associated with a valve in Condition A expires. Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire. Condition B is entered separately for each valve and separate Completion Times start and'are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status. Condition B is exited for that valve. Since the Note in this exemple allows multiple Condition ' entry and tracking of separate Completion Times. Completion Time extensions do not apply. EXAMPLE 1.3-6 MULTIPLE ACTLONS WITHIN A CONDITION / COMPLETION T ME EXTENSIONS ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. . One channel A.1 Perform On'ce per inoperable. SR 3.x.x.x. 8 hours A.2 Reduce THERMAL 8 hours POWER to 5 50% RTP. B. Required B.1 Be in MODE 3. 6 hours Action and associated . Completion Time not , met. 4
-(continued)
BRAIDWOOD - UNITS 1 & 2 1.3-10 Revision A .
.-CN +ERT :
f_ pg CompletionTimeg, er. 1.3 Completion Times N J l l EXAMPLES EXAMPLE 1.3-6 (continued) ) Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" l Completion Time, which qualifies for the 25% extension, per i SR 3.0.2 to each performance after the initial performance. ; The initial 8 hour interval of Required Action A.1 begins l when Condition A is entered and the initial performance of 1
- ' Required Action A.1 must be complete within the first 8 hour interval. If Required Action A.1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2). Condition B is entered.
If Required Action A.2 is followed and the Completion Time of 8 hours is not met. Condition B is entered. ! If after . entry into Condition B. Required Action A.1 or A.2-is met. Condition B is exited and operation may then continue in Condition A. . 4 i 1 (continued) BRAIDWOOD - UNITS 1 & 2 1.3-11 Revision A
l'fA % e.f jg Completion T1
. \
Y l 1.3 Completion Times 8 UJ ! 1 EXAMPLES EXAMPLE 1.3-7 MULTIPLE ACT:'ONS W: THIN A CONDITION / (continued) COMPLETION TLME EX"ENSIONS l 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour subsystem subsystem inoperable. isolated. AND Once per 8 hours thereafter M l A.2 Restore subsystem 72 h'ours { to OPERABLE status. J B. Required B.1 Be in MODE 3. f hours Action and associated M Completion Time not B.2 Be in MODE 5. 36 hours
. met.
Required Action A.1 has two Completion Times. The 1 hour Completion Time begins at the time the Condition is-entered and each "Once 3er 8 hours thereafter" interval begins upon performance of Required Action A.1. (continued) BRAIDWOOD - UNITS 1 & 2~ 1.3-12 Revision A r e
r 3 M EET Completion Times 1-8A - 1. 3 ' fa.$g i 1.3 Completion Times qM 2lj EXAMPLES EXAMPLE 1~.3-7 (continued) I If after Condition A is entered. Required Action A.11s not met within either the initial 1 hour or any subsequent 8 hour interval from the previous performance (plus-the extension allowed by SR 3.0.2). Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from.the time ; Condition A was initially entered. If Required Action A.1 ' is met after Condition B is entered. Condition B is exited and operation may continue in accordance with Condition A. i provided the Completion Time for Required Action A.2 has not '
. expired. -
4 IMMEDIATE When "Immediately" is used as a-Completion Time, the i COMPLETION TIME Required Action should be pursued without delay hnd in a controlled manner. i l i BRAIDWOOD - UNITS 1 & 2 1.3-13 Revision A
Frequency g#6EFf3 1.4 ' I-4h 1.0 USE AND APPLICATION b#)#- 1.4 Frequency k !~/ af.2.l> PURPOSE The purpose of this section is to define the proper use and
. application of Frequency requirements.
DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance'must be met in order to meet the associated Limiting Condition for Operation (LCO). An
' understanding of the correct applicat.;n of the yacified Frequency is necessary for compliance with the SF., "'
The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements. Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LC0 is within its Applicability. represent potential SR 3.0.4 conflicts. To avoid these conflicts. the SR (i.e., the Surveillance or the Frequency) is stated such that it is only " required" when it can be and should be performed. With an SR satisfied. SR 3.0.4 imposes no restriction. EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LC0 (LC0 not shown) is MODES 1. 2. and 3. (continued) . RRAIDWOOD - UNITS 1 & 2 1.4-1 Revision A ,
r W M '3 ~ Frequency l-fA 1. 4 ' Pye 1.4 Frequency [# J EXAMPLES EXAMPLE 1.4-1 SINGLE FREQUENCY ' (continued) SURVEILLANCE REQUIREMENTS ; 1 SURVEILLANCE FRE0VENCY - Perform CHANNEL CHECK. 12 hours !
^
Exam 31e 1.4-1 contains the type of SR most often encountered i in t1e Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. 1
- Performance of the Surveillance initiates the subsequent l interval. Although the Frequency is stated as 12 hours an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not. required to be met per SR 3.0.1 (such as when the ecuipment is inoperable, a variable is outside specifiec limits, or the unit is outside the Applicability of the LCO). If the~1nterval specified by SR 3.0.2 is. exceeded while the un.it is in a MODE or other
- specified condition in the Applicability of the LCO, and the 1
performance of the Surveillance is not otherwise modified (refer to Example 1.4.-3). then SR 3.0.3 becomes applicable. If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a ~ MODE or other specified condition in 4 the Applicability of the LC0 for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the t MODE' or other specified condition. Failure to do so would result in a violation of SR 3.0.4. 7 l (continued) BRAIDWOOD - UNITS 1 & 2 1.4-2 Revision A , i
i [ Freque], g Pa.y i - 1.4 Frequency A N# > ' ! EXAMPLES' EXAMPLE 1.4-2 MULTIPLE FREQUENCIES 3 (continued) j SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY ! Verify flow is within limits. Once within i 12 hours after ! = 25% RTP ), AND a
- 24 hours
- thereafter i
1
- Example 1.4-2 has' two Frecuencies. The first is a one time i performance Frequency, anc the second is of the type shown
- - in Example 1.4-1. The logical connector." M " indicates that both Frequency requirements must be met. Each time
- reactor power is increased from a power level < 25% RTP to
= 25% RTP. the Surveillance must be performed within 12 hours.
The use of "once" indicates a single performance will i satisfy the specified Frequency (assuming no other Frequencies are connected by "M"). . This type of Frequency j does not qualify for the extension allowed by SR 3.0.2. 1 "Thereafter" indicates future performances must be established per SR 3.0.2. but.only after a specified
- condition is first ' met- (i.e. . the "once" performance in this l' example). If reactor power decreases to < 25% RTP. the measurement of both intervals stops. New intervals start
} upon reactor power reaching 25% RTP. 1 i . 4 )- - (continued) J ! BRAIDWOOD - UNITS 1 & 2 1 4-3 Revision A * ' 4
,m - - c -- - e, -
N Frequency' l- h 1,4 Pop
- 1.4 Frequency 8O>
EXAMPLES EXAMPLE 1.4-3 ' FREQUENCY BASED ON SPECIFIED CONDITION i (continued) l i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i j NOTE Not required to be performed until l 12 hours after = 25% RTP. l i Perform channel adjustment. 7 days i The interval continues, whether or not the un.it operation is i
< 25% RTP between performances.
As the Note modifies the required oerformance of the Surveillance it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP. this Note. allows 12 hours after i power reaches = 25% RTP to perform the Surveillance. The Surveillance is still considered to be 3erformed within the "specified Frequency." .Therefore. if t1e Surveillance was not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing H00ES. even with the 7 day Frequency not met, provided operation does not exceed 12 hours with power a 25% RTP. Once the unit reaches 25% RTP. 12 hours.would be allowed for completing the Surveillance. If the Surveillance was not performed within this 12 hour interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply. 4 (continued) BRAIDWOOD - UNITS 1 & 2 1.4-4 Revision A
l~ l ' i ffM+ SAT ^ , l-4A- *9"*h-f* P ' 1.4 Frequency 8 'MJ EXAMPLES EXAMPLE 1.4-4 FREOUENCY BASED ON SPECIFIED CONDITI0'N i (continued) SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I l NOTE Only required to be performed in MODE 1. l Perform complete cycle of the valve. 7 days 1 l L l The interval continues, whether or not the unit operation is ! in MODE 1, 2, or 3 (the assumed Applicability of the l associated LCO) between performances. ) As the Note modifies the required oerformance of the I Surveillance, the note is construed to be part of the L "specified Frequency."' Should the 7 day interval be 1 exceeded while operation is not in MODE 1, this Note allows l entry into and oxration in MODES 2 and 3 to perform the i Surveillance. T1e Surveillance is still considered to be ! performed within the "specified Frequency" if completed prior to MODE 1. Therefore, if the Surveillance was not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1. it would not constitute a failure of the SR or failure to meet the LCO. ~ Also,. no violation of SR 3.0.4 occurs when changing MODES. even with the 7 day Frequency not met, i provided operation' does not result in entry into MODE 1. l Once the unit reaches MODE 1, the requirement for the ! Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance was not performed upon entering MODE 1, there would then be a failure to >erform a Surveillance within the specified Frequency, and tie provisions of SR 3.0.3 would apply (as well as having had a violation of SR 3.0.4). BRAIDWOOD - UNITS 1 & 2 - 1.4-5 Revision A . i
S L 2. 0 j . _ IS Lil 2.0 SAFETY LIMITS 0.... - o , , . . . . .,.m . . . , . . m , , , ,,3 i. SLs 1 REACTOR CORE $h) oom0 { rQMe combination [of THERMAL POWER,(Reak C..r..a SA- (des))
- pressurizer pressure, and th c _ m
- :: loop mastume4empe_rature (A shall not exceed the GTMTF:344WD in Q 4: 22 2 z.
] ure for := lees ege, a ;.r,,
g,y,,, l C""L"."2IU 6 MODES I and 2) i 1 (72 (ACsL T IUN.g Veb b o nO-@ -
/("IfCL2.2.1 -+ere c.onitlin m vioided M e: et nhfg 3
- 5L 4
I M'I
/Ehenevgr the poityt defined A~y the con)bination of the highfst operating loop average temperat6re and TliCRMAL POWER has excedded the 46propriatekressuri]zer) i 1 $ressure line,}be in HOT _ STANDBY within I hour, f.d c1 rith th$ ,
7 = t -- : t;_ :f _ CHUl eW.; . ; .O.- f REACTORCOOLANTSYSTEMPRESSURE@ 4,76e Reactor Coolant System pressure shall not' exceed 2735 psig, PLIta=ILI'hnMODES 1, 2, 3, 4, and $h g[P (z.2 2. If SL 2.1. 2 ic vacilcrl-eck hh f1 MODES a_n.4 3 A
^
f :::1- ::: arrt r casunt sy r' - rr r r x "- _
-----d-d 27s ;; m be
! in HOT STANDBY with the Reactor Coolant System pressure within this limit i within 1 hour, e r e:: ::: n= :- - -" - ger tfi e:'ieaA >_ _o i SL a2.2 2 A j L1 MODES 3. 4 and 5") ! emenever -dr r.caciar :::::: r= : = :r-rr ve--d-d 'm reduce the Reactor Coolant System pressure to within this limit within se a3 l i 5 minutes, '-- ----- ris 12- r:: tr:::: : :f 5:::: :r= *r v n t sLAs@ 4 j 'Applicab}4toUnitIarIdUnit2unt completion cycle 5. 3
** Applicable to Unit 1/nd Unit 2 st tina with cv e 6.
J t 4 1 4 1 - i 1 Unit 1 - Amendment-No. 56 ] . . . . . . . - ,,,, - , . e 9.1 tinit ? - a-ead-na Na et
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100 ---120 i 4 POWDt (PERCD(T) 1
; FIGURE 2.1-1 i
j REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION 1 l Applicable to Unit I and Unit 2 until completion of cycle 5 I, p_p Unit 1 - Amendment No. 56 I BRAIDWOOD - UNITS 1 8 7 .~ . e . n . ..i_ ... ... cc
J 1 Gl AO 1 4 I . 1 ) 1 I 680 . .. i . ..
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1 BRAIDWOOD - UNITS 1 & 2 7 'h Unit
..e. ,
1 - Amendment ._.. No. 56 ) . . . . . ..
S t. 1.0 Lc0 3 3 t SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2 LIMITING SAFETY SYSTEM SETTINGS, N REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS i 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall \ be set consistent within the Trip Setpoint values shown in Table 2.2-1. APPLICABILITY: As shown for each channel in Table 3.3-1. , ACTION: l
- I i
- a. With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trjp Setpoint value.
- b. With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
l f hMrtmJ A. Sec b .I3.1. 3se DOC b 5=4 31.J i j i i 2 '3 Amendment No. 42 nonnunnn - t! NITS 1 & 2
Lco 3.3. \ soe&n 2 0 3.3. 8 Reea.% Tr.9 sya +en ~3'n,47sen. % .
= L:Y LIM 115 A= Lini 1NG-sArt:Y 5Ysitn stillm,r j Z. Z LII'I"?C 5AF""' 'Y", TIM SEIGGij LA4 l. A, RDCTOR_ TRIP SYSTEM INSTRUMENTATION SEfPOINTS 2.2.1 The Reac rip System Instrumentation and Interlock Set s shall be set consistent wit e Trip Setpoint values shown in - e 2.2-1.
APPLICABILITY: As shown for each c 1 in Tabl . -1. ACTION:
- a. With a Rea rip System Instrumentation or Inter Setpoint less conser than the value shown in the Trip Setpoint c n but more c ne ative than the value shown in the Allowable Value colu f able 2.2-1, adjust the Setpoint consistent with the Trip Setpoin value.
Cond A )f. With the Reactor Trip System Instrumentation cr ;mer;xa Setpoint 'g less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel. inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value. __, As 2-3 Amendment No. 42 BRAIDWOOD - UNITS 1 & 2 ,
~
$ TABLE 2.2-1 U 6 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 8 TRIP SETPOINT ALLOWABLE VALUE FUNCTIONAL UNIT h Manual Reactor Trip N.A. N.A. y 1.
- 2. Power Range, sectron Flux
- a. High Selpoint 1109% of'RTP* 1111.36% of RTP*
m
- b. Low Setpoint , 125% of RTP* 127.36% of RTP*
- 3. Power Range, Neutron Flux, <5% of RTP* with <6.3% of RTP* with i High Positive Rate i time constant i time constant 12 seconds , 12 seconds
- 4. Power Range, Neutron Flux, <5% of RTP* with <6.3% of RTP* with High Negative Rate i time constant i time constant m
4 12 seconds , 12 seconds l
- 5. Intermediate Range, 125% of RTP* 131.5% of RTP*
Neutron Flux ,
- 6. Sour'ce Range, Neutron Flux . 1105 cps $1.42 x 105 cps j Overtemperature AT See Note 1 See Note 2 .
7. Overpower AT See Note 3 See Note 4 !
- 8. ,
- 9. Pressurizer Pressure-Low 11885 psig 11869 psig ili Pressurizer Pressure-High $2385 psig $2393 psig g 10. i a
!+
- 11. Pressurizer Water Level-High '$92% of instrument span 193.5% of instrument span rm 8e" z
I
~
Wo w 1 _ O (" RIP = RAIED THERMAL POWER , dressed In 6e,63,, 3 l s ee, c o c c ~ se a . , 3Q.2 l
t t a, . 3.3.I-l g TABLE 2.2 1
$ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS :
8 ' l t g FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE
- 1. Manual Reactor Trip .A. N.A.
]
- 2. Power Range, Neutron Flux ,
- a. High Setpoint m 5 9% of RTP* $111.36% of RTP*
- b. Low Setpoint , 12 of RTP* $27.36% of RTP*
h,E Power Range, Neutron Flux, <5% f RTP* w th <6.3% of RTP* with t High Positive Rate i ti const t i time constant , 12 se onds 12 seconds ~8.b X Power liange, Neutron Flux, <5% of TP with <6.3% of RTP* with m High Negative Rate i time o tant i time constant : A 12 seco 12 seconds.i ,
'l .fr. Intermediate Range, 125% of P* $31.5% of kir*
Neutron Flux !
.(.6. Sourc~e Range, Neutron Flux ,
$105 s $1.42 x 105 cps !
6E Overtemperat'ure AT See te 1 See Note 2 ; i 7.&t Overpower AT See ote 3 See Note 4 l T.aK Pressurizer Pressure-Low 11 85 psig 11869 psig g
- b. Pressurizer Pressure-High 385 psig $2393 psig r- lb g T.H. Pressurizer Water Level-High~ . <93. 5% Ie"-+ net-cument j @C$ ;
2 )d92%ofinstrumen span ge (Al l by t A1 O 0 " RIP = RATED THERMAL POWER l
isou c . < .onu nuea s .
,. - - 7.
REACTOR TRIP SYSTEN INsin . dTATION TRIP SETPOINTS I sp .- FUNCTIONAL ~ UNIT
- IRIP SETPOINT ALLhWA8LEVALUE
- 12. Reactor Coolant Flow-Low 290% of loop mint- 189.3% of loop alpi-num measured flow num measured flow
- 13. Steam Generator Water Level Low-Low
- a. Unit 1 233.0% of narrow 231.0% of narrow range instrument range instrument span span
- b. Unit 2 217% (Cycle 3); 216.35 (Cycle 3);
236.3% (Cycle 4 134.8% (Cycle'4 and and after) of after) of narrow narrow range range instrument , instrument span span '
- 14. Undervoltage - Reactor 25268 volts - 14'920 volts -
Coolant Pumps each bus each bus ,
- 15. Underfrequency - Reactor 257.0 Hz 256.08 Hz toolant Pumps i
- 16. Turbine Trip
- a. Emergency Trip Header 21000 ps19 1815 psig
' Pressure -
- b. Turbine Throttle Valve 21% open 21% open Closure '
- 17. Safety injection Input N.A. N.A. :
from ESF
- 18. Reactor Coolant Pdep N.A. N.A. RM Breaker. Position Trip -
oe , w N ,
- Minimum measured flow - 97.600 gpm** (92,850 gpm)* .
L 'o -
**Appilcable to Unit 1 and Unit 2 untti completion of cycle 5. -
( #Appilcable to Unit I and Unit 2 starting with cycle 6. i i UNIT 1 - AMENDMENT NO. 56 AAl ned ,sa BRAIDWOOD - UNITS 1 & 2 2-5, UNIT 2 - AMENDMENT NO. 55 ,
%R 3.3.1. See, t Doc 4 h :,3.3. i
Jnutt A cus..s. - ) Lt.ont inued) REACTOR TRIP SYSTEM INS.ddMENTATION TRIP SETPOINTS FUNCTIONAL UNIT lp .. hRIPSETPolNT ALLOWA8LE VALUE
/0 J M Reactor Coolant Flow-low ;
2 of loop mini measured flow;- 189.3% 2f h:,. :::tg;iD (mMBHRe 36 id IhrF ; 141. 45. Steam Generator Water Level low-Low
- a. Unit i ,
233. of narr ' rang instruse t 231.0%f5f-;;;] tr: ;; et ;;.;,t span 14 san i
- b. Unit 2 217% ( ycle 3 ; '
236.3% (Cyc1 4 (;.n
'234.5%. = pl'C;:!:'
, '. 3)i Q:: '
and aft r) o ' eft -).e ?.:: ;;' r narrow ng gange-las4emment instrume t pan tasan i i::t -M'. Undervoltage - Reactor Coolant Pumps 15268 vol - 24920 volts - each bus , .each bus 13 4E Underfrequency - Reactor ; Coolant Pumps 257.0 Hz ~ 256.08 Hz
/f N Turbine Trip ,
- s. Emergency Trip Header Pressure 21000 psig . 1815 pstg
- b. Turbine Throttle Valve '
Closure 21% pen AIX open
/6 F. Safety In.jection input N. . y from ESF M.A.
l 11 -HI. Reactor Coolant Pdep .A. c0 N.A. Breaker. Position Trip
'4 .
f .m - g,; -- - > ~ -- - 4/97,6 ppitcab1pdo Unit g and Ur1 2 unt completto(of eyJc 4f 5. / plic@fe to Urdf I andXnit 2 s rtine witVcycle V pm' ^^^ Z^ - ?I h * [ !, l 2-5 UNIT 1 - AMENDMENT NO. 56 BRAIDWOOD - UNITS 1_& 2' , UNIT'2 - AMENDMENT NO. 55 ' __-____-____________________-_-____________--______--_____-_______________-._____-___________-.--_J
._. - -..-. -.-..- .- . - ~ . - _ - - - . - . ~ . . . . - . . . . - . - . - - . . - . - . . . . - - - - - .
- 1 i
TABLE 2.2-1 (Continued) ( REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS I ALLOWABLE VALUE TRIP SETPOINT - FUNCTIONAL UNIT l Reactor Trip System ka 19. Interlocks J - 11 x 10 18 amp 16 x 10 11 amp
- a. Intermediate Range ,
o - Neutron Flux, P-6
- b. Low Power Reactor Trips ;
Block, P-7
$10% of RTP* 17.9% to $12.1% of RTP*
- 1) P-10 input i
<10% RTP* Turbine <12.1% RTP* Turbine !
- 2) P-13 input .
Tapulse Pressure Tapulse Pressure i Equivalent Equivalent
't $30% of RTP* 132.1% of RTP*
- Power Range Neutron c.
Flux, P-8
$10% of RTP* 17.9% to $12.1% of RTP* ;
- d. Power Range Neutron '
Flux, P-10 <12.1% RTP* Turbine
<10% RTP* Turbine .
- e. Turbine Impulse Chamber Impulse Pressure Impulse Pressure ' '
Pressure, P-13 Equivalent Equivalent i N.A. N.A.
- 20. Reactor. Trip Breakers '
N.A. N.A. Automatic Trip and Interlock g 21. Logic g N.A. N.A. E Reactor Trip Bypass Breakers
- 22. '
\ g sn -
g 0 'g' _l W 5(*RTP=RATEDTHERMALPOWER I
~
j ru AJare a,,J L sg,, 3,3, , , See Doc. b Sechb 3.3. .
. i k
. _ ._ _ - _ _ .- _ _ _ _ ._ . ~ .-- _
3.3.l-l TABLE 4-44 (Continued) g ,~ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E
' / ALLOWABLE VALUE FUNCTIONAL UNIT _ (TRIPSETPOINT lii Reactor Trip System q 19 m terlocks ,
ea
** te Range
> x 10 10 amp >6 x amp .
- a. Interm - -
N Neutron Flu , -6 ,
- b. Low Power Reactor Hps Block, P-7
- 1) P-10 input of RTP* >7.9% to <12.1% of RTP*
- 2) P-13 input
<10% TP* rhine <12.1% RTP* Turbine ;
Impuls Pr ssure Impulse Pressure uiva en Equivalent y
- Power Range Neutron -<3 o P* -<32.1% of RTP*
- c. '
Flux, P-8
- d. Power Range Neut (10%ofdP* >7.9% to (12.1% of RTP*
Flux, P-10 l e Impulse Chamber <10% TP* Turbine <12.1% RT bine e .' T Impu e Pr(ssure Impulse Pressure ressure, P-13 Equivalent Equi alent \ ups N. . N.A. E Reactor Trip Breakers Automatic Trip and Interlock N A. N.A. g "_2r. g Logic Reactor Trip Bypass Breakers .A; N.A. R 8
$ .20. ?w 5 .
hie ; 5 *RTP = RATED THERMAL POWER , .
~
TABLE 2.2- anued) TABLE N01ATIONS r1IOTE1: OVERTEMPERATURE AT 1+t 1S) 1 4 1 A T ((1+t S) ( 1+t oS) s A(1+t 2 3 1 2 T [K (1+t 3S)S)-K [T( 1+t S) -T'] +K (P-PI) -f ( AI)] 3 1 Where: AT = Measured AT by.RTD Instrumentation . l 1+t i s . 1+t 2 S
- Lead-lag compensator on measured AT, .
r,, r, - Time constants utilized in lead-lag compensator for AT, r, - 8 s, r, - 3 s , 1 1+t 3 S - Lag compensator ori measured AT, r3 - Time constants utilized in the lag compensator for AT,3 r - O s*, s2s," l AT, - Indicated AT at RATED THERMAL POWER, [ K, - 1.164,' l.325" m K, - 0.0265/*F,* 0.0297/*F" 1 + t.S 1+t s s The function generated by the lead-lag compensator for T , dynamic compensation, r,, r3
- Time constants utilized in the lead-lag compensator for T , f4 - 33 s, ,
is-4s, - T - Average temperature *F,
-e .
I I
' Applicable to Unit I and Unit 2 untti completion of cycle 5.
(ApplicabletoUnitIandUnit2startingwithcycle6. , y pg 9h
~
AbmdL ',n Sennn 2,3,I ~ l See poc -Ge %% 3,3 BRAIDWOOD - UNITS 1 & 2 2-7 AMENOMENT NO. 66 t
TABLE 4 'it tnued) 33.1-l TABLE NOTATIO_NS NOTE 1: OVERTEMPERATURE AT - 1 1 1 A T(1+t (1+t 2S) S) ( 1+t S)o s A 2T(1+t 3 i [K S)3
-K (1+t*S) [T( 1+t,S) -T']1 +r (P-P') -f (AI)]
3 Where: AT - Measured AT by RTD Instrumentation. l {1h- g _ Lea 3,739 compe1Fil
-9
[ r , , r, - Time constants utilized in lead-lag compensator for AT, r, - 8 s, 77- 3 s, Ih ~
.. 4 229 1 + tp L a g - c ompe'llratiE_e[n- me as Q l i
s
- Time constants utilized in the lag compensator for AT, 3r - s2s, l h AT, - Indicated AT at RATED THERMAL POWER, K, .154 0 1.32 A7 x .- (0.;;;;; T C 0.0297/*F l 1+t s S
$_hifunctiongeneratedby_thelead-lagaompensator-fc
- T q dynamic romeensation, - - - - _ _ ; i t,r3 -
Time constants utilized in the lead-lag compensator for T,,, r - 33 s, is - 4 s,
- T - Average temperature, "F, '
4
*Appitcab1: t: "at t 1 - and Unit-2-until es;+1et4:n f cycle 5. 4 Eb
(" app!!ce!e te " nit ! :nd " t t 2 :tartina-with-cycle-6. -
~ [, 9 gW BRAIDWOOD - UNITS 1 & 2 2-7 AMENDMENT NO. 66
-i TABLE 2.2-1 (Continued) Ud '"s M'aw 8,3,l d See W- Ge %n 5,3 TABLE NOTATIONS (Continued)
[ NOTE 1: (Continued) ] 1 1+t s - Lag compensator on measured T ,, r, - Time constant utilized in the measured T lag compensator, r, - O s,' s 2s," T' s 588.4*F (Nominal T, at RATED' THERMAL POWER), K3 - 0.00134*, 0.00181** P - Pressurizer pressure, psig, 4 P' - 2235 psig (Nominal RCS operating pressure), , S - Laplacetransformoperator,si, and f;(AI) is a function of the indicated difference between top and bottom detectors of the ' power-range neutron ton chambers; wlth gains to be selected based on measured instrument response l during plant STARTUP tests such tha t: ; (1) for q - are percent i RATED,THEb- l POWER between in the top and -32%*, bottom-24%** halves ofand +13%', the core +10%** respect 1velf, an f'(AI) - 0, where q* ad q,
- total THERMAL POWER in percent of RATED THERMAL POWER; I (11) for each percent that the magn !
j automatically reduced by 1.74%jtude , 4.11% o of,q, f 1ts value ~at RATED THERMAL POWER.- q, exceeds (111) for automatically each percent that reduced bythe 1.67% magnjtude, 3.35% of,,q, o f its valde at RATED THERMAL POWER.- q, exceeds -32 {$ l tA P NOTE 2: The channel's,, maximum Trip. Setpoint shall not exceed its computed Trip Setpoint by more than 61 b 3.71% , 1.33% of AT span. - L ; i . ' Applicable to Unit I and Unit 2 until completion.of cycle 5. ( ** Applicable to Unit I and Unit 2 starting with cycle 6.
) '
. BRAIDWOOD - UNITS I & 2 2-8 ,
AMENDMENT NO. 66
. 3.3. l-l TABLE W (Continued 1 .
TABLE NOTATIONS (Continued)
- NOTE 1: (Continued) 1 *5
) .
6
- r. -
Time constant uttitzed in the measured T, lag compensator, t = $ 2s,- I , T' s 588.4*F (P inal T ,at RATED THERMAL POWER), K3 = fe.GG134 .0 M0
-l P - Pr'essurizer pressure, psig, 'e.
P' - 2235 psig (Nominal RCS operating pressure), S - Laplace transform operator, s, and f;(AI) is a function of the indicated difference between top and bottom detectors of the N l power-range neutron ton chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that: 4 , (1) for q - q, between -32W -24 and +1 f AI). - 0, where q and RATED, THERMAL POWER in the top and bottom halves of,(the core respectively,g are percent and q, + g is total THERMAL POWER-in percent of. RATED THERMAL. POWER; . (11) - g exceeds +10% the AT Trip Setpoint shall be for each percent automatically reducedthat the by maanitude G-MS 1 4.1of, q,o f its value at RATE THERMAL POWER. ,
, i
'(111) for each percent that the maan ude of - g exceeds -24 the AT trip setpoint shall be !
automat 11y reduced by(h475-) .3 ,o f its value at RATED TiiERMAL POWER. " 1 NOTE 2- Th annel' aximum Trip setpoint s all'not exceed its computed Trip Setpoint by more than ; 1.33 of AT span. 3 l Ro ' 4pplicable to unit 1 :ad Unit 2 satti ce +1etien of :r&-fr- ta
** App 110:b1: i U-it 1 :nd Unit 2 5tEitin9 With CJCi d 7b -
p-BRAIDWOOD - UNITS 1 & 2 2-8 , AMENDMENT NO. 66
TA8tE 2.2-1 (Continued) sa N E I
.TA8LE NOTATIONS (Continued)
O 7 NOTE 3: DVERPOWER AT .
)
g (1 + t is) 3 . ( t,S ( 1 1 ) ~
~ #8 IAI)I y o Ie- s 1 + t,5 1 + r.5 ) T - 4 [T(1 + tes AT (1 + T3 5) Il + T3 5) I A o=
" Mhere: AT = As defined in Note 1, 1 + tsS .
= As defined in Note 1 1 + t:5 i 13, is = As defined in Note 1
- I = As defined in Note 1
- u. 1 + Yss e
Ts
= As defined in Note l',
= As defined in Note 1, ;
AT,
. K.
= 1.072
= 0.02/*F for increasing average temperature and 0 for decreasing average-Ks temperature.
t t,$ :
= The function generated by the rate-lag compensator for T8 dynamic ;
compensation, [ 1 + t,5 t, = Time constants utt11 red in the rate-lag compensator for T,,,, t, = 10 s. 1 = As defined in Note 1 , 1+rse , i t, = As defined in Note 1, M ew7iA Seeb 3.3.t. See Doc & S.gu 3.3. i
3.3.1- 1 . e TABLE fr3=1 (Continued) E i TABLE NOTATIONS (Continued) O 7 NOTE : DVERPOWER AT (1 + t s) ( t,5 ) 1 ) 3 i 1 , ( t 1+r5e ) T - K, [T(1 + te s
- T9 - f (a!)]
y AT (1 + 1:5) Il + t 35) $ AT,(M4 - Ks 1 + r,5 w e. Where: AT = As defined in Note 1, 1- + t S .
= As defined in Note 1, 1 + t:5 ti,13 = As defined in Note 1,
= As defined in Note 1,
] 1 ts5
= As defined in Note 1, ts AT, = As defined in Note 1 K4 = 1.072, Ks
= 0.02/*F for increasing average temperature and 0 for decreasing average temperature, tr$ dynamic
= The function generated by the rate-lag compensator for T,,,
1 + t,S compensation,
, t, = Time constants utilized in the rate-lag compensator for T,,,, t, = 10 s, I + tes
* ^* * ' " " ' O en [
As defined in Note 1,
, g, = -
{ f
TABLE 2.2-1 (Continued) TABLE NOTATIONS (Continued) NOTE 3: (Continued)
)
Ka - 0.00170/*F*, 0.00245/*F** for T > T" and K, = 0 for T s T", T - As defined in Note 1, T" - Indicated T a l InstrumentaUon,tsRATED THERMAL POWER (Calibration temperature for AT 588.4*F), S - As defined in Note 1, and f(AI) 2
- O for all A1.
N0TE 4: Thechannel's,,maximumTripSetpointshallnotexceeditscomputedTripSetpointbymorethanj 2.31% , 3.65% of AT span. l l T cnSb l h* rm a> +>
,lAppilcable to Unit I and Unit 2 untti completion of cycle 5. $
( Appitcable to Unit 1.and Unit 2 starting with cycle 6. - BRAIDWOOD - UNITS 1 & 2 2-10 AMEN 0 MENT NO. 66 ;
t
- 3. 3. l-l -
TABLE M -4 (Continued) . TABLENOThTIONS(Continued) NOTEf:(Continued) K, - 5.GGi?Gl'T 0.00245/*ffor T > T" and K - O for T s T". T - As defined Note 1, T" - Indicated T a instrumentaITon,ts RATED 588.4*F),THERMAL POWER (Calibration temperature for AT S - As defined in Note 1, and i f,(at) - 0 for all AI. A, NOTE : Th c annel' aximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than _, 3.65 of AT span. l e t t t- (b
._ y a a >
h
,,'Applic;tle is Unit ; end Unit 2 stertisii with cycle G.Applic;ble L to Unit I ;ad Unit 2 until :....yletica cf eyel:
.$5.s
. P o ;
BRAIDWOOD - UNITS I & 2 2-10 AMENDMENT NO. 66
CTS INSERT (S) SECTION 2.0 BASES , The Bases of the current Technical Specifications have been replaced in their entirety by Bases reflecting the . format and applicable content of.NUREG-1431 Bases and proposed Byron and Braidwood Technical Specifications. D b 0 5 4 O 6 4 e 0 9 Revision A .
LCO APpikubildy .$ O l - p/' L!"!T!"C C0""!T!05 70" OPEPJt?!O" AO SURVEIRANGE-REGMAEMENf%) i- , , 9 ,(APPLICA8ILITY L LIMITING CONDITION FOR OPERATION ltc v
,.4 i
j to 3.0.O] Compliance with the Limiting Conditions for Operation contained in theN l Ai tsucceeding specifications is required durira the OPERATIONAL MODES or other / i (conditions specified therein; emeop4-4he4Epon failure to meet the Limiting (Conditions for Doeration, the manneistad ACTION canuirements shall be met,, y ceacare a woe.m . ao .1 es Lco 3. . ': n .;n inn .;f th
.-s v.s 9-e mratien thala_exi w er en: -- m a nn -f l
A2 th: Lietting C: Mitt:: fr- ^a--etica eSeesee4eted AC-T49Ntequire nu are
=ct ==* u th' O. .,,. a M t M ' Sn:h. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, /mus.w/ l l ~kompletion of the ACTION reouirements is not required % alm=*~"e **cOf DN u3.o i e, j LLGC)3.0.l) When a Limiting Condition for Operation is not met, except as provided
- i_n the associated ACTION requirements, within 1 hour action shall be initiated 3
! to place the unit in a MODE in which the specification does not appi placing it, as applicable, in:
- a. At least HOT STAND 8Y within the next 6 hours :
r%
"N w 4 j
- b.
At least HOT SHUTDOWN within the following 6 hours, an] , L_3.0IC.J ! c. At least COLD SHUTDOWN within the i ubsecuent 24 hours.] t ! Where corrective measures are completed that permit operation under the ACTION D i requirements, the action may be taken in accordance with the.specified time limits l as measured from the time of failure to meet the Limiting Condition for Operation. ;
; Exceptions to these requirements are stated in the ' individual. specifications. 9 '
l l
@kThisspecificationisnotapplicableinMODE5or6.
14). Entry into an OPERATIONAL MODE or other specified condition shall no [ @ews w7 { 'be made when the conditions for the Limiting Conditions f Operation are not g {- j Aq met and the associated ACTION requires a shutdown if the are not met within
~
j specified time interval. Entry-into an OPERATIONAL MOD or specified conditio i may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. ! This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications. M Limiting Conditions for Operation including the associated ACTION p ir ments b 4 ly to each unit individually unless otherwise indicated"as follows.
- a. Whenever the
./
ing Conditions for Operation.-refers to systems. or components which ar red by both uni , e ACTION requirements will apply to both units ta y. Lh i
- b. Whenever the Limiting Cc3di ons ration applies to only one unit, this will b 11fied in the AP)t'! ILITY section of the specificat , nd
- c. W er certain portions of a specification contain ting param-eters, Setpoints, et.c. , which are different for each unit,'this will 4 be identified in parentheses, footnotes or body of the requiren hen s
.Y $F 0 3'O '
_ 3c BRAIDWOOD - UNITS 1 & 2 3/4 0-1 AMENDMENT NO. 38
l s CTS INSERT (S) SECTION 3.0 LC0 3.0 INSERT 3.0 1A (A ) 3 I LCOs shall be met during the MODES or other specified conditions in the ' Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7. l l l
; INSERT 3.0 1B (A2 )
~
Upon discovery of a failure to meet an LCO. the Required Actions of the associated Conditions shall be met, except as provided in LC0 3.0.5 and i LCO 3.0.6. If the LC0 is met or is no longer a arior to expiration of the i specified Completion Time (s), complhplicable tion of t1e Required Action (s) is not 4 required unless otherwise stated. , Revision A
CTS INSERT (S) l SECTION 3.0 ! LCO 3.0 INSERT 3.0 1C (A3 and L ) 3 l (A3 ) When an LC0 is not met and the associated ACTIONS are not met. an associated ACTION is not provided, or if directed by the associated ACTIONS. the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour to place the unit as applicable, in: . (L1 ) .
- a. MODE 3 within 7 hours;
- b. MODE 4 within 13 hours: and I
- c. MODE 5 within 37 hours.
l l Exceptions to this Specification are stated in the individual Specifications. i 1 (A3 ) l Where corrective measures are completed that permit operation in accordance with the LC0 or ACTIONS completion of the actions required by LC0 3.0.3 is-not required. LC0 3.0.3 is only applicable in MODES 1, 2, 3. and'4. l d Revision A
CTS INSERT (S) - SECTION 3.0 t
. . LC0 3.0 !
INSERT 3.0 1D ( A,) i When an LC0 is not met, entry into a MODE or.other specified condition in the ! Ap'plicability shall not be made except when the associated ACTIONS to be l entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This Specification shall { not prevent changes in MODES or other specified conditions in the . Applicability that are required to comply with ACTIONS. j Exceptions to this Specification are stated in the individual Specifications. I These exceptions = allow entry into MODES or other specified conditions in the l' Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time. INSERT 3.0 1E (La) Equi > ment removed from service or declared inoperable to c q ly with ACTIONS may Je returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY the OPERABILITY of other equipment or variables to be within limits. This is an exception to LC0 3.0.2 for the system returned to service under administrative control to perform the required testing to demonstrate OPERABILITY. I Revision A e
r 4 CTS INSERT (S)
- SECTION 3.0 -
4 l LC0 3.0 INSERT 3.0 1F (A3 ) When a supported system LC0 is not met solely.due to a support system LC0 not
, being met, the Conditions and Required Actions associated with this supported' i system are not required to be entered. Only the' support system LC0 ACTIONS '
i are required to be entered. This is an exception to LC0 3.0.2 for the supported system. In this event, an evaluation shall be performed'in l accordance with Specification 5.5.15, " Safety Function Determination Program i 2 (SFDP)." If a loss of safety function is determined to exist by this program, , the appropriate Conditions and Required Actions of the LC0 in which the loss of safety function exists are-required to be entered. ~ i When a support system's Required Action directs a supported system to be I i- - declared inoperable or directs entry into Conditions and Required Actions for i a supported system, the applicable Conditions and Required Actions shall be l ' entered in'accordance with LC0 3.0.2. l INSERT 3.0 1G (As) I Exception LCOs allow specified Technical Specification (TS) requirements to be changed to permit carformance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance
- ~ . with Exception LCOs is optional. When an Exception LC0 is desired to be met 1 4 . but'is not met the ACTIONS of the Exception LC0 shall be met. -When an l 1 Exception LC0 is not desired to be met, entry into a MODE or other specified ;
condition in the Applicability shall be made in accordance with the other j l applicable Specifications. - l l - i k-
- j. .
.L L
- j. .
1 L , Revision A i .- o . J-
i . . SR AppVedilh 3.o b em g od Wsels SS ) (APPLICABILITYl i SURVEILLANCE REQUIREMENTS ISR) l SR V .0 J ) Surveillance Requirements shall be met during the OPERATIONAL MODE D r other conditions specified for individual Limiting Conditions for 1 i - 47 %t w/ ' eration unless otherwise stated in an indivirinal surveillance Raouiremente- 35MT 3.o-2 A l Ar g,
@8MJEach Surve111ance nequirement shall be performed within th
- necified surveillance me-interval with interval a maximum / w, allowable extension
,o, ,, 9, w,g o .g, ,, ,g not to exc ,
f5R 3g.0.3) Failure to perform a Surveillance Requirement within the allowed 'sur- f ' ance interval, defined by Specification 4.0.2, shall constitute noncomp.11 M *W ince with the OPERABILITY recuirements for a Limiting Condition for Ooeration. hasar "he time limits of the ACTIO6 requirements are applicable at the time it is +2c . identified that a Surveillance Requirement has not been performed. The ACTIO requirements may be delayed for up to 24 hours to permit the completion of th
) l surveillance when the allowable outage time limits of the ACTION requirements hre less than 24 hours / Surveillance nequirements ao not nave to De performed) g fn inoperable equipment.J (s.,,a % gey ..,3,3 ,g 3, % ,,,,, %
6R V.O.Yintry into an OPERATIONAL MODE or other specified condition shall not a sotr ! de unless the Surveillance Requirement (s) associated with a Limiting Conditio tJ o ab) or Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to PERATIONAL MODES as recuired to comply with ACTION requirements.
'4.0.5 Surveillance Requirements for inservice inspection and testing of ASME T ,
jCodeClass1,2,and3componentsshallbeapplicableasfollows: l l
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing'of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler
; and Pressure Vessel Code and applicable Addenda as required by i 10 CFR Part 50, Section 50.55a(g), except where specific written i relief has been granted by the Commission pursuant to 10 CFR Part 50,
\ Section 50.55a(g)(6)(i);
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspec-tion and testing activities shall be applicable as follows in these Technical Specifications: -
A&mdb se.cwo; 5,g, See Occfo, Sec% s.o, i BRAIDWOOD - UNITS 1 & 2 3/4 0-2 AMENDMENT NO. 38 .
W I
. CTS INSERT (S) -
- SECTION 3.0 SR 3.0 l' INSERT 3.0 2A ( A,)
' SRs shall be met during the MODES or other saecified conditions in the Applicability for individual LCOs. unless otlerwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LC0. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LC0 except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment .; or variables outside specified limits. 2 l INSERT 3.0 2B (A,. M y and L3 ) -: (A) i The specified Frequency for.each SR is met if the Surveillance is performed 1 within 1.25 times the interval specified in the Frequency, as measured from the arevious performance or as measured from the time a specified condition of the requency is met: (H2 )
.For Frequencies,specified as "once." the above interval extension does not apply.
(La) If a Com)letion Time requires periodic performance on a "once per . . ." basis, tie above Frequency extension applies to each performance after the initial performance. (A,) Exceptions to this Specification are stated in the individual Specifications. l Revision A i
- ~ _ _ . -- ~ ._ --
CTS INSERT (S) SECTION 3.0 SR 3.0 INSERT 3.0 2C (M2 and L;) (L4 ) If it is discovered that a Surveillance was not performed within its specified Frecuency. then compliance with the requirement to declare the LC0 not met may be celayed, from the time of discovery up to 24 hours or'up to the limit of the specified Frequency whichever is less. This delay period is permitted to allow performance of the Surveillance. (M2 ) If the Surveillance is not performed within the delay period, the LC0 must innediately be declared not met, and the applicable Condition (s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the LC0 must immediately be declared not met. and the applicable Condition (s) must be entered. INSERT 3.0 2D ( A,) Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. Revision A L
l . l SR ApplWbk% 3 3.o '
- .5pu.4 C 5.5.7
+
APPLICABILITY e _ { AJ4 rewed '., Su b 3.0 l SURVEILLANCE REQUIREMENTS See Doc 4 5-6 ao i l \
- 4. 0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES' c'r other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
I. 4.0.2 Each Surveillance Requirement shall be performed within the specified i time. interval specified with a maximum surveillance allowable extension not to exceed 25% of the interval. 4 4.0.3 Failure to perform a Surveillance Requirement within the allowed sur . veillance interval, defined by Specification 4.0.2, shall constitute noncompli-ance with the OPERABILITY requirements for a Limiting Condition for Operation. l The time limits of the ACTION requirements are applicable at the time it is i identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time limit _s of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to.be performed j on inoperable equipment. l 4.0.4' Entry into an OPERATIONAL N0DE or other specified condition shall not be i I made unless the. Surveillance Requirement (s) associated with a Limiting Condition for Operation has bee'n performed within the stated surveillance interval or as j otherwise specified. This provision shall not prevent passage through or to t 4 OPERATIONAL MODES as required to comply with ACTION requirements. ' ! 5.5 e 65fE9 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows: I a. icT inspection of ASME Code Class 1, 2, and 3 compon inservice
~of ASME Code Class 1, 2, and and valves shall be performe ance wit n XI o'f the ASME Boiler and Pressure Vessel Code e Addenda as required by-h 10 CFR Part 50 0.55a(g),excep reli 1 A . een granted by the Commission pursuant ecific written R Part 50, ection 50.55a(cM6)(i):
5.5.s.o A'. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspec-tion and testing activities shall be applicable as follows in these Technical Specifications: BRAIDWOOD - UNITS 1 & 2 3/4 0-2 AMENDMENT NO. 38 .
5A A ppb & \.g a.o l % y .,..a. n s s.s hPPLICA8ILITY SURVEILLANCE REQUIREMENT (Continued) 1 ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICA8LE ADDENDA - PERFORMING 1NSERVICE i TERMIN0 LOGY FOR INSERVICE INSPECTION AND TESTING INSPECTION AND TESTING ACTIVITIES ACTIVITIES i { Weekly i (-Marus,M Monthly At least once por 7 days At least once per 31 days l Seekn 5.5 Quarterly or every 3 months At least once per 92 days See 00C 4, . Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days (Subb 5.o ) _ Yearly or annually . At least once per 366 days e
- c. The provisions of Specification 4.0.2 are applicable to the above j
required frequencies for performing inservice inspection and testing activities; 1
- d. Performance of the above inservice inspection and testing activities i - -
- ,t ;l hc in coditics to GL:.s. speciflad *... 6 114..c. ;; yw*. ..b. enu i e.
i NothingintheASMEBoilerandPressureVe'sselCodeshallbeconstrueh
, to supersede the requirements of any Technical snecificatina /
i f4.0.6 Surv 111ance Requi nts shall apply each unit indivi 11y unless j otherwise ndicated as s ated in Specificati 3.0.5 for indivi ual specifica j tg, tions or never cert n portions'of a sp ification contain urveillance parame rs different (octn es or body t,f her each unit, which ill be identified in parentheses, j reautrement. 3 ; ) I 1
)
i i l-I i a 1 i
)
1 1,
- i BRAIDWOOD - UNITS 1 & 2 3/4 0-3 l
i SR Appbcobil&q 3 0 l Spec.Ses G S.5.E l APPLICABILITY 1 0 SURVEILLANCE REQUIREMENTS (Continued) N ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA - - PERFORMING INSERVICE i TERMINOLOGY FOR INSERVICE INSPECTION AND TESTING j INSPECTION AND TESTING ACTIVITIES ACTIVITIES 5 Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At-least once per 276 days j i g Yearly or annually A". least once per'366 days L 'e u ially or e ver, 2 yeen M laat one co- 731eJa n 1 l 3.g, L b - E. The provisions of 5pecification 4.0.2 are applicable to the above ! ! required frequencies for performing inservice inspection and testing !
. activities; '
4
%. ?;cf;..x;;; ;f 0.'.;
;t ' :,,
- t:v; ';;;ni;; in;;;;;i;. ;;d 0;;;i.; ;;ti.! ie; h
- c. e.:.:! u;c. L ;' : c ;;;;
- f :e; ~.. .. ' : :.....m.
~
..m ,, a
- $.5,B d /.
- Nothing in the ASME Boiler and Pressure Ve'ssel Code shall be construed
'to supersede the requirements of any Technical Specification.-
' 4. 0. 6 Surveillance Requirements shall apply to each unit individually unless I otherwise indicated as stated in Specification 3.0.5 for individual specifica- !
tions or whenever certain portions of a specification contain surveillance parameters different for each unit, which will be identified in parentheses, j footnotes or body of the requirement. ) r% i - L AMreueJ ;, 5.c.s. 3.0 A Doc 4 .b6 3.0. L_
.6.6.S , c, : "The prod.$oeit cI ,St. 3.o.3 we app M le k >;*rv;<'- %
4ennq acbRes , ..ul s 4 BRAIDWOOD - UNITS 1 & 2 3/4 0-3
-.. .- .- -.- . _ . - - - . . . . - .. . _ - - - _ - . - - - = _ . - - .
n CTS INSERT (S) SECTION 3.0 1 BASES i The Bases of the current Technical Specifications have been replaced in their entirety by Bases reflecting the format and applicable content of NUREG-1431 Bases and proposed Byron and Braidwood Technical Specifications, i i 1 6 i 4 ) E l J i 1 k 1 1 j . Revision A
_ _ . . . _ . ~ _ _ _ _ _ _ _ . _ _ _ _ - . . _ - .._. _ _ . t
.Beb , L s 1.1 '
Lco 3.1.1 . i
- l. '
1.c o 3.1.2. . 3/4.1 REACTIVITY CONTROL SYSTEMS g 3, ) 4 j 3/4.1.1 80 RATION CONTROL' Lco 3. l.5 l d SHUTOOWN MARGIN - T >200*F - ~ L co 3.1. 6 ! E AMrewJ 5 S'e.c4.d.1 LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% ak/k I for four loop operation. 1 APPLICABILITY: MODES 1, 2", 3, and 4. ACTION: f With the SHUTDOWN MARGIN less than 1.3% Ak/k, immediately initiate and continue j boration at greater than or equal to 30 gpm of a solution containing greater j than or equal to 7000 ppa boron or. equivalent until the required SHUTOOWN MARGIN is restored. l l SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined_-to be greater than or equal 1 _ i to 1.3% ak/k: i i
- a. Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (sF is inoperable.
i
- }( f f
If the inoperable control rod (s) is immovable or untrippable, the above requiredSHUTDOWNMARGINshallbeverifiedacceptablewithan~ increased j' 4.dc4.$ %7 g allowance for the withdrawn worth of the immovable or untrippable control rod (s); j b. When in MODE 1 or MODE 2 with K,ff greater than or equal to 1 at } ' least once per 12 hours by verifying that control bank insertion is within the limits of Specification 3.1.3.6;
- c. When in MODE 2 with K,ff E less than 1, within 4 hours prior to j '
achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification ~3.1.3.6; j d. Prior to initial operation abov'e'5% RATED THERMAL POWER af ter each-a fuel loading, by consideration of the factors of Specification
- 4.1.1.1.le. below, with the control banks at the maximum insertion
! limit of Specification 3.1.3.6; and i f "See Special Test Exceptions Specification 3.10.1. f
= -
i AMn.sseci m .Su+len 3.i.] l Se.e. Doc he sec+i.,.3.l. ) 4 BRAIDWOOD - UNITS 1 & 2 3/4 1-1 1 j . .
LCO 3. l.1 LCO 3.1.1 2
- LCO 3.1.4 i
Lco 3.15 l 3.1 M REACTIVITY CONTROL SYSTEMS LCD 31G j $
, Specification f.I
[3/".1.1 00"" ! ; = ;;;r"00 i 3.l.) SHUTDOWN MARGIN O T g;; O (sog) 1 I
. LIMITING CONDITION FOR OPERATION wdhin 4he' hnds specLEed 'O Ille COLR- -
LCO 3.1.8 The SHUTDOWN MARGIN shall be ra*=='a-
"=a a-
=? 51 +a 1 ?? %
(";r "nr :n; :;;rn::.) l p4ede 2 wWh kar & t.0 ) q APPLICABILITY: MODES +3, and 4. Q i ' O l ACTION: . LA
~ within limit ' =dhin is m inu+es U i cono A With the SHUTDOWN MARGIN '-5! 'h=a 1 'M _^
W .C' m 9 5t=1 initiate and continue boration.ldt-greater /than or e al to 30 gpe/bf-a solutiof containinygreater / than or Aqual to 7f00 ppe bo n or equivalfnt until the/ required Sif0TDOWN MApGIN is respred.( .
~
SURVEILLANCE RE'0UIREMENTS
- sa 2.t.1.1 ..
; waw a nei;,,,;+,s g.i m g w coi.a.
(" L L I. ; The SHUTDOWN MARGIN shall be determined to.be er;=:r = = er a,.C . le 1. ;:; oi/L.' oe h e rw ro n ab .
'/ddim[in he9wan i.i If the inoperable control rod (s) is immovable or untrippable, the above '. ~
'Qee " coc kr Jeebon i.tf. ' required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s);
J
. 58 3. l. (e.2_. 6. Whe in M00 or MOD 2 with than 'or qual to ff great at ast onc per 12 urs by v ifying at contr bank i ertion i within e limit of Spec ~i cation
.3.6; SR 3.l.6 1 s. Whe in_ MODE , with X less th 1, wit 'n 4 hour prior to f
A, I,h4eving eactor er ticality y verify g that e predic d criti control d posit n is wit n the li ts of 5 cificatio 3.1.3.6-Ce&du etoPe. t k 4: Prior tot ftic' : rr:M " r Er ""Is" 7" ""n "^' r"la f ter each D'I' A' I -
' feel.loadino f::, := :: n n:= :: n: :::.;r: :" ;;;;;"t::tts R.1.1.1.1:. ::';r./.;ith the n =r:1 trt; n th: :=in: M; --t i;nl L3 C , W 1 of S w c ;fic n ;e,. 2. 1. 2.C. s $
LA c 6 u ci ' a n , s e:.;er.; ;;;;i't a t = 2.2".1.2 g BRAIDWOOD - UNITS 1 & 2 3/4 1-1
$ .. - L ( 0 2 .l I L C D E . l 2. ' 'l trc 2.1 4 REACTIVITY CONTROL SYSTEMS LC 3 II L co 3.14
,y SURVEILLANCE REQUIREMENTS (Continued)
( Nrle 2 witi krs. 4 6 O onclin SR 3l.l.1 .e When inE M00E 3 or 4. at least once per 24 hours by consi ration of ) t following factor . , h-/1) Reactor Coo nt System boron ncentration.
- 2) ControlrIdposition, .-
l , ' 3) React r Coolant System verage temperatu ,
- 4) F burnup based a gross thermal ene/ rgy generation,
- 5) Xenonconcentratfn,and Lif Samarium concpntration.
Sp,'d.t.2 2 /JoTY-10 TN4 E AT 3 I ~ 88 3 -f M ' 8 * *'*-O m 3 l.2 2, (4.1.1.1.2 he O.n e:17 tore reactivity N shall be c'ompared to predicted values to demonstrate feceeeme*G within t 1% Ak/k at least once per 31 4 Effective Full Power Days (EFPD).fThis r/mparisJrh shalj1 tonsiefer atrieast l (thnWfactnM staMd in Jr n .cifician 4A i 1 y e.f._f 73: pr 4 :;7, reactivity values q-y be adjusted (normalized) to correspond to the actual core conditions prior 'to ext ding a fuel burnup of 60 EFPD after each fuel ! loading. g ,
- (I NSECT 3.1-2.Ak 4
4 i 1 J BRAIDWOOD - UNITS 1 & 2 3/4 1-2
CTS INSERT (S) SECTION 3.1 , LC0 3.1.2 INSERT 3.1 2A (An and M,) 3.1 REACTIVITY CONTROL SYSTEMS . s 1 3.1.2 Core Reactivity ; LC0 3.1.2 The measured core reactivity shall be within 1% Ak/k of- , predicted values. l APPLICABILITY: MODES 1 and 2. ACTIONS- - CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core A.1 Re-evaluate core 72 hours reactivity not within design and safety limit. analysis. and determine that the reactor core is ac.ceptable for ! continued operation. l
. MQ. -
A.2 Establish appropriate 72 hours operating restrictions and SRs. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. Revision A e
4 4 CTS INSERT (S) SECTION 3.1 LC0 3.1.2 INSERT 3.1 2B (La)
- SURVEILLANCE FREQUENCY l 2 SR 3.1.2.2 NOTES I
- 1. Only required to be performed sfter
. 60 Effective Full Power Days (EFPD).
- 2. ...
I j ... i 1 i. i 1 I i . 3 Revision A f ,
~ ~ . - - - - _ . . - . _ . - - . . - - . . . . . . - - . - . - - - - . - . . . - . . .- . . - . . .
Sp u'. C a h u n. 0 L eo 3. l. l 4 L eo y, t 4 i ' REACTIVITY CONTROL SYSTEMS - i i . SHUTDOWN MARGIN - T,yg i 200*F AclJreu,s . su s,. ii .
. See Dot L. s' ra% 2. s -
LIMITING CONDITION FOR OPERATION i 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k. l APPLICABILITY: MODE 5. ] l
- ACTION
- a. With the SHUTDOWN MARGIN less than 1.3% Ak/k declare both Boron
~ i i
DiTution Protection Systes subsystems inoperable and apply Specifi-cation 3.1.2.7.b. ,
- b. With the SHUTDOWN MARGIN less than 1% Ak/k, immediately initiate and ;
i continue boration at greater than or equal to 30 gpa of a solution 1 i containing greater than or equal to 7000 ppe. boron or equivalent i until the SHUTDOWN MARGIN is restored to greater than or equal to i 1 1% Ak/k.- a SURVEILLANCE REQUIREMENTS l ! 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal i a to 1% Ak/k: , i a. Withiii 1 hour'after detection of an inoperable control rod (s) and at i
- least once per 12 hours thereafter while the tod(s) is inoperable. l If the inoperable control rod (s) is Immovable or untrippable, the
,', I i guno ,a SHUTDOWN MARGIN shall be verified acceptable with an increased '
i mwu M allowance for the withdrawn worth of the immovable or untrippable i control rod (s): and
- b. At least once per 24 hours by consideration of the following factors:
l 1) Reactor Coolant System boron concentration, J
- 2) Control rod position,
- 3) Reactor Coolant System average temperature,
- 4) Fuel burnup based on gross themal energy generation,
! Xenon concentration, and
- 5) -
I
- 6) Samarium concentration.
y= A-A Jdrev b $< A. J. l.
; Q, Ooc 4 Se. G 3. I ,
! BRAIDWOOD - UNITS 1 & 2 3/4'l-3 ~ Amendment No. 40 a
u co 3 1. L
/fo 3.IA s pu. f. c d . . . y 3.1 REACTIVITY CONTROL SYSTEMS 3.t.1SHLTTDOWNMARGIN(T, I b (gog)
LIMITING CONDITION FOR OPERATION will..n +he Im.h ryeuned n i ii.e. COLf<. LCO 3.1 9 The SHUTDOWN MARGIN shall be fer m : tt:.- er:cm teLn 9AJ l APPLICABILITY: MODE 5. t m, , ACTION: . ar. -With he SHUTD MARGIN 1ps than 1.K Ak/k degare both B on Di tion Prot ion Systesisubsystems"inoperabTe and apol Decifi-ion 3.1.2 .b.1 eio4 will..n bn.d wahui 15 n..ndes.
-+. With the SHUTDOWN MARGIN a--" "- " ^ ~ i- ] e -2 :t:9/) initiate and gg continue' boration.lat greater t an or equal to gpm of a solu on containing grAater than or e al to 7000 ppm oron or equival nt until the Sp0TDOWN MARGIN i restored to gr ter than or eq 1 to 1% Ak/k.l LA SURVEILLANCE REQUIREMENTS SR 3.l.l l ,
will..ii il.e ine d: yoited on ilie COLM. L4,1,1.0 The SHUTDOWN MARGIN shall be determined to be'irT:t:r th:n r ccc: _
;to = ta/G one h er to ~
ea If the inoperable control rod (s) is immovable or untrippable, the fjg= - ~. SHUTDOWN MARGIN shall be verified acceptable with an increased 6 7d(( coy allowance for the withdrawn worth of the. immovable or untrippable N- ' control rod (s); and _ sa 3.n.l.1 -b. At least once per 24 hours by considerati of the followi factors: g 1 Reactor Coolant ystem boron con ntration, p
- 2) Controlrodiosition, ,/
- 3) Reactor Coolant System average temperature,, /
- 4) Fuel burnup based.on gross thermal energy generation, ,f
- 5) Xenon concentration', and I
6,) Samarium concentration. ; 3/4 1-3 Amendment No. 40 . BRAIDWOOD - UNITS 1 & 2
L C,o 3. l .3 l 31 REACTIVITY CONTROL SYSTEMS , 3.l.3 MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION .
- 3. l. 3 (core ) O j L O UJ .31 The moderator temperature coefficient (MTC) shal1['be within the l l limits specified in theo0perating Limits Report (OLR). The maximum l upper limit shall be less than or equal to that shown in.
Figures M 3.1.3-l c 3 ,._ ,. , ; Oncr Mic APPLICABILITY:' 'esinnina ef .ife =.nlimit - MODES 1 and' o ly . l C W c' ' M*-Fol4 limit - MODES 1, 2, and 3 . N
~
Lower MTC , ACTION: ' l u:cer Mrc. i
- coNO A +. With the MTC more positive than the E )1imit S cified in it.e m m, l l
, operation in MODES I and 2 may proceed provided: ,
, g ,, y .e
- 4. Control rod withdrawal limits are established and maintained sufficient to restore the'MTC to less positive than the BOL coso e- limit specified in the OLR within 24 hours or be inc=: : ".=; .,
within the next 6 hours.j These Vithdrawal limits shall be in h addition to the 1Fisrt]on limit / of Specification 3.1.3.6;
+.
~
s
/he control roa 've established areuntil maintain a s sequent d within the withdrawal calculati'on verifies limits
/that
@ the MTC has' en restored withdrawn c dition: and within its limit / for' the al/ rods
-3 . A Special Report is prepsred and sutimi 'ed to the Commission pursuant to Specification 6.9.2 withi. 10 days, desciibing the value o the measured C, the inter' control rod sithdrawal h limits and the pred eted average c re burnup.necessary for.
resto ing the posit ve MTC to with n its limit for the all rods with rawn conditio . f h +. (Ttie erevisiegs er Ssec1ricafiwr-3foif5rse_nd app 31Gb CNLC 4. WiththeMTCmorenegativethantheylimitspecifiedinthe LR, l be in HOT SHUTDOWN within 12 hours. a tw r A With K y greater than or equal to 1.j q a ';ee ';seciti-Test--ExceutroliTWE.iYication,__3. IO.3. ) BRAIDWOOD - UNITS 1 & 2 3/4 1-4 Amendment No.65
L co 3.1.3 0 . 2 REACTIVITY CONTR0i. SYSTEMS SURVEILLANCE REOUTREMENTS (4.1.1.2 ) The MTC shall be determined to be within its limits during each fuel cycle as follows: W%% ne.ugger hmW G8 3.t.3.1 4- The MTC shall bel measured an comparedtothdBOLpredicte MTC to Astablish adn/nistrative ro withdrawal ligrits, as necess y, to assure that Ahe BOL limit ecified.in th,'OLR, is met t oughout ! CLe fare life,l prior to initial operation aboveG; er RATED THE""AL) POWER, after each fuel leading, and. 1 G R 3.l.3.2-b. The MTC shall be measured f :""f.L " W:")and compared to the 300 ppm surveillance limit ~it :; specified in the@LR (all rods withdrawn,
- cue ei 3- c- ~mm Per"
- : ene s) within 7 EFPD a'ter reachino an eauilibrium boron concentration of 300 ppm.l In the event this
! comparison indicates the MTC is more negative than the 300 ppm (we 2 p surveillance limi specified in the@tR, the MTC shall be remeasured, at_least once peand c mpared 14 EFPD duringto the @'the remainder of the fuel cycle.M i Old
, .(Gd Lco limi+)) , , (MTE 3 Insert 3.1-5A l 4 4 I BRAIDWOOD - UtlITS 1 & 2 3/4 1-5 , Amendment No. 65
i ~ CTS INSERT (S) SECTION 3.1 LC0 3.1.3 INSERT 3.1 5A (La) SURVEILLANCE FREQUENCY SR 3.1.3.2 NOTES ...
- 3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of 5 60 ppm is less negative than the 60 ppm Surveillance 4
limit specified in the COLR. i . , 4 i i Revision A i i
LCD 3.1.3
- 4 4
i J l 10 , i
- 9 -
Unacceptable Operation f 8 E i.
- j 6'h U
.i e $ ' 5 i 1 - kd E b Acceptable Operation 3'.h . g <- 2 .: . 5 2 7 h 1-7 5 k n h A J & i - h A b 0 10 20 30 40 50 60 70 80 90 100 Percent RTP
- 3. I.3 - t FIGURE O i MODERATOR TEMPERTURE COEFFICIENT vs. POWER LEVEL BRAIDWOOD - UNITS 1 & 2 3/4 1-5a AMENDMENT N0.65 O
I 6cc4ioh 5,l l-Go 3,e/,1, 1 Adclressecl in Sechon 31 SeeDocj.,rsechen 3 4 REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY ! l LIMITING CONDITION FOR OPERATION 3.1.1.4 shall beThe Reactor greater than Coolant or equalSystem lowest operating loop temperature ('Tavg) to 550*F. , l APPLICABILITY: MODES 1 and 2#*. , 1 ACTION: With a Reactor Coolant System operating loop temperature (T,yg) less than 550*F, restore T,yg to within its limit within 15 minutes or be in HOT I STANDBY within the next 15 minutes. SURVEILLANCE REQUIREMENTS l 4.1.1.4 be greaterThe Reactor than Coolant. or equal System temperature *.(T**9)'shall be determined to to 550*F: I a. Within 15 minutes prior to achieving reactor criticality, and
- b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T,yg is less than 557*F with the T,yg-T ref Deviation Alarm not reset.
fWith K,ff greater than or equal to 1.
*See Special Test Exceptions Specification 3.10.3.
BRAIDWOOD - UNITS 1 & 2 3/4 1-6 J
l
-~ c . r , o-l Sec6 3.1
.l 3M Rsu foA NPT st yrEti (ES)- d l h,y,g Ft.6 MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION F'OR OPERATION Loo 3A,3 i EM-t-49 shall beThe Reactor greater thanCoolant or equal System to 5 lowest operating loop temperature (T,y9)
*F.
APPLICABILITY: MODES 1and2d . ACTION: COND 4 With a Reactor Coolant System operating loop temperature (T,yg) less than 550*F,t = ::: : u: .n"- i n :::: ui:n" .: - :::: : ,be in %
}ST*"DS9withinthenext15 minutes. l Mapa 2. or.tk K 4 < (.o) l r
l SURVEILLANCE 'AEQUIREMENTi, 1 6 A 'JA 9. t ' RbeI.1.6greater The than~or Reactorequal Coolant: System temperature'(T**9)'shall be determined to to 550*F: l L. Sith'- 15 etnut:: ;rter t: ::ht:;' ; r:::::r critt::::ty, 2nd 1 m
- b. At least once oe/MO minut when e -rea tor is ritic and' the ]
J ctor olant ystem T g is le s than 557'F w th the T avg-Tre fJ' lfR viat n Ala not re t.f I f [Il h o u rs , g4 N Fhkl U W fWith Kg f greater than or equal to 1. ("Swc Svw ioI Iwai [auspiivua SpwwiI;wainwu 3.10.3 5 BRAIDWOOD - UNITS 1 & 2 3/4 1-6 8 4 9
T Mah. 3.1
\EACTIVITYCONTROLSYSTEMS 3 1. 2 BORATION SYSTEMS FLOW TH - SHUTDOWN 1
l , LIMITING CONDITION FOR OPERATION i l 1 3.1.2.1 . i
- j. beOPERABLEandca(pableofbeingpoweredfromanOPERABLEemergencypo j; source: .
~
. a. A flow path p the Boric Acid Storage System via a borf acid transfer 1 pump and a cent,rifugal charging pump to the Reactor Coo nt System if
{. the 8eric Acid Storage System is OPERABLE as given in pecification i 3.1.2.5a. for M00' 5 an.d 6 or as given in Specific ion 3.1.2.6a. ' i for MODE 4; or . I , b. The flow path from the charging pump to the Re\ refueling actor Coolant water storage System i theank via a centrifugal refueling water j storage tank is OPERABLE 'as given in Specif
- ation 3.1.2.5b. for l MODES-5 and 6 or as given in Specificatio 3.1.2.6b. fnr MonF a i
, APPLICABILITY: MODES 4", 5 and 6. .
' ~
ACTION: With none of the above flow paths OPERABLE or capable of being powered from an OPERABLEemergencypowersource,suspenfalloperationsinvolvingCORE
- ALTERATIONS or positive reactivity changes.
i SURVEI'LLANCE REQUIREMENTS i - 4.1.2.1 At least.one of t
\
above required flow paths shall be demonstrated '
- OPERABLE
- a. At least onge per'7 days by verifying that the tempergture of the a heat traced portion of the flow path is greater than o equal to-65'F who a flow path from the Boric Acid Storage System is used, and l
- b. At east once per 31 days by verifying that each valve (manual,, ,
} p r-operated, or automatic) in the flow path that is not locked,
. ealed, or otherwise secured in position, is in its correct position.
1
\
{ "A ximum of one charging pump shall be OPERABLE, and that pump shall be a i - ntrifugal charging pump, whenever the temperature of one or more of the CS cold legs is less than or equal to 330*F. j . . BRAIDWOOD - UNITS 1 & 2 3/4 1-7
-ww- e - - , -- -- ~ s. . . , - +
r G ecAion 3al xREACTIVITY CONTROL SYSTEMS @-
\
FLOW PATHS - OPERATING
\
LIMITING CONDITION FOR OPERATION
/
\
3.1.2.2 At least two of the following three boron' injection flow paths s, hall
/
be OPERA 8LE: /
- a. The flow' path from the Boric Acid Storage System via a borjt acid transfer giump and a charging pump to the Reactor Coolant 6ystem, and f
- b. Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System. ' ,
\
APPLICA8ILITY: MODES 1, 2,Nand 3. ACTION: flow paths'to the Reactor With Coolant only oneOPERA System of the8LE, above required restore at\least two boron injectioy' injection flow paths to bct,on the Reactor Coolant System to OPERABLE. status w) thin 72 hours or be in at leastHOTSTAND8YandboratedtoaSHUTDOWNMfRGINequivalenttoatleast 1% Ak/k at. 700*F within the adit ~f hodi s hrpsto"re '2t '..:.:t tac f D. '.!.. to OPERA 8LE status within the next 7 days r be in COLD SHUTDOWN within tne next 30 hours. SURVEILLANCE REQUIREMENT'S \
' 4.1.2.2 At least two of the a e required flow pa shall be demons'trated OPERA 8LE:
- a. At least once per 7 days by verifying that the s ;
heattraced,p6rtionoftheflowpathfromthebor\peratureofthe- c acid tanks is ' greatgr than or equal to 65'F when it is a required water source;
. b. Atleastdnceper31daysbyverifyingthateachvalv (manual.
power-sperated, or automatic) in the flow path that is et locked, seale' d , or otherwise secured ir, position, is in its corr t position; c.
/
A,t least once per 18 months during shutdown by verifying t t each fautomatic valve in the flow pa'th actuates to its correct pos ion on a Safety Injection test signal; and
.d. At least once per 18 months by verifying that the flow path requ zed
/ by Specification 3.1.2.2a. delivers at least 30 gpm to the Reactor Coolant System.
e BRAIDWOOD - UNITS 1 & 2 3/4 1-8 4
W % . 5,\ i . EACTIVITY CONTROL SYSTEMS CH RGING PUMP - SHUTDOWN N LIMITING. CONDITION FOR OPERATION N l i
\
3.1.2.3 One charging pump in the boron injection flow path required by 1 ' Specification 3 1.2.1 A shall be OPERABLE and capable.of being powered fr an OPERABLE emergency power source.
\ .
- APPLICABILITY
- MODES 4", 5, and 6.
. ACTION:
i \ With no charging pump OPERABLE or capable of,being powere.d f, rom an OPERABLE 4 emergency power source, susp,end all operations involving CORE ALTERATIONS or positive reactivity changes. SURVEILLANCE REQUIREMENTS \
\
t { .
- 4.1.2.3.1 The above required charging / pump shall be demonstrated OPERABLE by verifying, on recirculation flow, thpt a diffe'ential r pressure across the ;
pump of greater than or equal to 2 96 psid is de\ eloped when tested pursuant to ' Specification 4.0.5. 4.1.2.3.2 Whenever the tempe 'ture of one or more of the RC5 cold legs is , less than or equal to 330*F 11 charging pumps, exclu ing the above required . OPERABLE pump, shall be deponstrated inoperable"" at le t once per 31 days, except when the reactor (ssel head is removed, by verify \ g that the motor circuit breakers are s ured in the open position.
"A maximum of one charging pump shall be OPERABLE, and that pump sha be a centrifugal charging pump, whenever the temperature of one or more of he RCS cold legs is less than or equal to 330*F.
4
**An operable pump may b'e energized for testing provided the discharge o pe pump has been isolated from the RCS by a closed isolation valve with ower removed from the valve operator, or by a manual isolation valve secured in the closed position.
5 BRAIDWOOD - UNITS 1 & 2 3/4 1-9 .
Oh L \ IBACTIVITYCONTROLSYSTEMS kh) CHARGINGPUMPS-OPERATING i LIMITING CD TION FOR OPERATION p p' 3.1.2.4 At least two harging pumps shall be OPERABLE. l ! APPLICABILITY: MODES 1, and 3.
- ACTION
With only one charging pump OPERA , restore at least wo' charging pumps to OPERABLE status within 72 hours or b in at least H STANDBY and borated to a SHUTDOWN MARGIN equivalent to at lea 1% ak/k 200*F within the next 6 hours; restore at least two charging p st PERABLE status within the next 7 days or be in COLD SHUTDOWN within the ne 30 hours.
. j 2
4
~
SURVEILLANCE REQU MENTS I . 1
- l l
4.1.2.4 .At least two charging pumps shall be demonstrated OPERABLE by verif ng, on recirculation flow, that a differential pressure across each p of greater than or equal to 2396 psid is developed when tested pursuant o Specification.4.0.5. - 1 ~ s . t 9 BRAIDWOOD - UNITS 1 & 2 3/4 1-10 l
[Rl9LCTIVITVCONTROLSYSTEMS D 6ec4(ak. 3, ( a -BDR ED WATER _1QPRCE - SHt/TDQ)fh LIMITINO CONDITION'FOR OPERATION
\
k 3.1.2.5 A$Na minimum, one of the following borated water sources shall /- OPERABLE: \
- a. A Bo ic Acid Storage System with: '
- 1) A nimum contained borated water level of 7.0%, ' i j .c... 2) A miMaum boron concentration of 7000 ppe, and
\
- 3) A minimum solution temperature of 65*F.
- b. The refuelingwater \ storage tank (RWST) with: '
1) A minimum on c\(ained borated f 9.0%, water level
- 2) a)
*Aminikboronconcentration f 2000 ppm, b) **A boron to tration betwe n 2300 and 2500 ppm, and
- 3) A minimum solution teperature f 35*F. '
APPLICABILITY: MODES 5 and 6. ACTION: With no borated water source OPERABLE susphnd all operations involving CORE ALTERATIONS or positive reactivity. anges.
*SURVETLLANCE REOUIREMENTS 4.1.2.5 The above required OPERABLE: rated water source sha 1 be demonstrated -
- a. At least onc per 7 days by:
- 1) Verif ing th'e ' boron concentration of the wa r,
- 2) V ifying the contained borated water level, a
- 3) erifying the boric acid storage tank solution t erature when it is the source of borated water.
- b. t least once per 24 hours by verifying the RWST temperat e when it is the source of borated water and the outside air temperat re is less than 35'F.
~ pplicable to Unit I and Unit 2 until completion of cycle 5.
l Applicable to Unit I and Unit 2 starting with cycle 6. . BRAIDWOOD - UNITS 1 & 2 Unit l'- Amendment No. 56 ' 3/4 1-11 Unit 2 - Amendment No. 55
- = - . . . . . . ~ - - . -.-. _ - -. _ . - _ - - - - . . - . - ..
6 2c.6 ph 3.! l REACTTVfTY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING
- 3 '
LIMITING CONDITION FOR OPERATION 4 3.1.2.6 s a minimum, the following borated waker source (s) shall be OPE
- . LE s
1
' 3.1.2.1 as require'd for by Specification 3.1.2.2 for MODES 1, 2 and 3 and on j E 4:
! g_ a. A Bori Acid Storage System with: . 4
- 1) A mi mum contained borated water level of 40%, -
- 2) A mini boron concentration of 7000 ppe, a j 3) A minimum s ution temperature of 65*F. -
- b. The refseling wate torage tank (RWST), wit' 1)
A minimum contai ed borated water le el of 89%,
- 2) a)
N~ /
.A' minimum boron concentration of 2000 ppm, -
b) **A boron concent a on ' tween 2300 and 2500 ppm, l ) 3) A minimum solution temperat0re of 35*F, and i
/
- 4) A maximum solution tempe'ratu\ ra of 100*F.
APPLICABILITY: MODES 1, 2, 3, and ACTION: / i a.
/ -\
With the Boric Acid / Storage System inoperable and being used as one i
.I of the above requifed borated water sources fqM00E 1, 2, or 3, l restore the systdm to OPERABLE status within 72g h ours or be in at least HOT ST MARGIN equi Y within the next 6 hours and borated to a SHUT 00WN Acid Stora enttoatleast1%ok/kat200*F;rhtoretheBoric System to OPERABLE status within the n t 7 days or be in COLD SHUTDOWN within the next 30 hours.
. b. With th RWST inoperable in MODE 1, 2, or 3, restore th tank to OPE I' LE status within I hour or be in at least HOT STAN08Y th next 6 hours and in COLD SHUTDOWN with'in the following\ within 30 hours.
- c. ith no borated water source OPERABLE in M00E 4, restore one orated water source to OPERABLE status within 6 hours or be in COLD SH' DOWN within the following 30 hours.
. \
' i
. lApplicabletoUnitIandUnit2startingwithcycle6. Applicable to Unit I and \\ Unit 2 un{ j Unit 1 - Amendment No. 56 BRAIDWOOD - UNITS 112 3/4 1-12 Unit 2 - Amendment No. 55 i
1
- -_ _ .. . = . . . - .. _ - . . ~ . . _ - ____.__ - -. .-
_ M#k .5 ( 4 g -- -- .-.. . . . . . ,
- h. _ . . , _ , , , _ , , , _ _ , __ _ , , _
] REACTIVITY CONTROL SYSTEMS 'l
. SURVEILLANCE REQUIREMENTS l
s l s 4.1.2.6 Each borated, water source shall be demonstrated OPER : I l
's
- a. Atleastonceper(7daysby:
! '1) Verifying thebo\ concentration the water,- 1
- 2) Verifying the containe or ed water level of the water :
source, and l 2 !i 3) Verifying the Bor Acid Storage stem solution temperature when it is th ource of borated wa .
- b. At least onc er 24 hours by verifying the temperature when the outs air temperature is either less than 3 or greater than 100*F nd
- i c. least once per 24 hours by verifying the'FNST vent path perature 1 to be greater than or equal to 35'F when the outside air tempe ure f,, is less than 35'F.
f' - l
? ,
r f i 4 i P e BRAIDWOOD - UNITS 1 & 2- 3/4 1-13
$&ow So \
; W TS 9 l REACTIVITY CONTROL SYSTEMS MSBsa3a
, BORON Dill 1 TION PROTECTION SYSTEM LIMITING CONDITION FOR OPERATION ,
I I3.1.2.7 Two independent Baron Dilution Protection System (BDPS) subsystems l shall be OPERABLE.* - APPLICABILITY: MODES 3_, 4, and 5.
, ACTION:
)
i
- a. With one BDPS subsystem inoperable, restore the inoperable subsystem I
to OPERADLE status within 72 hours or within the next hour, and at
- least once every 31 days thereafter, v'erify valves CV-1118, CV-8428, 4 i CV-8439, CV-8441, and CV-8435 are closed and secured in position.**
i
- b. With both BDPS subsystem.s inoperable, within 1 hour, and at least
; once every 12 hours thereafter: !
- 1. Verify valves CV-111B, CV-8428, CV-8439, CV-8441, and CV-8435 l are closed and secured'in position **, and
- 2. Verify compliance with the SHUTDOWN MARGIN requirements of
- l. Specification 3.1.1.1 or 3.1.1.2, as applicable.
s l '*The BDPS Flux Doubling signals may be blocked during reactor startup. .
. , s.
!**Thesevalvesmaybeopenedonanintermittentbasisunderadministrative control when required to support pl. ant evolutions.
BRAIDWOOD - UNITS 1 & 2 3/4 1-13a Amendment No. 40
LCO 3.3.9 3.3 rns4ru AG., Se.e. % . 5.\
/yR,CTIVITY 00=0L SYST=j i
333 BORON DIllfi10N PROTECTION SYSTEM [ cops)
; LIMITING CONDITION FOR OPERATION tco J.J.4 dE:FF:h Two independent Boron Dilution Protection System (BDPS) subsystems '
shall be OPERABLE. APPLICABILITY: MODES 3, 4, and 5. ACTION: I Cond 4
- With one BDPS subsystem inoperable, restore the inoperable subsystem
, to OPERABLE status within 72 hours for within the next hour, ano at i Aeast once every 31 days thereafter, verify valves EV 1113. CV 0028J ' CW 8 *-fg."-en rv am . ==? cv er.; are closed --; --- =6 4- rrritirr =*- 4 Co.,a D .M With both BDPS subsystems inop hin I hour, and at least once every 12 hours thereafter:
,R Verify valves CV-1113, CV-0420, CV 04r. CV Ot:1, .ad CV 0435 are closed) em rec" ed ' ::itha**l, and E Verify compliance with the SHLITDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable.
Qf4p C M "14WES"T 7.l"I M ) i 4 t l f 4e M he BDPS Flux Doubling signals may be blocked during reactor startup, . Acbf*These valves may be opened on an intermittent basis under administrative Mo4e control when required to support plant evolutions. BRAIDWOOD - UNITS 1 & 2 3/4 1-13a Amendment No. 40
M . . CTS INSERT (S) . SECTION 3.3 . . L.C0 3.3.9 INSERT 3.1 13aA (M4 ) CONDITION REQUIRED ACTION COMPLETION TIME l C. Two trains inoperable C.1 Close and deactivate 8 hours
- due to an unisolated unborated water unborated water source source isolation from the refueling valves.
water storage tank. I l 1 l l i { l Revision A l
- -- . _ . - . _ _ _ _ ~ _. .- - _. -- . ..~ . - . --- .._- -..
6 Men 3,( Adciresur.ed m Sechton 3.3 @ 3,7.7 See Doc kr sedion 3 3 REACTIVITY CONTROL SYSTEMS 4 SURVEILLANCE REQUIREMENTS
~
4.1.2.7 Each BDPS subsystem shall be demonstrated OPERABLE: j
- a. JOL least once per 12 hours by: i 1
j l 1 8
- 1. Verifying that its associated nuclear instrumentation source
- l
. range detector is DPERABLE and indicating greater than or equal j I to 10 counts per second.
i
- 2. Verifying that all reactor coolant loop stop isolation valves 1 are open, and -
- 3. Verifying that at least one reactor coolant pump is in
{ l operation. i ~ I
- b. At least once per 31 days by verifying that each valve (manual, I power-operated, or automatic) in the flow path that is not locked, j j sealed, or otherwise secured in position, is in its . correct position. i i
l l
- c. At least once per 92 days by verifying that the BDRS Alarm Shtpoint i is less than or equal to an increase of twice the count rate within a 10-minute period.
- d. At least once per IB months when shutdown by verifying that on a i simulated BDPS Flux Doubling test signal valves CV-1120 and CV-112E l i open and valves CV-112B and CV-112C close in less than or equal to i 30 seconds. l l
l I l l
~
BRAIDWOOD - UNITS 1 & 2 3/4 1-13b Amendment No. 40 l i
- Ico.3.3.9
- Scc h 3.1 i REACTIVITY CONTROL SYSTEMS l SURVEILLANCE REQUIREMENTS 16K3 Each BDPS sWsystem shall be demonstrated OPERABLE
1 At least once per 12 ho s by:
- f.
- SR 3.3 A i Nor l'INsm 3.1-13bA lu ,
i 5% 3.3.9 i 2. Verifying that its ssociated nuclear instrumentation source l ! range detector is OPEr.ABLE and indicating greater than or equal 1 to 10 counts per second. l SR3.3,9,3 E' Verifying that all reactor coolant' loop stop isolation valves j are open, and i SR J.J.9 2 .W. Verifying that at least one reactor coolant pump is in , operation. ! SR A.3?l. 5 X At least once per 31 days by verifying that each valve (manual, i power-operated, or automatic) in the flow path that is not locked, j sealed, or otherwise secured in position, is in its correct position. ! SR 3.33.6 g. At least once per 92 days by verifying that the BDPS.Alare Setpoint
- is less than or equal to an increase of twice the count rate within
- a 10 minute period. reau +, so
- W c.nm+pnA.C (ma aAl ne [24
} S R 3.3.9.8 d! Atleastonc'eper18 mon".h_swhen_shutdownbyvehifyina_'thatons/ i simulatedlBDPf Flux Doutf ing testlsional valves >CV-112f and CV-117t1 4 Toper}/and valfes CV-112Vand CV-11/C close An less th46 or equal go J ! (30/,econds.f ! LAs i 1 1 i i i BRAIDWOOD - UNITS 1 & 2 3/4 1-13b Amendment No. 40 A h
- - - n,
cts INSERT (S) SECTION 3.3 LC0 3.3 9 INSERT 3.1 13bA (L33 ) d j SURVEILLANCE FREQUENCY SR 3.3.9.1 NOTE ... Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours afte-
; entry into MODE 3.
i i 9 4 9 . l l l i i Revision A
. I
.._ m .. . _ . _ _ _ _ - _ . _ . . _ _ ..-_._ ___ _ . . _ - _ _ . _ _ _ _ _ _ . _ _
I _, Leo 3.14 as i j at REACTIVITY CONTROL SYSTEMS s si, ..s ....- .,.. . .. ~ . ~ , 3.I. 4 Rod Group Alignmerd Limth l- N { LIMITING CONDITION FOR OPERATION
- +
j LCO 3.1.6 All full-length shutdown and control rods shall be OPERABLE and 4 positioned within i 12 steps (indicated position) of their group step counter demand position. ! A5
- - APPLICABILITY
- MODES and , i 1
j ACTION: !~ CONO A as With one or more full-length rods inoperable /idue/to beina' immovable) i R A A.t.t as k resulp of exofessive frictioff or mec,nanical/interfefence of to pe untrippable/ determine that the SHUTDOWN MARGIN require +' n h , RA A.t.2 ment.':: 1 :; ;;;u;n ..;.1.; satisfiedtwithin I hour and e in U - l HOT STANDBY within 6 hours. AS C Inser+ s. i- i4 A l A - j j cowo e 4 . With one full-lencth rod ippable/but indrable /ue to c/uses /l [gther thp6 addregsed by) TION af above,for misaligned from its h i group step counter oemana neight by'more than 212 steps (indicated ;
- position), POWER OPERATION may continue provided that within 1 j l hour:
rod s restored to tus in the bove l t. alignmen[t requir,ements or RABi.E
//fl
- 4. T ' rod i declar d.ino 'able an the.r 'inder cyf'the rod in.
gro with .inopprable are al gned topithin I
- 12 s eps of heinopgrabler while4aintainingther/ od M v ',
i seq ce and, nserti n limi of n: n 2.M/ The THERMAL P R l < lev shall cted pyrrsuant t' Spec , To'n'7T.7-fr / [ d ing subs /be res equent peration, or / 5=ac2c=Hek st% 4#
),
# B.u 4. The rod is declared inoperable and the SHUTDOWN MARGIN -
l i requirement of Specification 3.1.1.1 is satisfied. I PDWER j , OPERATIDN may then continue provided that: r aw z e,.,q g 7 ! RA 's .2 .e-) The THERMAL POWER level is reduced to less than or equal ! to 75% of RATED THERMAL POWER--withiri the next' houri ano l j pthin ge he fo t isp/lowingf educedjto hoursjthe less/thanHigVNeutron/ or/ equal tp'85% Flux of TriTED h THE L PO,WER.l [ m B.3 M The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 . is determined at least once per 12 hours; , o j (*0;; Speciel Test L;eptiens Sp;;ific;tiens 3.10.2 and 3.10.3. ) h } Is . f i BRAIDWOOD - UNITS 1 & 2 3/4 1-14 Amendment No. 32 i
CTS INSERT (S) i SECTION 3.1 i l LCO 3.1.4 INSERT 3.1-14A (A7 ) , CONDITION REQUIRED ACTION COMPLETION TIME A. ... ... ,,, QB A.1.2 Initiate boration to 1 hour restore SDM to within limit. ' 1 1 INSERT 3.1-148 (A7 ) l . CONDITION REQUIRED ACTION COMPLETION TIME B. ... B.1.1 ... ... QB B.1.2 Initiate boration to 1 hour restore SDM to within limit. Revision A
LC.o 3.t A i REACTIVITY CONTROL SYSTEMS i } LIMITING CONDITION FOR OPERATION ACTION (Continued) @ RA B.4 4 A POWft distpibutionsmap is/obtaiped froar the rr#vable) gg g,y Linen /a rintoAnrsfand F (Z) and F" are verified to be within their limits wi hin 72 hours; and g RA8.(o 4) A reevaluation of each accident analysis (;f Th 0.1 Ilis i performed within 5 days; this reevaluation shall confirm l that the previously analyzed results of these accidents remain valid for the duration of operation under these i . conditions: l Cowol
'Cesa0 0 +.
fo % ia beia m.oe s wim G hours) With more than one full-length rod /trippaD/e but/inopet'able dub tc/ O h s causey other Anan Eddrested Dv ACMON a. Above/or/ misaligned from GONp 47its group step counter demand height by mors than i 12 steps (indicated position), POWER OPER ON may continue ovided that:
- 1. Within our, the rem der of the rods the group (s) with l
Wm 3 5-59,1 the i perable rods e aligned to wit n 12 steps of the i ino rable rods w ' e maintaining t rod sequence and g i ertion limit of 7 6m < 3.1-;.- hall be rest 'cted pursuant . he THERMAL POWER lev
~
- 3. 3.6 ring
.=ubsequent eration, and '
gg, 4
- 2. The in rable rods shall e re orei n & mAB status within
- 72 h rs.
l {0ther se,!beinHOTSTANDBYwithin6 hours. 4 l SURVEILLANCE REOUTREMENTS ' sR 3.hu.) ! . A-*-*-+-e The position of each full-length rod shall be determined to be L49 i within the group demand limit by verifying the individual rod positions at least once Der 12 hours A/ cept duringAlme Intervalywhen the rod p6sition j devigtion mogitor is ino6erable. ther/ verify the orhuo oositions Et least on
.oer/4 hourJc )
, SR 3.1.4.1.
.' n Each full-length rod not fully inserted in the core shall be determined OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.
J 2 BRAIDWOOD - UNITS 1 & 2 3/4 1-15 AMENDMENT NO. 74 e 4 6 0 e
. = - .. . . . . . - . .-.
CTS INSERT (S) SECTION 3.1 . l LC0 3.1.4 j INSERT 3.1 15A (M,) CONDITION REQUIRED ACTION COMPLETION TIME I D. ... D.1.1 Verify SDM is within
. 1 hour .
the limits specified
. in the COLR.
QB D.1.2 Initiate boration to 1 ' hour restore required SDM i to within limit. MD
~
O.2 ... 4 Revision A
& 3, to TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE 4ULL-LENGTH ROD Rod Cluster Control Ass Insertion Chapacteristics.
Rod Cluster Control Assembly Mism i nt. Loss of' Reactor Coolant from il R red Pipes or from Cracks in' Large Pipes Which Actuates Emergency re Cooling System. Single Ro' Cluster Co 01 Assembly Withdrawal
^
full Power. Major Reactor Co ant System Pipe Ruptures (Loss 'of lant Accident). Major Seco ary Coolant System Pipe Rupture. ! Rupt e of a Control Rod Drive Mechanism Housing (Rod Cluster Con el ' A ably Ejection).
)
I 6 9 BRAIDWD0D - UNITS 1 & 2 3/4 1-26
-__ - --- - ..- . . - .- .. - _ . _ . -. - _ ~ . - .. -. . - . _ _ _ _ . _ -
g LCo 3. l . *t L C. O 3.l.9 3.1 REACTIVITY' CONTROL SYSTEMS
- .L7 POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 1
l LU ~ L~l a L12) The Digital Rod Position Indicatierr System and the Demand Position * *
- _ Indication System shall be OPERA 8LE(;nd
- :::ti: .
- f :: : :"' : th: ::ntr:: - ,d loosittene .5 0.5 . ; ;; ;te 3.
i LA APPLICABILITY: MODES 1 and 2. OriyBy CImer+ 3.i-in ) I"' "' ACTION: c.oND A L Ca@ 4 g / @ cap
+ With(a maximum of ana) digital rod position indicator per ~ inoper-coND E able either:
Lei L Determine the position of the nonindicating rod (s) 'indirectl by the movable incore detectors at least,once oer 8 hours a j rimmeata y after a motion g the n indica 'ng rod wh' ' excee 24 steps one dirpftion s ce the
,of stdeterm*ation) e rod's p tion A r Q' A,2 +.
' Reduce THERMAL POWER to less than 50% of RATED THERMAL within 8 hours.
CMC 9 -b: With a maximum of one bank demand position indicator inoperable either: p f y g
$h.hl,; -h Verify that all digital rod position indicators for the affected gg g , ,2 bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the' bank are within a maximum of 12 steps of each other at least once 'per 8 hours, or ER p,2 e. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours.
t In er4 s. i - n e_ .' > ceuo p a SURdEILLANCEREQUIREMENTS M E ' i'l 3.1. 2. 2) Each digital rod position indicator shall be determined OPERABLE by verifying that the Bank Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours xcept ring time in rvals wnen Tne a position aeviftion alarm isjnoperg ble, hen compare t e Demand Positi Indication Systen and the Diaftal Rod / osi ion Indicatio System at least nce per 4 hours./ BRAIDWOOD - UNITS I & 2 3/4 1-17
-y .
4 CTS INSERT (S) SECTION 3.1 LC0 3.1.7 INSERT 3.1-17A (Au) ACTIONS NOTE Separate Condition entry is allowed for each inoperable Digital Rod Position Indicator (DRPI) and each demand position indicator. INSERT 3.1 17B (Mn ) CONDITION ' REQUIRED' ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion-Time not met. l l 4 Revision A
. - . . .- - . . . ~ . - _ - . - . ...... - .- . . . . --- .
i i- CTS INSERT (S) . SECTION 3.1 k LCO 3.1.7
- INSERT 3.1 17C (L )
j CONDITION' REQUIRED ACTION COMPLETI'ON TIME - 1 B. More than one DRPI per B.1 ... ...
; group inoperable for l . one or more groups. AND B.2 Restore ino)erable 24 hours DRPIs to OPERABLE j status such that a 3
maximum of one DRPI j per group is
- 4 inoperable.
i
~
4 . l
- u j I l l Revision A
l l lC.O 3.i.'1 i JVITY CONTROL SYSTEMS POSITION ATION SYSTEM - SHUTOOWN LIMITING CONDITION F0 SPERATION / a 3.1.3.3 One digital rod position ind ha or (excluding bank demand position indication) shall be OPERABLE and casrsble s of determining the control rod position within i 12 steps foryc'h shutdown 4r control rod not fully inserted.
/ N l qAPPLICABILITY: MODES 3,* g 4"# and 5*#. '
ACTION: With op les5 4han the above required position indicator (s) OPERABLE, immediately tfe Reactor Trip System breakers. ' l SURVEILLANCE REQUIREMENTS
& 3.L71
.~ ,
(4.1.3.2; Each of the.above re' quired digital rod position indicator (s) shall be determined OPERABLE by verifying that the digital rod position indicator agrees with the demand position indicator within 12 steps when exercised over the full-range,of rod travel G . ;;m m;e per 10 pilo r m d.r'. M CA O f y ei.OJ. Q' oNr ecni fcocval of it'd . rcO NTI. Cods p
"With the Reactor Trip System breakers in the closed,40sition.
4
,SeeSpeciapstExceptions5,e(4fication3.10./
BRAIDWOOD - UNITS 1 & 2 3/4 1-18
' Lco31A REACTIVITY CONTROL SYSTEMS h . ROD DROP TIME LIMITIN'G C0kDITION FOR OPERATION d
ER 3.l.4 3 @ 6 The individual full-length shutdown and control rod crop time from _the fully' withdrawn position shall be lens than or saual tol2 4/secon# t t 7and Upit 2 C erNle 1)/and 2.7 secondsl(U/ fit 1 C9cle 3 4nd_ i 4 pnit 1/ ycle fter:/ Unit 2/tycle I and a from ceginning of decay of stationary gripper Jcoil voltage to dashpot entry w'th:
- a. T,yg greater than or equal to 550'F, and
- b. All reactor coolant pumps operating.
APPLICABILIT_Y/ MODES 1 and
- l. -
4 ACTION:
+ With the rod op time of any ull-length red termined to a eed 8 the above li it,. restore the rod drop time to'within the above limit prior to pr ceeding to MOD 1 or 2. / /
j
&. )dth the rod dro time within 1 its but detardnad with three/ d f .
/reactorcoolan pumps operatinless , operation maf proceed than or qual to 66% of pr6vi I THERMAL POWER s restricted RATED THERMA). POWER.
4 SURVEILLANCE REQUIREMENTS I SR 3.1. +. ?, l
'4.1.3.4] The rod drop time of full-length rods shall be demonstrated through l ceesurement prior to @entee criticality:
t. For all rods following each removal of the reactor vessel head,. 4
- b. For sp cifically affec d individual to s following any aintenance on o modification to he Control Rod rive System'whi could @
aff ct the drop tim of those specif c rods, and
+. Atleast,dnceper18mongs.
1 Amendment No. 23
- --- .....-- < , o 3/4.1-19
l 6,D B t. T
@@ 3.I REACTIVITY CONTROL SYSTEMS
. m ne M* I limilecl in ph ycicol int.erhon 1 SNUTDOWN93C RINSERTION LIMIT cic coecihed ir 4he Of'EJJPT'JMhr ^ 's LIMIT 4 RMPRT www LIMITING CONDITION FOR OPERATION 1 Lonks.
L.C0 3.1.$5 shutdown @M @ shall be fully withcrewr0 APPLICABILITY: MODES 1%) and 2$. ACTION: US A ( '(I 'd II h one or more shone b i s 'l^ -
# N +"
Withc: :e: :: er ene ehetee-n redR. t "e!17 w;therest., except for surveillance' 1 testina cursuant to Seecificetien 4.1.3.1.T), within I hour either: (wi6 bin 2 hourc,, r n a. i, .i.2
- .%4a
. u. ,, ,,4 % ,,+. inh the incer 4 ion i.a.,C RA A.2. ei 4 (fully withdm the red. er) ._cpeedie,d igagst.Aftig petir{
gf..[jit. Declare the rod to be inoperable and apply Specification 3.1.2.1. g coND S Wdli fie:[uired Adich cand cicsociatec( Con @leboo Time no+ n.c+, , Le ni t.locle. 2 wnb all cor4rol bankr. fully imerieci ' vM lin i fo hour , SURVEILLANCE REQUIREMENTS
. . -~-
sa 3.l.5.1 g {g. Le . . with , ne l (".1.3.!R Each shutdown @ shall be determined (fully .i u.e, - J. O -
"* A
+: /Within 15 minu s prior to wit rawal of any r s in Control 2
Bank A, 8, C' r D during an proach to reac or criticality, nd f b At least once per 12 hours nhae==ftar? i AppbcoLiity ( "se 3pecie: Test E-cestiene ;pec;r cet;en. 3.10.3 ene 3.10.3.) (With " g gr;:::r th:r. ;r ;;ee t; 1.3 ,Q ' h l.Aq ce) bank not fulli inStAul i
- 8RAIDWOOD - UNITS 1 & 2 3/4 1-20
4 s Ltc 31 G
- ~
3.l REACTIVITY CONTROL' 5YSTEMS CONTROL RCD INSERTION LIMITS . . 1 ' I LIMITING CONDITION FOR OPERATION ' senoenee one4 on.rnao simi+s )
- L
- o: 3.1.66 The control banks shall be limited iTi, phys,tcal.1 a ... . ;. ; ; :Js' 'e.ciWed '.
. s . . '.ui
.u
%d m mw.
'CENRdtiNr' a Ui.11TE REFOR m
A T,nsertion, as (:h:= ' ' APPLICA81LITY: MODES 1 and w 8. a ACTION: ' L C O N oi e. _With the control banks inserted beyond the above insertion limits,(exceot for'. p l surveillance testino nursuant to Specification 4.1.3.1.2t ' s
- cczo A M A A. 2. e. Restore the' control banks to within the limits.within 2 hours, or J 1 1'
i
-tr. Redu e THE L P0 f wit n2h rs to ess th or eq l to tha A\"3r 8
fr tion- f RATEV THER POWE whic i.s d,.by,t bank ~ itio ncFtAW eles C(L11o
~
ing/t. / / ihed i + lie. , 6,N,C i LiMI ftEFo , o r,./ CDHD C. c. Se in at'least . .- -.,within 6 hcurs. i .
- ( MODE 2 woh het6 't.0 J
eno A. RA A4.i ( In't e r + s.s - 2 A ri, omen s.i-aos) c,9 s
- RA A.i.z SURVEILLANCE REQUIREMENTS 1
] SR 3l.L.2 6 The position of each control bank shall be. determined to be within }. the insertion limits at least once per.12 hourslexcep during time yttervals ( i w n the Rod Jsisertion Limi larm is in
- j od positiopf at least o e per 4 houry.gerable, 1 t n verify thegndividuay i
L% C R 3.l.6.3 (Ince r + s.i - 2 i c. l } l i C -';ee ';eec i e : T a; Lc.e;;e..a ';eeci ficatie..a 3.10. 2 e..d 3.10. 33 h. l ' ApyhC.ch M y #With K gf greater than or equal to 1.
- 5 4
'BRAIDWOOD - UNITS 1 & 2 -
3/4 1-21' * . 4 4
. ~ . . , . , . . . . - - . . , n .. - - , . , _ . y
\
J M CTS INSERT (S) SECTION 3.1 i LCO 3.1.6 , INSERT 3.1 21A (M,) $ l CONDITION REQUIRED ACTION COMPLETION TIME i i A. ... A.1.1 Verify SDM is within 1 hour the limits specified , in the COLR. ' .i g A.1.2 Initiate boration to 1 hour restore SDM to within i limit, i a j ... 1 e Revision A
. . . _ - .. . . . _ _ _ . . -. -- _ . ... - - = - -
4 CTS INSERT (S)
- SECTION 3.1 LC0 3'.1'.6
~
' ~'
l INSERT 3.1 21B (M,) 4 A CONDITION REQUIRED ACTION COMPLETION T'IME 4 , B. ... B.1.1 Verify SDM is within 1 hour the limits specified
- in the COLR.
t QB B.1.2 Initiate boration to I hour restore SDM to within - j limit. MD B.2 Restore control bank 2 hours sequence and overlap
- to within ' limits.
i 5 i 1 Revision A i e
4 d CTS INSERT (S) SECTION 3.1 LC0 3.1.6 l INSERT 3.1 21C (%) ! SURVEILLANCE FREQUENCY
- SR 3.1.6.3 Verify each control bank not fully withdrawn 12 hours
- from the core is within the sequence and overlap limits specified in the COLR.
i d Revision A 4 E
+-
g tMt hah h ,i
- (7 . , or s o, .4 u%) )
h\_ o A- V 1 i n I h *
......,: ,.f. (29%,225) ' ~~ ~ ~~~
~ "" : /:(79% 229) :-
4 :-
- .:.-.: :-.=:.::-- - 3. : . . - - / .
1-
. --. m : = .: . .:. :-
200 ...:...... . .. . , f- .
. . ... 8ANKB, .
,3 . _- ; 180 ' ' :
.~.~~~~~.j_%"--'---+212'~--- .--
! =- n: . _ _- i . s
- . i.-~ (100%,161)'
, 160 (0%,1621:=M-t .- -- _
a
/
y ... .. -
,/ _ .=. . :
..... :g-...;.:_- -
g ::.a -
.- BANK C x 3 =.l -
r---1-- , , .: .
, ugtgr.n-
. ,/ ----- 7 3g 2 ...:=...
-s
- - * ..=-
/ --
.C s.
tl- . . :i 2idi==.=r=-[ ~~ . . . .. , ' , [ : 8-- - - gM f' r - s .., ,,. ,. .. g. -. W= :.g . . : . 2; :.:-- _. r/ . .
\
u .-- E.- -
!;-fib..-.
2 -
) a -
- ~
.: .: ! . E_.i(... BANK D ".i.
o
-(
O / ' i:iUI:5. - m 60 ::- ,-
/" * -
l
,. - . . I . . . . . . ; ._.
/ ........._.,i -
(0%,47)7:: _ ._
.t- -
40 I
/.. -
~
- i.:!fBC 2 -
-^/ .. .. : i:=- _--
-- - ._r '_
s. 20 ,,_ ,, ,: ; ,;_ g. , - ,
,f
- s. ,
.E;0iH::~? "(30%,0)k,~-*
-, '" )
'/ 0 0 20 40 60 0 100 REl.ATIVE POWER (Percent)
)
\
\
,s s FIGURE 3.1-1
/ ROD BANK INSERTION 1.IMITS VERSUS THERMAL POWER 1 ,
FOUR LOOP OPERATION f' p
-e._.. "
-A}'
BRAIDWOOD - UNITS 1 & 2 3/4 1~22 9 )
_. _ _._._ _.___.~.__ . _ _ . 4 I j Lco 3 2.3 I i @ I 3.1 M power 0157RIBUT10N LIMITS 1 j 3.2,3 0 '" Z. 2 AXIAL FLUX O!FFERENCE ' f h large+ 1x.aJ s s% % l A2 I.ws epaisia < -18. , l j LIMITING CON 0! TION FOR OPERATION MPNTIN6 G Pm h ooAT I l 4 _- . i -- indicated AXIAL FLUX DIFFERENCE (AFD) s' hall be maintained within the
<= E=atarget band (flux difference units) abcut the target flux differencer' l l
A a. Cycle 1 core average accumulated burnup of less th ' equal to and
/
- b. + 3%, -95 for Cycle 1 core ulated burnup of greater than !
5000 MWD /MTU
)
/
I . -12% for each subsequent cycle. b .) iN viat M E E N e
- than or equal to 50% but less than 90% of THERMAL 10W
- cated AFD is within the Acceptable Operation Limits % m ilL zu gylded andthe the indi-
- cumulative penalty deviation time does not exceed 1"6h M s =' Qra*=w h =
1 24 hours. c'hedsa *e. A PEMTIN() W.U5 Affe@ ) e ndit:sted AFD may deviate outside the . requirebarget band at BugEEP
--.m.,
==L
_ = ...-<,.,,m._ less than 50% of RATED THERMAr~POWERp :g;g ^.r.g cg:g;;.g
. .. .. , m ... . .,.,..............m , , , , , , ,
g ! ! ' APPLICABILITY: MODE I above 15% of RATED THERMAL P0WER N l ACTION: i Cerd A .aK With the indicated AFD outside of th required target band and with THERMAL POWER greater than or equa 90% of RATED THERMAL POWER, within @ nutes, either: y-4
- 2. Restore'the indicated AFD to within the required
- target band limits,.or l
CoM E ' t. Reduce T.HERMAL POWER to less than 90% RATED THERMAL POWER. Corvj C. X. With the indicated AFD outside of the equired target band for , more than I hour of cumulative penalt tion time during b AqQhours or outside the Acceptable Operation Limits 4 S:-- 1 and with THERMAL POWER less than 90% u a er an 50% of' RATED THERMAL POWER, reduce: A2. wM s > 1Hir OTERhTINb L3 tarts R EPoRy-i
- 2. THERMAL POWER to less than 50% of RATED THERMAL ruw a y.ith J 30 minutas, and _ .
eau o R H MAL r y r'5:: E::: W T::t E::: tier: E:i'icetie_2.10,2) 10 .o-S h 1 ' 2Tg urveillance testing of the Power Range Neutron Flux channel may be performed pursuant to Specification 4.3.1.1 provi _d t h_a J ruitent ar* AFD is maintained 4 within the Accectable Operation Limit q'_ y ; g 7 V A 1 of 16 hours operation may be accumulaten with the m octside 3 ine uir'ed target banc during testing without penalty deviation ,M ,h ERA' N OD - UNITS 1 & 2 3/4 2-1 04RRZMr wr:Affo}
Lcc .3.2.2'
- LIMITING CONDITION FOR OPERATION
! \ ACTION (Continued) ! c. indicated.AFD outside of th @]requiredtar or i i more than umulative penalty at' uring the l l previous 24 hours and w ess than 50% but greater' l than 15% of RATED TH ,t POWER shall not be g7 increased or greater thma-3M of RA POWER until ! l cated AFD is within thekabeweWequired target ban . _ SURVEIL. LANCE REQUIREMENTS
\
i i a m a=a The indicated AFD shall be determined'to be within its limits during , ', ' POWER OPF.PATION above 15% of RATED THERMAL POWER by: . l l Jl' Monitoring the indicated AFD for each OPERABLE excore channel:
.5R .3.2.3.1 S At least once per 7 days when the AFD Monitor Alarm is OPERABLE, I
- and
! P^ ' to la
'n and logging the indicated AFD for each OPER P s h i channel at er hour for the f rs and at least ;
i LA, once per 30 minutes ther , e AFD Monitor Alam is inoperable. E: ivvge values of the 1no w. W shall be l M exist durina. the interval Drecedina each on 1 tro m+ci li 5lThe indicated AFD shall be considered outside of its target band
- \ l
- when two or more OPERABLE excore channels are indicatino the AFD to be outside)
! ;the taraet band.1 Penalty deviation outside of the uired target band shall be accumulated on a time basis of: i (fb Abk 2 E. One minute penalty deviation for each 1 minute o POWER'0PERATION
- j. outside of the target band at' THERMAL POWER levels equal to or above~ i j 50% of RATED THERMAL POWER, and- -
i LLoAMe3 Ar. One-half minute penalty deviation for each 1 minute of POWER OPERATION ; outside of the target band at THERMAL POWER levels between 15% and l I 50% of RATED THERMAL POWER. 1 _5R3.1.3 SLA2 3.3 3 Note 7
= ~
/The initial determination of target flux difference following a refuel-j
! Iino outaae shall >e )ased on desian DredictionsJ Otherwise, the target flux 1 differenceJof ear 5 fl4RABG mariarvehamfieD shall be determined bv measurement i 7 at least once ==- 4 ; ;+rs- ~ "-- '--4: h 38 No a* M rtfuG3
*
- l
- .St 3.1.3 1 i em--4) The target flux difference shall be updated *at least once ner
- 31 Effective Full Power Days /by either determining the taroet m ~ J. ierence ) -
pursu m. R, S y m cation 4.2.1.3 above or T Mr .r interpolation between the [ most recently measured v=t: . . .u 6... ; : 9 +ad value at the end of the cycle 4 ilifa J
- . 4E+g.e4 j AX+kW eu.A u& 5 e.yi EM)M/
BRAIDWOOD - UNITS 1 & 2 3/4 2-2 AMENDMENT NO. 38
i i. LCD 3 2.5 j i-ha'a F.our. 'ts noF meJ ) A1 j FIGURE 3.2-1
- .cc I ^3:^.L FLL'X O!FFE"iMOE L!MIT' ** *
{ T"",0 TION Oi n"AT;0 T"i"".'.L 5 " i i a
,1 i
i i
/
l ( l Es g f
-~
i Oi E i $!i:.J s i <: 4 ) j mi :'-g3
- w I :
3" ;"2' 100 EjUNACCEPTABLElj.1t@) : 1 =*(11,90)E$CCEPTABLE ~ _ - 13 EP,ATION ~ -- -
+ ~ D. rERATION t :
SO _- { _-_ I . r !? i(
=
l _-- _ 00 _ 5liiACCEPTABLEj f0PERAh0N t _ j (31.50) - (31,80) I ! 40 l~ i l i 20 l / l ' ! 0 - t - 40 , 1 30, 20 10 0 10 20 30 40. W r i i j FLUX DIFFERENCE (All 5 ' l l,
% _%.% v .v -
RAIDWOOD - UNITS 1 & 2 3/4 2-3
i j Q Lc0 3.2.1 3.21 d '" '7 HEAT FLUX HOT CHANNEL FACTOR - ,
- LIMITING CONDITION FOR OPERATION g o> aperumimo+,d by FsM aad FTldh @**
O' IMS *MI l Fq (Z) shall be -trtier 2- tre ::: u n :::=:=". - _ _ Q
- [K(Z)] for P > 0.5, :nd (Unit 1 Cy: h 2 p
eny 3 ,e 9.o g ru,1. 1) . Fq (Z) < U..yJK(Z)] for P < 0.5. i p r p ~- r e en, r u n L . T s~n c ' .. _.:_ W K1,.i. 3 .2 i-
$ 9 P #ter; Urit 2 Cy;h 2 y ns < rc nn, rutvs, <- o < d Mt0d 7- = 3 r' j
b Where: ER &,= & p , THERMAL , g gno restw.
- RAT HERMAL POWER twa m,)3o,1,gg ,oerpuN gmts a v.a j is the fun'tio height location.
c t rrrrrrr her " r r i_ -2 Mor a ivan
- spee;f,y) in -mec otAAT. ret, kiMIX IE'd
~m-~
l APPLICABILITY: MODE 1. j ACTION: q !; With exceeding its limit: pg/g) [, Coact A s. Reduce THERMAL POWER at least 1% for each 1% exceeds the limit RA A.) within 15 minutes /and similarly reduce the Power Ranae Neutron / GJ ILA A.2.$ Flux-High Trio Setooints within the next@ hours: 85WEROPERATION G.nd A RA A'3 may proceed for up to a total of 72'hoursN subsequent POWER OPERATION may proceed provided the.0verpowir AT Trip 5etpoints Q have been reduced at least 1%.for each 1% g exceeds the limit; M Fels)&
'Id tify nd corfect thf cause pf the fut-of-finit cphditiph priofj iner asing,plERMAL 70WER ab6ve thvreduced limit /reoui/ed by / /
5 CTIO a.. absve:JTHERMAL POWER may then be increased provided id A R A 4.4j is demonstrated Ctwouen locoreAhaDDTnQ)to be within its limit. @, Cov,1 A No4e. . O (_T.uSERT .3.2 -4A hQ BRAIDWOOD - UNITS 1 & 2 3/4 2-4 Amendment No. 23 9
CTS INSERT (S) SECTION 3.2 ' l
'LCO 3.2.1 1 INSERT 3.2-4A (L,) l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. F#(Z) not within B.1.1 Reduce THERMAL POWER 4 hours limits, below the Allowed Power Limit (APL). -
68D l l B.1.2 NOTE 1 Required Action B.I.2 l must be completed if Required Action B.1.1 1s implemented.- . l l a.. Perform SR 3.2.1.2. Prior to. exceeding the THERMAL POWER l limit of Required Action B.1.1
- QB !
- B.2.1 Reduce AFD limits = 1% 4 hours l -
for.each 1% Fi(Z) i exceeds limit. 1 . I AND B.2.2 NOTE Required Action B.2.2 must be completed if-I Required Action B.2.1 is implemented. Perform SR 3 2.1.2. Prior to restoring AFD
; limits i
e Revision A 5 . 9 4
4 i l CTS INSERT (S) SECTION 3.2 LCO 3.2.1 l INSERT 3.2 4A (continued) (L,) .
' l I
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in 100E 2. 6 hours associated , Completion Time not ! met. l 1 l l 1 j 1 Revision A I p
s 1 I 4 e q J J . 4 4 r L [TNs Fnc,ure es wo4 Osed ) A n. 1
- - ~ -
p,$are. 5.2 _.2--_ - s 1 f 1 z _ __. ._ L,,,iks
=
l r. . . . . . e- _ . . _ . . . . . . _ ___ c. r,. .
. , =,
g y . _. .. .. .= s., a -. - . , e r e. =. . l4 , . _ .
)
. F. . . . _ . _
.c. .
- _y. .e. . g:.pg . _ _.._.qqpe - .
y" , ,ii ( f ,, ,, s i FE.. : I 4. . ._1.] j,.s.p. .. . . _.
. . .=. _. _ .e.,s. ... .p.,g .. a. =_qua. r- _ . . . . -
- w uo a
. . ,, w ., . . . . . . . . _ -- , , .
. "E .3 T T 7 I I _, _, .Pyg "a t J. t J
( t.=.._;- v. .=. N y g g gg 1:=...g.,nr.a.s_._- 1w_ - ! s,Sloi
,- g ,,_g, w - .o. .
w
.. 3 7- .
- a. 6
/ .-
# .__]. -T ".1.C- 7 3.. _ . .WEl*r Eg i, ,,,s _ . _ g3,._. _. . , .._ .
. _ _ _ __ *. _ _ _ _ ,.t..:rr.. _..
j lo
. -I . -=
!g n r.. - I ,=. . - - ..
. . .n
.- u a
.. . . .... mns -r m m. - - ..
l
/, [_. . . l . i- :j myp.m :is =HC J.wili"dl.W.jlud-E h ' 2 iEis.!' ""- . "
P4 i , f.**. d. .!....5..I . l . . . . * * ' ..b.kf.al5N.f. 'i :
~ . 8. 4A.F,[n.i.l,i,3
.a : T( .. M Fil m --
g t..?dNk .'. ."r[,[,
. ._ . .. . . . . - . - . _ . - T l 7 l ~~W '" .E h 4"*E N- t3=;d.;? I< F.
9;..W'W.r* *"" j i I g_r ,=_ : -1 ,a ,,,,,m :.=2 .. . __ .. r=n = ,w.,,,ir.
. . _... . s.w = .=..
- g. .,4.. __g g...u . .x.
.. _ . . _ n .y_.i._w
= .. _ . . . _ - w
. . ~ - -
,3 s t
1 e b 'i t : si.rJ 4MM a521*E.lF%iti!*.!!a8H*elmiiniG - i l l b=iu . =t l/ilin ilks &=='l"E*.~hd.+.:le dMf " =uTali.EEinE'n' se B_1.- , ,.3 . . . _ . . ,3. ..m , . _..- --,.=r-.,m___..i- :.r_--h.
. ._=. ._ =:ri = -
- s
)
, ., . _ _ - . . . . . . . _ z____.
- g ..
..._,...=. .
g I e o e n e \ 4 .n .e e as si e i ! = ' fr@d earnmuoN * (ZW
^
- \-L.C .
BRAIDWOOD - UNITS 1 & 2 3/4 2-5 - Amendment No.23 1 4 E
L(_o . 3.2 I 4 4 SR @ j POWER DISTRIBUTION LIMITS - f Replea.a e/ ~ JR 3.2.1.1 SURVEILLANCE REQUIREMENTS
-- 22 4 R 3.2 1.2.
i
- 2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2. 2 F,y shall be evaluated to determine if qF (Z) is within its limit by: I
- a. Using the movable incore detectors to obtain a power distributio i p at any THERMAL POWER greater than 5% but prior to exceedin 50%
! RATED THERMAL POWER following a refueling outage. The 24 our {. c letion time provisions of Specification 4.0.3 are not licable;
- l b.
Increa ing the measured F,y component of the power dist bution map j by 3% to ecount for manufacturing tolerances and fur er increasing l l the value SX to account for measurement uncertai iss; . l f c. Comparing the computed (F,f)obtainedinSp ification 4.2.2.2b.,
- above, to
- 1) The F,y limits for RATED THERMAL POWE (FR P) for tM appmpriate 1 measured core p1 es given in Spec ications 4.2.2.2e. and f. , I j
below, and
- 2) The relationship:
F,y = p, [1+0.2(1 ] l Where F*Y is the limi for fra tional THERMA'L POWER operation expressed as a fun ion of F RTP d P is the fraction of RATED xy THERMAL POWER a ich Fxy was meas ed,- j d. Remeasuring F xy ording to the following s edule: C
- 1. . When F is greater than the F,RTP limit for he appropriate meas ed core plane but less than the F l rela onship,. additional p r distribution maps shall be taken a d F c ared to F RTP nd F,y:
a) Within 24 hours after exceeding by 20% of RATED TH L POWER or greater, the THERMAL POWER at which F was st determined, or , b) At least once per 31 EFPD, whichever occurs first. e BRAIDWOOD - UNITS 1 & 2 3/4 2-6 AMENDMENT NO. 38
1 LCD 3.2..I POWER D_ISTRIBUTION LIMITS Repke w /
.sa m 1, sg, yn g
, SURVEILLANCE REQUIREMENTS (Continued) M N 32-M S R t I l.2. 1
- 2) When the F is less than or equal to the FxRTP limit for the
- appropriate measured core plane, additional power distribution maps shall be taken and F compared to F RTP and F at lea x
once per 31 EFPD. t
- e. The limits for RATED THERMAL POWER x (FRTP) shall bein withe -
2 limits rovided in the OPERATING LIMITS REPORT for all re planes } containin Bank "0" control rods and for all unrodde core planes;
- f. The F limit of Specification 4.2.2.2e., above are not applicable xy ;
in the followin ore planes regions as measur in percent of core height from the b tom of the fuel: 1
- 1) Lower core regio from'O to.15%, inc sive, i -
l 2) Upper core region f a 85 to 10 inclusive,
- 3) Within i 2% of grid pla reg ns (except VANTAGE 5 assembly IFM* grids) such that no or than 20% of the total core height in the center core region affected, and
- 4) Core plane regions wit ni of core height (* 2.88 inches) about the bank deman osition the Bank "0" control rods, L
- g. With F exceeding F the effects of on Fn (Z) shall be x
evaluated to determ e if F9 (Z) is within s limits. 4.2.2.3 When Fq (Z) is m sured 'for other than F,y determ ations, an overall measured qF (Z) shall obtained from a power distribution m and increased by 3% to account fo manufacturing to'lerances and further inct sed by 5% to account for measu ment uncertainty.
/
/ -
/IFM-IntermediateflowMixer BRAIDWOOD - UNITS 1 & 2 3/4 2-7 Amendment No. 23
. _. . - . . . .- = - - _ .. - - . _ _ _ . . _ _ - . . - - . . . .
l l
~
1 l
\
CTS INSERT (S) . I SECTION 3.2 ~
- i LCO 3.2.1 INSERT 3.2 7A (L,)
SURVEILLANCE REQUIREMENTS NOTE . During power escalation at the beginning of each cycle. THERMAL POWER may be ' increased until an equilibrium power level has been achieved, at which a power distribution map is obtained.
- 1 SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify Fj(Z) is within limit specified in Prior to. !
the COLR. exceeding l 75% RTP after l each refueling g I Once within , 12 hours after achieving equilibrium , conditions-after exceeding, by a 20% RTP. the THERMAL POWER at'which Fs(Z) was last verified E 31 Effective Full Power Days (EFPD) thereafter (continued)' Revision A
1 CTS INSERT (S) SECTION 3.2 LC0 3.2.1
- INSERT 3.2 7A (continued) (L,)
- SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.2 NOTE If Fs(Z) measurements indicate Fj(Z) maximum over z K(Z) . has nereased since the previous evaluation of (Z):
- a. Increase Fs(Z) by the appropriate factor specified in the COLR and reverify F5(Z) is within limits sp?cified in the COLR: or
- b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive flux maps indicate FE(Z) i maximum over z K(Z) .
has not increased. Ver'ify Fs(Z) is within limit specified in Prior to the COLR. exceeding 75%'RTP after each refueling 6 tid (continued) Revision A O
CTS INSERT (S) i SECTION 3.2 2 l LC0 3.2.1 l INSERT 3.2 7A (continued) (L,) SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued) ' Once within.
'12 hours after
, achieving equilibrium conditions after exceeding, by a 20% RPT. the THERMAL POWER at which F#(Z) was la'st verified AND 31 EFPD thereafter p
Revision A ,
- - _ _ - _ _ _ - . - _ - . _ . . -. - . - .. ..... . - ~ _ _ _ - . - - . . . - . - - . _ - 3.2, POWER DISTRIBUTION LIMITS LCO 3.2.2.
. 3 2.7. = = 7 1 .'"" ; = - : t r"s NUCLE AR ENTHALPY RISE HOT CHANNEL FACTOR Lco 3.4. l LIMITING CONDITION FOR 0PERATION E3 lw&a ne laa somAM in N CotRJ
-.a ..<..- / Indicated
. . - ,Reactor
, . - . . . .Coolan".
. . . . System (RCS) total f[cw rate and)F", shall be y
[ a. 1) *RCS Total Flowrate 2 390,400 gpe,and) fAMremia b 4 1
- 2) ,,RCS Total Flowrate 2 371,400 gpm, and \
g g5ea poc. b Sun,3 4 ; e 1
- b. 5 Q [1.0 +f4EiEBl(1.0-P))(#g? y@ ,
~ _ UYW _ .
f,, .; 1. .. ^ " ". 2 ~'l ^ ""'fr Y."S*SE j fi';j_) h where: Pfa = ik it)
,ec,6 edin A Measured Fl? = % FE I:n ed i he optMu*n amrs g fie liiovaose incore y
@ detectors. Anappro$r shall then be ap a
uncerta f 4% (nominal) or greater to th ed va f F,", before it is compared to requirement
.... c... ;_ . .
7nav [n=v E=n ua7"nSur APPLICABILITY: MODE 1. ACTION: ' With (RCS total flow rate or) F",, outside the region of acceptable operation: 4 La breuiJ i. SutiL 3Al.
- s. Within hours either: See Doc. 6e Seeb 3 4. __
E. rwfRCS total flow rate and.E t; .;tth'- th: :h:'; ' i-i t: F CW A PA A. I X.
*e -
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER an CW A RA A.3 e---[t jpan or equal to 55% of RATED THERMAL POWER within m --mredu M hours. / SG . AMreswd in Sec4 .3 4 l. See Doc. 6, Sun 3.4.
),,'Applicable Applicable to Unit I and Unit ~2 until completion of cycle 5.
to Unit I and Unit 2 starting with cycle I 6. Unit 1 - Amendment No. 56 BRAIDWOOD - UNITS 1 & 2 3/4 2-8 , Unit 2 - Amendment No. 55
. _ - .. .. _= .. ._ _ . .
i u:0 5,4,I s.4 Reacrw- eoewr W4 ten (RcQ T0""" O!ST"!O'JTIO*' LI"'TS) 3A, t C/ 2.2 ) RCS FLOW RATE Cud:A; EH HA1.?i RISE HGT Cll",,0EL TACTOR) 11MITING CONDTTION FOR OPERATION
; Loo 3.4.1.c M MIndicated L= : n.:: n ::::: Reactor
.. ::r ::;rCoolant System
- ;;;r; usa. (RCS) total flow rate (and Fl, g
- g. [ 3 ,g #n.e e .r . . , ....m t_ ........r4_.___i _
, . , . , _ _ AEA c .. .,,.. m.. ,
. . . .m
; N M h Schon 12.2 b .
c 2) kCS Total Flowrate 2 371,400 gpm,and
- h. Fl, s 1.55 [1.0 + 0.3 (1.0-P)] for OFA fuel D
F,", s 1.65 [1.0 + 0.3 (1.0-P)] for VANTAGE 5 fuel where: Measured values of Fl, are obtained by using the movable incore detectors. shall then be applied to the measured value of Fl, before compared to the requirements, and ( P= THERMAL POWER ( RATED THERMAL POWER j 4 APPLICABILITY: MODE 1. ACTION: 4 With RCS total flow ratefor F,",)outside the region of__acceptable operation: _ 1 (_ _
. r Addrt.eed 'en A4.** .I.2. A Within 2. hours either: ) Sc.4 Do c G e Q : ,w 5. 2 cono A E.
Restore RCS total flow rate (and F",)to within the above limits, or 4080 B E' ReduceTHERMALPOWERtolie:: [redoc;th: thr. SON ef Pf.TED "EP?f.L POE!EP. r.O (thr**r :g:;;j to 55% ef-EATCO Tj!"REL 70WERJwithin the kope. A. 2
..pplic;bi: : ,'Applicabic to Wit : Wit 2 end hit 2 ;ntil ;;;pl:ti;n ;f cycle 5.
- nd %it 2 storting with cyci; 0 .
BRAIDWOOD - UNITS 1 & 2 Unit 1 - Amendment No. 56 3/4 2-8 Unit 2 - Amendment No. 55
- Lco 3 2.1 j POWER DlSTRIBUTION LIMITS -
LIMITING CONDITION FOR OPERATION l l ACTION (Continued) d )
- (=l A LA Al tr. Within 24 hours of initially being outside the above limits, verify.
{ ttnrouan incore "luf waind and RC5 total flow rate ca=a=risonithat ] thecombinationofFhfandRCStotalflowrate[arerestoredto 1 Q&< within the above limits./or reduce THERMAL POWER to less than 5% of) ' { / RATED THERMAL POWER within the next %Ao'urs; and / . i s: fl ntify d correct the saute o the o -of-1) tit naitioff priori
- incre sing TH5HMAL PQWER ab e the educetVTHE L POWER lia W 1
- 5 i aui by ACT10N a.2/aad/o b. =1 .e:Isubsequent POWER OPERATION l A _may proceed provided that the combination'ofaF"Hfand (indicated RCS L a
rtotal flow rate /are demonstrated. (thfouaV ncore nn ein_dland ) , i f 44\ _ RCS total flow rate comparisonJto be with' n the c :::n ;7 ;;;;;t==
- Qlwh,nW f-0
- :;nti;;0;7t;; :;V 1 ;171;C1;.. 2.2.I prio to exceeding the fol '
- ' lowing THERMAL POWER levels: -- -
i
< AMrmed to Se&a 3 4.Id I
- M. A nominal 50% of RATED THERMAL POWER, .5y_boc_gc6n]
i 2: A nominal 75% of RATED THERMAL POWER, and X Within 24 hours of attaining greater than or equal to 95% of } %s A RA AA Age < RATED THERMAL M . ( TmMAL powut dm not hoe h be ruled +.) ! SURVEILLANCE REQUIREMENTS } hsW e 4 6 Rerm mJ Ah . A*
? . 2. L : ' n: ;== =n :: rrPM:- : = . c. := n: n-k i::M 'i I
- .5R 3.2 2J
=- -
The(conD1 nation of indicatea m totai riow rate anaiFy shall be sHa - m _ - - , i determined to be within the e ') f AM,e.Ja$ L3.4 L
' H :::i't::ti:n 3.2.3:1 g.
(Las .soecLJ io & COLR.; I h Prior to operation above_75% of RATED THERMAL POWER after each fuel ($ce bOC Q44 3 4. i loading, and
~
i ; j X. At least once per 31 Effective Full Power Days. ! 4.2.3.3 The indicated RCS total flow rate shall be verified to be within the 2 region of acceptable operation of Specificatiori 3.2.3 at least once per 12 hours whenthemostrecentlyobtainedvalueofFh,obtainedperSpecification4.2.3.2, 4 is assumed to exist. l 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL. j CALIBRATION at least once per 18 months. l l 4.2.3.5 The RCS total flow rate shall be determined by precision heat balance
- measurement prior to completion'of PHYSICS TESTS after each fuel loading.
! The 24 hour completion time provisions of Specification 4.0.3 are not applicable. The measurement instrumentation shall be calibrated within seven days prior to 2 the performance of the calorimetric flow measurement. Prior to-the precision
- heat balance measurement, at least two of the four feedwater flow meter venturis shall be visually inspected and, if fouling.is found, all venturis shall be cleaned.
! BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AMENDMENT N0. 38
- n. -, , , , - .--
P i cc_o s,4. ) ; j POWER DISTRIBUTION LIMITS - i hM[*hbb Q5es. poc. Fo fwH*, sA) r s.M i i " " - - ~ - LIMITING CONDITION FOR OPERATION /
~
i } ACTION (Continued) j . Within 24 hours of initially /being outside the above limits, verify { i through (incore flux mapping and)RCS total flow rate comparison . ' i t ombinationofFhand[RCStotalflowratearerestoreo i ' within above limits, or-reduce THERMAL POWER to less than 5% of RATED THE R within the next 2 hours; and/ l c. Identify and cor the i:ause of the out-ofpMaiit condition prior i to increasing THE R above the reduc'ed THERMAL POWER limit i required by ACTION a.2. '
/or b. yab; subsecuent POWER OPERATION
! may proceed provided that th'e i ination of F'H A and)indicatedRCS - ! total flow rate are demo ated, t ugh incore flux mappingJarid i RCS total flow rate comparison, to be w in the region of acceptable i operation defined..b[ Specification 3.2.3 p for to exceeding the 101-l lowing THERMAL R levels: 4 L j 8
- 1. An g inal 50% of RATED THERMAL POWER, ,
2 A nominal 75% of RATED THERMAL POWER, and l 4 3. Within 24 hours of attaining greater than or equal to 95% o ! l RATED THERMAL POWER. i i ! SURVEILLANCE REQUIREMENTS l t 1 (4:Y:H:T)(Tt: ;rni:i=; ;f i;nif t:: tin t.C.i r; ;;t - ;1i0:51: ., - l (. ThecombinationofindicatedRCStotalflowrate(andFN'~, j determined to ' *hQtheregionofacceptableoperati j Specification 3.2.3: Le
~
- a. r to operatioJL.abovt /S% of RXTEB-THE L POWER after eac.h fuel i
i a ( . t least once per 3'1 Effective Full 'ower P Days. M 81 G.2.2.D The indicated RCS_ total flow rate shall be verified (t: 5: - ith" the 2 f :;ter f cre;t91: :;r:tten:!5;::t't::tt:n2.2.qatleastonceper12 hours m2= e:==a r==t:y euix: a:= ;f %, cuiad pu :puif=taa 4.2.:.2,y 3
==: =4:1.,
.{4.2.0.4 in; "C0 tetel fh sc;iete nr indic; tere cell t,e e t,iected O e C"r~:L CALI""4TIO" et leest 10 n te./
g se.s.4.t.4 G-'F!EF) The RCS total flow rate shall be detemined6 ma _ =--- # ex = = = a ; = = =,es =* = m+w- ~
-..a b n#
cue.,7 ;, ,litl;; tin ;reli-isne of 0;G~i k;t' G t.0.3 ;r ;;t ;;;1i0:510. (Q=iph: n:nr;nnt insteunentat4en--sheWhe--sa14brated-w&tMn ::^;;; d yspor--tih gr t e p = fe- 2 = ef t s 2 , r4 = t-4: <! = = = = = t. -i= u te p i:4-hnt hl:=: =:=::xnt, :t 1:=t t= Of th: ? = r f:: i:ter '! = = t=* vent =i: thal-1-be vi=:lly ' :peeted :-d, f: l' ; i; frend, Ol' ;;;teri: ) Lt,, Qhli 5 :10:=d.f BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AMENDMENT NO. 38
f k i - Lco 3.2.4 i O 3.2 POWER DISTRIBUTION LIMITS
.3.2 .4 (= - - - _ = _ OUADRANT POWER TILT RATIO i
i 1 LIMITING CONDITION FOR OPERATION I i k0 3.2.4 . GiiBiiB l ! THERMAL The QUADRANT POWER.T POWER TILT RATIO shall not exceed 1.02(above 50% of
- i i
! - - A cel b 6 I;hv APPLICABILITY: MODE . , ACTION: j i As
)Hth the QUADRANT POWER TILT RATI0r----- ---
be4 wM.x l..c.O Q
-- ---- r - u r = -
I . j C..J A RA A.2. J. i Calculate unt ei he . the QUADRANT POWER TILT RATIO at least once per e gg % f 12 hwu and rulue THER. mat %te 13% bRipT nenarh 19. & Q PTR > f. on . ] 4 it[ ! Coad . B .b)' i THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER. I, .
- X Within 2 hours either
~.
- IA ** "'
C J A.RA 4.1 by . Reduce THERMAL POWER at least 35 from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in
- i. excess of 1.i-; :n :r:
[ Repte. W/.Tusu 4 ) g
.m . . . . . . . . . . . . . . . ,,n:::
' ~ ~ ~
_ . . . : ...2:. =. n :=;; n;.tr;al l ~~~'~'""i
~ - ~ ~
~~ ~~ ~ ~~~~~ ~ ~ ~
j / .3. 2.- lo A fy y;7; g ;;,;; ;;,; y;g ;,7 n g ;;;; - ;;
- ;; ,,;;;,;a ;;; ;;;t) d th'- 2' 5
- r:,
t LN 'l c" r :::::dir: tr. 'f=itior reduce THERMAL i 0ME POWER to less than-50% of RATED THERMAL POWER within the next q hours pna r uce F^~^^r Na Neut n Flu M19ft 19 i ( 'bespo s to ess o equal 55% RAT THER withi the ext 4 urs and 1 A 'I nd correct the cause of the out-of-limit c j Cc.nd A RA A,4 prior to inc THERMAL POWER; subse 0PERATION. ! C.ncl A RA A.5 . above 50% of RATED T coed provided that the l i C ,J A A A A.g,} QUADRANT POWER TILT ve. ithin its limit at less once per h hours or until veri 1 . table at 95% er RATED THERMAL POWER. i h Reece w/ I'A15ER.T 3.2-10B N f ,... ...ci.. .... _ . .._._ . .-...---. .. . --._) Q j . BRAIDWOOD - UNITS 1 & 2 3/4 2-10 l i 5 ,
.. .. . . - . . - .~. ..-.- -. - - -. - - . - - - - . _ . . . - - - . . - . - . . .
i i I
- CTS INSERT (S) i SECTION 3.2 j LCO 3.2.4 )
INSERT 3.2 10A and INSERT 3.2 10B (L7 and Lu) CONDITION REQUIRED ACTION COMPLETION TIME l A. QPTR not within limit. A.2 ... M A.3 Perform SR 3.2.1.1 24 hours after ! and SR 3.2.2.1. achieving-equilibr.ium i conditions with ! THERMAL POWER reduced by Required Actions A.1 or A.2'
.E Once per 7 days thereafter
.M
'A.4 Re-evaluate safety Prior to arialyses and confirm exceeding the results remain valid THERMAL POWER-for duration of limits of operation under this Required condition. Actions A.1-and A.2 M
(continued) i 1 Revision A
_ _ _ . _ _ _ _ . _ . _ _ _ _ . _ _ . _ . . _ _ . _ . . _ . .__m . _ . _ . . . 4 CTS INSERT (S) - SECTION 3.2 l LCO 3.2.4 } INSERT 3.2 10A and INSERT 3.2 10B (continued) (L and Ln) 7 , I l
- CONDITION REQUIRED ACTION COMPLETION TIME i .
A. (continued) A.5 .N0TE Perform Required - Action A.5 only after 3 Required Action A.4 2 is completed. < Normalize excore Prior to detectors to exceeding the. eliminate tilt. THERMAL POWER j limits of
- Required i Actions A.1 and A.2 l
b!W , A.6 NOTES Required Action A.6
- must be completed when-Required Action A.5 is implemented.
Perform SR 3.2.1.1 24 hours after , and SR 3.2.2.1. achieving equilibrium i . conditions with
- THERMAL POWER exceeding the limits of Required. '
Actions A.1 and A.2 - 1 5 Revision A 4 ^
_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ . _ ~ _ _ - . . _ _ _ _ _ _ . _ _ _ _
._._m._
i i LCO 3.2.4-4 i POWER DISTRIBUTION LIMITS I LIMITING CONDITION FOR OPERATION 4
}CTION (Continued) 4 \ b With the QUADRANT POWER TILT RATIO determined to exceed 1.09 du to j misalignment of either a shutdown or control rod:
1 I Calculate the QUADRANT POWER TILT RATIO at least once er hour ' 4 until either: i 1 ! The QUADRANT POWER TILT RATIO is reduced to ithin its limit, or j
, b) ERMAL POWER is reduced to less than of RATED THERMAL
! R. j 2. Reduce TH L POWER at least 3% from TED THERMAL POWER for i each 1% of' icated QUADRANT POWER LT RATIO in excess of j 1, within 30 nutes; . l 3. Verify that the ADRANT POWER ILT RATIO is within its limit within 2 hours aft exceedi the limit or reduce THERMAL i - POWER.to less than of ED THERMAL POWER within the next 2 hours and reduce th P r Range Neutron Flux-High Trip b- Setpoints to less than equal to 55% of RATED THERMAL POWER within the next 4 hou ;
- 4. Identify and cor t the cau of the out-of-limit condition prior to increa THERMAL R; subsequent POWER OPERATION above 50% of RA ED THERMAL POWER y proceed provided that the j QUADRANT P TILT RATIO is verif d within its limit at least
- once per h r for 12 hours or until rified acceptable at 95%
or great RATED THERMAL POWER. p
- c. With the RANT POWER TILT RATIO determined exceed 1.09 due to causes o er than the misalignment of either a s tdown or control rod:
ce per hour
- 1. Calculate the QUADRANT POWER TILT RATIO at least until either:
a) The QUADRANT POWER TILT RATIO is reduced to withi its limit, or L b) THERMAL POWER is reduced to less than 50% of RATED THE POWER. BRAIDWOOD - UNITS 1 & 2 3/4 2-11 4
! I Q POWEk DISTRIBUTION LIMITS - Lco 3.z.4 { ! i b . ! LIMITING CONDITION FOR OPERATION i i
. z
- l AUTNHL (Continued) i l
l 2. Re HERMAL POWER to less than 50% of RATED L POWER . within 2 s and reduce the Power Range on Flux-High l Trip Setpoints less than or equal of RATED THERMAL.
- POWER within the ne hours;
- 3. Identify and correct cause he out-of-limit condition i prior to incre '
THERMAL POWER; quent POWER OPERATION
. above 50% TED THERMAL POWER may proc rovided that the QUAD POWER TILT RATIO is verified within imit at least e per hour for 12 hours or until verified at 95 reater l RATED THERMAL POWER. I
\
SURVEILLANCE REQUIREMENTS d=FPFR) The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by: .
.SR 3 1.4.1 ,
.a: Calculating .the ratio at least once per 7 days L.t; . tr.; e;;re. ;e' P1 m x . ;..;)
- h. [Cel;;letir.; th; 7;tt; ;t 1;;;; ; .;; ;;;r 1Z 7.;;r; durir.g ;t;;Oy ;tet;f SR 324.g , %)
_ :::r;ti:n .h:r th: :1:-- f: ' :::rd!;. ,- F 2 3 ,I " *"* 3 r- : . .- The.WUADRANT POWER TILT RATIO shall be dete eined to be within the gj_t'w-t7;;,';.; 5") of RATED THERMAL POWER with one* Power Ra iou c iannelJ
- (Innparablalby using the movable incore detectors t.o co ' re ia', t no lize i symme ic power ai riouyon, oppainea. from ty sets f fo s ri imb loc ions / a f -corr flux do. isAonsisMnt wi the ndic ed 0 RAN ' '
PO R TILT /RATIOJat least once per 12 hours.
,5k 3.2.4.1 N Me Mm a h cs afe.C h
BRAIDWOOD - UNITS 1 & 2
- 3/4 2-12
- AMENDMENT NO. 38
. . - - _ . _ - - . ,,- -e~ - , . . ~ - - - e , . - , -,m , _ , , , ,e, , .c .
LCO 3,4, l Secw 2.2. ,
- g.- _1 _ -- _
! POWER DISTRIBUTION LIMITS , Addressed k Sec6 3.4.1. ) 3/4.2.5 DNB PARAMETERS I
$ h bE*" 34-
=
1 i ! i LIMITING CONDITION FOR OPERATION l i l 3.2.5 The'following DNS related parameters shall be maintained within the 4 limits shown on Table 3.2-1:
- a. Reactor Coolant System T,,,, and
)
l b. Pressurizer Pressure. j APPLICABILJZ: MODE 1. ACTION: With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to less than 5% of i RATED THERMAL POWER within the next 4 hours. ? l l l SURVEILLANCE REDUIREMENTS i s. l 4.2.5 Each of the parameters of Table 3.2-1 shall be verified to be within I their limits at least once per 12 hours. i v i 4 T
\
e
\
BRAIDWOOD - UNITS 1 & 2 3/4 2-13' ,
. _ . . _ _ _ _ . _ . . _ . _ _ ~ . _ . . . _ _ . __.._._____.__._.___-___m . . . . _ _ _ . -
+
t-w 3.4. t S ec% *b .2. (3.4 NecTon. caos.W St.trut (Kas)) CO^.J:: 0 ;T:1007:0', L " TC) (.,,....-. . , . ..- - - . o r. v. .e. n. ,n 3.g . Kc.s rem are.fTiamsre-, ad R*"' Af'#"" L'.h @B) L'M+ LIMITING CONDITION FOR OPERATION C , The following DNB rel'ated parameters shall be maintained within the limits shown on Table 3.2-1:
' L40 3Mel.L K ' Reactor Coolant System T,yg, and L W 3 M.f.a. Fl Pressurizer Pressure. .
APPLICABILITY: MODE 1. . ACTION: MP h . WithanyoftNeaboveparametersexceedinaits' limit, rest 6retheparameter.to
.(m4p3 within its limit within 2 hours orfreduce THERMAL POWER to less than 5% of)
(RATED THERMAL POWER within the next @ hours.f SURVEILLANCE REQUIREMENTS gA 3.4.t.1 4 4
- 39. 3.4.1 3.
W) Eat.h of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12. hours. BRAIDWOOD - UNITS 1 & 2 3/4 2-13 l
t l 1 as TABLE 3.2-1 g i l
- l Die PARAMETERS PARAETER LIMITS i E
m Indicated Reactor Coolant System T
-t avg -< 591.2*F i g Indicated Pres.surizer Pressure
> 2219 psig* .
e. u~ r u D a E U' cp ua g oC1c. 5 n p;1 q g - O \ , n :t- ~ t
$~
N'l I W A 9
+ _ . < ,
- Limit not appilcable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL G F
'A POWER step in excess of 10% of RATED THERMAL POWER. +O T
.(A ,
N* ~ e 5 t w
- I
_ _ _ _ _ _ _ - _ - _ _ _ ~ . - . _ _ _ _ _ - _ _ _ . _ _ TABLE 3.2-1 E h DN8 PARAMETERS S O PARAMETER LIMITS E Leo y, q,r, b < 591.2*F Q Indicated Reactor Coolant System T,,,9
- Lco 3.4. l .4- Indicated Pressurizer Pressure > 2219 psig*
- e. .
-to i
b 4
'?
. Au.
gressure hs;gd3 fue f, , f'* Limit not applicable during*either a THERMAL POWER h ramp in W N#R " excess of 5% of RATED THERMAL POWIR per minute or a THERMAL (POWERste'pinexcessof10%ofRAlEDTHERMALPOWER. j LA E t0 fi
> (, ,.
h to -
~ . _,
1
+
CTS INSERT (S)
- SECTION 3.2
. BASES The Bases of the current Technical Specifications have been replaced in their !
entirety by Bases reflecting the format and applicable content of NUREG-1431 Bases and proposed Byron and Braidwood Technical Specifications. i 3
- I l l
\
J-1 ) i 4 i 4 4 P 1 I Revision A
, , , , -.. ,. . --- ~.,.s-,
.-- .- I LCO 3 3. I 3
f
- 33 6i9Ch INSTRUMENTATION F 5.l f"," .D REACTOR TRIP SYSTEM INSTRUMENTATION l .
LIMITING CONDITION FOR OPERATION ! Lco 3.3.1 As a minimum, the Reactor Trip System instrumentation channels ~and interlocks of Table 3.3-1 shall be OPERABLE. APPLICABILITY: As shown in Table 3.3-1.
- ACTION
As shown in Table 3.3-1. ' Acti. 3 &+e 4 kuseer J.3-iA h SURVEILLANCE REOUTREMENTS ! SR 9oTE l j AFB:F=h Each Reactor Trip System instrumentation channel c=c 'nte-":- a A4 the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1. ! SR 341.14 . N The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function ] shall be verified to be within its limit at least once per 18 months. l Each
'verifica on shall in ude at least pne train suc that both tr 'ns are verifie at least on per 36 month 4 and one cha nel per funct'on such that-all ch nels are ver fied at leas once every N times 18 mont s where N is he total umber of re ndant channel in a specif c Reactor tri function as show in the " Tot No. of Chan 1s* column o Table 3.3-1.
6 I
)
i i l l BRAIDWOOD - UNITS 1 & 2 3/4 3-1 AMENDHENT N0' 76 i i 4
+
f cts INSERT (S) SECTION 3.3 . LC0 3.3.1 1 INSERT 3.3 1A (4) NOTE . Separate Condition entry is allowed for each channel. t t l i i i I c + 4 i Revision A 6
(s.5. i -l J l I% Ae u4ed 4+ e. TABLEC.L: ) l t j REACTOR TRIP SYSTEN INSTRUNENTATION i e, 4%,3,r ! 1 MINIMUM f Re4 ered FUNCTIONAL UNIT h YOfAt-N9. (DF-CHANNELS j T TRIP NNELS CHANNE OPERAB E APPLICABLE' MODES - ACTION dwriTera q
- 1. Manual Reactor Trip 2 1 2 1, 2 47 g
, 2 2 3 *, 4*, 5* J6) . r. /c - - i 2:
- 2. Power Range, Meutron Flux
-(.
- a. High Setpoint 4. 2 3 1, 2 I $.. . .)/E.
- b. Low Setpoint 4 2 3 liff, 2 -
# .gp /E-6,4. Z Power Range, Neutron Flux 4 2 3 1, 2 g P/E-High Positive Rate 3,lo X. Power Range, Neutron Flux, 4 2 3 1, 2 E })/6 High Negative Rate g 81, .E Intermediate Range, Neutron Flux 2 1 2 l###, 4 F fE Source Range, Neutron Flux '
s: Startup 2 1 2 fff 4/ gg
.b. Shutdown *- 2 1 2 3*, 4*, $*. ,56 3 Lco J.1 9 .<' Shutdown ** NA 1 3**, 4**, 5** J5 D/G- ("#23D
(, Z Overtemperature AT 4 1, 2 5 h/E -
- 7. 9. Overpower AT 4 2 3 1, 2 A P/E-T.4.-9'. Pressurizer Pressure-Low l g
~
%,q(pAbove P-7D 4 2 3~ .T[k b *> b BRAIDWOOD-UNITSIk2 3/4 3-2 AMENONENT. NO. 72 ,4, .b. '
.w? i
-b -
~
f
__ . _ _ . . ._ ._ __ . . . _ . _ _ _ . ._ _ __ . . . _ . _ . . _ ._~ _ ( kw 3.3.1 - I TABLE t-t=t (Continued) , i REACTOR TRIP SYSTEM INSTRUMENTATION h<ju; red MINIMUM : FUNCTIONAL UNIT h -TOTAL .*J. tOF CHANNELS;
. CHANNELS TO TRIP CHANNELS OPERABL APPLICABLE MODES ACTION Cono
% b .MK Pressurizer Pressure-High 4 ~2 .'3 1, 2 # D/6 9 .H'. Pressurizer Water Level-High 3 2 1 # J/K GAnete(e)c.((Above P-7)) '
W Jr. Reactor Coolant Flow-Low g g a. Single Loop-(Above P-8) T 3/ loop 2/ loop in ny 2/1 op in each 1 E J/K ' operating op op rating loop
- b. TwoLoops(AboveP-7and/ 3/ loop 2/ loop in t / loop in each 1 y IX t i
below P-8) i >perating loop perating loop ,
\4 3r. Steam Generator Water Level- 4/sta. gen. 2/sta. gen. In 3/sts. gen. 1, 2 y bM Low-Low any operating each operaing '
, sim. gen.' sta. gen. l' X.. Underv e-Reactor Coolant 4-1/bu 2 3 ,1 g JMI WelaLPumps ( ove P-7)) (pc h i.) I'k _Hr. Underfrequency-Reactor Cool (4-1/busj 2 3 1 y Jfk . f Fade (,1 Pumps ((Above P-7)) (prb. gTurbine Trip ((Above P-8)) l
- a. Emergency Trip Header' dITralD Train 2/Tra 1- y'
[ PressureQerhid a nl6 L
- b. Turbine Throttle Valve . 4 1 1 p, LIM Closure (pu.4rsd .-
l r ; O' BRAIDWOOD - UNITS 1 & 2' 3/4 3-3 AMEN 0 MENT No. 44 t l f
. .- _. .. . - - . - . - . . - - . - .- . . - . - . . _ . ._ - .-. --- . .. .~ - .-
. \
3.'3. I - l . g n TABLE 4-3-1-(Continued) . . E REACTOR TRIP SYiTEM INSTRUMENTATION psred MINIMUM TOT *1 W. HANNELS CHANNELS e FUNCTIONAL UNIT - APPLICABLE z p CHANNELSJ TRIP OPERABLE 3 )b X. Safety Injection Input MODES ACTION M g from ESF 2 . 2 1, 2 X NIG e )).18. m Reactor Coolant Pump Breaker Position Tri 4 . fo M e6thbove P-D (per 4rai C/br R ; 2 1/br ker 1 E 3fM - per perati ng < 100
- i. eactor Trip System Interlocks
- a. reediate Range ,
y Neutr lux, P-6 2 1 2 2## 8
- b.
Low Power Rea ' { Trips Block, P-7 P-10,Inp 4
, 2 1 or , 8 P-13 Input 1 2 1 8
- c. Power Range Neutron - -
Flux,,P-8 4 3 1 8
- d. Power Range -
Neutron Flux, P-1 4 .,. 2 3 1, 2 8 i
- e. Tu I u se Chamber '
sure, P-13 2 1. l' 8 E17 Reactor Trip Breakers 2
~
g /lS.20'. 2 1 1 2 1 ~2 .tr O/P/G 2 3 4*, 5* 38' ' Ris 5 19 X Automatic Trip and Interlock Logic 2 2 1 2
-; 2
.sr N/G 2 3A, 4* , 5* .36 Rfs b '
17fl% #l. Reactor Trip Bypass Breakers . 2 1 1 W 0,* Jy* OlP/G , Ul _~ o
l CD 3.R,4 l Lt.o 3,3;\
; en u' % ' coi 4 .mr g.b .4 c9:g
. -~.T.Qh
' 9WlY * -! ' TABLE 3.3-1 (Continued) l ,
i Addre e sd 'ew 68<-+1 A F,3,I l TABLE NOTATIONS $se pg. far 6tcMeg y,3 i
*With the Reactor Trip System breakers in the closed position and the i
Control Rod Drive System capable of rod withdrawal. j **With Reactor Trip System Breakers in the open position. In this condition, source range function does not provide reactor trip, but does provide input i . to the Boron Dilution Protection System (Technical Specification 3.1.2.7) . I and indication. ! NBelow the P-6 (Intermediate Range' Neutron Flux Interlock) Setpoint. ! #N8elow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. i 9Whenever the Agactor Trip Bypass Breakers are racked in and closed for l bypassing a Reactor Trip Breaker. i ! ACTION STATEMENTS i . l ACTION 1 - With the number of OPERABLE channels one less than the Minimum l Channels OPERABLE requirement, restore the inoperable channel to i ' OPERABLE status within 48 hours or be in HOT STANDBY within the j next 6 hours. s j ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 6 hours;
- b. The Minimum Cha'nnels 0PERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1: and 1G75%
M A 2'N' < 4 [Either, THERMAL POWER is restricted to less than G - -- (of RATED THERMAL POWER (=d the ":=r P.::;;; ::tr:: rj = 7jp Nert. ' TS;;;; int i: r:d ::d te 105: th r er ect:1 to 95M ef PATED 5 l LT" ".'t "0"E" ri9'- t 5: r::f or, the QUADRANT POWER TILT RATIO gr. g. 2, y, 2 is monitored at ' east once per 12 hours per q% Specification 4.2.4.2. 4 ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL. POWER level:
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore'the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and
- b. Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL WER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER. BRAIDWOOD - UNITS 1 & 2 3/4 3-5 AMENDNENT NO. 72
__ - _ _ _ _ _ _ _ ~... _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ . . . _ _ l Lc0 3, 2 , 'i l l L.O 3.3,I (d 3a-U
,--~x. h p .h n:J.~ % - .,x u.yrp.y;q l
' M' ' " ~ TABLE .
. (Continued) i
! l 1 TABLE NOTATIONS g g 4 op j ( Ally twe.ch4) i M M ) *With theG;en br Trie L;ts Lrn L7; in th; c';;ad asitien .ad thd ; l
- tantrol oad Dr< ve System capable od rol withdrawa' , ,
or Trip System akers in tu n pos' tion. this cond n, l l f**WithRe sourc ange function s not provide actor trip, does prov input)i . . to Boron Diluti taction Sy (Technical cification) .2.7) ) . ( indiention.I l Fw%%e@ NBelow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. l i~neheG)fMBelow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoirit. LA F.,6wegg 9Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypassing a Reactor Trip' Breaker. hmmr 12-rA ACTION STATEMENTS M L2 ETY5fFT)- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours /or be in HOT STANDBY W1 thin the) yM Y'I y _}' .
' srt 6 hours. /
h
-{z.meJte 13-st 1 4 P.2 eff5iFB- With the number of OPERABLE channels one less than the Total Number of Channels./STARTUP and/or POWER OPERATION may proceed provided]
CM P f'- < fthe followina canditions are satisfied: l M The inoperable channel is placed in the tripped condition within i 6 hours; ' Co@ p ti,+e. X The Minimum Cha'nnels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification , 4.3.1.1; and 1 Addrewed in Se +iow S.2 c. Either, THERMAL POWER is restricted to less than or equal to. 75% g p g,,. of RATED THERMAL POWER and the Power Range Neutron Flux Trip m 2,2 Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours per Specification 4.2.4.2. EET HIP.B - With the number of chanaels OPERABLE one less than the Minimum Channels 0PERABLE requirement and with the THERMAL POWER level: 4 Ea,2 h k x Below the P-6 (Intermediate Range Neutron Flux Interlock) . Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the'P-6 Setpoint; and 4gg D 6 2,1 " M K Above the P-6 (Intermediate Range Neutron Flux Interlock) ' 4 F. 2,2 Setooint but below 30% of RATED THERMAL POWER,frestor M he) to incrgsing / Lv i (THERMAL POWEVabove 10% ofALATEDPOWER. THEinoperable g chapdl to OPERABJl g pg g (N Ett 11 -(C- ) 4 62 2 %A x aserer s.3- sc- 2 . BRAIDWOOD - UNITS 1 & 2 3/4 3-5 AMENDMENT NO,. 72
CTS INSERT (S) SECTION 3.3
. LC0 3.3.1 IgigB.T 3.3 5A (A3 )
CONDITION REQUIRED ACTION COMPLETION TIME B. As required by B.1 Restore one channel I ho0r from Recuired Action A.1 to OPERABLE status discovery of anc referenced by i i when two channels are two inoperable Table 3.3.1-1. -inoperable. channels ! .A.LD B.2 ... 1 1 i 1
- 4 4
i i e .o 1 t Revision A
CTS INSERT (S) . SECTION 3.3
, LQO3.3.1 INSERT 3.3 5B (3
_A) l CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 NOTE Recuired Action A.1 Performance of anc referenced by Required Action D.1 Table 3.3.1-1. may be delayed for up to 4 hours for surveillance testing and setpoint adjustment provided trip capability is maintained. Restore all but one 1 hour from channel to'0PERABLE discovery of status when two or two inoperable. more channels on the channels on the same Function are same Function inoperable b!!Q D.2 :.. Revision A
l i i CTS INSERT (S) SECTION 3.3 LCO 3.3.1 l 1 INSERT 3.3 5C (L4 and Lu) i CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 Suspend operations Immediately Required Action A.1 involving positive from discovery and referenced by reactivity additions. of two - l Table 3.3.1-1. inoperable ' channels AND l F.2.1 Reduce THERMAL POWER 2 hours to < P-6. ) F.2.2 NOTE Required Action F.2.2 is not applicable when:
- a. Two channels are .
Inoperable, or b'. THERMAL POWER.IS
< P-6. .
Increase THERMAL 2 hours POWER to > P-10. I e
. Revision A w - , ,
J l w mo., l Lco 3. 3,4 l - i
. TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued) l l i GE M R O- With the number of OPERABLE channels on- less than the Minimum , RA A2 Channels OPERABLE requirement suspend all operations involving ! I j gg_ positive reactivity changes. \g)
, u s e.n:r 3.3 - M , .
Ra H.2 GCMR ED- With the number of OPERADLE channels one less than the Minimum [ Channels OPERABLE requirement, restore the inoperable channel tol. DPERABLE status within 48 hours o tm t m the next ae"- :en the )
- Rh LI A4 AA ta+-C etr- tM t&=./ultn no caannels OPERABLE. immediately open
! M 414 ,'the reactor trip breakers M ad r, w m . g e ,b e m J q ! GCMBAA 'With no channels OPERABLE, immediately suspend operations invoivinal l Lt.0 7,3,4 AA E,1*--mositive reactivity additions And within I hour verify valves fLW f Leo 5,31 AA b.I ;- : L' 2:22- "! 2:22 CY 25 =: CY CC)are closed. Also,
' ithin I hour and at least once per 12 hours thereafter, verify I9 LC# 3 3 4 " D'# compliance with the SHUTDOWN MARGIN requirements of Specification l 3.1.1.1 or 3.1.1.2, as applicable.
U #'I % 1 n s.gr sa -05 2 M y,2) N With the number of OPERABLE channels one less than the Total Number i , 4 :r:;t awA M L,a of Channels./5TARTUP and/or POWER OPERATION may proceed provided) j n~a ' conditions are satisfied: ; conp t.ony K c.4, Wthe follow I c.ot9 ti g The inoperable channel s placed.in the tripped condit' ion within l 6 hours; and y l g 4 g , g _' --wnser is - 6 c-conP D Wet. X The Minimum Channels OPERABLE requirement is met; however, the c.vdP J tW'. inoperable channel may be bypassed for up to 4 hours for 40t4p L teht surveillance testing of other channels per Specification 4.3.1.1. N 1ess than th inimum Number f Channels RABLE, with (ACTION 8 - W hour deterni y observati of the asso ted permiss } 4 annunciator ' dow(s) that e interlock ' in its req ' ed state for the n tina niant e ition, or y Specific on 3.0.3. )
-u ns e.w 3 3 - G D 3 A
- With the number of OPERABL annels one less than the Minimum U "' Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hoursf or be in at least HOT STANDBY J
. (.DNp Q :. (within the next 6 hours:/nowever, one channel may be bypassed for Cup to 4 hours for surveillance testing per Specification 4.3.1.1, coNP N IM*.-7provided the other channel is OPERABLE.-
RA B,a GCME E- With the number of OPERABLE channels one less than the Minimum W ed 4 R.a Channels OPERABLE requirement, restore the inoperable channel to DPERABLE status within 48 hoursfor open the Reactor trip breakers RA CA g3g,,gLLq3,R6 63 +-(within the next hour. RA C GUMETD - With the number of OPERABLE channels less than the Total Number of coap p~ Channels.Joperation may continue provided]tiie inoperable channels are placed in the tripped condition within 6 hours. 73 0 [' MIM E
- T 5 3- s.F ] 4 BRAIDWOOD - UNITS 1 & 2 3/4 3-6 AMENDMENT NO. 72
4
, CTS INSERT (S) .
SECTION 3.3 LCO 3.3.1 INSERT 3.3 6A (L3 )
' CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and I.1 Initiate action to Immediately associated Completion fully insert all Time of Condition H rods.
not met. AN.Q I.2 Place the Rod Control 1 hour System in a condition incapable of rod withdrawal.
\
I i i Revision A l
3 j ' CTsINSERT(S) SECTION 3.3
- LCO 3.3.1 INSERT 3.3 6B (A3 )
CONDITION REQUIRED ACTION COMPLETION TIME J. As pequired by J.1 NOTE 3
. Required Action A.1 Performance of and referenced by Required Action J.1 Table 3.3.1-1. may be delayed for up to 4 hours for surveillance testing' i provided. trip
, capability is ;
j maintained. - l l Restore all but'one 1 hour from channel to OPERABLE discovery of status when two or two inoperable more channels on the channels on the same Function are same Function ! inoperable. , J.2 ... Revision A
1 I i- . i CTS INSERT (S) l SECTION 3.3 LCO 3.3.1 INSERT 3.3 6C (Aa) i j CONDITION REQUIRED ACTION COMPLETION TIME t 1 ) L. As required by L.1 NOTE
- Recuired Action A.1 Performance of.
i anc referenced by Required Action L.1 Table 3.3.1-1. . may be delayed for up
- to 4 hours for ,
surveillance testing
- provided trip. ,
capability is maintained. Restore al.1 but one 1 hour from channel to OPERABLE discovery of status when two or two inoperable more channels on the channels on the same Function are same Function inoperable. 9
.AR L.2 ...
e Revision A
i l 4 CTS INSERT (S) l SECTION 3.3 l LC0 3.3.1 INSERT 3.3 6D (A3 ) . i
, CONDITION- REQUIRED ACTION ~ COMPLETION TIME i
N. As required by N.1 Restore one train to I hour from Recuired Action A.1 OPERABLE status when discovery of-anc referenced by two trains on the two inoperable Table 3.3.1-1. same Function are trains on the - inoperable. same Function AND N.2 .. 9 9 Revision A
CTS INSERT (S) SECTION 3.3 LC0 3.3.1 INSERT 3.3 6E (Lu) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 ...
. ' associated Completion Time of Condition B E not met.
C.2 Initiate action to ' 6 hours fully insert all i- rods. g . C.3 Place Rod Control 7 hours System in a Condition incapable of rod withdrawal. CONDITION REQUIRED ACTION COMPLETION TIME S. Required Action and S.I. Initiate action to Immediately associated Completion fully. insert all
. Time of Condition R rods, not met.
AND S.2 P1aceRodControl I hour System in a Condition incapable of rod withdrawal. Revision A
l 1 i o i CTS INSERT (S) r SECTION 3.3 ! 'LCO 3.3.1 !
- 1
)
INSERT 3.3 6F (An )
- i CONDITION REQUIRED ACTION COMPLETION TIME '
l i i_ 0. As required by 0.1 Restore one train to 1 hour from i Recuired Action A.1 OPERABLE status when discovery of f - anc referenced by two trains are two inoperable Table 3.3.1-1. c-inoperable.. trains MD 0.2 ... CONDITION REQUIRED ACTION COMPLETION TIME P. As required by P.1 Restore one tria 1 hour from Recuired Action A.1 mechanis.m to OPERABLE discovery of anc referenced hy status when two trip two inoperable Table 3.3.1-1. mechanisms are- trip mechanisms inoperable. , AND P.2 ... Revision A i 4
. ___ _ _- ._ ._ ..-_. _ . _ .__ _. _._-__. __ . _ _ . _ _ _ _ _ _ _ _ - - . _ - - ~.
l CTS INSERT (S) SECTION 3.3 i LC0 3.3.1 INSERT 3.3 6F (continued) (A3 ) . l i i CONDITION REQUIRED ACTION COMPLETION TIME ! l R. As required by R.1 Re' store one trip 1 hour from Recuired Action A.1 mechanism to OPERABLE discovery of l
. anc referenced by status when two trip two inoperable l Table 3.3.1-1. aechanisms or two trip mechanisms -
. trains on the same or trains on j Function are the same i inoperable. Function l R.2 ... l l
l 1 INSERT 3.3 6G (M7 ) . CONDITION REQUIRED ACTION COMPLETION TIME G. As required by . G.1 Open Reactor Trip Immediately l Required Action A.1 Breakers (RTBs) and from discovery and referenced by Reactor' Trip Bypass of two Table 3.3.1-1. Breakers (RTBBs). inoperable channels AND. G.2 ... 0 Revision A
. _ _ . _ . _ . - __ _ ._.. __ _ _ . - . . . _ . ~ . _ . . . _ _ _ . . _ . _ . _
j . LCo 3.3.i 4 ?
. TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued) O 91 MM- y. WittLone of the diverse trip features (Undervoltage or Shunt) i (Tri > Attachment)) inoperable, restore it to OPERAB.E status i wit 11n 48 hours or declare the breaker inonerable and pply
- the requirements of b below. /The breaker shall not be
! bypassed while one of the diverse trio features is ! Cend O t&e 2 ._ _._ inoperable, except for'" ^ '-- - ----- '--1 for performing f , maintenance and testing to restore theN#1 verse trip feature to OPERABLE status.1 . 3, y 7 g,, .
- 0.o4 G X. With one of the Reactor Trip Breakers otheryise inoperable, j . be in at least HOT STANDBY within 6 hours;lhowever, one
- Reactor Trip Breaker may be bypassed for up to 2 hours for i Cod o Ndel sury.111ance testing per Specification 4.3.1.1, provided th d
other Reactor Trip Breaker is OPERABLE.1 4 i
"""" '" / Mith the Reactor Trip Bypass Breaker inoperable, restore the.
e CondC Ndels(ReactorReactor Trip TripBypass Bypass Breaker Breaker to bypass to OPERABLE status a Reactor Trip prior toIfusing Breaker. the Reactor Trip Bypass Breaker is racked in and closed for . .Ccn4 C / bypassing a Reactor Trip Breaker and it becomes inoperable, be in Ccnd R at least HOT STANDBY within 6 hours. Restore the Bypass Breaker , to OPERABLE status within the next 48 hours or open the Bypass '
- Breaker within the following hour.
2 i i i i ? l l l
- BRAIDWOOD - UNITS 1 & 2 3/4 3-6a AMENDMENT NO. 44
. "~ Les-a b-
- 4 J-K- '
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RAIDWOOD - UNITS 1 &'2 3/4 3-7 AMENDMENT NO.12 l
.un4 .n na ..~-.-a, - - + * - ,k-.- au n. a,.~a .c 4 ,.- w hu . e.21 s -a 1 2 4 +s+-aa ~--n - - - e, a. t-s-.- -Am .Aw . as s -no - a s, SecWa 3 3 l l
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9 9 I i 1 l i i h i
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i . BRAIDWOOD - UNITS 1 & 2 3/4 3-8 .- AMENDMENT NO.12 l ,
.- -_..m _ _ _ . - . _ _ - - . _ . . _ _ _ .- _ _ _.. _ ._ . _ . . _ - . . _ _ _ _ . . . _ - . . - _ _ - . . _ _ _ _. TABLE REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIREMENTS r SR irarr. ops .wly 4hr 4 41 'num6w h h,ir- 3 TRIP ACTUATING M00ES FOR l- ) se 3.3.l.1 .4 ANALOG DEVICE WHICH CHANNEL
} - => S R 3.3.1. 7 , e4c. . .. CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCF CHECK CAllBRATION TEST TEST LOGIC TEST IS REQUIRED FUNCTIONAL UNIT Manual Reactor Trip N . A .' N.A. N.A. 12- R(14) N.A. 1 , 2 , 3' , 4* , 5' 1.
- 2. Power Range, Neutron Flux -
- a. High Setpoint t-5 a- D(2,4?, 7- Q . M.A.- N.A. 1, 2 3- M(3, 4) 's .
4 A- Q(4, 6),/ lI- R(4, 5a) l 1", !
- b. Low Setpoint I u- R(4) 3-Q N.A. N.A. 2 N.A. 1, 2 !
g.hPower Range, Neutron Flux, High N.A. 88- R(4) 7- Q N.A. Positive Rate A3bPower Range, Neutron Flux, High N.A. 11-R(4) 7- Q N.A. N.A. 1, 2 - l Negative Rate E.4 Intermediate Range, Neutron Flux I- S 11- R(4, Sa) 7-Q N.A. ,M.A. 1", 2 l X.5 Source Range, Neutron Flux g,5 Ig4,Sb) 3,,hg N.A. N.A. 2", 1, 2 3, 4, 5 l l I.'bovertemperature AT i- S to- r-Q N.A. N.A.. X.7 Overpower AT I-S to-R 7- Q N.A. ~ N.A. 1, 2 l 1- S 10- R 7-Q. M.A. M.A. 1 l XJaPressurtzer Pressure-Low (Above P-7) 1-S 10- R 7- Q N.A. N.A. 1, 2 l J0fbPressurizer Pressure-High M.9 Pressurizer Water Level-High I- S ro- R 7- Q N.A. N.A. I r- r-(Above P-7) 8Ql
** u
** in a __
3/4 3-9 AMENDNENT'NO.44 BRAIDWOOD - UNITS 1 & 2
^
~
3.B. I-l . TABLE G fContinued) REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCL ! FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED , .lf.foReactor Coolant Flow-Low l-S lo-R ~7- Q N.A. N.A. I b ,
~
J3'.l(Steam Generator Water Level- i 1- S to- R 7-Q N.A. N.A. 1, 2 ! l Low-low J(.12Undervoltage-Reactor Coolant N.A. lo .R N.A. 9 - Q(10) N.A. 1 l Pumps (Above P-7) ' 15 D Underfrequency-Reactor Coolant N.A. fo- R N.A. 'i- Q(10) N.A. I i Pumps (Above P-7) JsJ5 Turbine Trip (Above P-8) , l
.a. Emergency Trip Header N.A. lo-R N.A. 13 - S/U(1, 10) N.A. I !
Pressure ;
- b. Turbine Throttle Valve N.A. fo-R N.A. 13- 5/U(1, .10) N.A. I ;
Closure R)foSafety Injection Input from, ESF N.A. N.A. ~N.A. . 12 - R N.A. 1, 2 - N .llReactor' Coolant Pump Breaker N.A. N.A. N.A. 12-R N.A. 1 [ Position ~ Trip (Above P-7) - ;
' ~
'" ~~
'19. Rea {or Trip Sys em Interlocks . !
- a. Intermediate Range Neutron N.A. R(4) R .A. .A. 2 !
Flux, P-6 y i
. Low Power eactor Trips Block, P-7 N.A. R(4) R N.A. N.A. Il K !
- c. Power Ra e Neutron Flu , P-8 N.A. .
R(4) R f N.A. N.A. I hl l - l . - _ . ..
. . . . . . - - .H .
BRAIDWOOD - UNITS 1 & 2 3/4 3-10 AMENDMENT NO. 44 1
. . - . - . . - . - . .. -.. . . . . ~ . . . - , . . . . ..- . - .
, 3.3.1-l .
TABLE @ fContinued) . REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REOUIREMENTS TRIP ' ANALOG ACTUATING NODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL . ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED / 19. R ctor Trip System Interlocks (Continued) / ~~T-d LowSetpoin[PowerRange Neutron F16x, P-10 N.A. . R(4) R ! N.A. M.A. 1, 2
/ ,/ j j j/e..TurbinefmpulseChamber/ N.A. / R / R N.A. ; M.A.
/
/ 1 l.
.e Pressure, P-13 / .... i
/
. 1 . .. . . . . .
261?fteactor Trip Breakers N.A. N.A. N.A. +- N(II) N.A. 1, 2, 3*, 4*, 5* MJ9 Automatic Trip and Interlock N.A. N.A. N.A. N.A. 5- N(7) 1, 2, 3*, 4*, 5* logic -
. jlflfl1 Reactor Trip Bypass Breakers M.A-. N.A. M.A. 12.-(15), R(16) N.A. 1, 2, 3*, - 4*, 5*
4 e e o 0.
~
W ion BRAIDWOOD - UNITS 1.& 2 3/4 3-11 AMEN 0 MENT NO. 44
, _ . . _ _ . . _ _ _1 i i j J,3,1-; Lc.o 3.3.) i i
TABLE 4:F:M (C.gIttinued) i l l TABLE NOTATIONS ' ! M"dCN /With the In:::t:r Tri; Syster bre:Le. lo J ...J uiel Control Rod Dri j ! System capable of rod withdrawal;. For au c a m w w in m N Nid.(c').MBelow P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. 1 Mnk(b)dMBelow P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint. l i If not performed in previous 31 days. ! SR33.1.13' M I S R 3 4.1,2 W Comparison of calorimetric to excore power indication above 15% of RATED i THERMAL POWER. Adjust excore . channel gains consistent with calorimetric cf l cower if absolute 4._._(5pegirig,,,un difference 4,v,4 ,,, noi, .ppi is kcreater
,';, y fy, ,than n ;, ,2%. , , n /The t,y previ ica:;g 2y ,, ;, jg
.y.2. ,
CH S.I.b yW) The initial single point comparison of incore to excore AXIAL FLUX SR 3.3.1'3 hTF DIFFERENCE following a refueling outage shall be performed prior to
- exceeding 75% of RATED THERMAL Power. Otherwise the single point
- comparison of incore to excore AXIAL FLUX DIFFERENCE shall be performed above 15% of RATED THERMAL POWER. Recalibrate if the absolute
[ difference 'is greater than or' equal to 3%. The provisions of ! Specification 4.0.4 are not applicable for entry into MODE 2 or 1. For the purpose of this surveillance, monthly shall mean at least once oer i j 31 pr:vt: ::: f Specific:ti:n 4.0.3I l har:EFPD.lThe2'heur::cetiontie n:t :::lic:ble. MM# l.h .(4) Neutron detectors may be excluded from CHANNEL CALIBRATION. ] e ..
- per) fMtial plateau-curver-shall -be measured-for-each. detecter. S'aheequenth A' "
j . pl:te: :;rv:: :h:ll b; Obt:ined. evehated-end-costared-to-the-inittal/ 4 m vess /f:r th: Int: x:di:t: R:ng: :nd P:.;;r n:n;; N::tr:n Fl;;; j
- d annel: th: previ:ica: Of Sp::ific:ti:n 4.0.t Or: net-eppli :ble for ~ ~
j ( .: ntry int: ".00E 2 cr 1. / i (5b)'With he high v tage setti g varied a recommended the manufalcturer,
- an itial dis riminator b'as curve s 11 be measur foreachdetector.}
i' Su sequent di criminator ias curves hall be obtai ed, evaluat d and n kcmparedto he initial urves. j j h : :.t e Jfr)' /I cer - Excere Calibrat4ony-.above-7-E% Of P^.TED TMEP".fi POWER. TheT ! previ;ien: ef Speci'ic:t-icn ' .0M-are-eet :;;lic ble fer entry inlop nuvu c .. ../ For the purposes of this surveillance, quarterly shall mean at least once per 92 EFPD. ns
, ,}
5 v., w. fi .(7 ) Each train shall be tested at least every . days on a STAGGERED TEST BASIS. A 31 (S) M:t " :d. (9) Surveil, lance in MODES 3*, 4 , and 5* / hall also/ include perification that permissives' P-6 and ,P 10 are iq/their req 6 ired state for exilting plany conditions by observation of /he permissive annunciator wi/dow. ~ sW a3 :.u.-) 3.l *! Net&$c
. SR 3.3. l.9, 64e I t 04' F- f."Insenx 3.3 -l2c) Lo BRAIDWOOD - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 44
1 I l 1 1 ! l
. CTS INSERT (S) .
SECTION 3.3 LCO 3.3.1 1 ,
; INSERT 3.3 12A (Ma )
j- SURVEILLANCE FREQUENCY SR 3.3.1.2 NOTE Not required to be performed until 12 hours ' after THERMAL POWER is = 15% RTP. l
* '1 1
I 1 t , . INSERT 3.3 128 (M3 ) 2. SURVEILLANCE FREQUENCY SR 3.3.1.6- NOTE ! Not required to be performed until 24 hours after THERMAL POWER is = 75% RTP. i a 1 i N i 4 Revision A i 9 M
1
?
M CTS' INSERT (S) l SECTION 3.3 l LC0 3.3.1 INSERT 3.3 12C (Lu ) i l l SURVEILLANCE FREQUENCY l l i SR 3.3.1.7 NOTE . . . f Not required to be performed for source range instrumentation prior to entering , MODE 3 from MODE 2 until-4 hours after i entry into MODE 3. l, 5 SR 3.3.1.8 NOTES . . .
- 1. Not required to be performed for power and intermediate range instrumentation Ontil 4 hours after reducing power below P-10. ;
- 2. Not required to be performed for source range instrumentation until 4 hours after reducing power below
'P-6. !
l f
)
i I Revision A 9
l l ' CT$ INSERT (S) SECTION 3.3 LC0 3.3.9 INSERT 3.3 12C (continued) (Ln) l SURVEILLANCE FRE0VENCY SR 3.3.9.7 NOTE ... Not required to be performed for source range instrumentation prior to entering MODE 3 from HODE 2 until 4 hours after entry into MODE 3. , l l Revision A a
i i l 4 t
.e l CO -E F / 1 i
{ l' l 3.1.1-l TABLE A (Continued)
- TABLE NOTATIONS
. SR 3.3,l.4 thrte !
$ A 1,1,1,1 3 f4ste l 1 pet Setpoint verification is not applicable. #
2 l SRs.1,s.4 pt7 The TRIP ACTUATING DEVICE OPERATIONAL TEST shall be performed such that ] oachtrainistestedutleasteverydddays on a STAGGERED TEST BASIS'and fol 4 Wino sfainten(nce OVadius)6ent pt theAeactpf Try, Breaters/and llJ j *i 'ude i penderVverifijdtion ofAe OPEJABILITY# _the Jeffdervo ge j j g d Shu rio At(achment(of the>ttactor)fic BradarsJ-i , m $7 1 d::; :=xt : L:=T:= :t:11 i=1:d: th: "Te t;;= : !=:: n:e ste." %! i f(14) Veri that the repriate gnals rea the under tage an unt Tr' ~i i r ys, for bo the Reac Trip an ypass Bre rs from e Manua
\ witches. ,
rip )l 5 A J,5.l.y tJete. j pfPr Manual Shunt Trip prior to the Reactor Trip Bypass Breaker being racked in and closed by bypassing a Reactor Trip Breaker. 1 l [(16)/utomatic ug#frvolpige 36p. 1 b i s 1, I i i 1 1 07 f!hi: not i: ppli abi: : Unit : =d Unit : until e xpl:ti:n ;f :ni: 5.) ^ BRAIDWOOD - UNITS 1 & 2 3/4 3-12 a AMENDMENT NO. 66 J
. - - - - . - - . - . ~ - . - - - - - . . - . . - . . - - . .....--- - -
j ..
- t. ;
l - ! 33 INSTRUMENTATION
- - M. 2. i 7
.(4 0.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ;
LIMITING CONDITION FOR OPERATION Lc.o 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation
- channels and interlocks shown in Table 3.3-3 shall be OPERABLEMth + heir-q
- Ian pu..15 ::: re m e' ant with the valuae =he:- u. ;i.. irip setpoint column of g ' 4
\ Table 3.3 4 -
t . g g , ,APPLICABILTTX: As shown in Table 3.3-3.
~
! ' ACTION. . fa. thanESFASIdstrumentat'onorInter1 k Trip Setpgint less ep-ervative thav the value hown in the ip Setpoint/ column butpore l
- 2 conservative /than the va ue shown in t e Allowable /Value colu Table 3.3-4/ adjust the getpoint cons / stent with the Trip Set int of % i i
- value. / / / / '
(
- - - - . - .i-_.. .. . . . . . . . . _
1 i Coni A g. With an ESFAS Instrumentation orQ.tuleiTrio Setooint lessLS con- i Q servative than the value shown in the Allowable Values column of 6 Table 3.3-4, declare the channel inoperable and apply the applicable! ( ACTION statement requirements of Table 3.3-3 until the channel is ! l h's restored to OPERABLE status with its Setpoint adjusted consistent
' }
w ith the Tr_ip.Je_tpoint value. -j l C x.d A r. With an ESFAS . instrumentation channel & inh.;vc2 inoperable, take the ACTION shown in Table 3.3-3. 3/4 3-13 AMENDMENT NO. 42 BRAIDWOOD - UNITS 1 & 2 ,
CTS INSERT (S) SECTION 3.3 lC03.3.2 INSERT 3.3-13A (As) NOTE Separate Condition entry is allowed for each channel. e e e e 6 Revision A e
LCD 3 5. 2. n INSTRUMENTATION g l SURVEILLANCE REOUIREMENTS SK M I i N Each ESFAS instrumentation channel and the automatic j actuation logic and relays shall be demonstrated OPERABLE by the performance j of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2. R 7,3.2.t/ l M1? ?) The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function
- ' sgy,3.2,12 shalT be verified to be within the limit at least once per 18 months. / Each
/verific on shall inclu at least one tra' such that bo trains are
- ! verif at least once er 36 months and e channel. per nction such th all j cha els are verifi at least once per times 18 mon s where N is t total i r of redunda channels in a sp ific ESFAS fu ion as shown i he i
Total No. of C nnels' Column of ble 3.3-3. 1 i
- il 1
t i i 4 1 4 4 e BRAIDWOOD - UNITS 1 & 2 3/4 3-14 AMENDMENT NC 76
& *nr ^l Wl-4 3 3.2-; mou o!
pn TABLE 3.3-3 i ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Q Required
& I MINIMUM D h T4 10.AL NO.
FUNCTIONAL UNIT g(-9F CHANNELS CHANNELS TO TRIP CHANNEL OPERAB APPLICABLE MODES ACTION Cond i
- 1. Safety In_lection f(Reactor Tr ,
water Isolat on, Sta
. Dies enerators, C inment . .
Cooling , Con Room - Isolation, "A" Isolation. 15
' Turbine Tr . Au ary -
Feedwa , Containee ent Is914 fon, and Essential vice E ter). , i
- a. Manual Initiation 2 1 - 2 1, 2, 3, 4 Jfr B/E '
- b. Automatic Actuation Logic 2 1 2 1,2,3,4 J4' C/C and Actuation Relays
- c. Containment Pressure-High-1 3 2 2- 1,nt, 3 Jf- F/Jf j 8
- d. Pressurizer. Pressure-Low 4 2 . 3 1, 2, 3 J9' K/C Fuoh'oh%4--{(Above P-II)) . i
- e. Steam Line Pressure-Low 3/ steam line 2/ steam ine' 2/ eam line 1, 2, 3' JV k/d FocAnMak-4(Above P-II)) any ste 11hc .
l
- 2. Containment Spray LAs '
- a. Manual Initiation 2 pair 2p r 1, 2, 3, 4 .18- 3lE
- b. Automatic Actuation Logic 2 1 2 1,.2, 3,.4 34- dE j and-Actuation Re1ays ;
- c. Containment Pressure-High-3 4 .2 3 1, 2, 3 ' 16' G/J r n >
0 I BRAIDWOOD - UNITS 1 & 2 3/4 3-15 AMEN 0 MENT NO. 44 Y !* 58 P [ t
?
. . _ . - . - _ __ _ _ _ . _ _ _ _ . . _ _ _ . . - _ . _ _ . _ _ . _ . . . _ . . - _ . - _ - . . _ . _ _ . _ _ ~_.._.. _ = __ 3s3,.2-f TA8tE 3.3-3 (Cont inued) ENGINEERED SAFETY FEATURES ACTUATI(N SYSTEM INSTRUMENTATION E ^ lad 8 Be.y="ei MINIMUM h} FUNCTIONAL UNIT h T0 tat-NO:
'4F CHANNELS l ANNELS T TRIP -
CHANNELS OPERA 8t APPLICA8tE MODES t.CTION L o.d E Q' u.
- 3. Containment Isolation . -
- a. Phase "A" Isolation
- 1) Manual Initiation 2 1 2 1,2,3,4 M N
- 2) Automatic Actuation. 2 1 2 1,2,3,4 cl6 Logic and Actuation J4-
-Relays
- 3) Safety injection S.ee Item 1. above ftr all Safety Injection initiating functions and requirements. / ,
u '
) b. Phase "B" Isolation -
L-
/
h
- 1) Manual Initiation 2 1 pair.! ' 2 pair 1, 2, 3, 4 K k
- 2) Automatic Actuation 2 1 2 1,2,3,4 J4' C/t-Logic and Actuation /
Relays ~j
- 3) Containment 4 2" 1, 2, 3 GI>
Pressure-High-3 38" Di%4 Containment Vent Isolation 3 17 Automatic Actuation 2 1 2 1,2,3,4 Logic and Actuation JY' ' Relays l ty Manual Phase "A" See Item 3.a.1 for all manual Phase "A" Isolation initiating
- Is-olation functions and requirements.
r- r
- 2. J7 Manual Phase "B" See Item 3.b.1 for all manual Phase "B" Isolation initiating
~
A6 Isolation functions and requirements. 0 I AT
~
Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements. .
3 3. i .-
. TABLE -3.3 (Cont inued)
ENGINEERED SAFETY FEATURES _. ACTUATION SYSTEM INSTRUMENTATION
,. m W &
4 h~ h( ReTOTAL-NO-p,. CHANNELS MINIMUM CHANNELS '
/ APPLICABLE FUNCTIONAL UNIT (OFCHANNELS TO 1 RIP OPERABLE MODES ACTION f_e.d
- 4. Steam Line Isolation ,/
- a. Manual Initiation .
/'
- 1) Individu;l I/steaa; 1ine 1/stea line 1/opdrating-- - --1 ;- t r3 7.. _.
-'23 g
/ 2}-System-- 2 1 j
2 1T,3 2 2f H/J
- b. Automation Actuation Logic 2 1 2 1, 2, 3 ff '1/ J W*-4) and Actuation Relays ,/-'
. c. Containment Pressure-High-2 3 2 ,' 2 1, 2, 3 f/J!
( #2.ll.Le_am Line Pressure-Low 3/ steam line 2/steamline/ 2/ steam line 1, 2, 3' I JI K/L! h(g -((above P-il)} any steam 11,ne UI e-A15 team Line Pressure-Negative 3/ steam line 2/ steam.11he 2 team line Ef. o/Pl any steam ,ine a gg(gg Rate-High[(below P-11)J S. Turbine Trip & Feedwater f=bk 6 ')5 Is01ation 4,)
- a. Automatic Actuation Logic 2 1 2 1, 2,3 ,24' 1/J
- and Actuation Relays
- b. ' Steam Generator Water Level- 4/sts. gen. 2/s m. gen. In 3/ste. gen. In 1, J9' IN '
High-High (P-14) arly_ operating each operati g
,j .s,tm. gen. sim. gen. \
- c. Safety Injection See Item 1.- above for all Safety injection initiating functions and requirements.
. r b
w s BRAIDWOOD - UNITS 1 & 2 3/4 3-17 AMENOMENT NO. 44
. . . . . . . . . - . . . . .. -..-..-...- .- .- -._ . -...-~. -~ . . . . . - ~ - . - - - -~
k
. .t 3 3. 2 - ! ,
- ~
- =
TABLE 3.3 3-(Continued) -
@' F.NGINEERED SAFETY FEATURES ACTUATIDN SYSTEM INSTRUMENTATION .I s
gL r l
' MINIMUM E' " "a HANNELS CHANNELS APPLICABLE
! FUNCTIONAL UNIT <0F CHANNELS TRIP OPERABLE MDDES ACTION Cord d
- 6. Auxiliary Feedwater e- (:. ";aual Initiet. ion 2 $ 2 ~~ 1.~2. T-~ ~ 21 Automatic Actuation logic I/J to - o Ar. 2 ~l~ -'2 1,2,3 K and Actuation Relays b p. Stm. Gen. Water Level-Low-Low -
Start Motor 7'
- w DrivenPd 4/sta. gen. 2/sta, n. 3 sim. gen. 1, 2, 3 pf F/J !
in any era- each 1 ting sta gen. perating n w __ to. gen. M '
- 2) Start Die 1- -
4/sta. gen. 2/sta. gen. Driven Pump 3/sta. gen. ' 1, 2, 3 39' plJ . , in any in each
. operating operating -
sim. gen. sta. gen. - t. e..d' Undervoltage - RCP Bus t Motof 'N 4-1/ bus 2 3 1, 2 19" $il l r ven.P nd 1 - O Diessi-Driven
- c. p. Safety In.jection -
k ' See Item 1. above for all-Safety Injection initiating functions and g m h l6t
- ndrt01"eter : 1-Orht;er k."qj :"-} ,
requirements.
\
5 d/: z W(Ditt ton 21 for, Unit 2)vis. ion 11 for Unit P T r-P - ESF Bus de.v61tage- 40
! Start Mo -
iven Q
@ l Pum p s art as 2 2 2 1,2,3 w Q )G sequencing) 4 JSd' f/J l9 bg
. Lgg frr ofQrh! hade .
- i Q q.
33.2-I
. TABLE 3.0-0-(Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION
~
Regwred b M g2 \ MINIMUM .
-TOTE "0. . $1ANNELS CHANNE APPLICABLE i FUNCTIONAL UNIT . pCHANNELS T1 TRIP OPE E MODES ACTION Cood
- 6. Auxillary Feedwater.(Continued) .
' fg Auxillary Feedwater Pump 1/ Train 1/Tr in I rain 1, 2, 3 J5( M[tJl Suction Pressure-Low (Tr:::fer t: E::::ti:1 ~
i (Servi ":ter) *
- 7. Automatic Opening of Containment Sump Suction Isolation Valves
- a. Automatic Actuation Logic 2 1 2 1,2,3,4 '
Jt C/6
; and Actuation Re. lays
- b. RWST Level - Low-Low 4 2 3 1,2,3,4 fr t>fEl Coincident With safety l See item 1. above for Safety Injection initiating functions and Injection requirements. '
~
Co715 W Loss. of Power . g 3,,,,y
- a. ESF Bus Undervoltage 2/ Bus / Bus 2/8 1,2,3,4 g 4/8/C
- b. Grid -Degraded Voltage 2/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 y A/8/C. ,
1 4 l ' BRAIDWOOD - UNITS 1 & 2 3/4 3-19 AMEN 0 MENT NO. 44 gg 99 vp .
~
l
..____.________..._.____._______-____m__________.____________m_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. 332-I TABLE 4.-3 (Continued)
~
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION t 9. Engineered Safety Feptures / ,
/ '
Actuation System In erlocks ,/ ,/ / f l [
- a. Pressurizer Pr ssure, P-Il 3 l 2 L
2 i,2,3 Y 20 m@- b Reactor Trip, P-4 4-2/ Train f 2/Traf'n 2 1, 2, 3 22
. Low-Low T, P-12 4 2 [/ Train 3 1, 2, 3 'ho s
O k 4 V BRAIDWOOD - UNITS I & 2 3/4 3-20 AMENDMENT NO. 44
. p
--- - - . - . .-.-.. .-.-.- -- - - . ~ - - - . . - . - -
! L cc 3 3 ."L L c o 3 .3 (, 3.3.1-1 ) TABLE' 5 7 3 (Continued) l TABLE NOTATIONS i .
~
Fo4de(() TTrip' function may be blocked in this MODE below the P-11 (Pressurizer
. Pressure Interlock) Setpir.t.
{ Feebde(d 'ffTrip function automatically blocked above P-11 and may be blocked below P-11 l when-Safety Injection on low steam line pressure is not blocked. , ._ ACTION STATEMENTS - M C,.I M TMc,E.RT 3. 3- 2 l A J-- h
- SAQ.2 bCT = id- With the number of 0PERABLE channels one less than the Mir.imum
! Channels OPERABLE requirement, restore the inoperable channel to ! OPERABLE status within 6 hours. lor be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within 0.ond EM 30 hourse however, one channel may be bypassed for up to 4 hours inh the follo j Cond C g ether for surveillance testing per Specification 4.3.2.1, provided the. channel is ERABLE. - 8k D.) 2 C[NsEftT 3 3- 2i B RAD.'2. ! ACT!= !!)- With the number o PERABLE channels one less than the Total
- Number of Channels.foperation may proceed until perfomanceJof l Ithe next reouired ANALOG CHANNEL OPERATIONAL TEST orovided/the j , inoperable channel is placed in the tripped condition within 6 l Ound D Nate; hours. 1,INsegt 3,3 - 2.i 8 1 Q
15al- With the number of OPERABLE channels one less than the Total } . CONI 7 M fACTIL -(Ieur 3.pzic> Number of Channels,Mdeclare the associated j WN take the ON ired by Specification 3.7.1.2. SA 6.1 : :TNwRT ?.3-zi0 j 1 PAG.2 ( ACT:= 10}- With the nu ro (An Wuo @ PERABLE channels one less than the Total ! C.o nd 'I , Number of Channels.( operation may proceed providedithe '- inoperable
' channel is alaced in the bypassed conditio.m...,. ........rl Os j ICh::::1; 0" "".".E r;;;;t r;;; t i; :::t.; One additional channel lRIf j Cmd6NdefSpecification 4.3.2.1.be bypassed for up to 4 hours for surveillance ltesting LC 3'3'O EACT:3 ;D- With less than the Minimum Channels OPERABLE requirement, l
operation may continue provided the containment purge supply and
, e v lves are maintained closed.
t~<.%.! 4-Es s tRT s a 2E 9m+L g SAS A (AGT-HWH9)- With the r of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE states within 48 hours /or be in at least HOT STANDBY \
"d ,
r within the next 6 -hours and in COLD SHtTTDOWN within the following\ RA i30 hours.) RAM Ro o.1 %Acidf1ssem 5 6- zip q para;m, .,UMM - With theYumber of OPERABLE channels one less than the Total Number of Channels./STARTUP and/or POWER OPERATION may proceed \ qRAci.2Cond 'I J/provided )' the followino conditions are satisfied: I g, Cond L ', C.od?,Cond R b BRAIDWOOD - UNITS 1 & 2 3/4 3-21 AMENDMENT NO. 44
= l l l CTS INSERT (S) SECTION 3.3 LC0 3.3.2 INSERT 3.3 21A (A3 ) 1 l l CONDITION -. REQUIRED ACTION COMPLETION TIME I C. As required by C.1 Restore one train to 1 hour from Recuired Action A.1 OPERABLE status when discovery of l anc referenced by two trains on the two inoperable Table 3.3.2-1. same Function are trains on the inoperable. same Function bHQ C.2 ... Revision A
-, , .- v
1 I CTS INSERT (S) SECTION 3.3 ! i LC0 3.3.2 ; INSERT 3.3 21B (A3 and L6 ) l CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 NOTE Recuired Action A.1 Performance of anc referenced by Required Action D.1 Table 3.3.2-1. may be delayed for up i to 4 hours for l surveillance testing ! provided actuation ! capability is i maintained. Restore all but one 1 hour from l channel to OPERABLE discovery of ' status when two or two. inoperable l more channels on the channels on the ' same Function are same Function inoperable. 6H0 0.2 ... 4 Revision A
CTS INSERT (S) SECTION 3.3 LCO 3.3.2 INSERT 3.3 21C (L,) CONDITION REQUIRED ACTION COMPLETION TIME M. As required by M.1 Res~ tore channel (s) of 1 hour from Recuired Action A.1 one train to OPERABLE discovery of anc referenced by status when both inoperable !
.: Table 3.3.2-1. trains on the same channels on Function have both trains inoperable channels. within the same Function bEQ '
H.2 Restore channel,to 48 hours OPERABLE status. Revision A
\
CTS INSERT (S) i SECTION 3.3 I LC0 3.3.2 l INSERT 3.3 21D (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME G. As required by G.1 NOTE 1 Required Action A.1 Performance of , . and referenced by Required Action G.1 ! Table 3.3.2-1. may be delayed'for up ~ to 4 hours for - i surveillance testing l provided actuation ! capability is j maintained. ; I Restore all.but one 1 hour from channel to OPERABLE discovery of status when two or two inoperable more channels on the channels on the same Function are same Function inoperable. 9.D G.2 ... i 4 E 4 i Revision A h
1 CTS INSERT (S) SECTION 3.3 LCO 3.3.2 INSERT 3.3 21E (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME i B. As required by B.1 Restore all but one 1 hou'r from
'Recuired Action A.1 channel to OPERABLE discovery of anc referenced by status when both two inoperable Table 3.3.2-1. channels on the same channels on the ,
Function are same Function l inoperable. 6E B.2 ...
\
l
+
l f E Revision A
, ,----y . , - -
l l 1 CTS INSERT (S) SECTION 3.3
'LCO 3.3.2 INSERT 3.3 21F (A3) i CONDITION REQUIRED ACTION COMPLETION TIME l
F. As required by F.1 NOTE l Recuired Action A.1 Performance of ' anc referenced by Required Action F.1 Table 3.3.2-1. may be del.ayed for up to 4 hours for surveillance testing i provided actuation ! capability is ! maintained. 1 l l
' Restore all but one 1 hour from '
channel to OPERABLE discovery of status when two or two inoperable more channels on the channels on the j same Function are same Function ) inoperable. ! l AND F.2 ... l l l Revision A
. . ~_ ._ ._. __. __. .- . . _ _ .
l CTS INSERT (S) l 4 SECTION 3.3 q LCO 3.3.2 INSERT 3.3 21F (continued) (A3 ) A CONDITION REQUIRED ACTION COMPLETION TIME K. As required by K.1 NOTE Required Action A.1 Performance of, . and referenced by Required Action K.1 < Table 3.3.2-1. . may be delayed for up to 4 hours for surveillance testing provided actuation capability is maintained. 4 Restore all but one 1 hour'from channel to OPERABLE discovery of status when two or two inoperable more channels on the channels on the same Function are same Function inoperable. MQ K.2 ... i i ! 1 Revision A
t 1
. CTS INSERT (.S) .
SECTION 3.3 LCO 3.3.2 INSERT 3.3 21F (continued) (A3 ) ) l CONDITION REQUIRED ACTION COMPLETION TIME !
- 0. As required by 0.1 NOTE l Required Action A.1 Performance of and referenced by Required Action 0.1 Table 3.3.2-1. may be delayed for up to 4 hours for surveillance testing ;
provided actuation capability is maintained. Restore all but.one 1 hour from channel to OPERABLE discovery of status when'two or two inoperable more channels on the channels on the same Function are same Function inoperable, e_ND
- 0.2 ...
4 . I Revision A 9 .
l l l l CTS INSERT (S) SECTION 3.3 i 'CO L 3.3.2 INSERT 3.3 21F (continued) (A3 )
! CONDITION REQUIRED ACTION COMPLETION TIME '
Q. As required by 0.1 NOTE Required Action A.1 Performance of .I and referenced by Required Action 0.1 Table 3.3.2-1. may be delayed for up 2 to 4 hours for surveillance testing provided actuation
. capability is i maintained. I J
Restore all but one 1 hour from channel to OPERABLE discovery of , status when two or two inoperable I more channels on the channals on the same Function are same Function ,
, inoperable. l 1
08 0.2 ...
. l l
i Revision A 6 e
- I b l I
l i L.co ? 3.5
~
TABLE (Continued) , ACTION STATEMENTS (Continued) t . l pl The inoperable channel is placed in the tripped condition j within 6 hours, and , h Cond F flott.) p. The Minimum Channels OPERABLE requirement is met; ~ however, i I I cond g Nott; the inoperable channel may be bypassed for.up to 4 hours I l for surveillance testing of q$her channels per Specification Gnd O Notc ; j
, conA Matt 4.3.2.1. ! l ACT 20 - Wi less t n the Mi mus Numbe of.Chann s OPERABL , within j l
{ r dete ne by obs rvation o the assoc ated para sive ' l i nunciat window (s that the nterlock s in its r quired s te j .. for the e sting p1 t conditi n, or app Specific tion 3.0. . QAI.l MNSERT 55-22A i RAI.2. := :C: C 1- With.the r of OPERABLE Channels one less than the Minimum Channels SPERABLE requirement, restore the inoperable channel to
.0PERABLE status within 6 hours. lor be in at least HOT STANDBYN gg' 'within the next 6 hours and in at least HOT SHUTDOWN within the\
<followina 6 hours: nowever one enannel may be bypassed for up to Co g g 4 hours for surveillance testing per Specification 4.3.2.1 orovided t her channel is OPERABLE.
RAH.l( Flasm 5.5- 22 6 l RA M.2. SCT"* 22 - With the n r of OPERABLE channels one less than the Total , Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours /or be In at least HOT STANDBY within 6
. Cond 7 4---{ hours and in at least HOT SHUTDOWN within the following 6 hours
'h ACT DN 23 - 64th the n r of OPE BLE chann s one les than the otal umber of C nnels, r tore the operable annel to PERABLE LA N i status with 48 hour or decla the asso ated valv inopera e
\ and take th ACTION equired by pecificat on 3.7.1.5 RAI.I< !TNS W %5 e etAI.2. ! =::: m- witn the r of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel t OPERABLE status within 6 hours, for be in at least NOT STANDBY 0.ond 7 < lwithin the next 6 hours;Ihowever, one channel may be bypassed for CondTrdo+4 Lco 3 3.5 Conel4 # {up *to a nours
* """' for
- surveiilance testing per Specifica
!ACT:^" 20- p: With the number of OPERABLE channels one less than the Minimum LCO 3.3.5 Cmd SM ,' Number of Channels.lSTARTUP and/or POWER OPERATION may oroceed/
lorovidedithe inoperable channel is placed in the tripped M.o3;$,2.Cospp/7 condition within.~1 hour. The inoperable. channel may be . bypassed for up to 2 hours for surveillance testing of the OPERABLE channel per Specification 4.3.2.1. m.m u-m LCO 3 3,.5 Cond A X With the number of OPERABLE channels one less than the Minimum haber of Channels.(STARTU3 and/or POWER OPERATION may oroceed tco 3 3:5 Ccodif: inrevided Ithe inoperable channel is placed in the tripped condition within I hour. -
) '
BRAIDWOOD - UNITS 1 & 2 3/4 3-22 AMENDMENT NO. 44
M i
- CTS INSERT (S) .
SECTION 3.3 LCO 3.3.2 INSERT 3.3 22A (A35 ) i CONDITION REQUIRED ACTION COMPLETION TIME I. As required by I.1 Restore one train to 1 hour from Recuired Action A.1 OPERABLE status when discovery of , anc referenced by two trains on the two inoperable i Table 3.3.2-1, same Function are trains on the l inoperable. same Function l I.2 ... i 4 I ~ INSERT 3.3.??R (Ais) 4 CONDITION- REQUIRED ACTION COMPLETION TIME i l H. As r'equired by . H.1 Restore all but one 1 hour from 4
.Recuired Action A'.1 channel to OPERABLE discovery of anc referenced by status when two or two inoperable Table 3.3.2-1, more channels on the channels on the I
' same Function are ' same Function inoperable.
'H.2 ...
j 1 Revision A
CTS INSERT (S) SECTION 3.3 LCO 3.3.5 INSERT 3.3 22C (L,) CONDITION REQUIRED ACTION COMPLET10N. TIME B. One or more Functions B.1 Restore one channel - I hour with two channels on for the Function on ' one or more buses the affected bus to inoperable. OPERABLE' status.
.C. Required Action and C.1 En't'er applicable Immediately associated Completion Condition (s) and Time not met. Required Action (s) for the associated DG if made inoperable by LOP DG start
. instrumentation.
x l l l D i 0
- e
- Revision A
. 3 3.2 -
, TABLE 3.0 0 E
~ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP ALLOWABLE
, FUNCTIONAL UNIT SETPOINT VALUE
$ 1. Safety Injection
-d (Reactor Trip, Feedwater g Isolation,' Start Diesel *
,, Generators, Containment. .
u Cooling Fans, Control Room Isolation, Phase "A" Isolation Turbine Trip, Aux 111ary,Feedwater, Containment Vent Isolation and Essential Service Water)
-[- a. Manual Initiation N.A. M.A.
- b. Automatic Actuation N.A. N.A.
4 w logic and Actuation Relays g I
- c. Containment Pressure-High-1 , 5 3. sig 5 4'.6 psig
- d. Pressurizer Pressure-Low (Above'P-11) 2 29 ig 1 1813 psig
~
- e. Steam Line Pressure-Low (Above P-11) 1 40 psi
- 1 614 psig*
i ka 2. Containment Spray g a. Manual Initiation .A. N.A. E b. Automatic Actuation ( Logic and Actuation - I <$ m Relays N.A. N.A. w
- c. Containment Pressure- p High-3 Q 20.0 psig JS21.2psig
l , 3. 3. 2 - I l, TABLE tc3-t (Continued) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS _- 1 l$- lg TRIP i ALLOWABLE g FUNCTIONAL UNIT SETPOINT VALUE
$ 3. Containment Isolation i gj a. Phase "A" Isolation g 1) Manual Initiation N.A. N.A.
[ 2) Automatic Actuation Logic and Actuation Relays A. N.A.
- 3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
w b. Phase "B" Isolation s
- 1) Manual Initiation N.A. N.A.
- 2) Automatic Actuation N.A. N.A.
Logic and Actuation : Relays
- 3) Containment Pressure-High-3 $ 0.0 sig 5 21.2 psig Lto 3. % y. Containment Vent Isolation
~
3 E ' Automatic Actuation F Logic and Actuation -
@ Relays N.A. N.A.
ka i E Manual Phase "A" N.A. N.A. [ Isolation F Z,27 Manual Phase "B" N.A. N.A. EE O Isolation - 00 ta v: 5A) Safety Injection See Item 1 above for all Safety Injection Trip Setpoints % and Allowable Values. r4
. . . . . .- . . . . . - - . . - . - - . - . . - .-. - .~.__. -. . --. - ~ . . . .- - - _. .-- - - . -
33.2-I TABLE-3.3 4 sentinued)
~
j ,, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
- E ---
G TRIP ALLOWA8LE
$ FUNCTIONAL UNIT -SETPOINT VALUE 8
, 4. Steam Line Isolation .
5 a. Manual Initiation N.A. N.A. a i
- b. Automatic Actuation .
4 H Logic and Actuation l o* Relays .A. N.A.
- c. Containment Pressure-High-2 .2 psi 19.4 psig d.) .d: Steam Line. Pressure- ,
Low (Above P-11) > 0 ps ig* d
>614 psig*
_ -l' 11.e: Steam Line Pressure w Negative Rate-High
} ' (Below P-11) il si** $165.3 ps1**
ty 5. Turbine Trip and g Feedwater Isolation , ;
~
. a. Automatic Actuation :'
. Logic and Actuation
. Relays M. . M.A.
- b. Steam Generator Water Level-High-High (P-14) .
- 1) Unit 1 81.4% f <83.4% of arrow ange instr it i
ins ~ ~ ~ t-J
- -g span n g '
g E 2) Unit 2 <78.1% ( cle (c;.M ';yck 3); g 3); <80. <82.8FfCach a 2.d ; (CycTe 4 & d of naryow-E after) of. trement lb E narrow ra instrument r-e span 8
?. ,
b
{ i , 3-4 2.-l TABLE 3.3 'J . entinued) - ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS T. >- TRIP ALLOWABLE SETPOINT VALUE o FUNCTIONAL UNIT ' 7 5. Turbine Trip and , Feedwater Isolation (continued) E c. Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and ! q in A11cwable Values. [ 6. Auxiliary Feedwater . ! {e. ".a..eal Ir.itict'en "I.. [ " A. _j aK Automatic Actuation Logic and Actuation Relays N.A. N.A. 3 bg Steam Generator Water' , Level-Low-Low-Start . E Motor-Driven Pump and i Diesel-Driven Pump [e i M .1)-Unit 1 >33. of >31.0% of nar range ow !_ ins'r- nt I inst t i sp 1 n
- 2) Unit-2 > % (Cy le Q15.2 l0.;;e 30, Ar 3( yc
>36.
; Te 4 >34.8% (C-M ' i nd .: :.terW i i ter) of a ow rArYtje g3 arrowrathe inst nt- :
nstrument ga f 3 span E R e# Undervoltage-RCP Bus- ->5268 vol s >4920 volts
~
g Start Motor Driven Pump t and Diesel-Driven Pump ! g . i r (, p! Safety Injection- t g Start Motor- .
-See Item 1. above for all Safety Injection Trip Setpoints and 8
Driven Pump and w ! Diesel-Driven Pump Allowable Values. 9
. 3.3.1 - 8 ,
TABLE 4r9-4 (Continued) , E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g TRIP ALLOWABLE SETPOINT VALUE
, FUNCTIONAL UNIT Aun111ery Feedwatee (Continued) ~T E 6.' 7 i i;! Les fr Ob4w- Peaes- !
p <A % slon 11 for Uni !
,, (D on 21 for 2] ;
, y ESF Bus age- ' Start en 287 vo ts 2730 volts P , fg Auxiliary Feedwater Pump Suction Pressure-Low (Transfer to - A. 1
. Essential Service 1.2 vac " Hg vac
} Water) w b 7. Automatic Opening of Containment Sump Suction Isolation Valves
- a. Automatic Actuation N.A. M.A. ,
Logic and Actuation Relays > is 46.7% 4.7% i
- b. RWST Level-Low-Low Coincident with See Ites 1. above for Safety Injection Trip 5etpoints and Allowable Values.
g Safety Injection , M' a , r
~
R - s V i
~
TABLE 3.3 mtinued) . ENGINEERED SAFETY FEATURES ACTUATION .aTEM INSTRUMENTATION TRIP SETPOINTS TRIP - ALLOWA8tE FUNCTIONAL UNIT SETPOINT VALUE , SR335p p _ .
- a. ESF Bus Undervoltage 2 0 volt: 0 volts 2
w/ 8s d 'ay w/sl. del
- b. Grid Degraded $
3804 vo s 1372 olts Voltage w/31 elay 0 1 30s de 9 Ineered Safety Featu tuation System Inte s f'y ~ ;
- a. Pressurizer Pressu / .
.e
.P-11 5 93F Psig .s1936 pstg
- b. Reactor Trip, P-4 / .A. M.A.
- c. Low-Low T,,, P-12 ,. 7 '~ \. - 2550*F 2 547.2*F', 2 546.9'F** .
- d. Steam Generat ate 5.b. above for all SteamMe'PatorJater Level Trip Leve Setpoints and Allowable Values. -
h-High) s,
~- -
t l t- n
" *App11 table io ii i ariu Uiili 2 uiit H-etnvietb-1 f- cyde-5. }' g u os i .Applicab!e te Ue!t ! and-Unit--2-start ing-with-eye le i I 68 68 i pq BRAIDWOOD - UNITS I & 2 3/4 3-28 AMENDMENT NO. 66 ,
i 4 l I ' Lco 3.12, 4 TA8LE 3.3 4 (Continued) i 1 .
..' TABLE NOTATIONS j Fednote (b) Mime constants utilized in the lead-lag controller for Steam Line Pressure-Low are t, > 50 seconds and t. < 5 seconds. /t"_^""2 t*LI"="IO" 9:P e eu e J
) (ett 55:: ti= x: txt : = cdj :--t t O n: n1:=.- 6 I MMO) **The time constant utilized in the rate-fag controller for Steam Line Pressure Mecative Rata - Mieh .h. ormatar than ar eaual. ta 50 seconds.-/ :'.""":L 0;;IT,6^ 4 { lTIO',' ;7. ell unn 2-0 Oi: ti : :n:txt 1: Odje:ted *= eff ":1":./ ') 4 i i i 4 4 e i i 1 a d e J G \ i J . - l 4 e d i 1 i 1 9 1
,9-1 J . .
BRAIDWOOD - UNITS 1 & 2 3/4 3-29 d
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BRAIDWOOD - UNITS 1 & 2 3/4 3-30 AMENDMENT NO. 12 y e
. . , . . ~ . . - .- ,.-a .- . -.._ -... -. - - - . ~ - - - _ .-.~ ~.- - -, . ...- - - , . u... . . . . .---an._.-.
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4 0 S S BRAIDWOOD - UNITS 1 & 2 3/4 3-31 AMEN 0 MENT NO. 12
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s BRAIDWOOD - UNITS 1 & 2' 3/4 3-32 AMENDMENT $0.12
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n e BRAIDWD00 - UNITS 1 & 2 3/4 3-33 AMENDMENT NO. 12 4
- e t
63.2.-l TABLE N b '5 R w r=e r h O * < I Q mbe n sb.m i. e s ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
/ SURVEILLANCE REQUIREMENTS
\ _ => sq 3. 3 2.1 M r
} !
C.t :-) q q 3.3.2 3 e b ' g TRIP ANALCS ACTUAflNG IINES CNANNEL DEVICE - ACitahrte MASTER SLAVE FOR WICN CNANNEL CNANNEL OPERATIONAL OPERAfl0NAL LO8tC RELAT RELAY SURVEILLANCE , FUNCil0NAL %P_III. CNECE _ Call 8RAfl0N TEST TEST TEST TEST.. IU.L. If MeUltED
- 1. Safety injection (Reetter frlp, .
Feedseter f eeletion, Start Slesel ' I Seneratore, Contelterent Coellns ! Fene, Centret toen footetten, l Phase "A" lootetten, furbine frlp, i Atatlllery Feedseter, Centelrument Vent teolation and Essential Service Weter) I
- a. Nenuel inttletten N.A. N.A. N.A. f-R N.A. N.A. N.A. 1,2,3,4
- b. Automette Actuetten Logle N.A. N.A. N.A. N.A. t/ _el(1) pil(1) 7-g 1, 2, 3, 4 i eru3 Actuellen Ref ere ,e ;
- c. Contalesment Pressure-Righ-1 l-S lp-R 4-0 N. A'. N.A. N.A. N.A. 1,2,3
- d. Presourlaer Pressure Lou l- S ]p-R 6-G , N .'A . N.A. N.A. N.A. 1,2,3 (Above P-11)
- e. Stesse Line Pressure-Lou l- 8 fp, R SG N.A. N.A.
- N.A. N.A. 1,2,3 !
(Above P-11)
- 2. Contalrsment Spray
\
- a. Manuel Inittetten . N.A. N.A. N.A.
fR N.A. N.A. N.A. 1,2,3,4
- b. Automette Actuotten Logle N.A. N.A. N.A. N.A. t/ -N(1) MN(1) 7e 1, 2, 3, 4 l end Actuotton Releye !
- c. Centelement Pressure-Illsh-3 l- S /d. R 6-# N.A. N.A. N.A. N.A. 1,2,3
- 3. Contairement leetetten "
- a. Phase "A" leoletten -
+
i
- 1) Itenuet inttletten N.A. N.A. N.A. 7 -R N.A. N.A. N.A. 1, 2, 3, 4 l t
- 2) Automette Actuation N.A. N.A. N.A. N.A. 'f-N(1) f M(1) /-e 1,2,3,4 g Logle and Actuetten ,
p Reteye O , 14 l
'el !
g . t BRAIDWOOD - UNITS 1 & 2 3/4 3-34 AMENOMENT NO. 44
l 1 - 314-1 TABLE he- (Continued) l ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l SURVElllANCE REQUIREMENTS TRIP ANALOG ACTUATING INBES CRANNEL DEVICE ACTUATION MASTER SLAVE FOR intICE CNANNEL CHANNEL OPERATIONAL OPERATIONAL LOSit RELAY RELAT SURVEILLANCE i fUNCfl04AL UNIT CNECK _ CAlltaAfl0N TEST TEST TEST TEST .. TEST. 18 REeulRED . 3.e. Phase "A" leetetton (continued)
- 3) Safety Injection See Iten 1. above for ett safety injectlen Survelttence Repiremente.
- b. Phase "S" leetetten
- 1) Manuel Inittetten N.A. N.A. N.A. Y-R N.A. W.A. N.A. 1,2,3,4
- 2) Automette Actuetten N.A. N.A. N.A. N.A. l[-M(1) F M(1) 7e 1,2,3,4 Loele Actuetten Refere
- 3) Contalement Pressure- 1-S /O- R @e N.A. . N.A. N.A. II. A. 1,2,3 i Elsh-3 l L.CO 3 %
.r." Centalesment vent teetetten 3 _.fr Autoestle Actuotten N.A. N.A. N.A. N.A[ 3.3. 6.1. gggy g3,g,3. pggg gg,ggp8 1,2,3,4 ,
Leste and Actuetten Reteye
) .Jt Menuel Phase "A" See Item 3.e.1 above for ett annual Phase "A" lootetten Survel,ttence Reptrements. .
lootetlen , 1 J5- Manuel Phase "S* See itse 3.b.1 above for ett manuel Phase "S" lootetten Survelttence Reptremente. lootetton [,Af~ Safety injection See Item 1. above for ett safety Injeetten Survelltence Re ptremente. A. Steam Line footetton
- e. MoreJet Inittetten N.A. II. A. N.A. f-- R N;A. N.A. W.A. 1,2,3
- b. Automette Actuetten Logle N.A. II. A. II. A. N.A. g-M(1) K M(1) 7-e 1,2,3 and Actuation Reteye
- c. Contalrunent Pressure-Nigh-2 l- S /#- R .M-0 II. A. N.A. N.A. N.A'. 1,2,3 f c$,l ,d; Steam Line Pressure-Lee l- S OR [a - G N.A. N.A. N.A. N.A. 1,2,3 IdYl 8ol '
(Above P-11) 3
. W t b 6' '
i 3.3 z-1 TABLE 5-2 (Continued) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVElllANCE REQUIREMENTS a TRIP ANALOG ACTUAflN8 INSES CNANNEL DEVICE ACTUATION MASTER SLAVE FOR INitCW CNANNEL CNANNEL OPERAllONAL OPERATIONAL LOGIC RELAY RELAT SURVEILLANCE FUNCfl0NAL UNIT CNECE CALjBRAtlON TEST TEST TEST TEST .. 15 REeUIRED 13.11. , 4 Stems Line Isolation (continued) d.2.pc Steen Line Pressure - l- S NR 0-e N.A. N.A. N.A. N.A. 3 Negettve Rete - Nigh (Below P-11) ,
- 5. Turbine felp and Feeduster teolation
- e. Automette Actuotton Logle N.A. N.A. W.A. N.A. Y -N(1) A N(1) 7-e 1, 2 ;
and Actuellen Refey
- b. ,Steme senerater Water Levet- l- S @ -R 4-0 N.A. f-N(l) 5 N(1) 7- e 1, 2 Nish-Nish (P-14
- c. Safety injection See item 1. above for att Safety injecitan Survelttence Re w irements.
- 4. Auisillery Feeeseter O. - L ;;l-8n{ 4 te* !- -N.A -
N.A. ..._._ - - M.A. .-.a "^ _ !.A. N.A 1[-2;5S
- tl XI Automette Actuetlen Legle N.A. N.A. N.A. N.A. y -N(1) g W(1) 7-e 1, 2, 3 and Actuotton Retey b pr Steam senerator Water Level l- 5 /D- R g;e N.A. N.A. N.A. M.A. 1,2,3 Low-Lou e .4f Undervottoge RCP Nun N.A. D-R N.A. E-e(3) N.A. N.A. N.A. 1, 2 cy Safety injg tlen See item 1. alme for ett Safety Injectlen Surve~ltlance Regfrements.
t.eu nG o%41%e yow , dff N.A. /d- R M.A. 8-N(2,33- N.A. R.A. N.A. 1,2,3,4 j (Divle Il for yUnit
) ESF 2
, L l'
rvel'.eee y-g Aunf tlery feedseter Ptap I- S M-R 2- N N.A. N.A. N.A. N.A. 1, 2, 3 Suction Prer.eure-Lou , l
. Ut !
l BRAIDWOOD - UNITS 1 & 2 . 3/4 3-36 AMENDMENT NO. 44 j i
.~ . -.
.3.5. Z l
. TABLE -4r3-B- fContinued)
~
ENGINEERED SAFETY FEATURES ACTUATIO' N SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOS ACTUATING - 8NSES CNANNEL DEVICE ACiuntielt RRSTER SLAVE FOR lHitCN CNANNEL CNANNEL OPERA 110NAL OPERAll0NAL LOGIC RELAf RELAY SURVEILLANCE FUNCfl0NAL UNif CNECE . CALIBRAflCII *EST TEST TEST E JggJ,_ 13_REglRED . T.. Automette Opening of tenteltaent Stamp Suetten Isoletion valves ,
- e. Automette Actuetten Logle N.A. N.A. N.A. II.A. k-N(1) f-R(1) 7- a 1,2,3,4 end Actuetten Releye be RUST Level-Lou-Lou l- 5 /D R 4,- N N.A. N.A. N.A. N.A. 1,2,3,4 Colncident With Safety injection See Ites 1. above for ett Sofety injection Surveltlance Reapairements W Ey.[ ;
J7. Lees of Power
- s. ESF Bus Undervoltage N.A. R -SR 3.3.T. 2. N.A M(2, 3)-51 %5. 8 N.A. N.A. N.A. 1, 2, 3, 4
- b. trld Degraded Vettese N.A. R-LR33."..L N.A. N(31-SA 4.3.5 I N.A. N.A. N.A. 1,2,3,4
~~ '~ ~ ~~ ~ ~
- 9. E IneeredSafetyFee5ure~ -
tuetion System in elecke ,
. presourirer e eseure, e.it N.A. N N. . N. . N. . N.A t, 2, 3,
- b. Reseter fri , P-4 N.A. .A. .A. R N . N.A. N. . 1, 2, i
.. tou.tou f , .n N.A. R N d.A. 2A. N.A. . N.a. ,, 2 3 I
> ;. _ ._. _ _j l.
. - - - - . . - . . t
/g g TABLE NOTATION (if Each train shall be tested at least every days on a STAGGERED TEST BASIS.
(27 Undervoltage relay operability is to be vertfled independently. An inoperable channel may be bypassed for up to 2 hours for s~urveillance testing of the OPERABLE channel per-Specification 4.3.2.1.
.pf etpoint verification is not appilcable. ;
R 5.%. G.I rJoA c u.s.z3 It 3.3. 2.8 AMe m e>}> . n n tco 3.3.5 RA A.I AloTC 00 ; Oco 2 7.1 M F. I IM Y t- ; SR 3. 3 2.1 . MOTE -=-- 245Elrr 3 3 - 37A U ~ BRAIDWOOD - UNITS 1 & 2 3/4 3-37 AMEN 0 MENT No. 44 f
4 l
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CTsINSERT(S) SECTION 3.3 LC0 3.3. 2 INSERT 3.3 37A (Ar) i i SURVEILIA U. FREQUENCY 't . SR 3.3 2.9 NOTE ... j . Verification of setpoint not required for
- manual initiation functions.
J
- a. .
A 1 i
. 1 4
i 4 4 4-j- Revision A 3 s
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i.co 31t. Lc o 12 7 j INSTRUMENTATION - Lco 3. 5.s O/4.33 MONITORING INSTRUMENTdTION RADIATION MONITORING FOR PLANT OPERATIONS i j LIMITING CONDITION FOR OPERATION 134 kO3Il G-d-3-s The radiation monitoring instrumentation channels for plant onerations shown in Table 3.3-6 shall be OPERABLE M +h t Mi- ^1e _P -i; S:tpcint: within' Lt.03.13 (ty.: :pect<3:e itegte.; 7
. APPLICABILITY: As shown in Table 3.3-6.
!, ACTION: l a. operations ation exceemonitoring channel Alarm / Trip _latpoiet-1sf plant f ng-t ue hown-in-TibTe 3.3-6, adjust the n e c..a A g. With one or more radiation monitoring channels for plant operations j co~18 inoperable, take the ACTION shown in Table 3.3-6. ! { r. % previsiens ef Speci'icatier 3.0.2 :r: net :;plicable -h f bM Nott. 2 3ERJ .3.1 2dhA' * (Lco 3 3 .' ) e I SUROEILLANCE REQUIREMENTS
$R Me+c- ( vo 3 3.b e 1Co 3 3.'t ) .
(::ikEa Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL i' CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3. BRAIDWOOD - UNITS 1 & 2 3/4 3-39 AMENDMENT NO. 38
i CTS INSERT (S) SECTION 3.3 . LCO 3.3.6 INSERT 3.3 39A (A6 ) NOTE Separate Condition entry is allowed for each Function. I O O e Revision A s e e
, -T.'"'I 1.10 ~
E RA01ATION MONITORING INSTRUNENTATION FOR PLANT OPERATIONS
\ CHANNELS
/ M @LSt CHANNE APPLICA8LE ALARM / TRIP
$ FUNCTIONAL UNIT TO TRIP / ALAR 5 kOPERA96El M00ES SETPOINT ACTION c.-a gLcosae g E Fuel Building Is.olation-Ste. RadioactivitpHigh_aQ
,,118-l
, Criticallty a0 C A 0~,5/.n,f @ 1 -2 *
<5 mR/h / A/s LCO 3 3 (a E. Containment Isolation- hva .
Mk lMContainment Radioactivity. )'DJ5EEET3.3-404) M*W High . " - r 7 1 2 ** K A/a /c. (bYUniV2(2RJ-AR011/12a) ( Lopntt J IRE1ARO U/1Z) 2 ** Kr A/s/c.
~ ~ ~ ~ ~ ~ ~ ~ - - '
$ 3. Gaseous Radioactivity- - -
, RCS Leakage Detection ..
.m
;, a) Unit 1 (1RE-PR0118) N.A. I 1, 2. 3. 4 N.A. 28 A&l*s e Se< 4 34 o b) Unit 2 (2RE-PR0118) N.A. I 1.2.3.4 N.A. 28 See.bx L N y l
- 4. Particulate Radioactivity-RCS Leakage Detection a) Unit 1 (1RE-PR011A) N. . I 1, 2,.3. 4 M.A. 28 b) Unit 2 (2RE-PR011A) M. . 1 1.2.3.4 N.A. 28 L* 17 '7 Main Control Room Isolation-A.
T4te 3.m Outside Air Intake-Gaseous - ' Rad osctivity-HI di 1ii ' Vain A (ORE >R0318/328) LA" 1 2 All < 2 mR/h F Aleicl DIE AIB/N@br
~
s= (b fral/8(ORE-PRQ338/348 1 2 All 32mR/h JT m oono , oOOo u te u W A EA Us h 8 9 (p ..I C U' - :.
CTS INSERT (S) SECTION 3.3 LCO 3.3.6 ! INSERT 3.3-40A (La)
- 1. 2, 3. 4, (a) When Item C.2 of LC0 3.9.4 is required.
9 1
-).
4 4 Revision A Q e
g
~
TABLE 3.3-6 '
~
RADIATION MONITORING INSTRUNENTATION FOR PLANT OPERATIONS 3 O
, NINIMUM CHANNELS CHANNELS APPLICABLE ALARM / TRIP
! 4 FUNCTIONAL UNIT TO TRIP / ALARM OPERA 8LE MODES SETPOINT ACTION ,
[ 1. Fuel Building Isolation-Radioactivity-High and
,, g,,a ;, g u
, Criticality (0RE-AR055/56) 1 2 *
<5 mR/h 29 g m g ,. g ,3
- 2. Containment Isolation- i Containment Radioactivity- '
High a) Unit 1 (1RE-AR011/12) .1 2 .All ** 26 b) Unit 2 (2RE-AR011/12) 1- 2 All ** 26 - 3 Gaseous Radioactivity-
$ tco. R m
T l'I.if :CS) Leakane Detectian Sit 1jitt7:0115) N.A. 1. 2. 3. 4 N t) Wit 2 J;~ GeHIO }; [427 N.A. 28 8
$ N.A. I 1.2.3.4 N.A. 28
- 4. Particulate Radioactivity-tco RC M IC.-e)S Leakana DetectiongettiLA1 (1:C.TRG11A)
~
N.A. '
- 1. 2. 3. 4 N.A. 28
;b)-Uni. w-m . -- , ; N.A. 1. 2. 3. 4 @
M.A.
- 5. Main Control Room Isolation- p ,_
Outside Air Intake-Gaseous - Radioactivity-High 9g D a) Train A (ORE-PR031B/328) l' 2 . All < 2 mR/h 27 $$ . , b) Train 8 (ORE-PR0338/348) 1 2 All 27
?__.2.. mR/. h ..
, .. &3 l5 .
,s.nas\ m a.1. og y
, s. , u s .. i
,5 54c+
- 3 e.
e, G [
- Lco .5 .:> g i - - -
Lco s. 3 1 1 T- - Lcn 3.18
- W"T " g TABLE NOTATIONS t.cc> s.4. ly f 1 stere;;e are;2 er f 1 doti4+d
~
\ m;i.h ... r-1.,- i. ..ci.t.c r 1 1., t;
** Trip Setpoint is to be established such that the actual submersion dose rate would not exceed 10 mR/hr in the containment building. For containment purge i or vent the Setpoint value may tpe increased /up tar ce . maxis concen a' 1
p)on activi in the ntal dete ned by s e analys s perfo d-prior to ch releas in ace nce Tabl 4.11-2 rovided he val does ) act exe d 10% of eoui ont li ts of ecific ion 3. .1.alin accord-
, ance with the methodology and parameters in the ODCM.
! ACTION STATEMENTS l ~DMEET 3.3 4 l A {, , Leo 3.3.G ~ g !
- dETWh% 'WithTss than-the Minimum _ Channels .0PERABIreq'uirementNraWon '
j Conel A . Co J B i ' may continue provided the_conta,ir.;..6 piirge valves,are maintained j Conj C iclosetL- ' ~N
%)
! Nu ;= ra - With the number of OPERABLE channels less than the Minimum i Cod A / Coed B Channels OPERABLE requirement, within I hour switch to the ! redundant train of Control Room Ventilation, provided the i redundant train meets the Minimum Channels OPERABLE requirement - i
.*J0I0/E) or isolate the Control Room Ventilation System and initiate
! ihrasea.r 3.3-418 H operation of the Control Room Make-un System. /Res ts -th(v . __ /ino;ier rs to OPERABLE.statu_s_withi s days or submit Me m i . n 6 4 J &. a Special Report C H aston~ pursuant to Specification l 4, s. gn :a. g.9.2wi ng 30 h i F - y -4noperahu ity_am Lthe_ plans _for.restorati.on.
\ ACTION 28 Must satisfy the ACTION requirement for Specification 3.4.6.1..
Lco3.3.8 AETf9N:P9 With the number of OPERABLE channels one less than the Minimum ) Channels 0PERABLE requirement.lACTION a. of Soecification 3.9.123 i (must be satisfied. )With both channels inoperable. Ji.resid; en
- pe- P !: centinen = iter dth the c A1; ; Set- 2' l
E;preprietint in tb 1; 1 :::1 n :1with one F_u_eLttandling_ Budding Exhaust filter plenus in operation. [0thentise satisfy ACTION b.' ' ! of Specification 3.9.12. T ] ) I Se e vr e .,o.d ,'o nw k-up o4 LC0 3.9.l 4 i ) i i e
- e i
i i BRAIDWOOD - UNITS 1 & 2 3/4 3-41 AMENDMENT NO. 37 1
. CTS INSERT (S) -
SECTION 3.3 i LC0 3.3.6 INSERT 3.3 41A (Lu) CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation A.1 Restore the affected 4 hours monitoring channel channel to OPERABLE inoperable, status. I 1 B. NOTE B.1 Enter applicable Immediately , Only applicable in Conditions and ; MODE 1. 2. 3. or.4. Required Actions of LC0 3.6.3, l
" Containment One or more automatic Isolation Valve's,"
actuation trains for containment purge inoperable, valves made I inoperable by^ l QB isolation I instrumentation. l Two radiation ' monitoring channels i inoperable. l 08 I Required Actior and associated Completion Time of Condition A not met. Revision A
. - .- . . = . . . .- .-
CTS INSERT (S) SECTION 3.3
'LCO 3.3.6 INSERT 3.3 41A (continued) (Lu)
CONDITION REQUIRED ACTION COMPLETION TIME' C. NOTE C.1 Place and maintain Immediately Only applicable when containment purge Item C.2 of LC0 3.9.4 valves in the closed is required, position. Two rat.ation I monitoring channels C.2 Enter applicable Immediately ! inoperable. Conaitions and Required Actions of QB LC0 3.9.4, !
" Containment 1 Required Action and Penetrations." for l associated Completion containment purge J
. Time of Condition A valves made not met, inoperable by isolation instrumentation. l Revision A
i CTS INSERT (S) : SECTION 3.3 4 LC0 3.3.7 h INSERT 3.3 418 (M i ) ' i CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours ' associated Completion T1me of Condition A 6@ ' or B not met in - MODE 1, 2. 3.. or 4. C.2 -Be in MODE 5. 36 hours , i l
'l CONDITION REQUIRED ACTION COMPLETION TIME-1 D. Required Action and D.1 Suspend movement of Immediately .I associated Completion irradiated fuel.
Time of Condition A assemblies. or B not met during movement' of irradiated ' fuel assemblies. Revision A
i 1 -
. CTS INSERT (S)
SECTION 3.3 - LC0 3.3.7 INSERT 3.3 41B (continued) (M3 ) 3 CONDITION REQUIRED ACTION COMPLETION TIME 4 E. Required Action and E.1 SusbendCORE Innediately , associated Completion ALTERATIONS. i Time of Condition A
- or B not met in MODE 5 6NQ or 6.
. E.2 Initiate action to Immediately r store one VC
- Filtoation System train to OPERABLE status.
4 l I i o l
- 1 l -
- i i.
4 i 1 Revision A
1 CTS INSERT (S) SECTION 3.3 1 LCO 3.3.8 INSERT 3.3 41C (Lu and LAg ) (a) During movement of irradiated fuel assemblies in the fuel handling building. (b) During movement of irradiated fuel assemblies in th.e containment with the equipment hatch not intact.' (c) During CORE ALTERATIONS with the equipment hatch not intact. l l 1 l l l l l l I l Revision A 9
i
..[Ake,irdtwSeebu3.3 M 3.4f 4 ,3 t .
TABLE N71AT10NS l see hoc. (.c See bb 3.3] l *With new fuel or irradiated fuel in the fuel storage areas or fuel building.
"* Trip'Setpoint,is to be established such that the actual submersion dose rate 4
would not exceed 10 mR/hr in the containment building. For containment purge 1 or vent the Setpoint value may be increased up to twice the. maximum concentra-
- tion activity in the containment determined by the sample analysis performed i ' prior to each release in accordance with Table 4.11-2 provided the value does not exceed 10% of the equivalent limits of Specification 3.11.2.1.a in accord-
- ance with the methodology and parameters in the ODCM.
- ACTION STATEMENTS l ACTION 26 -
With less than the Minimum Channels OPERABLE requirement, operation
- may continue provided the containment purge valves are maintained closed. ,
ACTION 27 - With the number of OPERABLE channels less than the Minimum
- Channels OPERABLE requirement, within 1 hour switch to the i
redundant train of Control Room Ventilation, provided the ] redundant train meets the Minimum Channels OPERABLE requirement i or isolate the Control Room Ventilation System and ' initiate operation of the Control Room Make-up System. Restore the 1 inoperable monitors to OPERABLE status within 30 days or submit a Special Report to the Commission pursuant to Specification ! 6.9.2 within the following 30 days that provides.the cause of -
- j. the inoperability and the plans for restoration. /
ACTION 28 - Mustsatisfythe_ACTIONrequirementforSpecification3.4.6.1.[b
. ACTION 29 -
With the number of OPERABLE channels one less than the Minimum 4 Channels OPERABLE requirement, ACTION a. of Specification 3.9.12 i must be satisfied. With both channels inoperable, provide an i i appropriate portable continuous monitor with the 'same Alam Set- ! point in the fuel pool area with one Fuel Handling Building Exhaust filter plenum in operation. Otherwise. satisfy ACTION b. i
- of Specification 3.9.12.
. n i FA M resse/ E 5 ,< 4 I 3 1 bte b0lt N $ 9t E*'
- w _ - -
i O h j - i
- BRAIDWOOD - UNITS 1 & 2 3/4 3-41 AMENDMENT NO. 37 1
1
5 ,- < g, w ric a p , 4 , t c o T ' O'l 4.3 3 w ker ad fle At %mt.er- ~ c o m w e. + , i a e % g .fy d e. RADIATION HONITORING INSTRUMENTATION FOR PLANT gn,pe,a r m gq OPERATIONS SURVEILLANCE REQUIREMENTS i.e, for Lc o 3,3,17, (- => s rt, 3,3 8 I, ete-,," DIGITAL CHANNEL CHANNEL CHANNEL OPERATIONAL %ESFORWHICH / FUNCTIONAL UNIT CHECK CALIBRATION TEST SURVEILLANCE IS REQUIRED
- t. coy y,gt. Fuel Building Isolation- -
Radioactivity-High and '
.T A-m -l Criticallty qual 4RU55/5513
, , i
( -S 3-R 2-Q l L.co 5.3,4Z Containment Isolatton-Tiil,ks34-( containment Radioactivity- .
"### it 1 ( -AR0ll 2) l-S 4-R V-Q All it 2 -ARS 2)) t-S 4-R 4-Q All !
- 3. Gaseous Radioactivity-RCS Leakage Detection a) Unit 1 (IRE-PR0llB) S R Q 1, 2, 3, 4 b) Unit 2 (2RE-PR0llB) S R Q 1, 2, 3, 4
- 4. Particulate Radioactivity-RCS Leakage Detection .
a) Unit 1 (IRE-PRO 11A) S R -Q 1, 2, 3, 4 b) Unit 2 (2RE-PR0llA) S R Q 1, 2, 3, 4 W 35 7% Main Control Room Isolation- - Takte 3.1,7-t Outside Air Intake-Gaseous Radioactivity-High _ [ l
) l-S 3-R 2-Q
(,afrainA(pHE-PR031Bf52B)i M Train BA0RE-PR03}5/34B) t- S 3-R st-Q 11 l t '- Y ;
*n R&Q \
Adre s"sa%34
' 58" * ' ' "
p$[ y)_c $h Se+ N!ih 7.0% fGGl Or ITT0d!!IOd fSOl " IbO fUOl IIOrI"" IIO3I OI fSOl build!""- # BRAIDWOOD - UNITS 1 & 2 3/4 3-42 AMENDHENT NO. 74
TABLE 4,3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL CHANNEL CHANNEL OPERATIONAL FUNCTIONAL UNIT _ MODES FOR WHICH CHECK CAllBRATION TEST ; SURVEILLANCE 15 REQUIRED
- 1. Fuel Building Isolation-Radioactivity-High and
~ Criticality (ORE-AR055/56) S R Q -
- 2. Containment Isolation- '
Containment Radioactivity-High . a) Unit 1 (IRE-AR0ll/12) S R All b) Unit 2 (2RE-AR0ll/12) S R Q 0 All O$ a r I
\ c' ;;::
- 3. Gaseous Radioactivity _ s m .6,/ SR 2.4.ts.4 se lit.is.7. 1 gL RCS Leakage Detection _
6 [ ,5, y.
'a) Unit I (IRE-PR0llB)1 b) Unit 2 (2RE-PR0llB).
S S R [Q' 1, 2, 3, 4 *w, l [g, R Q 1, 2, 3, 4 , y( i
- 4. Particulate Radioactivity-
. RCS Leakage Detection _ p[L u a) Unit 1 (IRE-PR0llA) S .R Q~ 1, 2, 3, 4 " ,y b) Unit 2 (2RE-PRollA) 3 1, 2, 3, 4 l
- 5. Main Control Room Isolation-R S hab' Outside Air Intake-Gaseous '
Radioactivity-High a) Train A (ORE-PR031B/328)- S R Q All b) Train B (ORE-PR033B/348) S R Q All
- E R EE o ooo
_w PP" WP" _A q ao 4 tr
*With 'new fuel or irradiated fuel in the fuel storage areas or fuel building.
BRAIDWOOD - UNITS 1 & 2 . 3/4 3-42 , AMFNOMFNT NO. -74
$3c h 3.5 MNSTRUMENTATION YABLEINCOREDETECTORS M
\
LIMITING' CONDITION FOR OPERATION
,/
l \
\
3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:
- a. At least\75%
\ of the detector thimbles,
'N 1
- b. A minimum of two detector thinoles per core quadrant, and
- c. Sufficient mov'able detectors, drive, and readout e puent to map these thimbles. \.
APPLICABILITY' : When the Novab' incore Detection System s used for:
- a. Recalibration of the ex re neutron flux tection system, or 1
'N -
/*
- b. Monitoring the QUADRANT P TILT RA , or d
- c. Measurement of Fg , F g(Z) and ./
ACTION:
/ x With the Movable Incore Detection System inoper'able, do not use the system for the above applicable monitoring ord alibration functions. The provisions of Specification 3.0.3 are not appl.idable. y -
/ \s
', /
y-
'N
\
SURVEILLANCEREQUIREMEkTS
\
/ '\
!4.3.3.2 The MoIable Incore Detection System shall be demonstrated' OPERABLE at '
least once per 24 hours by normalizing each detector output when required for: l i a. j'Recalibration of the Excore Neutron Flux Detection System, or l
./ ,
I
- f. ti Monitoring the QUADRANT POWER TILT RATIO, or y I / -
I,/ c. MeasurementofFh,F(2),andF q xy* \ L .._ _ - __ BRAIDWOOD - UNITS 1 & 2 3/4 3-43 AMENDMENT NO. 38
INSTRUMENTATION SEISMIC INSTRUMENTATION s LIMITI(G CONDITION FOR OPERATION
\
3.3.3.3 T seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE. APPLICABILITY: t all times. ACTION:
- a. With one oranore of the above required seismic monitoring instruments inoperablefor,morethan30 days,prepareandsubmitaSpecialReport to the Commission pursuant to, Specification 6.9.2 withip the next 10 days outlining t'he cause of the malfunction and the pmns for restoring the instrument (s)'to OPERABLE status,
- b. The provisions of Specification 3.0.3 are not app cable.
SURVEILLANCE REQUIREMENTS \ ' 4.3.3.3.1 The seismic monitoring instrumentation s 1 be determined OPERABLE:
- a. At least once per 31 days by ' verifying etable status indications of the seismic monitoring instrumentatio .
- b. At least once per 92 days by veriYy' g that:
- 1) The triaxial acceleration s so s and the time-history accelero-graphs properly process the' equi ent internal' test signals.
- 2) The response spectrum an/alyzer prop rly executes its diagnostic routine. j/
- c. At least o'nce per 184 daps by verifying tha 'f.he triaxial acceleration .
sensors and the time-history accelprographs prqperly record the equipment ' internal test. signals. The test may be perform in lieu of the test required by Speci).ication 4.3.3.3.1.b.1), and ~ d. Atleastoncepr18monthsby.
- 1) Verifying the electronic calibration of the time istory acceglographs.
- 2) Installing fresh magnetic recording plates in the tr' xial peak adeelerographs.
/
4.3.3.3.2 Up'on actuation of the seismic monitoring instruments, the eq
- ment listed in Jable 3.3-7 shall be restored to OPERABLE status within 24 hour g followingthe seismic event. Data shall be retrieved from actuated instrum nts and analyzed to determine the magnitude of the vibratory ground motion. A fl Report shall be prepared and submitted to the Commission pursuant to Spec)ification6.9.2within14daysdescribingthemagnitude,frequencyspectrua, ec Sp'd an resultant effect upon facility features importanT. to safety.
BRAIDWOOD - UNITS 1 & 2 3/4 3-44 AMENDMENT NO. 38 4
l l SecG.33 1 R ,. 1 4 l TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION NIMUM MEASUREMENT INSTRUMENTS l 1 ' INSTRUMENTS AND SfMSOR LOCATIONS RANGE OPERABLE-1. N Time - History Accelerographs l
- a. Aux. Elect. Ra, OPA02J
\ < N. A. 1
- 2. Triaxial Peak Accelerographs
) a. Cont./ Reactor Eq. Accumulators -2 g to +2 g 1 I
- b. Cont./ Reactor piping
- c. Aux. Bldg./ Cat. I piping \s-2gto+2g
-2 g to +2 g I
1
- 3. Response-Spectrum Anclyze i Aux Elect Re, OP 2J None 1
, 4. Triaxial Accele tion Sensors i
- a. Cont./ - 377' -2 g to +2 g 1
- b. Con OW - 502' -2 g to +2 g 1
- c. Corft./10X - 426' -2 g to +2 g N1 d
e/.ree Field /38 + 015, 34 + 15E. -2 g to +2 g IN
. Aux. Bldg./18N - 426'. -2 g to +2 g 1 \s i
'f. Aux. Bldg./18L - 338' , -2 g to +2 g 1 'N i '
a t W i o , BRAIDWOOD - UNITS 1 & 2 3/4 3-45 Amendment No. 28
A 1
.i Sec h T.3 -l 2
~ l l i ' 4 i 1 1 t - 1 I i t This Page ntentionally ft Blank l s . t 4 . 1 4 d 1 l 1
)
T . 9
/.
- i 1-1 4
2 BRAIDWOOD - UNITS 1 & 2 3/4 3-46 . v w-
I I l J
. lWSTRUMENTATION -
Sech. 3.3 l
- s METE'OROLOGICAL INSTRUMENTATION j LIMITING CONDITION FOR OPERATION /
4
\N j ' 3.3.3.4 The meteorcIlo.gical monitoring instrumentation channels giv in Table.
, 3.3-8 shall be OPERABLE) APPLICABILITY: At all times. l ACTION:
' a. With one or more required teerological nitoring channels inoperable for more than 7 days, prepareN and subej a Special Report to the
] Commission pursuant to Specificatio .9.2 within the next 10 days outlining the cause of the malfu 4on and the plans for restoring , l 1 the channel (s) to OPERABLE sta s. N !
- b. Th'e provisions of Specifice n 3.0.3 e' snot applicable,
/ \
/ \
/ 1 f
SURVEILLANCE REQUIREMENTS - x l
/
/ ..
4.3.3.4 .Each of the above meteorological monitoring' instrumentation ch nels \ shall .be demonstrated OPERABLE by the performance of the CHANNEL CHECK an i HANNEL' CALIBRATION. operations'at the frequencies given in Table 4.3-5. l O I D BRAIDWOOD - UNITS 1 & 2. 3/4 3-47 AMENDMENT NO. 38
y .
& Seaw.n 3.3 l
%. i TA8LE 3.3-8
) ,
METEOROLOGICAL MONITORING INSTRUMENTATIO l MINIMUM INSTRUMENT LOCATION OPERA 8LE
- 1. Wind Speed Elev. 34 ft 1 5 1 Elev. 203 ft 1
- 2. Wind Directi n Nominal Elev. ft 1 Nominal Elev. 203 ft 1 )
l
- 3. Air Temperature - AT Nominal Elev. 30 fu199 ft i
j j' - - 1 e e S 8AAIDWOOD - UNITS 1 & 2 3/4 3-48
~ .- _.- ____._ __
g . 5 - : o,3.3 N -
'; . TA8LE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION 4
SURVEILLANCE REQUIREMENTS .. T s CHANNE CHANNEL INSTRUMENT' CH CALIBRATION j
- 1. Wind Speed
, s. Nominal Elev. ft 0 SA
- b. Nominal Elev. 203 0 SA 4
- 2. Wir.d Oiesction ,
- a. Nomitid Elev. 34 ft D SA b.
/inal Elev. 203 ft C SA
. Air Temperature - AT i
Nominal Flev. 3n ft/199 ft 0 5 i 0 '
. 1 l
i i t I i i l BRAIDWOOO-UNITS 1&2 3/4 3-49
i s LCD 3.3.4 l 1 l
~
3.3 INSTRUMENTATION l--{.sy s +e n ) ' 23.4 REMOTE SHUTDOWNUTOS"~"CC%) l l 1 LIMITING CONDITION FOR OPERATION I l LCO .2.3 4 \ N The remote shutdown monitorine instrumentatiotr channels alven in'""- Taale 3.3-9 shall be OPERA 8LE'rie ::::::: ci:;;1;ys cat;rr.;1 : t..; ;ert m U 1 1 APPLICA81LITY: MODES 1, 2. and 3. ! ACTION. CmetA ,#. With the number of OPERA 8LE remote shutdown monitoring channels less than the Minimum Channels OPERA 8LE as required by Table 3.3-9, restort I the inoperable channel (s) to OPERA 8tf status wittt'inpays.f or ne tn' l GdB ,
/af least MUT STAND 5Y within the next 6 hours and in HOT SHUTDOWN J twithin the followinc 6 hours. 1 ,
30 dCTior6 %fe ) p. The provisions of Specification 3.0.4 are not applicable. -
,; ACTiou, Ooft 2 < j .INSEET .3.3 - Go A SURVEILLANCE REQUIREMENTS (4keA h nmaL eeeen n-4
.5R 3.3 4.1( 6 ' Each remote shutdown monitoring instrumentation channeldshall be
.5R .3.3 4. 2. demonstrated'0PERA8LE by performance ot' the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies given in Table 4.3-6.
.52. J 3.4. 2 mic. ;
/2mte r a2 ses/ h 4
. 8aAlowo00 - UN TS 1 & 2 3/4 3-50 .
D
l 1 s 1 CTS INSERT (S) SECTION 3.3 LC0 3.3.4 INSERT 3.3 50A (4,) .
- 1. ...
- 2. Separate Condition. entry is allowed for each Function.
i INSERT 3.3 50B (du) SURVEILLANCE FREQUENCY SR.3.3.4.2 NOTE Neutron detectors are excluded from CHANNEL CALIBRATION. l I l I i i Revision A
~- . . _;
TA8tE 3.3-9 - o REH0if $HUTOOWN HONiiORING INSTRUMENTATION 6 8 TOTAL NG. MINI / .
. REA000i 0F LS l INSTRUMENT LOCATION PERA8tE '
CHANNEL $'_ h 1. Intermediate Range Neutron lux PLO6J 2 1 ,
- e. 2. Source Range Neutron Flux PLO6J 2 1 u
- 3. Reactor Coolant Temperature -
Wide Range
- a. Hot Leg PLO 1/ loop 1/ loop
- b. Cold Leg SJ 1/ loop 1/ loop 3 8
1: 4. Pressurizer Pressure . PLb6J 1 T 5. Pressurtrer level PLO6J 2 1 .
- 6. Steam Generator assure PLO4J/PLD5J 1/sta gen sta gen . .
- 7. Steam Ge ator Level PLO4J 1/ste gen 1/ste
- 8. RH emperature LOCAL 2 1 .
. Auxfilary Feedwater Flow Rate PLO4J/PLD5J 2/ste gen 1/sta gen r-0
. U.
. td !
A !
T/BLE4.3-6/ h ,' REMOTE, SHUT MONITORIP It!5TRUMENTATION i 5 / SURV4{LLANCE R6(CIRlNENT5 s _, 8 . . SK 3.3 4.I -CHANREE13RR41-' CHANNEL
, INSTRUMENT CHECK l CALIBRATION e '- I
$ 1.' Intermediate Range Neutron Flux M l RV
- 2. Sourte., Range Neutron Flux #
[ 3. ReactorCdolantTemperatur - Wide Range M /
- 4. PressurizerPhessure M [ '
- 5. Pressurizer Lev N M /
- 6. Steam Gener or Pressure < M #
- 7. Steam nerator Level M R[ / t w
} 8. R Temperature .
M R w a. 'N -
. Auxiliary Feedwater Flow Rate M R j
Az r:n 5 := r-n fThe ;p;;ifled 18 =r.th interv=1 =y 5: :::te..p;" t:12_=r.the-for cyc1; I sr.lyj- , I ; E
= ,
m L x e
.O O u - O-W Y
A e 9 y
lLo 3.3.3 . .. . , Seu A m W 5%.7 i f I S. . .L3 INSTRUMENTATION 4 .13.3 fb4 ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION tro 3.L1 M FM'8 The accident monitoring instrumentation channels shown in Table 3.3-10 i shall be OPERA 8LE.
- i APPLICA8!LITY: MODES 1, 2, and 3.
i ACTION: (3n i C ~1 A p!' With the number of OPERA 8LE accident monitoring instrumenta ion chan-C ar.13 nels less than the Required Number of Channels shown in Tab 3.3-10, restore the_ inoperable _ channel (s) to OPERA 8LE status within days; b otherwistJt: ' :t ?:::t T T m == : tv - -- - :: e ner ::: 1
+--- 4""! '"'.""^' : wi n i 2: f:16f ; 5 5:;r:. Lg ,g E. 'With the number of OPERABLE accident monitoring instrumentation Coad D channels, except the containment high range area radiation monitor, Coad E main steam line radiation monitor, and the auxiliary building vent
- s. tack wi& range.notric 21: cniter,A - "- * *- ~.'.4..do OPERA 8LE requirements of Table 3.3-10, restore the inoperable
')
- CJ -
C,. e channel (s)toCPERA8LEstatuswithinmaastijtherwise,beinat\ least NOT STAN08Y the followina 6 hours i within the next 6 h< urs anl in HOT- 5NUTDOWN within
,D cla.>o L kg,,,,,,Te,n w +., #m d, (ond D p. With the number of OPERA 8LE channels for the conta nt higt)/ rance 2 area radiation monitor. or main steam line radiation monitend lee-the4 A li; a b ildi;; 4;;; ;;;;; wic; r ;; ;;ti; ;;; -;aitoriless than the Minimum Channels OPERA 8LE reouirements of Table 3. 3-10.11ni ti ate \
an alternate method of monitoring the appropriate parameter (s) within) yg ?! W iana etener restore tne snoperable channel to OPERABLE status within 7 days,lor prepare and submit a special Report to the y j" ' commission pursuant to Specification 6.9.2 within 14 days that provides actions taken, cause of the inoperability and plans and schedule for g[7[ - h festaring the channels to OPERABLE statuq) A4, . n3 _10de. #; The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS
.St. 33 3 i I - - ' ~Each accident monitoring instrumentation channel.shall be demonstrated S R 3 3.2 2. OPERA 8LE by performance of the CNANNEL CHECK and CHANNEL CALIBRATION operations et the frecuencies shown in Table 4.3-7./
$fT Abit I .
BRAIDWOOD - UNITS 1 & 2 3/4 3-53
I CTS INSERT (S) SECTION 3.3 ! LC0 3.3.3 INSERT 3.3 53A -(L3 ) CONDITION REQUIRED ACTION COMPLETION TIME , C. Required Action and C.1 Initiate action in .Imediately
. associated Completion accordance with Time of Condition B Specification S.6.7.
not met. l I 4 Revision A 9 6
- b+ . . - - ,
- ~
Spec.10c4, 34,7 1 J j N , INSTRUMENTATION ) - ACCIDENT MONITORING INSTRUMENTATION
- LIMITING CON 0! TION FOR OPERATION I
- 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 i
. shall be OPERA 8LE. - 1 APPLICABILITY: MODES 1, 2, and 3. s . j ACTION: i i
- a. With the number of OPERA 8LE accident monituring instrumentation chan-j nels less than the Required Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERA 8LE status within 7 days; i otherwise, be in at least NOT STAN06Y within the next'6 hours and in j HOT $ HUT 00WN within the following 6 hours.
- b. With the number of OPERA 8LE accident monitoring instrumentation
' channels, except the containment high range area radiation monitor. sain steam line radiation monitor, and the auxiliary building vent . l . - stack wirier ranga .nogle g:: :::enitor,1..;. th :; thc ".i. k;:.:. "..'.a ....I. 4 OPERABLE requirements of Table 3.3-10, restore the inoperable 1 ' s ' diannel(s) to OPERA 8LE status within 48 hours; otherwise, be in at
'j '
least NOT STANOBY within the next 6 hours and in FOT SHUT 00WN within the fallowi.ng.6 hours.
- c. With the number of OPERA 8LE channels for the containment high range area radiation monitor, or main steam line radiation monitor, or the auxiliary building vent stack wide range noble gas monitor less than the Minimum channels OPERA 8LE'reevirements of Table 3.3-10.Ita;:::t:
. (, . /
L' 6M.;i..._ a .t ;f ;;c. fir + - th: ;;.,-;;ri;;; :::r: :nr(0 .;i th 8-h::r: land either restore the inanerah' '. ehanami i to OPERABLE status [ _ , _ within 7 days.]or prepare and submit a Special Report to,the - A/dr<.ss,d /o wm.3 C'""ission pursuant to specification 6.9.2 within 14 days that provides w ;=. = = d cause bf the inoperability and' plans and schedule for
.5 n occs Ag+33 7,,g,7. ng the channels to'0PERA8LE status,
- d. The provisions of Specification 3.0.4 are not applicable.
Qn QVfl na od 4b. pr(ples.pd O[' 3 i o l5tenede rntOOO O $ enon.4er.en , SURVEILLANCE REQUIREMErlT5
~
4.3.3.6 Each accident. monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. *
.u. g i
$ BRAIDWOOD - UNITS 1 & 2 3/4 3-53 . - l
-L . -
./
. .)
. i
~
~ .
j 3 3 5-s _TA8tE 3-9-44, - E
"$ INSTRl44ENT ACCIDFNT HONITORING Ih$iRUMENTATION fREQUIREOl N
INIMist MANNELS e i
< CHANNEL 5; O 7E Containment Pressure ERA 8tE
- 2. .
2 41 g Reactor Coolant Outlet Temperatura - Tgy.(Wide Range) 2 a g 3. Reactor Coolant inlet Temperature - TCOLD (Wide Range) . 2- ' y I f: Reactor Coolant Pressure - Wide Range 2
** 1 (o S. Pressuriner Water Level 2 1 -
t B E. Steam Line Pressure ! 2/ steam generator 1/s eam se ratoi 5% Stess Generator Water Level - Narrow Range ', 1/ steam generator 1/st as g eratoi
.4 # Steam Generator Water Level - Wide Range ; 1/ steam generator 1/st a nerator
- 9. Refueling Water Storage Tank Water Level '
2 1 j R IID - ^p ! 1 Feedater Flow Rate - 2/ steam generator
, 1,/ste generIGi !
[ 11. PbRV Position In c Closed) 1/ Val.ve- 1/Valv i h 12. PORV Block Valve Position Indicator ** (0 pen alve 1/Valv
- 13. Safety Valve Position _.IndicatM0peii7 Closed) 1/ Val e 14 C;.is175Ent Floor Drain Sump Water Level (Narrow Rance) 2 -
to 15. Containment Water Level (Wide Range) 2 1 13.16'. In Core Thermocouples 4/ core quadrant 2/c re quad at 1117. Containment High Range Area Radiation. l@ 1
^
[1.a ..=lliery-Buildleg-Vent-Stech -Wid: "=;; nom: S: '
-N.". 18t::t ti lt. Main Steam Line Radiation I @ [3+mthe sta line 1420' Reactor Vessel Water Level 2 t~
M--ReactoMeelant--Subcoo1Ing Margin Monitor 2*** j [1*** O u f **N appilcable' lf the as ated block va'Ive is in closeil pos (lon. U
*N t appilcable if the b k valve is v/rlfled in t closed pos Ion and p is remov va O ** .
Usemonjitfingchannej (10 highest 'verage core xit tessera res) In to unction - with RCy Pressure (jrea 4 above) determine e subcoolin margin. _ _ }
@**Lf . r :) ~
i ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g INSTRUMENT 233.3., _fCHANNEL CHECKj $HANNEL CAllBRATION b 5g 3 3.3.z 5 7 +. Containment Pressure M FF
- 2. Reactor Coolant Outlet Temperature - THOT (Wide Range) M pp *
. 3. Reactor Coolant Inlet Temperature - TCOLD (Wide Range) M 51' E l 4: Reactor Coolant Pressure - Wide Range M' R P d 6 9. Pressurizer Water Level M R r
- 84. Steam Line Pressure M R P I I e.
m 5 +. Steam Generator Water Lgvel'- Narrow Range M R P d 4. Steam Generator Water Level - Wide Range M R P l
- 9. Refueling Water Storage Tank Water Level M R P i Il0. Auxillefy Feedater low Rate M R
- 11. PORY osition In cator* (0 pen / losed) A.
. 12.. PO Block Valve Position In cator** (Ope / Closed) M N.A. j w 13. afety Valve osition Indi tor (0 pen /C1 sed) M N.A.
x
*- 14. Containeerg Floor Orain Water' Lev (Narrow R nee) M R#
w J, 10 -15. Containment Water Level (Wide Range) M Ut 13 -1 6. In Core Thermocouples M -v' I 88 -14 . Containment High Range Area Radiation M R ** ;
- 40. Asiliary Suf fdine-Vent-Steck -Wide hange-Noble-Ges M T 12.19- Main Steam Line Radiation M' .Rii
, kx M f9. Reactor Vessel Water level . M R1 y . m *Not plicabi f the/ associate ' block valve is infhe closefdosition. / !
** appilca e if blockylveisvdifiedip/the close (positio, nd powerA s remov .
k gg ~g[gk***4= CHANNEL CALIBRATION N:
=z = = e= =-e= = 10.and-._.i h
= = = = = = nmmreu _ = . am7 enrict ef er electronie-ca14bration-of-the-chan w ar.usme = g=tel o ==e. r L
/ !!he ces-iTied- IS enth interve! ::V 5 jtxtended tej2_-month;__fsr_..qql_t _1 cr1v-L-Q g
Sech 33 l 1.kTRUMENTATION MONI RING INSTRUMENTATION 1 l LIMITING NDITION FOR OPERATION l l
-3.3.3.7 \
(ini. y=wiiic.i.ivn numver i not-usedd I e
. . l
/
/
/
/
/
./
l
/
/ '
e 6
/
l
/
/
/.
,/ .
/
/ \
x
/ N.
, e e
e t B 6 BRAIDWOOD - UNITS 1 & 2 3/4 3-56
secha 3.3
. . e. . ..
(it.i; 'd 's r. d ,er is ret s. W
- v. .a ,..._ ,. . ,./,- -
(iii;e tid,le r.w aer-is-mot-used
,/
/
/ .
/
/
,i
/
/ \
\
/
/
/
/
s l BRAIDWOOD - UNITS 14 2 3/4 3-57 AMENDMENT NO. 35
. - - - - . . . . - - - - . - . . . - - . . . - _._ _ . ...~.- .- - .- . - .. - . - -
t INSTRUMENTATION LOOSE-PART DETECTION SYSTEM Eu LIMITING b'NDITIONFOROPERATION
- ~
3.3.3.8 The Loose-Part Detection. System shall be OPERABLE. APPLICABILITY: MODES 1 and 2. . i ACTION: i . i . a. With one or,more Loose-Part Detection System ch nels inoperable for more than 30 days, prepare and submit a Spec
- Report to.the Commission pursuant to Specification 6.9.2 thin the next 10 days outlining the cause of'the malfunction a the plans for restoring the channel (s) to OPERABLE status,
- b. The provisions of Specification 3' .3 are not applicable.
I SURVEILLANCE REQUIREMENTS
\.
4.3.3.8 Each chann .\ of the Loose-Part Detection Systems shall he demonstrated OPERABLE by perfo nce of:
- a. A ANNEL CHECK at least once'per 24' hours,
- b. An ANALOG CHANNEL OPERATIONAL TEST'except for verification of s'etpoint at least once per 31 days, and ,
I
,/ c. A CHANNEL CALIBRATION at least once per 18 months.
O BRAIDWOOO - UNITS 1 & 2 3/4 3-58 AMENDMENT NO. 38 8
4 S eeWo a 33 /
. ' hSTRUMENTATION RAD ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITIN CONDITION FOR OPERATION 4 \ /
0.0.0.9 ( is specification number-is-not-used.') l
/ {
/
N . I i 1 5 l l I 4 a h 4 1 e .\\ f
's
, N\
/ \
j - s
/ :N
.)
/ s %
/ y N
4 BRAIDWOOD - UNITS 1 & 2 3/4 3-59 AMENDMENT NO. 35
1 I STRUMENTATION - EXP IVE GAS MONITORING INSTRU ENTATION LINITING C DITION FOR OPERATION 1 3.'3.3.10 The exp sive gas monitoring instrumentation cha'nnels shown i able 3.3-13 shall be OPE BLE with their Alarm / Trip Setpoints set to ensur that the limits of Specifi tion 3.11.2.5 are not exceeded. APPLICABILITY: As shown Table 3.3-13
' ACTION: .
- a. With an' explosive gas nitoring instrument on channel Alarm / Trip Setpoint less conservati than required the above specification, declare the channel inoper le and take e ACTION shown in Table 3.3-13.
- b. With less than the minimum numbe f explosive gas monitoring'instru-mentation channels OPERABLE, t e e ACTION shown in Table 3.3-13.
Restore the inoperable instr ntat n to 0PERABLE status within 30 days and, if unsuccessful, repare an submit a Special Report to the Commission within the ne 30 days purs nt to Specification 6.9.2 to explain why this inop ability was not to ected in.a timely manner.
- c. The provisions of pecification 3.0.3 are not pp,11 cable.
SURVEILLANCE REQ EMENTS
/
~
l .
!4.3.3.1 Each explosive gas monitoring instrumentation channel shall be idemony rated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRAT N andAIGITALCHANNELOPERATIONALTESTatthefrequenciesshowninTable4.3-9.
O BRAIDWOOD - UNITS 1 & 2 3/4 3-60 AMENDHENT NO. 38
\ ~
in N ' TA8tE 3.3-13 b EXPLOSIVE GAS MONITORING INSTRtMENTATIONI l N MINIMUM CHANNELS ~ INSTRUMENT OPERABLE i x APPLICA8ILITY ACTION E 1. (Not Used)
-e t pJ
- 2. (NotUsed) !
i
** 3.
~
=
m Gaseous Waste Management Syst ,
- a. Hydrogen Analyzer (OAT-GW8000 1 ** . 38
- b. Oxygen Analyzer (0AT-GW8003) ** 38 I
- c. Waste Gas Compressor Discharge i OxygenAnalyzer(OAIT-GWOO4) *** 38 R.
j Y~ TABLE NOTATIONS .
*(Not used)
**During WASTE GAS HOLDUP
***During Waste Gas Comp TEM operation. \ -
ser Operation. l All instruments re red for Unit 1 or Unit 2 operation. ~ ' ACTION STATEMENTS ACTION 3 ' With the number of channels OPERA 8LE less than required by the Minimum Channels 0PERABLE I requirement, operation of this system may continue provided grab samples are taken and analyzed at least once per 4 hours during degassing operations and at least once per 2 r.s hx during other operations. . n 3 . 3 g - w i W t ta
~
l
, N, TABLE 4.3-9
~
b ' g o xN EXPLOSIVE GAS MONITORING INSTRUMENTATION S'URVEILLANCE REQUIREMENTS DIGITAL
- FUNCT10NAL UNIT
'\ CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL OPERATIO SURVEILLANCE ES FOR WIICH TES IS REQUIRED g 1. (Not Used) I
[ 2.. (Not Used)
- 3. Gaseous Waste Management System ~
- a. Hydrogen Analyzer (OAT-GW8000)' D N. Q(4) M **
- b. Oxygen Analyzer (OAT-GW8003) D N.A. Q(5) M **
R c. Waste Gas Compressor Discharge' N i [. 0xygen Analyzer (OAIT-GWOO4) . N.A. Q(5) M *** , l S TABLE NOTATIONS
- t l
t
. *(Not used) ;
**During WASTE GAS HOLDUP SYSTEA operation. :
***During Waste Gas Compresfof Operation.
#All instruments requir(d for Unit 1 or Unit 2 operation.
/
(1) (Not Used) 7 < (2) (Not Used) g (3) (Notded) I E e CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and ni en. "
! ,(4)
J (- ) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen. t 4 .- I i E
- u i u .
. t
1 hSTRUMENTATION - HIG ENERGY LINE BREAK ISOLATION SENSORS {- N Es x LIMITING CONDITION FOR OPERATION i / 3.3.3.11 The hi
\
i energy line break instrumentation shown in Table 3.3-1 shall be OPERABLE. APPLICABILITY: As shown in Table 3.3-14 ACTION:
- a. With the number of OPERABL uxiliary steam ~isolat' n instruments less than the Minimum Channels OPE LE as required Table 3.3-14, restore l the inoperable instrument (s) to ERABLE sta within 7 days, or suspend 4
the supply of auxiliary steam to t Auxil' ry Building, or establish a ! continuous watch in the affected are s ntil the inoperable sensors are restored to OPERABLE status. i b. With the number of OPERABLE stea geaerato blowdown line isolation instru-i ments less than the Minimum C nels OPERABL as required by Table 3.3-14, i restore the inoperable inst nt(s) u OPERAB status within 7 days, or limit the total steam ge ator blowdown flow ra to'less than or equal ! to 60 gpm or establish continuous watch in the e the inoperable senso cted area (s) until are restored to OPERABLE stat c, The provisions Specification 3.0.3 are not applicable. l I i SURVEILLANC{QUIREMENTS s 4.3.3. Each of the above high energy line break isolation instruments all ; be onstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONA
- pS and' CHANNEL CALIBRATION at least once per 18 months.
I ~ 4 i i 3 ! BRAIDWOOD UNITS 1 & 2 3/4 3-63 AMENDMENT NO. 38
T S cch 33 TABLE 3.3-14 i HIGH ENERGY LINE BREAK It'STRUMENTATION 150 10N INSTRUMENT MINIMUM CHANNELS APP ABLE FUNCTI CHANNEL OPERABLE . A00ES
- 1. Auxil. ry Steam OTS-A5031A 1 *
- Isolati OTS-AS032A
~
! OTS-A5031B 1 *
. _ OTS-A5032B
! 0TS-A503'C 1 1 /- * ,- DTS-A5032C 4 TS-A5031D
- i O' -A5032D OTS- 031E- 1 *
- OTS-ASb 2E ..
i ! OTS-AS031 1
- j OTS-A5032F .
~ ~ '
- 2. Steam Generator - TS-SD045A 1 1, 2, 3, 4 Blowdown Line TS- SB i
Isolation TS-50046A 1 1,~2, 3, 4 j T -500468 TS-SD045C ' 1 1,2,3,4 . TS-SD045D l TS-SD046C 1 1,2,3,4 TS-SD046D i ) !
/Requiredwhenauxiliarysteamisbeingsupplied,fromanysource,tothe .
./ Auxiliary Building.
i . 1 0 0 [ BRAIDWOOD UNITS 1 & 2 '3/4 3-64 , AMENDMENT NO. 35 -
i 4 s l iNSTRUMENTAkION 3/b.4 TURBINE OVERSPEED PROTECTION K . LIMIT CONDITION FOR OPERATION #
/
3.3.4 At east one Turbine Overspeed Protection System shall be OPERABLE'. j APPLICABILI MODES 1, 2, and 3. 1 ACTION: l l a. With one hrottle valve or one governor valve per high essure turbine- ! , steam line inoperable and/or with one reheat stop val or one i reheat inte apt valve per low pressure turbine st line inoperable, i - restore the perable valve (s) to OPERABLE statu thin 72 hours, i or close at le t one valve in the affected steam line(s) or isolate j , the turbine f the steam supply within the 6 hours. - 4 l b. With the above req ' red Turbine Overspeed P taction System otherwise l ! inoperable, within 6 ours isolate the tu ne from the steam supply. i j , SURVEILLANCE REQUIREMENTS r l l 4.3.4.1 The provisions of Specifications,4 .4 are not applic~able.
\
! 4.3.4.2 The above required Turbine 0v sp d. Protection System shall be
- demonstrated OPERABLE
- -
I l
- a. During turbine operation t least once per 31 days by direct obser-j -vation of the movement f the valves ow through one complete cycle
, from the running posi lon:
- I
- 1) Four high pre ute turbine throttle v ves,
- 2) Four high p ssure turbine governor va es,
- 3) Six turbi reheat stop valves, and Six turbi reheat intercept valves.
[ :
, 4) l I b. Within 7'da prior to entering MODE 3 from MODE by cycling each L of the 12 xtraction team nonreturn check valves on the closed
[ position
~
i c. Durin turbine operation at least once per 31' days by ' rect observa-I tion of freedom of movement of each of the 12 extractio steam non-l re rn check valve weight anos, , l d. least once per 18 months by performance of CHANNEL CALIB TION i on the Turbine Overspeed Protection Systems, and
- e At least once per 40 months by disassembling at least one of ea of the valves given in Specifications 4.3.4.2a. and b. above, and pe forming a visual and surface inspection of valve seats., disks and j stems and verifying no unacceptable flaws or corrosion.
~
j. J t ! BRAIDWOOD UNITS 1 & 2 '3/4 3-65 AMENDMENT NO. 35
- l LCO 5,4.41 4
, 3.'l SM-43 REACTOR COOLANT SYSTEM, (Ac.5)
C/0.0.; : ACTO 000L'"T LOOPS ^!:0 COOL'"! CIRCUL^TIOC i' UT'"Tur ^!: ^^'; Or;;;.TIO !Mg,q,y acs L.,,p - Mopas l and 2.)
- LIMITING CONDITION FOR OPERATIONS L.c.o 5.4.4 . o PERAs w e d An N All reactor coolant loops shall beiin operation.
i APPLICABILITY: MODES I and 2. i ACTION: 4 l CoHp A With less than the above required reactor coolant loops in operation, be in l at least HOT STANDBY within 6 hours. , I l l l
. l l
4 j SURVEILLANCE REQUIREMENTS SK 3.*t.4.l (4-4-h-H The above required reactor coolant loops shall be verified in operation (ere cir ::::::: c:;;ter coeler,U at le u t once per 12 hours. LAs t l ("See Sg w o; Twai Eurgi.un. Syww;T; cot;vn 0.10. 4.) A6 i e BRAIDWOOD - UNITS 1 & 2 3/4~4-1
_.. _ _ _ . _ _ _ _ _ _ _._ .. _ .._.m._. _ __
~ . , a, 34 REACTORCOOLANTSYSTEM(RCS) t GP*M4 of rmL Mhal t=T ST ^.== L__- (44# - Rc6 Loop + -M#P' 3) m LIMITING CONDITION FOR OPERATION M At least two of the reactor coolant loops " ' ' 'shall be v .
, OPERABLE with two reactor coolant loops in operation when the c:::t:r M : ;
-; ;nt:; =:: ::: ::: ::::.3 and one reactor coolant loop in operation when the
' c:::t:r '-:: R:t:: tr::t:r: n; ::nl. p%g,
.3 g ugg, ,f , A ggwG Reactor Coolant Loop A and its associated steam generator ,
r coolant pump,- LJ
- b. Reactor Coo o B and its associat am generator and reactor coolant pump, g
- c. Reactor Coolant Loop ts ated steam generatoi and C:V reactor coolan , and
- d. Rea oolant Loop D and its associated steam ge r and y actor coolant pump.
APPLICABILITY: ' MODE 3. w c,,u,t spie ,, ACTION: _ con D C lla w + .1 A-18 t.ONp P y Wth le?? th?r the above required reteter coc!!'it leeps OPERABLE, restore the required loops to OPERABLE status within 72 hoursf or ce} usP F. 'in HDT 5HUIDOWN within the neXL 12 nours. J Co@ h y' ,With only one reactor coolant foop in operation and the er :t:r '-t:f _ y gm ,', int:: truir. '- th: :1: nc ::::::: ] within I hour = er M ::t:ri I
- :=t:: trut:r:4 %,,%.w%w,aw a3ury,q.g
$"jfc M ,l k g. j With no reactor coola'nt loop in operation,tsuspend all oper ions involving a reduction in boron concentration of the Reactor Coolant uM F C. A M. Systemfand immediately initiate corrective action to return thel I Mw ?' C'3 ' required reactor coolant loop to operation.J co W D F f.'l'e.serl 3 A *2 6 '
SURVEILLANCE REQUIREMENT
.A M.f 3 G. ".1.2.D At le'ast the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
n M C GMTF:B The required steam generators shall be determ'ined OPERABLE by verif ing secondary side narrow range water level to be greater than or equal to for U it 1 for Unit 2) at least once per 12 hours. W LS 9.346.1 4"E4TE e required coolant loops shall be verified in operation -r a < - - <
' 1: tin; r:n ta a;; st)at least once per 12 hours.
g
*All Reactor Coolant pumps may be' d::= r ;. : forupto1hourhprovided:
per s W.- pe<.e4 ) . tzo Nerc (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is
- maintairied at least 10*F below saturation temperature.
(**:: 0; uif in t R u pti a. 0;nifisti n 2.10.4. , BRAIDWOOD - UNITS 1 & 2 3/4 4-2' ,
I i CTS INSERT (S) SECTION 3.4 LC0 3.4.5-INSERT 3.4 2A (L3 )
~l CONDITION REQUIRED ACTION , COMPLETION TIME A. One required RCS loo) A.1 Place the Rod Control I hour
, not in operation wit 1 System in a condition Rod Control System incapable of rod 4 capable of rod withdrawal. !
withdrawal. INSERT 3.4 2B (Ln)
. CONDITION ' REQUIRED ACTION- COMPLETION TIME Cl Two required RCS loo)s C.1 Initfate action to Immediately j
'not in operation witi- place the Rod Control Rod Control System System in a condition capable of rod incapable of rod withdrawal. -
withdrawal.
.QB MD I Required Action and C.2 Suspend all Immediately associated Completion operations involving Time of Condition A a reduction of RCS not met, boron concentration.
1 MQ C.3 - Initiate action t'o Immediately l restore RCS loop (s) 1
. to operation.
Revision A
i i l CTS' INSERT (S) SECTION 3.4 LCO 3'.4'5 INSERT 3.4 2C (Ln) - i CONDITION REQUIRED ACTION COMPLETION TIME [ F. Two required RCS loops F.1 Initiate action to Immediately
- . inoperable. place the Rod Control System in a condition incapable of rod withdrawal.
AND F.2 Suspend all Immediately operations involving a reduction of RCS boron concentration. AND F.3 Initiate action to Immediately _ restore one RCS loop to OPERABLE status. 6 Revision A
, W G.7 t w 3
i j 3.si ' REACTOR' COOLANT SYSTEM (Rc.5) twp-emeeWu) (s.v.6 es L n, - Hope. 4) LIMITING CONDITION FOR OPERATION j Le.o s.u (*d *5 "$ ** ^"Y o'* W *** **
- W 5 8**r* A4
- M h**+ f* *** (R eAHaan)
ET:E3.R At least two of the loopst"t:d i:';J shall be OPERABLE and at least
- one of these' loops shall be in operation
- "
j Reactor Coolant Loop A and its associated steam generator and reac 7
- lant pump,**
i i b. Reactor nt Loop B and its associated steam ge er and reactor !' coolant pump,
- c. Reactor Coolant Loop C a ts ass ed steam gr.nerator and reactor coolant pump,** -
- d. Reactor Coolant Loo and its associate eam generator and reactor coolant pump,** -
I' e. RHR A, and j . RHR Loop B'. . / APPLICABILITY: MODE 4. .I ! ACTION: 1 E: With less than the.above required reactor coolant and/or RHR loops
>> 11l LA R.I OPERABLE, immediately initiate corrective action to return the l W C L A C.1.
required loops to OPERABLE status as soon as possiblet/IN I, c.g g ag,ggj,4g[ remaining DPERABLE loop is an RHR loop lbe in COLD SHUTDOWN within ! Comb B AA B.t. 24 hours. 1 l W P A " A-(WithnoreactorcoolantorRHRloopinoperation,suspendall As i operations involving a reduction in boron concentration of the
#I C ** U
! LReactor Coolant Systemiand immediately initiate corrective action to il de0AAAA2 return the required coolant loop to operation. Q wed % operJ Q Ptr 8 h**' W k ). L.f o tkre. t All-reactorcoolantpumpsandRHRpumpsmaybedn.L.:
/ _ d for up to I hour provided: (1) no operations are permitted that would cause dilution of the
' Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at.least 10*F below saturation temperature. - LCD H** ' ""'A reactor coolant pump shall not be started with one or more of'the Reactor l~ Coolant System cold' leg temperatures less than or equal'to 350*F unless the secondary. water temperature of each steam generator is less than 50*F above !. each of the Reactor Coolant System cold leg temperatures. } BRAIDWOOD - UNITS 1 & 2 3/4 4 13 I
~
- .-o a ,. w REACTOR COOLANT SYSTEM I SURVEILLANCE REQUIREMENTS sk s.4.6.3 N The required reactor coolant pump (s) and/or RHR pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker-'alig sand indicated power availability.
6A3.44.A Ls i i (+r4-l-a-M e quir team generator (s) shall be determined OPERABLE by verif i secondary narrow range water level to be greater th'an or equal tol or Unit 1 ( for Unit 2)'at least once per 12 hours. Se, s.4.t.. I ' 3 3 ** _ [N rehite/l Ag
" 1. 2. 22 71 !:::t r.B reacto oolant or RHR loop shall be verified in operation trd :tr::::t.E; r ::::7 cula..D at least once per 12 hours.
O l O k 9 4 0 5 BRAIDWOOD - UNITS 1 & 2 3/4 4-4
_ - . _ _ _ . _ _ __._-~.____ - _..._..___.____.._ _ _ _ _ _ _ _ _ _ m.._.___. . _ _ _ , t LCo 3A.7
~
4 4 . 3 4 REACTOR COOLANT SYSTEM (R(5) - ) (COLO OF.C00= LOOP; M LLC 3.*l.7 Rt s Leops - Nope.5, t n Rile () l { LIMITING CONDITION FOR OPERATION i Lt.o M .7 G:f:EM:0 At least one residual heat removal (RHR) loop shall be OPERABLE and
- in operation *, and either
} L c o M ,7. - r.- One additional RHR loop"shall be OPERABLE #, p - i l Lt.h 3.474 K. MID--- j (The secondary side narrow range wLter lese at _ ast two si.eam i SR 3.at.7.L 1 generators shall b greater than GB for Unit 1 (W for Unit 2).) occuauWA,
, APPLICABILITY: MODE 5 with reactor coolant Toops filled ##.
t ACTION ,g,.y 34.g4
- a. (WithoneoftheRHRloopsinoperableGnuwithlessthantherequired cnp g RA S.l L steam generator level, immediately initiate corrective action to g
CAN P S M B.7-0 eturn the__inonerable RHR loon to OPERABLE statusfor restore the required steam generator lleveM as soon as possible. K 14e cerAA cts s+.b H9 - cos? A R A A.t WithnoRHRloopinoperation,suspendalloperationsinvolvingja reduction in boron concentesLion of Line Avect.or Cooiant systemJano 49 g immediately initiate corrective action to return the required RHR loop to operation. SURVEILLANCE REQUIREMENTS
'St,s.4 7. t.
( Na occ.c.1. c.1.13 The secondary s'ide water level of at least two steam generators when required shall be determi o be within limits at least once per 12 hours. 6F3.4.7.l '**' "ON > M t.^t 1:;;;t ;.QRHR loop shall be determined to be in operation '
, / e q;.1 t t . r:::t:r :::::no at'least once per 12 hours. g
~ S e. 3.'t.7.5 = Mseer M-SA 1 g g g W **- 1 "The RHR pump may tie'dasanagedd for up to 1 hour ovided: (1) no op'e rations are permitted that would cause dilution of the Reactor Coolant System baron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
Lto NoTf :L #0ne RHR loop may be inoperable for up to 2 hours for surveillance testing provided the other RHR loop is OPERABLE and in operation. Lt.o Norf.3 ##A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 350*F unless the secondary water temperature of each steam generator is less than 50*F above
, each of the Reactor Coolant System cold leg temperatures. ,
. g BRAIDWOOD - UNITS 1 & 2 3/4 4-5 n -
s CTS INSERT (S) SECTION 3.4 LCO 3.4.7 , INSERT 3.4 5A (Hn) i !- CONDITION REQUIRED ACTION COMPLETION TIME i l 'C. Two required RHR loops C.1 Suspend all. Immediately . inoperable. operations involving
. a reduction of'RCS
- QB boron concentration.
4 Required RHR loop AND inoperable and one or . bot 1 required SGs C.2 Initiate action to Immediately 1 inoperable, restore one RHR loop i - to OPERABLE status. . l I 1 j INSERT 3.4 5B (M3 ) 4 SURVEILLANCE FREQUENCY SR 3.4.7.3 Verify correct breaker alignment and 7 days indicated power are available to each required RHR pump. 4 Revision A
,v- . - , , - r ,- - , w w
4 i 1 CTS INSERT (S) . SECTION 3.4 ! LCO 3.4.7
- i l INSERT 3.4 5C (Ly)
- NOTE
~ 4. All RHR loops may be removed from omration during planned j heatup to MODE 4 when at least one ICS loop is in operation.
i l 1 i' . a 4
. a
.i s Revision A H G
- g. e--, .- ,
LCO 3.'t.8 4
, FA REACTOR COOLANT SYSTEM (r.c.6)
(C0LO 5"'.'T00P' - LOOP: NOI T LLE0Q4.'t,T RC5. Laep+- MOPE- 6 4.,,o N,t Atlad) . LIMITING CONDITION FOR OPERATION t.co 3.4.T ET.3:"4:F) Two ' residual heat ~ removal (RHR) loops shall' be OPERABLE
- and at-i least one RHR loop shall be'in operation.** '
! APPLICABILITY: MODE 5 with reactor coolant loops not filled. ACTION: p 5 4 X. With less than the above required RHR loops OPERABLE, immediately cogp c Ag e a. initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible. fWithnoRHRloopinoperation,suspendalloperationsinvolvingja
- N4RA .
"* (reductioninboron'concentrationoftheReactorCoolant'Systemfand k)X.
immediately initiate corrective action to return the required RHR j t.sNpA A4 A.A loop to operation. . coup c IIns er4 3 4 - (. A SURVEILLANCE REQUIREMENTS 6R SA.t.) C4. 4.1. 4. ") We resulcelf I it !:::t : ::RHR loop shall be determined to be in operation jetreal: tin: r:::t:r :::1:r.3 at least once per 12 hours. 5R. 3.4.t.> +--U;nss str 3A- 6 8) 4 Lt.o NorE A *0ne RHR loop may be inoperable for up to 2 hours for surveillance testing provided the other RHR loop is OPERABLE and i peration. Gov.a % . m Au tt.o NorE- I **The RHR pump may be d:! -W-d for up to 1 ho provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and-(2) core outlet temperature'is maintained at least 10*F below saturation temperature ( $ $ h$ $ 0 ( redu.e ne. Acs 4.rahr Volan. j BRAIDWOOD - UNITS 1 & 2 3/4 4-6
. _ _ .. . _ _ . . _ . _ _ . , . . . - . _ . . _ . _ _ _ _ _ _ _ _ . . . . ~ __. _ . . . . . _ _ - _ _ - . _ . - . _ -
N ! CTS INSERT (S)
- -SECTION 3.4 i
LCO 3.4.8 l INSERT 3.4 6A- (M13 ) i CONDITION REQUIRED ACTION COMPLET10N TIME
- C. Two required RHR C.1 Suspend all operations Innediately i loops inoperable. involving reduction in
- RCS boron -
i concentration. I M@ C.2 Initia'te action to Immediately restore one RHR loop to - OPERABLE status. INSERT 3.4 68 (M ) 1 SURVEILLANCE FREQUENCY SR 3.4.8.2 Verify correct breaker alignment and indicated 7~ days power are available to each required RHR pump. G A 4 Revision A i
. _ . . _ __ _ _... _ _ _ ~ .. _ _ _ ____ _. _ _ _ .. _ .._ _ _ _. .. _. _ _ _ _ _ _ _ _ _ _-.~. _ _ - .
1 \ t . Lt:.D L 'l, I 7 . l i d 1 4 l 1 a 3.4 REACTOR COOLANT SYSTEM (gc.5) l 1 . e
- i 3.'f. l 7 LOOP ISOLATION VALVES .,
. l 1
i l , . LIMITING CONDITION FOR OPERATION i 1 l tto 3A. i 7
~
i .. .- l !. . N All RCS loop isolation valves (hot leg and cold leg stop valves) ' shall be open and power removed from the isolation valve operators. A
' APPLICABILITY: DES 1, 2, 3,'and 4.
[, g % mg c ,% , 4 : (mur sw-re T w Actions nors.-CrdssAv 34-74 , ap3 AGHW With any RCS loop isolation valve closed, (-"---- - -- - -' -" '- ' and be in at least HOT SHUTDOWN within 6 hours and in at least COLD' within the following 30 hours. CA @ t NorE ; ( ensar a.# 7C h .y. '^
*L'::vCILLANCE.
. ::EMEME::TS n.. . .: 2:... ' : .
li m" SP, 3A.tT. \ . N All RCS loop isolation valves shall be verified open and power removed from the isolation valve operators at least once per 31 days.
't h
4 e o en e .e
. BRAIDWOOD - UNITS 1 & 2 3/4 4-7 iJ -
l l CTS INSERT (S) 4 SECTION 3.4 LCO 3.4.17 INSERT 3.4 7A (L.)
- ACTIONS NOTE l
Separate Condition entry is allowed for each RCS loop isolation valve. i l l 3 INSERT 3.4 7B (L6) CONDITION . REQUIRED ACTION . COMPLETION TIME l A. Power available to one A.1 Remove power from 30 minutes or more. loop isolation loop isolation valve valve operators. operators. l l JNSERT 3.4 7C (An ) ,
- CONDITION REQUIRED ACTION COMPLETION TIME B. NOTE All Required Actions shall be completed whenever this Condition is entered. .
t -t Revision A e 4
L Co 3J/.'l8
.v i
.1,'f REACTOR COOLANT SYSTEM (Ar 5) 3.M.13 (kOGG COLATION VALV:0( fRc.5 L. ops - T.s.\a4ed ]
l M ' LIMITING CONDITION FOR OPERATION Lt.o '3.4.19 j Nvalves If an closed RCS loopuntil:is isolated, maintain the hot leg and cold leg stop ' 6towreer.shhko.untrores% ss a. The boron concentration o othe isolated loop is greater than or equal boron concentration of the(r;; e= .r: 're:J,and I any e.ela t WQA l ' b. The temperature otetne cold Teg of the isolated loop is within 20*F of the hiahest cold le temperature of the Far- m ac ma y g s APPLICABIL Y: E5 5 nd 6. .. 'i5'I"**d ? " b '
! MA
/ ACTION: With the requirements of the above specification not sitisfied, do not) lopen either the hot leg or cold leg stop valves.f Lq SURVEILLANCE REQUIREMENTS f
i
$R 3.4.lt.1 .
G.4.1.5.2.11 The isolated loop cold legitemperature shall be determined to be _ Y" - within 30 minutes 20*F of thetohighest prior o ing cold leg temperature of thep peret4no-Joop4 within Att } the cold leg stop valv.e. S A 3.4.lf. 2,. lany coolant w] ,g gg4
- G.4.1.;.2.3 The boron oncentration of +an isolated loop shall.,be determined to be grea er than or equal to the n I
within hours prior to opening boron concentration of thelcr: Nttec 'ee60 either the hot leg or cold ' leg stop valves' of an isolated loop. '
.~
4 [reguired shad %M mar $d 4 l i I l i BRAIDWOOD - UNITS 1 & 2 3/4 4-8 l I
l 1 l l
.. _ _ . . _. Sec h 3.4 .
MEACTORCOOLANTSYSTEM 3 4.2 SAFETY VALVES.
- SHUTD0 3
LIMITING CD TION FOR OPERATION ' j J 3.4.2.1 A minim of one pressurizer Code safety valve shall be OPERABL ith i i a lift setting of f485 psig i IL
- APPLICABILITY: MODES 4.and 5. !
ACTION: N
/
l~ , ,/ l With no pressurizer Code safety valve OPERABLE, immediately p0 spend all opera-
,tions involving positive react'ivity. changes and place an.0.PERABLE RHR loop into operation in the shutdown cooli mode.
/
- \,
i '
,/
f s,' i i
/\
, SURVEILLANCE REQUIREMENTS .
\
'o , i
.. \
4.4.2.1 No addiiional requirements other than thos6s
,. \ required by Specification 4.0.5. ,.'
4
'g s .
4 N
/
[ \. ~
/ ,
'e l; ,- \
\ .
1 1
+
/,
'. i l
i
- l"T e lift setting pressure shall correspond to ambient conditions of the valve l ! at nominal operating temperature and pressure.
1 BRAIDWOOD - UNITS 1 & 2 3/4 4-9 ) .
,, --m . -. - , , ,
i ltD 3. 4. IO
- 3.y RFACTOR COOLANT SYSTEM (Rcs) . .
3.4.to Prusar! car $4e.y Alvas
. j LIMITING CONDITION FOR OPERATION LLo M.so M All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig 2 ILF j APPLICABILITY: MODES 1, 2, and 3.
ACTION: GONP 4 With one pressurizer Code safety valve inoperable, either restore the inonerablevalvetoOPERABLEstatuswithin15minutesorfbeinatleastHOT] con 9 8 [ STANDBY within 6 hours and in at least HOT SHUTOOWN within the fcilowing ]
\ 6 hours.f-W0= (TN6 La T 3,4- tO b) '
1 SURVEILL'ANCE REQUIREHENTS ttt3.8.8e.1 M No additional requirements other than those, required by Specification 4.0.5. Lco More : (yg gar ,g,g.fo4)
~
["Thelift[ettingpressureshallcorrespondtoambientconditionsofthevalve) i at noniinal operating temperature and pressure.f 9 f e s 3/4 4-10 BRAIDWOOD - UNITS 1 & 2 .
1 -' _. _ CTS INSERT (S) SECTION 3.4 2 LCO 3.4.10 ~ INSERT 3.410A- (Mu ) NOTE The lift settings are not required to be within the LC0 limits during MODE 3 for the puraose of setting the pressurizer-safety valves under hot conditions.' T11s exception is allowed for 54 hours following entry into MODE 3.at normal operating temperature and 3ressure provided a preliminary cold setting was made prior to leatup. 1 f
- INSERT 3.4 10B (MS ) -
4 CONDITION REQUIRED ACTION COMPLETION TIME a B. .. B.1 Be in MODE 3. 6 hours QB 6ND Two or more B.2 Be in MODE 4. 12 hours
- pressurizer safety i valves inoperable.
i i 1 4
) . .
d Revision A i
i i 4 LCO 3A.9 h J.4 REACTOR COOLANT SYSTEM [RCS) l l 3.to g /' . : . : PRESSURIZER i LIMITING CONDITION FOR OPERATION
- i L c o .3.4 A i
i:.:.E The pressurizer shall be OPERABLE with at least two groups of i pressurizer heaters each having a capacity of at least 150 kW,and a water j level of less than or equal to 92%. T i AP3ICABILITY: MODES 1, 2, and 3. o.d espak d ke;$ powered 4rm u
' e giaeeted scJ e43 bMes poeers 9 pig !
l AQ.I.IDH: "
- Cum 8 g. With less than two groups of pressurizer heaters OPERABLE, restore at
! least two aroups of pressurizer heaters to OPERABLE status within i 72 hoursfor be in at least HOT STANDBY within the next 6 hours and In] Coos C +--{ HOT SHUTDOWN within the following 6 hours.J g hrle..tnot w;&iw h a ib C., A y. With' the _ pressurizer ;":=t:: ' :::r:::;; be in at least HOT STANDBY x::t ::: n;.;;;r ;r:p tr;;t:r: :::alwithin 6 hours and in HOT SHUTDOWN within the following 6 ,1ours.
, (\\g kserb c.n rols ad See Red Cw+re{ )
3
' 595+em k a. cwai+im Wea@\e of toA wibwd .
J
~
i SURVEILLANCE REOUIREMENTS J
$ K 3.U.9,l , i
- .3.U The pressurizer wat ir level shall be determined to be within its limp at least once per 12 hours. 1 u 2.aA.2
.H.t.3.2]Th'ecapacityof__eachoftheaboverequiredgroupsofpressurizer(
heaters shall be 5trifiid te er.er; L..iv i.... ... 6 .a . .u .. .. . . i.; ; ; rn : t
. ::rr;r.t) at least once rach (refueling interval.) _ 'g l
j be 3.4 A3 \capab.IH __ o 6 l 14.4.3.;} The Ec::- a.2 g . t A, pressurizer heaters t
, shall be demonstrated GP. RABLE at least once per 18lithe ESF power supply , )
months ' U,; ate n '
) '
De poveredg 1 BRAIDWOOD - UNITS 1 & 2 3/4 4-11 AMENDMENT NO. 74 e
LM 3. 't , t i O i i 3,4 REACTOR' COOLANT SYSTEM (acM l l l e.g.n c:::.:.: = =aj n,., r- o,.c.wa.c w am.)) 8 ] LIMITING CONDITION FOR OPERATION l tto 14.fi 6 Both power-operated relief valves (PORVs) and their associated block l
. valves shall be OPERABLE.
, _ APPLICABILITY: MDDES 1, 2, and 3.
nors. a ~ ACTION: C "5" " Asa h
, pd c@le of be% mammfly eyeled]
! 6dA pt With one or more PORV(s) inoperable c: = = e :: = = ir: ren i:R=e i within I hour em= =1 r --- - f r) - E+R = m:; or close i the associated block valve (s) with >ower maintained to the block - i palvefs):lothentise be in at least 10T'5TANDB" within 6 hour's anj;[] gD h8f v n HO" 5HilTDOWN within the followina 6 hours. ' daid e.,c.c.pa,le m ny ev se+ k;'"d Cepb - '- ----- -"-- "-- ------- --- - 1 if. With one PORV. inoperabl e e Meeasee), wi thi n I hour ( " -- --^ --- - """" " ""'""" ' i Nelose the associated block valve and remove power from the bloi:k ! ' valve; restore the PORV to OPERABLE status withinah f:W'W } ! 72 hoursfor be in HDT STANDBY within the next 6 hours and in HOT) l Cood 0 ! ! OleMHUTDOWN v . within the followina 6 hours. I dcia _e.~ . ur evei.4_ec+w w bn _ i
- c e 0 fE Jr With both PORVs inoperab'e c_
- ^.: ::=:: 2n:- t'.:n :=.=: =t ',-- g#
l '; +eemane), statador close within 1 hourWths its associated sta: block :t !=t valve and = P0hV removet: power 0^E':^from' ALE.' Au b' ock valveland be in HDI STANDBY within the next 6 hours and) i h 'the ' in HOT 5HUTDOWN within the followina 6 hours. I Q ! Wit . cot 40 C/F (D:h one
- " or more block
_.5 rvalves _i r e rinoperable, e place its within 1 hourdEtore associated SoRv in thed J i I manual l contro'. Restore at ' east one block valve to OPERABLE status
.. iiili T.he test hour 11 Lotti block V&ives are inoperable; restore ,
4 any remaining inoperable block valve to OPERABLE status within 72 hours:Iot.herwise, be in ec seast HOI 5fANDB) within the next 6 hours) l cc.m o Ohh Can_d_.H0T. SHUTDOWN within.the followina 6 hours.1 1 M . ,g u, ie, - The provisions of Specification 3.0.4 are not applicable. j l l i
- SURVEILLANCE REQUIPEMENTS .
t f M Cn ;dditie , t; th .--r:;.;i==t; cf 0;;xifiuti:n 0.0.5Qch PORV l shall be demonstrated DPERABLE at least one:e per 18 months by: 4, l j f.e- P:-f; = =:: Of : C".^.""El CALIRRATXO" Of th: Oc-tuation i
; L inst = =t:ti: . :MJ ,
LA ' Operating solenoid air control and ci.?ck valves on associated air 5es.4.u.3 .K accumulators in the PORV control system through one complete cycle of fuil travel, and _ i 6r. M,ll.a. s' ,0perati the valve through one complete cycle of full travel Burinap
$2.34 tl 2 Ab+c. -d Moors J or Insert 3 4-1261 sn.r.s.u.t (4T4 E Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve throuah one complete cycle of full trave 1]unless )
MMil>l rthe block valve '.s closedlidtA4cwftrMem6ve6)in order to meet the requirements J W tof ACTION b. or c. :f h.ification 3.4.4.] An . 3/4 4-12 AMENDMENT NO. 2, 33 BRAIDWOOD - UNITS-1 & 2
. .~ - . . _ . - . - . . .. . -. .. .. .. . . - . .
4 J CTS INSERT (S) SECTION 3.4
- j. LCO 3.4.11 INSERT 3.4 12A (Aio)
ACTIONS
. NOTES
- 1. Separate Condition entry is allowed for each PORV and each block valve.
l- 2. ... 1 j s
- s 3
l INSERT 3.4128 (L3 ) - l ~ l SURVEILLANCE FREQUENCY SR 3,4.11.2 NOTE
- Only required to be performed in MODES 1 i
l and 2. 1 l i e i i i i 5 i
- i Revision A E
l WACTOR CGOLANT SYSTEM g d Q g. l 3/4 AM EENERATR&1
/
LIMITING CONDITI OPERATION i N /
- 3.4.5 Each steam generator shall DPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4. j g. .- ! With one or more steam g tors inoperable, restore the operable steam l generator (s) to OPE status prior to increasing 'i , abov DF F. i \
'SURVE CE REQUIREMENTS ,
! / \ \ sn u.In : c 1mur s,q.m Q l 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of
- the fol. lowing augmented inservice inspection program and the requirements of
. Specification 4.0.5.
~
4.4.5.1 Steam Generator Samnle Selection and Insnection - Each steam generator , shall be detemined OPERABLE during shutdown by selecting and inspecting at i least the minimum number of steam generators specified in Table 4.4-1. 4 . 4 '. 5. 2 Steam Generator Tube
- S== ale Selection and Insnection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required.shall be as specified in Table 4.4-2. The ,
inservice inspection of steam generator tubes shall be performed at the fre-quencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. When applying the expectations of 4.4.5.2.a through 4.4.5.2.c, previous defects or imperfections in the area repaired by the sleeve are not considered an area requiring reinspection. The tubes selected for each inservice inspection shall include at least 3% of.the total number of tubes in all steam generators; the tubes selected for these inspections shall be . selected on a random basis except: -
- a. Where exper'ience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of-the tubes inspected shall be from these critical areas;
- b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
*When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.5.4.a.10.
I h N See tsc. % S&.wm Sp BRAIDWD0D - UNITS 3 & 2 3/4 4-13 AMENDMENT NO. 46
i CTS INSERT (S) SECTION 3.4 LCO 3.4.13 INSERT 3.4-13A (A3 )
. SURVEILLANCE FREQUENCY SR 3.4.13.2 Verify steam generator tube integrity is in In accordance ,
i accordance with the Steam Generator Tube 'with the Steam Surveillance Program. Generator Tube Surveillance
- Program t
f J. 5 l 1-i 4 a 1 Revision A J
REACTOR COOLANT SYSTEM Lco 3.4.1& I 3/4.4.5 STEAM GENERATORS ____ 5dc1% ss.q W J in Seen.- .3.4 - l LIMITING CONDITION'FOR OPERATION Su Doc 4 Sd.a M l .
- 3.4*.5 Each steam generator shall be OPERABLE.
- APPLICABILITY: MODES 1, 2, 3 and 4. .
l ACTION: - - ! With one or more steam' generators inoperable, restore the inoperable steam l generator (s) to OPERABLE status prior to increasing T, above 200*F. l l SURVEILLANCE REDUIREMENTS L 1 e i 5.5 A 5;60 Each steam generator shall' be demonstrated OPERABLE by performance of i the following augmented inservice inspection progradiQ--- --- - rm m - eti 4 &- :: ::::::: 2 22 ..,
.5.5.9. a C G E T1 Steam Generator Samole Selection and Insnection - Each steam generator i shall be determined OPERABLE during shutdown by selecting and inspecting at
- least the minimum number of steam generators specified in Table 4.4-1.
- 5.5A.b 4:4:3:E Steam Generator Tube
- Samnle Selection and Insnection - The steam l generator tube minimum sample size, inspection result classification, and the 4
corresponding action required shall be as specified in Table 4.4-2. The l inservire inspection of steam generator tubes shall be performed at the fre-t quencies specified in Specification 4.4.5.3 and the inspected tubes shall be j verified acceptable per the acceptance criteria of Specification 4.4.5.4. When
- applying the expectations of 4.4.5.2.a though 4.4.5.2.c, previous defects or
{ imperfections in the a ea repaired by the sleeve are not considered an area
- requiring reinspection. The tubes selected for each inservice inspection shall i include at least 3% of the total number of tubes in all steam generators; the j tubes selected for these iuspections shall be selected on a random basis 4 except:
s s. n . y. Where experience in similar plants with'similar water chemistry j indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas;
~
5 53.b.1 .kr. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include: k *When referring to a. steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4AE.4.. ads. S.s . g. e. BRAIDWD0D - UNITS 1 & 2 3/4 4-13 AMENDMENT NO. 46
A gh[% a humaw nm-a u ana m a mer 3 -a l S ee b a 3.4 l SURVEILLANCE RE001REMENTS (Continued) Sm&m 5S l l 1) All tubes that previously had detechble tube wall penetrations greater than 20% that have not bee: Jged or sleeved in the j j affee.ted area, and all tubes that pr m ously had detectable sleeve ; wall. penetrations that have not'been plugged, 4
- 21___. Tubes in those areas where experience has. indicated potential problems, .
) 3) A tube inspection pursuant to S i performed on each s(elected tube.pecification 4.4.5.4a.8) If any selected shall tube does notbe i permit the passage of the eddy current this shall be recorded and an adjacent' probe for a tube inspection, { subjected to a tube inspection,' tube shall be selected and I i 4) For Unit 1, indications left in service as a result of application of the tube support plate voltage-based repair criteria shall be l j - g inspected by bobbin coil probe during all future refueling outages, and I ! I
- 5) For Upit 1, tubes which remain in service due to the application of
( l i the all future F criteria will be inspected, in the tubesheet region, during outages. I
- c. -
The tubes selected as the second and third samples (if required by Table 4.4-2) inspection during each inservice inspection may be subjected to's partial tube provided: '
- 1) The tubes selected for these samples include the tubes from those l areas of the tube sheet array where tubes with imperfections were j
previously found, and
.2) The inspections include those portions of.the tubes where
! imperfections were previously found. 1 ' { d. Foi Unit 1 Cycle 6, implementation of the steam generator tube / tube
- support plate repair criteria requires a 100-percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down
! to the lowest col
- stress corrosion d-leg tube support plate with known outside diameter cracking lowest cold-leg tube suppor(00 t plateSCC) indications.
intersections The 00 having determination of the SCC indications i shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length. i e. A random sample of at least 20% of the total number of laser welded
- sleeves and at least 20%'of the total number of TIG welded sleeves l
installed shall be inspected for axial and circumferential indications at the end of each cycle. In the event that an imperfection exceeding the i i repair limit is detected, an additional 20% of the unsampled sleeves shall be inspected, and if an imperfection exceeding the repair limit is 4 detected in the second sample, all remaining sleeves shall be inspected. i These inservice inspections will include the entire sleeve, the tube at j the heat treated area, and the tube to sleeve joints. The inservice 2 inspection for the sleeves is required on all types of sleeves installed in the Byron and Braidwood Steam Generators to demonstrate acceptable } i structural integrity. I 3ref5ad'in $tCk'e
- i r.0j Jee hoc~ In Seeyom BRAIDWOOO - UNITS 1 & 2 3/4 4-14 AME5DMENTNO.75 -
.; . .- . -- - - - - . - - - - ~ - - -
REACTOR COOLANT SYSTEM
- spwI;<.a.u S.o j SURVEILLANCE REOUIREMENTS (Continued) Sa.d..a 34
- 5. 5.Q. b.a.0Q ' All tubes that previously had detectable tube wall penetrations greater than 20% that have not been plugged or sleeved in the affected area, and all tubes that previously had detectable sleeve
. wall penetrations that have not been plugged,
! 5 E 4 64.'d h Tubes in those areas where experience has indicated potential j problems, - ' 3.q . b.J. g 1) A tube inspection (pursuant to Specification 4.4.5.4a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a. tube inspection, this shall be recorded and an adjacent tube shall b'e selected and subjected to a tube inspection, ' S 5A A2e N)
'. For Unit 1, indications left in service as a' result of application of the tube support plate voltage-based repair criteria shall ,be inspected by bobbin coil probe during all future refueling outages, and 5 5.9.6.a.tr 1) For Unit 1, tubes which remain in service due to the application of the F* criteria will be inspected, in the tubesheet region, during all future outages.
g'g'q,gg. The tubes selected as th'e second 'and third samples (if required by Table 4.4-2) during each inservice inspection may be . subjected to a partial tube inspection,provided: s.5.443. @ The tubes se'lected for.these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 5.s.9.6 3.2 b The inspections. include those portions of the tubes where imperfection w previously found.-
'I 5:59.b.1k. For Unit I Cycle ,1 ementation of the steam g.enerator tube / tube support' plate repair criteria requires a~100-percent bobbin coil inspection for hot-leg and cold-leg tube support plate intersections down to th'e lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold-leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.
5.5.9.b. 5%. A random sample of at least 20% of the total number of laser welded sleeves and at least 20% of the total number of TIG welded sleeves installed shall be inspected for axial and circumferential indications at the end of each cycle, in tne event that an imperfection exceeding the repair limit is detected, an additional 20% of the unsampled sleeves shall be inspected, and if an imperfection exceeding the repair limit is detected in the second sample,. all remaining sleeves shall be inspected. These inservice inspections will include the entire sleeve, the tube at the heat treated area, and the tube to sleeve joints. The inservice O in'spection for the sleeves is required on all types of. sleeves installed VS/ in th'esycee-ene Braidwood Steam Generators to demonstrate acceptnble structural integrity. - BRAIDWOOD - UNITS 1 & 2 3/4 4-14 AMENDMENT NO. 75
Sub 1+ syc.Ge.hbo s 5 l i REACTOR COOLANT SYSTEM - [ ^[ SURVEILLANCE REQUIREMENTS (Continued) - I The resuTts of each sample inspection shall be classified into one of the
- following three categories:
- Category Insnection Results
- C-1 Less than'5% of the total tubes inspected are .,
degraded tubes and none of the inspected tubes i are defe.ctive. I i i C-2 ' One or'more tubes, 'but not more than 1% of the total tubes inspected are defective, or between 55 and 10% of the total tubes inspected are j degraded tubes. 1 t l j C-3 More than 10% of the total tubes inspected are 3 degraded tubes or more than-l% of the inspected i tubes are defective. i 4 Note: 'In all inspections, previously degraded tubes or sleeves l must exhi. bit significant (greater than 10% of wall thickness) further wall penetrations to be included in the above percentage calculations. } ' l i 4 i t BRAIDWOOD - UNITS 1 1 2 3/4 4-14a AMENDMENT NO. 75 O
e sp u 4ic. h 5.s.9 5 < cA i o n 3 d REACTOR COOLANT SYSTEM
~5 . 5 9. c. 76 5 A e ofi e n Re,sv l+ c la ss f. ce,4,,,, \
SURVEILLANCE RE0VIREMENTS (Continued) 9 The results of each sample inspection shall be ctassified into one of the following three categories: M Cateaory Insoection Results 4 C-1 Less than.5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. .
) C-2 One or more tubes, but not more than '1% of the
- total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective. Note: -I,. all inspection:,,$feviously degrade'd tubes or sleeves must exhibit significant (greater than 10% of wall thickness) further wall penetrations to be included in the ahaue percentage calculations. BRAIDWOOD - UNITS 1 & 2 3/4 4-140, AMENDMENT NO. 75
' See% 3.4 sp w Go. w .5 5 i A41rwr+ed W SacAigk 60 W Poc Gr Sak\n 1:0 REACTOR COOLANT SYSTEM ! T 4 s' , SURVEILLANCE REQUIREMENTS (Continued) ~ 4.4.5.3 Inspection Frequencies'- The above required inservice inspections of steam generator tubes shall be performed at the following frequencies: - ! a. The first inservice inspection shall be performed after 6 Effective ! ! Full Power Months but within 24 calendar months of initial criticality. l l . Subsequent inservice inspections shall be performed at intervals of j not less than 12 nor more than 24 calendar months after the previous i i inspection. If two consecutive inspections, not including the pre- ' service inspection, result in all inspection results falling into the I C-1 category or if two consecutive inspections demonstrate that pre- '
- i. viously observed degradation has not continued and no additional
} degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months;
- b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40-month intervals fall in Category 'C-3, the inspection frequency shall-be increased to at least once per 20 months. The increase.in inspection frequency
. shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3a.; the interval may then be extended to a maximum.of once per 40 months; and *
~
- c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions: ;
- 1) Reactor-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2c., or
- 2) A seismic occurrence greater than the Operating Basis Earthquake, or
- 3) A Condition IV loss-of-coolant accident requiring actuation of the Engineered Safety Features, or
- 4) A Condition IV main steam line or feedWater line break.
BRAIDWOOD - UNITS 1 & 2 3/4 4-15
b S m,Rn.M.,5.o s.c h 3.4 i i I REACTOR COOLANT SYSTEM i i 1
\'
SURVEILLANCE REQUIREMENTS (Continued)
- S EM.J d"3
- 8m* Inspection Frequencies - The above required inservice inspections of j steam generator tubes shall be performed at the following frequencies:
i s. The first inservice inspection shall be performed after 6 Effective 5.T,9 d'1 Full Power Months but within 24 calendar months of initial criticality, i Subsequent inservice inspections shall be performed at intervals of ! not less than 12 nor more than 24 calendar months after the previous i .5.5.9.d .1 , inspection. S If two consecutive inspections, not including the pre-l ' service inspection, result in all inspection results falling into the i C-1 category or if two consecutive inspections demonstrate that pre-i viously observed degradation has not continued and no additional i degradation,has occurred, the inspection interval may be extended
- to a maximum of once per 40 months; -
I 55.9.J.3 Ar. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40-month intervals fall l in Category C-3, the inspection frequency shall be increased to at i least once per 20 months. The increase in inspection frequency
.shall apply until the subsequent inspections satisfy the criteria of j' Specification 4.4.5.3a.; the interval may then be extended to a
) maximum of once per 40 months; and 4
(' i S.1.JA p. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection 1 specified in Table 4.4-2 during the shutdown subsequent to any of j the following conditions: ) SEM.J A. i. Ej Reactor-to secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of j Specification 3.4.6.2c., or l M.9. J A.cl & A seismic occurrence greater than the Operating Basis Earthquake, l or j E.5.9.J.4.16 M A Condition IV loss-of-coolant accident requiring actuation of the Engineered Safety Features, or i E .S'M . J . 4 . ir & A Condition IV main steam line or feedwater line break. I j Q (In sa r+ 3. A - ISD I j motinunnn . stutTc , r. 9 4 /4 a.7 r, .
4 CTS INSERT (S) SECTION 5.0-i Braidwood Specification 5.5.9 INSERT 3.4 15A (A3 )
- The provisions of SR 3.0.2 are not applicable to SG Tube Surveillance Program i inspection frequencies.
1 . 1 i ,
- l 1
- l l
l 4 1 4 i 4 4 i i 4 Revision A
t l l REACTOR COOLANT SYSTEM laeened S $ecNm s o y SURVEILLANCE REOUIREMENTS tContinued) Gee hoc h Se<%s'.o g' 4.4.5.4 j Accentance Criteria i t j a. As used in this specification: 1 i
--- 1 ) Innerfection means an exception tT"The dimensions, finish or
! contour oforaspecifications. drawings tube or sleeve from that required by fabrication i ' Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if ! detectable, may be considered as imperfections; i 2) Deoradation means a service-induced cracking, wastage, wear ~or { general tube corrosion occurring on either inside or outside of a or sleeve; ' i 4 3) j Deoraded Tube means a tube or sleeve containing unrepaired 1 imperfections greater than or equal to 20% of the nominal tube i I or sleeve wall thickness caused by degradation; ! l 4) ! % Deoradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation; j
)
5) i Defect means an imperfection of such severity that it exceeds . i the plugging or repair limit. unrepaired defect is defective;A tube or sleeve containing an 6)
- Pluacino or Renair Limit means the imperfection depth at or
- beyond which the tube shall be removed from service by plugging
! or repaired by sleeving in the affected area. The plugging or i repair limit imperfection depth for the tubing and . laser welded sleeves is equal to 40% of the nominal wall thickness. The i plugging limit imperfection depth for TIG welded sleeves is j equal do 32% of the nominal wall thickness. For Unit 1, this
- definition does not apply to defects in the tubesheet that meet i the criteria for an F tube. For Unit 1 Cycle 6, this j definition does not apply to the tube support plate
- intersections being applied. for which the voltage-based repair criteria are l Refer to 4.4.5.4.a.11 for the repair liinit applicable to these intersections; 7) i I
Unserviceable describes the condition of a tube if it leaks or ! rity in the event of an Operating Basis Earthquake,. a lo j coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c., above; 8) i Tube Insoection means an inspection of the steam generator tube ! from the point of entry (hot leg side) com i U-bend to the top support of the cold leg.pletely For a around tube thatthehas been repaired by sleeving, the tube inspection shall include the sleeved portion of the tube, and I. I . j BRAIDWOOD - UNITS 1 & 2 3/4 4-16 -
' AMENDMENT NO. 75
I . .I REACTOR COOLANT SYSTEM A, p , g, g,., y,,
- SURVEILLANCE REOUIREMENTS (Continued)
SU *a 3 4 , l 5 Sag,e 4 .4.s.4- Acceptance Criteria e, . L nwJ i.. t.'.is @ hificetier.H . 5. ! .5.s.q,e,, Imoerfection means an exception-to-the dimensions, finish or I
' K contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications i 4
below 20% of the nominal -tube or sleeve wall thickness, if I i- detectable, may be considered as imperfections; U
~
5.5.q.e 4 pj
Dearadation means a service-induced cracking,
wastage, wear or i general corrosion occurring on either inside or outside of a i tube or sleeve;. l 5 5:9.e.3 Jf Dearaded Tube means a tube or sleeve containing unrepaired j imperfections greater than.or equal to 2C% of the nominal tube ; or sleeve wall thickness caused by degradation; ' ! 5.s .9. e 4 p[ % Dearadation means the percentage of the tube or sleeve wall thickness affected or removed by degradation;
^
i i 55.9.e.5-/ -Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube or sleeve containing an unrepaired defect is defective; 4 l 5. 5 A e 4 g Pluaaina or Reoair Limit means the imperfection depth at or
- j. -
beyond which the- tube shall be removed from service'by plugging or repaired by sleeving in the affected area. The plugging or
- repair limit . imperfection depth for the tubing and laser welded sleeves is' equal to 40% of the nominal wall thickness. The i plugging limit imperfection depth for TIG' welded sleeves is i equal .to 32% of the nominal wall thickness. For Unit 1, this i definition does not. apply to defects in the~tubesheet that' meet i the criteria for an F i definition does not. applytube.g to theFor Unit tube. 1 Cycle support plateA thrQ7. 4 intersections for which the voltage-based repair criter.ia are for he rep' air limit being applied. Refer to 4.4.5.4.a.
applicable to these intersections; 13 ( 5 5 4.e.7 J>/ Unserviceable describes the condition of a tube if it leaks'or contains a defect large enough to affect its structural ~integ- '. rity in the event of an Oper.ating Basis Earthquake, a loss-of-coolant accident, or a steam line 'or feedwater line break as -
- - specified in 4.4.5.3c., above; ,
5 5'c1* e~ g g Tube inspection means an inspection of the steam generator tube d
-from the point of entry (hot leg side) completely around the
- U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection shall include the
~ sleeved portion of the tube, and [! l , BRAIDWOOD - UNITS 1 & 2 3/4 4-16 AMENDMENT N0. 75
..w-i REACTOR C001 ANT SYSTDI "
M* M See boC Ar Sec4.a T.D pAhh SURVEILLANCE REGUIREMENTS (Continued) U
- 9) Preservice Insnection means an inspection of the full length of
- each tube in each steam generator performed by addy current i- techniques prior to service to establish a baseline condition i ==- 'of the tubing. This inspection shall be performed prior to initial i POWER OPERATLON using the equipnerrt und techniques expected to be used during subsequent inservice inspections. '
,10) Tube Renair refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by.the.
following processes: , a). Laser welded sleeving as described in a Westinghouse-Technical i Report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff, or I b) TIG welded sleeving as_ described in A88 Combustion Eng1'neering { i Inc. Technical Reports: Licensing Report CEN-621-P, j Revision 00, " Commonwealth Edison Byron and Braidwood Unit 1 j and 2 Steam Generators Tube Repair Using Leak Tight Sleeves, ~ FINAL REPORT," April 1995, and Licensing Report CEN-627-P, Revision 00-P, " Verification of the Installation Process and Operating Performance of the A88 CEN0 Steam Generator Tube Sleeve for Use at Commonwealth Edison Byron and Braidwood Units 1 and 2,* January 1996, subject to the limitations and restrictions as noted by the NRC Staff.. Tube repair includes the removal of plugs that were previously installed as a corrective or preventative measure. A tube inspection per 4.4.5.4.a.8 is required prior to returning previously plugged tubes to service.
- 11) For Unit 1 Cycle.6, the Tube Sunnort Plate Pluacina Limit is used
- for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thi'ckness of the tube support plates. At tube support plate intersections, the plugging (repair) limit ~is based on maintaining steam generator tube serviceability as described below,
- a. Steam generator tubes, with degradation attributed to outside diameter stress corrosion cracking within the bounds of the cold-leg tube support plate with bobbin. voltages less than or equal to the lower voltage repair limit [ Note 1] will be allowed to remain in service. Steam generator tubes, with degradation attributed to outside diameter stress corrosion cracking within the bounds of the hot'-leg tube support plate with bobbin voltages less than or equal to 3.0 volts will be allowed to remain in service.
- b. Steam generator tubes with degradation attribu'ted to outside diameter stress corrosion cracking within the bounds of the cold-leg. tube support plate with a bobbin voltage greater than the lower voltage repair limit [ Note 1], will be repaired or plugged, except as noted in 4.4.5.4.a.11.d below.
BRAIDWOOD - UNITS 1 & 2 3/4 4-17 , AMENDMENT NO. 75
-_... - ._ _ _ ._.~ _ - _...--.- _ -....-..-.-. . - . - . . . - - . . .
i . i-
- REACTOR' COOLANT SYSTEM Sp a c T,' c cA,en 5. o
" 3'#
l SURVETllANCE RE0VIREMENTS (Continuedf 5.5.9., q h' Preservice Insoection means an inspection of the full length of f each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition =
'of the tubing. This inspection shall be performed prior to initia' 4,
POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections. c I 5.5 9.e.lo %) Tube Reoair refers to a prccess that reestablishes tube-i serviceability. Acceptable tube repairs will be performed by the
- following processes
5.5.u.:oD) Laser welded sleeving as described in a West'inghouse Technical ! Report currently approved by the NRC, subject to the j limitations.and restrictions as noted by the NRC staff, or i- 5.5.c. .e 4% TIG welded sleeving as described in ABB Combustion Engineering
- Inc. Technical Reports: Licensing Report CEN-621-P, j Revision 00, " Commonwealth Edison Byron and Braidwood Unit 1 and 2 Steam Generators Tube Repair Using Leak. Tight Sleeves, FINAL REPORT," April 1995, and Licensing Report CEN-627-P, Revision 00-P, " Verification of the I'nstallation Process and l Operating Performance of the ABB CEN0 Steam Generator Tube
! . Sleeve for Use at Commonwealth Edison Byron and Braidwood i Units I and 2," January 1996, subject to the. limitations and restrictions as noted by the NRC Staff.' Tube repair _ includes the' removal of. plugs that were previously installed as a corrective or preventative measure. A tube ins ection per 4.4.5.4.a.8 is requ' ired prior to returning nmn plug s to service. A 4 CInse d i.4- l iO N h) ,, N, nit 1. Cycl , - Tube Sunoort Plate Pluooino limit is used
,. I for the dispo'itions of an alloy 600 steam generator tube for
- N '
- d3 continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At' tube support plate intersections, the plugging (repair) limit is based on maintaining steam generator tube serviceability as described below.
- 5. 5 9. e . u. A Steam generator tubes, with degradation attributed to outside diameter stress corrosion cracking within the bounds of the oeu- W tut rrrr:rt mtBwith bobbin voltages less than or
(( ym_sg.,. L % ,,,,ti.@d m equal to the lower voltage. repair limit [ Note 1] will be allowed to remain in service. Steam generator
- degradation attributed to outsid r ss corrosion cracking within the bounds of t 2:t 1r- " - 5:n 2;mp with bobbin voltages less than or eaual to 3.0 volts will be .
allowed.to remain in service. l flock.<v-744 M od e ll
\ss a sea..ns J 4 5 5.9.c.11 4 h. Steam gener' a tor tubes with degra a ibuted to out e r f , q diameter stress corrosion cracking within the b .the w
with a. bobbin voltage greater.than (Fm-5 F
'" %}:eM M "5+'** [heh; +"he lower =ppert voltage repairpht limit [ Note 1], will be repaired or lugged, except.as.noted in 4,1.5.4.a. .d below.
.BRAIDWOOD . UNITS 1 & 2- .3/4 4-17 AMENDMENT NO. 75 u . . . . , , . . _ . - . . . , _ _ . ._., _
e CTS INSERT (S) SECTION 5.0 Specification 5.5 9 INSERT 3.4 17A (A3 and Ai ) y N h ' 5.5.9.e.1T N T N .kodel Intersection means all steam generator hot-leg ( tube-to-tube support plate intersections which have been analyzed to experience a tube support plate displacement less than 0.1 l inches during accident conditions excluding the following: l 1.4) All tube-to-tube support plate intersections where IPC
- i cannot be applied per Generic Letter 95-05:
?
\
Jik) All Flow Distribution Baffle intersections: f
/DNQ All steam generator tube intersections adjacent to an
' intersection that contains a corrosion induced dent greater than 0.065 inches; and I\
Arh All tube-to-tube support plate intersections that will be displaced more than 0.1 inches during accident conditions due to failure of the steam generator internal structures.
.5.5.9.e.1 Free-Soan Model Intersection means all steam generator tube-to-tube support plate intersections to which the Locked-Tube Model does not apply and which meet the criteria of Generic Letter 95-05, excluding the following: j C '
i.iN . All tube-to-tube support plate intersections where IPC cannot be applied per. Generic Letter 95-05: and
\
1
/
[k All Flow Distribution. Baffle intersections.
\ '
v \ yJ J Revision A
A Mam41 in .h e,% 9 , PIACTOR COOLANT $1HQi M*N O l l Sec h 3 4 SURVEILLANCE REOUIREMENTS (Continued) Spe rEa4 d5
- c. Steam generator tubes with degradation attributed to outside diameter stress corrosion cracking within the ;
i bounds of the hot-leg tube support plate with a bobbin j, voltage greater than 3.0 volts will be repaired or pluggad. l } d. ,
- Steam generator tubes, with indications of potential !
degradation attributed to outside diameter stress ;
- corrosion cracking within the bounds of the cold-leg tube l i
support plate with a bobbin voltage greater than the lower voltage repair limit ' equal to the upper voltage epair r[ Note 1] but less than or limit ! remain in service if a rotating pancake c[oilNote 2), may inspection does not detect degradation. Steam generator tubes, with indication of outside diameter stress corrosion cracking , degradation within the bounds of the cold-leg tube support plate with a bobbin voltage greater than the upper voltage repair limit [ Note 2] will be plugged or repaired.
- e. Certain intersections as identified in WCAP-14046, Section 4.7, will be excluded from application of the !
voltage-based repair criteria as it is determined that ! these intersections may collapse or defom following a postulated LOCA + 55E event. . l f. If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits identified in 4.4.5.4.a.11 a. 4.4.5.4.a.11.b and . 4.4.5.4.a.11.d for outside diameter stress corrosion l cracking indications occurring in the steam generator cold-legs. For outside diameter stress corrosion cracking indications occurring in the steam generator hot-legs, the limits in 4.4.5.4.a.11.a and 4.4.5.4.a.11.c apply. The mid-cycle re
.the following equations: pair limits are detemined from V
Ym"
- 1. 0 +NDE+Gr ( CL-A e )
Va= Vm (VmYm)(
)
BRAIDWOOD - UNITS 1 & 2 3/4 4-17a '
, AMENDMENT NO. 69
i Dpece ca. 6da ' REACTOR COOLANT SYSTEM
- g '3URVEILLANCF REOUIREMENTS (Continued) 55M.e.13 R r. Steam generator tubes with degradation attributed to
--%outside diameter stress corrosion cracking within the 1
M Nf4/ l.oc ked- 7A c I Punas of T,he/Aet -l; tri:
- Nd e I L4., M % 1ugged.
\vn1tage greater than;3.0 volts will be repaired or!?;;;"+ phts wit S.f.'l eJ3 iv g.
4 Steam generator tubes, with indications of potential
- degradation attributed to outside diameter stress m corrosion cracking within the bounds of the e
- M 'r; tub:
it;;rt phte with a bobbin voltage greater than the i Fr.. -spa n M ca, j (lower voltage repair limit [ Note 1] but less than or ! 4 qual to the upper voltage repair limit [ Note 2], may 4 7n 4c rud.ent .t in in service if a rotating pancake coil inspection
- oes not detect degradation. Steam generator tubes with '
l ! > indication of outside diameter stress corrosion crac, king degradation within the bounds of the c:M ' ; tub: j -::;;rt ;' te with a bobbin voltage greater than the
- upper voltage repair limit [ Note 2] will. be plugged or repaired.
i s S.9. e.13. v g. , Certain intersections as identified in WCAP-14046, i Section 4.7, will be excluded from application of the
. voltage-based repair criteria as it is detemined that '
i these intersections may collapse or deform following a i postulated LOCA + SSE event. 55.9.e.13 vi #. l3 % ! If an unscheduled mid-c pe is performed, the following mid-cyc1 pair lie ts apply limits identi ad of the in 4.4.5.4.a. .a, 4.4.5.4.a. .b and 4.4.5.4.a.
.d for outside diameter stress corrosion 3
tre e Spe n M odd cracking indications occurring in the st;= ;==:ter 1 a En+ersc<4 m - ( cracking
- 'd hgs ~ For outside diameter stress corrosion 14 / indications occurring in the ete r ;cr r ite I
L ocked-To b e %t 'e;:, the limits in 4.4.5.4.a. apply. The mid-cycle repair limits a.a andterni 4.4.5.4.a. .c rom M od e i L4"5"' N the following equations: 13 Va
- 1. 0 +NDE+Gr ( CL-A t )_ ,
p; g () g 4,, q,,,, Sa 4f Ie Ze krOt f.m
\ or e e,0so su e loded (rom ofplic*hv o$
Va= Vm- ( Vau, Y" m)I g_g g) a De al% -bd d te po or . t.raber;a . Ad BRAIDWOOD - UNITS 1 & 2 3/4 4-17a . AMENDMENT NO. 69
.l l 4AAr<++41 N 6echw fo kEALTOR C0OLANT_ SYSTEM
*** 3"**" i Sex % 3.+
SURVEILLANCE REDUIREMENTS (Continued! JerMeaG 8f 1 Where: i . . i i Vuu - . upper voltage repair limit i V = lower voltage repair limit , V.on.t mid-cycle upper voltage repair limit l based on time into cycle ' j Van - mid,-cycle lower voltage repair limit based on V t and time'into cycle i At - length of Une since last scheduled l ' inspection during which Vuu.and Von l were implemented. i ' CL - cycle length (the time between two scheduled steam generator 4 inspections) V a - structural limit voltage i Gr . average growth rate per cycle length
- NDE =
95-percent cumulative probability allowance for nondestructive examination. uncertainty (i.e., a i value.of 20 percent has been approved by NRC)
- Implementation of these mid-cycle repair limits should follow the ,
same approach as in TS 4.4.5.4.a.11.a. 4.4.5.4.a.11.b, 4.4.S.4.a.11.c and 4.4.5.4 a.11.d. ! Note 1: The lower voltage. repair limit is 1.0 volt for indications of l . outside diameter stress corrosion cracking occurring at cold-leg tube support plate inter::ections. l Note 2: The upper voltage repair limit for indications of outside diameter e stress corrosion cracking occurring at cold-leg tube support plate intersections is calculated according to the methodology in l Generic Letter 95-05 as supplemented.
- 12) F* Distance is the distance into the tubesheet from the i
secondary face of the tubesheet or the top of the last hardroll, whichever is further into the tubesheet, that has been determined to be 1.7 inches.
- 13) F* Tube is a Unit I steam generator tube with degradation below the F* distance and has no indications of degradation (i.e., no indication of cracking) within the F* distance.
Defects contained in an F tube are not dependant on flaw geometry. -
- b. The steam genera 1ior shall be determined OPERABLE after completing the corresponding actions (plug or repair in the affected area all tubes exceeding the plugging or repair limit) required by Table 4.4-2. '
BRAIDWOOD - UNITS 1 & 2 3/4 4-17b AMENDMENT NO. 69
' S p ea < D a.+, u S. o
- REACTOR COOLANT SYSTEM #
- d ' * M i
Q SURVEILLANCE REOUIREMENTS (Continued) j Where: 1 ' V t upper voltage repair limit V,tu = lower voltage repair limit ; V ,t - mid-cycle upper voltage repair limit l i based on time into cycle Vg - mid-cycle lower voltage repair limit i based on V and time into cycle ' At - t length of Une since last scheduled } j inspection during which V ,t and V tu were implemented. 4 CL - cycle length (the time between two scheduled steam generator 1 4 inspections) i V,t - structural limit voltage l Gr - average growth rate per cycle length NDE - 95-percent cumulative probability i allowance for nondestructive examination uncertainty (i.e., a i value of 20 percent has been
- l approved by NRC) i I implementation of these mid-cyc1 repair limits should follow the
[ same approach as in TS 4.4.5.4.a. .a, 4 .5.4.a. .b, j i 4.4.5.4.a. .can44.4.5.4.a. 13 l 5 .s A.e. O. o
- Note 1
- The lower volta repair limit 4 2
.0 volt for indic i outside diameter stress corrosion cracking occurr' .>+~'d '- !
debe re;;r-t pht: Intersections. ~ in +h e ke e '5pa n ' ' s.s.9.,,r3 Mohl ! Note 2: The upper voltage repair limit for indications o l ud: 'd L-- stress corrosion cracking occurring M tr'd hg trb: ::;;r-t ph u ptersections is calculated according to the methodology in Generic Letter'95-05 as supplemented. sr.q e. pt F* Distance is the distance into the tubesheet from th'e i secondary face of the tubesheet or the top of the last hardroll, whichever is further into the tubesheet, that has been determined to be 1.7 inches. l 5 .5 9.e. 1.5 F* Tube is a Unit I steam gerierator tube with degradation } below the' F* distance and has no indications of degradation ! (i.e., no indication of cracking) within the F* distance. . 4 Defects contained in an F* tube are not dependant on flaw . j geometry.
, 5.5.9.e..I f. tr. The steam generator shall be determined OPERABLE after completing i .
the corresponding actions (plug or repair in.the affected area all tubes exceeding the plugging or repair limit) required by Table 4.4-2. l 1 i BRAIDWOOD - UNITS 1 & 2 3/4 4-17b . AMENDMENT NO. 69 4
i 4 REACTOR COOLANT SYSTEf* *M *
)
! w~ seek s b A SURVEILLANCE REOUIREMENTS (Continued) :SpcAMa 5f 4.4.5.5 Reoorts j a. Within 15 days following the completion of each inservice i inspection of steam generator tubes, the number o.f tubes plugged i or repaired in each steam generator shall be reported to the Connission in a Special Report pursuant to Specification 6.9.2;
, b. The complete results of' the steam generator tube inservice -
l inspection shall be submitted to the Commission in a Special Report pursuant to Specifi. cation 6.9.2 within 12 months following i the completion of the inspection. This Special Report shall ' include: ,
- j. 1) Number and extent of tubes inspected,
- 2) Location and percent of wall-thickness penetration for each l indication of an imperfection, and -
i
- 3) Identification of tubes plugged or repaired.
i ! c. Results of steam generator tube inspections which fall.into j . Category C-3 shall be reported in a Special Report to the
- Commission pursuant to Specification 6.9.2 within 30 days and i prior to resumption of plant operation. This report shall provide 1
a description of investigations conducted to determine cause of
- j the tube degradation and corrective measures taken to prevent
; recurrence.
l l d. For implementation of the voltage based repair criteria to tube
- support plate intersections for Unit 1 Cycle 6, notify the staff prior to returning the steam generators to service should any of l the following conditions arise:
l l 1. If estimated leakage based on the projected end-of-cycle (or
- if not practical, using the actual measured end-of-cycle)
- ; voltage distribution exceeds the leak limit (determined from i the licensing basis dose calculation for the postulated main
- j steam line break) for the next operating cycle.
- 2. If circumferential crack-like indications are detected at
- the tube support plate intersections.
( . ! 3. If. indications are identified that extend beyond the i confines of the tube support plate. ! 4. If indications are identified at the tube support plate elevations that are attributable to primary water stress I corrosion cracking. 1 N
- .BRAIDWOOD - UNITS 1 & 2 .3/4 4-17c AMENDMENT NO. 69
_ _. --_ . _ _ _ . _ . _._.-._.___-____.__..___._.._.___....._____,_m._._
! SH E.M 50 REACTOR COOLANT SYSTEM i
j g SURVEILLANCE RE0UIREMENTS (Continued) ' 4 i M9F.E5:~M5PM
- 5.H . a. /, /Within 15 da W M lowing the completion of each inservice '
l ' inspection ? steam generator tubes, the number o.f tubes plugged or repaire _,in each steam generator shall be reported to the Commission n : :::::: r.:::r: : r:::: :: 5::::'::: ::: r.::1 ! 5. k. 7 b p. The complete results of the steam' generator tube inservice inspection shall be submitted to the Commission (m-+-4$*e4++-1 1 ;;rt _ur;;;;t t i q.:r m:F -- f ^ ^ within 12 months following - j the completion of the inspection. Thi Special Report shall include: ] Sik 9 b. I Ff' Number and extent of tubes inspected, i a s19 b.2. F) Location and percen,t of wall-thickness penetration for each i indication of an imperfection, and 5.h S h3 pf Identification of tubes plugged or . repaired. S.b. S .4 t. i Results of steam generator tube inspections which fall into o Categ' ry C-3 shall be reported in a S)ecial' Report to the Comission.scr::::: :: ::::: :::::nn 12 rlwithin 30 days and - j prior to resumption of plant operation. This report shall provide { a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence. l 5. b 9 d t. For implementation of the voltage based repai c iteria to tube-j support plate intersections for Unit 1 Cycle notify the, staff priortoreturning-thesteamgeneratorstose%,iceshouldanyof rv j the following conditions arise: / . ! 5.6.9.d.1 /. i If estimated leakage based on the projected end-of-cycle (or i - if not practical, using the actual measured end-of-cycle) j voltage distribut' ion exceeds the leak limit (determined from i the licensing basis dose calculation for the postulated main steam line break) for the next operating' cycle. 5.br i .d.1 p. If circumferential crack-like indications are detected at the tube support plate intersections. 4' ! 5. b. 9.11 7 If indications are identified that extend beyond the j confines of the tube support plate. j EL. 9 .J 4 y. If indications are identified at the tube support plate i elevations that are attributable to primary water stress j corrosion cracking. ' n,s.,,. f 3.4 - 17 c. A] i 9 t, . ! BRAIDWOOD - UNITS 1 & 2 3/4 4-17c ~ i AMENDMENT N0. 69
-- . - , ~ - ~ , ,-
1 CTS INSERT (S) SECTION 5.0 Specification 5.6.9 INSERT 3.4 17cA ( ).. % - m.
. e 5.6.9.d. If cracking is observed in the tube. support plates.
.5.6.9.d.) If any tube which previously passed a 0.610 inch diameter bobbin ~
) coil eddy current probe currently fails to pass a 0.610 inch diameter bobbin coil eddy current probe, i
'N
'd 1
~' W
~
- s. . ,;
l l i I l I l Revision A 4
. . _ _ _ _ .. _ .. ._ _ _ _ _ _ . . . _ _ . .._...___ _ _ . _ . _ _ _ _ . _ . _ _ _ _ _ _ ._ _m_
h 0 ce: S W Se. eases [ O ' REACTOR COOLANT SYSTEM 4ea. Tec Gee Sewon 50 m 1 See n 3.4 SURVEILLANCE REQUIREMENTS (Continued) 5puAcuNa88
- 5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actu '
x 10'gl, notify measured end-of-cycle) the NRC and provide voltage distributionof an assessment exceeds the 1 I safety significance of the occurrence.
- 6. Following a steam generator internals inspection, if.
indications detrimental to the integrity of the load path necessary to support the 3.0 volt IPC are found, notify the NRC and provide an assessment of the safety significance of the occurrence.
- e. The results of inspections of F* Tubes.shall be reported to the
.~ Commission prior to the resumption of plant operation. The report shall include:
- 1) Identification of F* Tubes, and
- 2) Location and size of the degradation.
&
- myeen l
l 4 9 4 BRAIDWOOD - UNITS 1 & 2 3/4 4-17d AMENDMENT NO. 69
3pe.o .'Sh% S. O REACTOR COOLANT SYSTEM 5 ' '4 ' * " 3 'i (b)SURVEILLANCERE0VIREMENTS(Continued) 5.69.d.*y Jr.- If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the ) actua l x 10",1 measured
, notify the NRCend-of-cycle) voltage and provide distributionofexceeds an assessment the 1 '
safety significance of the occurrence. l Sto.4.d.S . Following a steam generator. internals inspection, if l e 0;4 indications detrimental to the integrity of the load path necessary to support the 3.0 volt IPC are found, notify the NRC and provide an assessment of the safety significance of 1 the occurrence. t 6.6. 4 .t sr! The results of inspe.ctions of F* Tubes shall be reported to the . Commission prior to the resumption of plant operation. The report shal.1 include: i 5 b-4.e.l .?7 Identification of F* Tubes, and 5.b. 4. e.1 \ JHr Location and size of the degrad'ation. I i l l F e BRAIDHOOD - UNITS 1 & 2 3/4 4-17d AMENDHENT NO. 69
~
b S uM*n 34 _ . Spec ArsW 53 : ! l ! t TABLE 4.4-1 j MINIMUM NUMBER OF STEAM GENERATORS TO BE 4 INSPECTED DURING INSERVICE INSPECTION i 1 1 Preservice Inspection Yes ! No. of Steam Generators per Unit' Four ! First Inservice Inspection ? Two i Second & Subsequent Inservice Inspections One l ! i TABLE NOTATION i ? 1. The inservice inspection may be limited to one steam generator on t rotating schedule encompassing 3 N % of the tubes (where N is the number cf steam generators in the plant) if the results of the first-or previous inspections indicate that al.1' steam generators are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more s.evere than those in other steam generators. Under such
- circumstances the sample sequence shall be modified to inspect the i most severe conditions. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected ,'
during the second and third inspections. The fourth and subsequent inspections shall follow the instructions described above. fthkets+ek k Sedios Co , 6ee. )cc 4 c Ge w .w to e BRAIDWOOD - UNITS 1 & 2 3/4 4-18 ,
l S p e d h +,.a s. o i . s s e. + . o n 14 ! .r. s. Q ~ l TABLE 4-4-t i $ MINIMUM NUMBER OF STEAM GENERATORS TO BE' 1 INSPECTED DURING INSERVICE INSPECTION l i-s 1 i 4 Preservice Inspection Yes - I No. of Steam Generators per Unit . i Four
, First Inservice Inspection Two
' Second & Subsequent Inservice Inspections l One i i I TABLE NOTATION 2 1. The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the
- number of steam generators in the plant) if the results of the first
! or previous inspections indicate that all steam generators are t perfoming in a like manner. Note that under some circumstances, the , l operating conditions in one or more steam generators may be found to
- be more severs than those in other steam generators. Under such
- circumstances the sample sequence shall be modified to inspect the most severe conditions.
inspected during the first inservice insEach of the other two. steam generato during the second and third inspections.pections shall be inspected ; inspections shall follow the instructions described above,The fourth and subs i m 4 9 e BRAIDWOOD - UNITS 1 & 2 3/4 4-18 ' e
i ABi.s -4M-2 en g STEAM GENERATOR TUBE INSPECTION E; E g 1ST SAMPLE INSPECTION 2ND S AhPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required
$ A mininum of C.1 None N.A. N.A. N.A. N.A. -
d S Tubes per
- S. G. C-2 Plug or repair C-1 None N.A. N.A.
defective tubes and
" inspect additional C2 Plug or repair C-1 None l 2S tubes in this defective tubes S. G' -
andinspect C-2 Plug or repair l additional 4S defective tubes tubes in this S. G. C-3 Perform action for C-3 result of first sample R2 C-3 Perform action for N.A. N.A. C-3 result of first I" sample e' C-3 Inspect all tubes in All other' None N.A. N.A. this S. G.. plug or S. G.s are repair defective C-1 tubes and inspect , 2S tubes in each Some S. G.s Perform action for N.A. N.A. Other S. G. C-2 but no C-2 result of additional second sample a e,g [ Notification to NRC S. G. are C-3 pglp p pursuant to Additional Inspect all tubes N.A N.A' 5 50.72 (bil21 of 10
*g att M S. G. is C-3 in each S. G. and lug or repair h
ti, to g defective tubes. ~" , ff
'y Notification to . .
3S 9 NRC pursuant to S 5 5 50.72(bil2) of
, 10 CFR Part 50 U['
w -
- gi s 'U% miere N is die number or steam tienerators in the unit, and n is the number or steam
- n oeneratnrs inspected durinn an insnettinn .
T_ABis M 1M -A E STEAM.. G..E..N.ERATOR TUP 6 INSPECTION.
?
o
@ 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required c:
Result Action Required 5 A mininum of C-1 ~None. N.A. N.A. N.A. N.A. ij S Tubes per C-2 Plug or repair - C-1 t
- S. G. None N.A. N.A. l dMective tubes and b inspect additional C-2 Plug or repair C-1 None l I
2S tubes in this &fective tubes S. G. andinspect, C-2 Plug or repair I additional 4S l. defective tubes tubes in this S. G. C-3 Perform action for ; C-3 result nf first sample , y ~ C-3 Perform action for N.A. N.A. C-3 result of first
?
t sample g TEt.te_ ;
%g C Inspect all tubes in All other None N.A. N.A.
this S. G., plug or S. G.s are l repair defective C-1 i tubes and inspect - 2S tubes in each Some S. G.s Perform action for N.A. N.A. ! other S. G. C-2 but no C-2 result of i additional second sample !
. N cation to .C S. G. are C-3 ! 'g g
O
,,,, gg (b) f10 A lon S. G. is C-3 Inspect a in each S. G. and plug or repair defective tubes.
s N.A N.A. f[ e lp 3 g j Q ll tification to NRC s to yg { A = t
~ $50. of #
m FR Part 5 h
% f, Ngl#iere N is Llie numlier of steam generatnrs in tiie unit, and n is tlie numl>er nf steam 4 b" n generainrs inspected <loring an inspection
[
l ., Lf.C 3. et, tif* j l . i 3.'{ REACTOR COOLANT SYSTEM (ge.Q f O/;.,.; ;;ACT0" COOLANT SYSTC" LEA" ACE)(17./f M Mdf" bd*h """'"N j ( L5^.E".C5 05T5c!!0N SYST5".5f - LIMITING CONDI. TION FOR OPERATION 4 l .t.a M,/fGEi:E The following Reactor Coolant System Leakage Detection Systems shall j be OPERABLE: Ln l .{a'.b.TheContainmentAtmosphereParticulateRadioactivityMonitor"r.: 5: t em., Q @The Containment and p!e:r era r::::.cr_;e ::: m , T M Monito @ ( l j g i
'.b
. ormThe Containment Gaseous Radioactivity Monitoreep-5vetem). i i APPLICABILITY: MODES 1, 2, 3, and 4. -
(or prG % 4 a, v ,w w<yf.,4 a ) ' ACTION: g % ,.sy zy.; u ; Lao , (i. l Nb, . With a. or c. of the above required Leakage Detection Systems inoperable, l cosp 3 operation may continue for up to 30 days providec grab samples of the
, containment atmosphere are obtained and analyzed s;r ;;;;s ; and carticul;t;,' LAq gre)at least once per 24 hours, when the required Gaseous or
, Particulate Radioactivity Monitorina System is inoperable;]otherwise, be in) pp c._ fat least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within] l L the followina 30 hoursJ g y coup A k. m , With b. of the above required Leakage Detection Systems inoperable,+ restore ! to OPERABLE status within days;Jotherwise be in at least HOT STANDBY t j C8HP C *-(within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.) {
- r. With a. and c. of the above required Leakage Detection Systems inoperable:
p cow s sa s.21)~ Restore either 9::tter a; =;t:: ::. cr :. J to OPERABLE status within j UZ ha rakand i con 95 M 1.1.1 FJ . Obtain and analyze a gra sample of the containment atmosphere for
% g g -
W9 l
- gaseous and particulate radioactivity at least once per 24 hours,(4nd-) !
lcoupt4s.t.2#J' Perform a Reactor olant System water inventory balance at least once Or j Per$ hours. .w t.n 12 Imeer J.4 2oc.h . , , i comp c- Otherwise, be in at least HOT STANOBY within the next 6 hours and in COLD j g ,p', SHUTDOWN within the following 30 hours. ! SURVEILLANCE REQUIREMENTS 7 * * '# * " ~ "* * l . MTF'D The Leakage Detection Systems shall be demonstrated OPERABLE by: [f$',',y,$ .af Containment AtmosphereILaeee; end rer;.;sut:! Monitoring System-a y.y,ff,4 performance of CHANNEL CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL . LQ OPERATIONAL TEST at the frequencies specified in Table 4.3-3, Isump u 3,q,if;3 Af' Containment tn=r Or:1 ett F.::: tar c t = n:5 Monitor 5;; S:r-1 performance of CHANNEL CALIBRATION at least once per 18 months nd } ( c. i'erify th; :11 ::per; tor porti;n ;f th; :=t:innat '1::r dr:ii b7 4 cellectica saap h;; t,een filled t; the 1; vel ;f the everfi;w t; th:
; conteinment fleer drain tmidentified leeker,e sliectida weir ta =;;}
4 ( p;r 10 ;;ath:, fell; wing refueling, :ad pri: te i.mit441 :t:rtwr- L8v ("The :;>ecified-18 month-interval-may- be extended-to-32-months-fee.-cy:101 :n!y.)
- BRAIDWOOD - UNITS 1 & 2 3/4 4-20 AMENDMENT NO. 21
CTS INSERT (.S) SECTION 3.4 LCO 3.4.15 INSERT 3.4 20A (La) NOTE LC0 3.0.4 is.not applicable INSERT 3.4 20B (Ais ) CONDITION REQUIRED ACTION COMPLETION TIME l l D. All required monitors 0.1 Enter LCO 3.0.3. Immedi>tely inoperable. j l 9 f
. Revision A e
CTS INSERT (S) SECTION 3.4 LCO 3.4.15 INSERT 3.4 20C (Ln. L u . and L3 ) CONDITION REQUIRED ACTION COMPLETION TIME ' A. ... A.1 NOTE Not required until t 12 hours after-establishment of steady state operation near operating pressure. Perform SR 3.4.13.1. Once per 24 hours e.!!Q A.2 ... B. ... B.1.1 ... ... i B.1.2 NOTE-Not required until l 12 hours after i I establishment of steaay state operation at near " operating pressure.
... i l
i l Revision A t
l L. s 3.n . o l , Le.o F.4,/4 NO M' d.4 REACTOR C00UUrr SYSTEM (Ws) i 9.4.is N TIONAL LEAKAGE , '1 LIMITING _CONDlIl0K_ EOR @tATION ! Leo 3.9.t1
- .,5.'EEE Reactor Coolant System leakage shall be limited to
1 4 Lco s.4.is.4. .sf No PP. ESSURE B0UNDARY LEAKAGE, Lca J.4.lf.k F. I gpa UNIDENTIFIED LEAKAGE, WMMdc 600 gallons per total reactor-to-secondary leakage through al steam generators seideerne tha-neacWtn-Gop]=t 5=t= i; > ! L'# M54W150 gallons per day GiFiugh any one steam generator ) l Lt.0 9M.ts.4 t; 10 gym IDENTIFIED LEAKAGE from the Reactor Coolant' System, r e. 40 gpa CONTROLLED LEAKAGE at a Reactor Coolant System cressure of)
~*~
2235 i 20 psig, andl V*j= j="7
~ ~ ~ ~ ~
i l
'89" .$! ; A34N l . f. a-easoleakage at a Reactor Coolant System pressure of 2235 i 20 ostg
! .from any Reactor Coolant System Pressure Isolation Valve Cspecifh6di "
;1(Tahre Va-h9
- (0.feFmperem's4'surL.4a.lvei.ee4 % a. & m m *C S*gr Q APPLICABILITY: MODES 1, 2, 3, and 4.
3 Lg E.T.10N: ta, Lce s.a.s ! c6ap 5 .a . With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. , l l coup 4 4. With any Reactor Coolant System leakage greater than any one of the { above limits, excluding PRESSURE B0UNDARY LEAKAGE and leakage free
! Reactor Coolant System Pressure Isolation Valves, reduce the leakage ate to within limits within 4 hoursfor be in at least H6T $TANDBYT 1
I COMP E withinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing)
* "" b *
, y ,jy e
& 4 zusent as .u o With any Reactor Coolant System Pressure Isolation Valve leakage i CONO A above_ limit / reduce the leakage rate to within greater than t limits within. .hourd or be in atTaisiN0T STANDBY GitEin _the next) c.ony c : (6 hours and_,j_n ,_ COLD _SHUTD0WN,within the following 30 hours.J A:rses ear e M m o.r s.v. m e '
M B= --< zusus 3.4 .n c. > 8 . T [ Test-pre ssures-1 sss- than-2235- psig-but-greater-than -350 -psig -are-aMowee. Observed-leakage-sh:11 b; :djusted--for-the-actual-test-pressere g, to-2235-p;ig ;;e.eing-the ink ,;;; te be dir:ctly-properational t: ;rn:;r; differes,tial j ( te the =; 5:1f ; r:r.f 3/4 4-21 AMENDMENT NO. 57 BRAIDWOOD - UNITS I & 2
4 i i 1 CTS INSERT (S) l SECTION 3.4 j LCO 3.4.14 INSERT 3.4 21A (L,) l 4 CONDITION REQUIRED ACTION COMPLETION TIME l A. One or more flow paths NOTE . with leakage from one Each valve used to satisfy - 4 or more P.CS PIVs not Required Action A.1 and .' within limit. Required Action A'.2 must have been verified to meet i SR 3.4.14.1 and be in the i reactor coolant 3ressure ' boundary or the ligh pressure i portion of the system. l 4 ', A.1 Isolate the high 4 hours l pressure portion of
- the affected system
- from the low pressure l portion by use of one
- i. closed manual.
-de-energized power.
operated. de-activated automatic. or check valve. i
. AND A.2 ... ...
4 . i i . Revision A
4 t CTS INSERT (S) SECTION 3.4 4 LCO 3.4,14 j INSERT 3.4 21B (A3 ) 4 ACTIONS NOTES ,
- 1. Separate Condition entry is allowed for each flow path.
- 2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV. .
4-1 l INSERT 3.4 21C (M4 ) ! CONDITION REQUIRED ACTION . COMPLETION TIME 1 B. Residual Heat Removal B.1 Isolate the affected 4 hours 3 (RHR) System suction flow path by use of f isolation valve one deactivated interlock function automatic valve.
- inoperable.
i. 5 'l Revision A t e 6 6 % 4 ." O' 6
- , e
. L. O.,O '5. 5' . 5 3.5 Emmec.eue.v Cece Cwuwe, h re m (Ecu.d LC o 4 1 2.4.13 3s s.v,s m.. Iwxr.c:rica now raar .e...
)
L(0 34N i f j LIMITING CONDITION FOR OPERATION I '
%.S 8 StA\ k 00 l L C.O LS.4.0.D Reactor Coolant WyetesHeettese)shall be 5ui:- : 0g,g;,,, Q g ,,lg o f (g3,,g .3 5. 5 - i
- a. No PRESSURE BOUNDARY LEAKAGE,' h r e d
- M d
- A. O 1
l b. I gpa UNIDENTIFIED LEAKAGE, t see bDC Or 5.x% 3 A e i
- c. 600 gallons per day total reactor-to-secondary leakage through all '
steam generators not isolated from the Reactor Coolant System and j 150 gallons per day through any one steam generator, { g 10 gpa IDENTIFIED LEAKAGE fxs the Reactor Coolant System, , l [:. '^ ;;- C0"'"0LL*" :.E"""f5 :t : ":nter Occist Syst= ;,7;;sr; c' ) L 1 ( !??5 i !a ::10. ri ,' ! l f. I gpa leakage at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified I
< in Table 3.4-1. s l APPLICABILITY: MODES 1, 2, 3,(-end-4Q Q ddA (
on 3.A ., l AGIl9ti: ^-'ss a e
- a. With any PRESSURE B0UNDARY LEAKAGE, be in at least NOT STAND 8Y 1
within 6 hours and in COLD SHUTDOWN within the following 30 hours. { Cect A S With any Reactor Coolant System leakaae ornater than/any one og above limits / excluding PRESRM 800NDARY LEAKAGE and leakage from , 1 (Reactor Coolant System Pressure Isolation Valves. "2:s t.i: :nkeek ME F :t: t: ritt.t- 't=ttd within 4 hours or be in at leas 1' HOT STAND 8Y j thin the next 6 hours and in wwithin tte following j hours. [nser+ 3.4.ygA Modt. 4 g "c . With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, reduce the leakage rate to within j limits within 4 hours, or be in at least HOT STAND 8Y within the next i . 6 hours and in COLD SHUTD0WN within the following 30 hours. ' i 4 -,..<-e Addre. sed
- 6 chew.
See bot % 5ecAm M ' l i wM i } - n
" Test pressures less than,2235 psig but greater than 350 psig are allowed.
Observed leakage shall be adjusted for the actual test pressure up to 2235 1 j psig assuming the leakage to be directly properational to pressure differential to the one-half power. j BRAIDWOOD - UNITS 1 & 2 _ 3/4.4-21 . AMENDNENT NO. 57 I
- - - - . .- - - - . . .-. . _ . . = . . . ._
1 CTS INSERT (S) SECTION 3.5
- LCO 3.5.5 i INSERT 3.4 21A (Aa )
CONDITION REQUIRED ACTION COMPLETION TIME
- A. Seal injection flow A.1 Adjust manual seal 4 hours not within limit, injection throttle valves to give a flow within the limits of
- Figure 3.5.5-1.
4 3 i 1 1
- l i !
A Revision A i
. . _ , - _ y--
l L C O 2.4.13 1' - Leo 3.4,ltl REACTOR COOLANT SYSTEM LCO 3.5'.S* l
; SURVEILLANCE RE0UIREMENTS
, .52 3.4.6.l l 's.?.0.2.E Reactor Coolant System leakages shall be demonstrated to be within , each of the above limits by:
; ;. "e.. ; im . ..y Li..
. w.. .. i .. a; .1-y.... . v.aee ; n ;:rtt: 1:t: Lg j x "edicerti"ity :-iter :t 1 rt r r n r 12 h = = ;j
[t. "= tert ; the r:=ter s'. t; :
- h:r;;, =: = :: n:r. fat L(
7 f!: = d =i :" : dinh:r;;; ud '=:ter" :t 1:rt =:: ;r !? hrn; 3 A h .wd c. Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump ? h : s o : 3. , seals when the Reactor Coolant System pressure is 2235 i 20 psig at ! aleast once per 31 days with the modulating valve fully open. The
- h[s.,we.&
sm;.3.s( ' provisions of Specification 4.0.4 are not anolicable for entry into a MODE 3 or 4;I gn 3,y.22g
- d. Performance of a Reactor Coolant System water inventory balance \at
- least once per 72 hours; and
- it .
~ "eniteria; th: " net r ".nd c! r;: '.nk;ff Oj;te... et l ast ,,,,_ ,,;r) i gi h==q i L c o M. lti p*t
- p.4.6.2.2 -Each Reactor Coolant System Pressure Isolation Valvebperir4=d in ,I 3 ,I.bl; 2.t 1]shall be demonstrated OPERABLElby verifying leakage to De withinP
'[its limit: J 3R3y'MI &
a.- At least once per 18 months, ) b. Prior to entering MODE 2 whenever the plant has been in' COLD SHUTDOWN l for 7 days or more and if leakage testing has not been performed in the previous 9 months,
^
g
- . .ari r : r:: rain; th: =1 = t: nrvin fell:W; :!= tea , re?:id L cr r;plen= t' =ri = th; :1=, xd y
- d. Within 24 hours following valve actuation due to automatic or manual action or flow through the valvelexcept for valves RH 8701 A and B)
SR N.ie 3 *-@nd RH 8702 A and B. f ITh; preii; ea; ;f Oxifinti= 0.0.4 r: net ;;,,,licebl. Te. entry inte ",00 i Pe-4-J i k s g y.+e i , A, [Ioste.T 3.4 22E] L R. Ms+e .1 .TMSCt.T 3,U-22 C log-BRAIDWOOD - UNITS 1 & 2 3/4 4-22 AMENDMENT NO. 74 m-
CTS INSERT (S) 9 SECTION 3.4 LCO 3.4.13 INSERT 3.4 22A (L3 ) SURVEILLANCE FREDUENCY SR 3.4.13.1 NOTE Not required to be performed until 12 hours after establishment of steady state - " operation near operating pressure. Verify RCS operational leakage is within 72 hours limits by )erformance of RCS water inventory 3alance. ' i I a Revision A
CTS INSERT (S) SECTION 3.4 LC0 3.4.14 INSERT 3.4 ??R (A,)1 j l SURVEILLANCE FREQUENCY SR.3.4.14.1 NOTES
- 1. Only required to be performed 'in MODES 1 and 2.
- 2. ...
l INSERT 3.4 22C (L33) SURVEILLANCE FREQUENCY SR 3.4.14.1 NOTES
- 1. ... .
- 2. RCS PIVs actuated du' ring the performance of this Surveillance are
! not required to be tested more than once if a repetitive testing loop ! cannot be avoided. 3, ... j ,, 5 . 1 Revision A
L.t 0 3, b. 5 i L c o ~3o % I 3 L LD ~5 % N )
- .Q=6al = = "Cn c = *= de. SYSTMaw M b@
i l SURVEILLANCE RE0UTREMENTS ( i Sat L', ackioa Roo sn s.5,f,( (4.4.; 3 " Reactor Coolant ee:te 7em ;-J shall be demonstrated to be withi
'-- ' p the 's=p limitsy
,, ,g. , gym 3,y.m y
- a. nonitoring tne containment atmosphere gaseous and particulate
- radioactivity monitor at least once per 12 hours;
! b. Monitoring the reactor cavity sump discharge, and the containment
- j. floor drain sump discharge and inventory at least once per 12 hours; i
gl' TMeasurement gthe CONT LED LE E to th eactor lant pu seals whendhe Reacto Coolant stem pr ure is 5 i 20 g at least once per 31 days lwith e modul ng valv ully op 14he-gra t:i:= :f;;;:n::n::n :.c.: = ::: :;;::::::: f:r ::tr; int: ; ggg d. msn.tr 2.4-axs
. Performance of a Reactor Coolant System water inventory balance at h
least once per 72 hours; and *
- e. Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:
- a. At least once per 18 months, b .' Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,
- c. Prior to returning the ~ valve to service following maintenance, repair or replacement work on the valve, and
- d. Within 24 hours following valve actuation due to automatic or manual action or flow through the valve except for valves RH 8701 A and B and RH 8702 A and B.
The provisions of Specification 4.0,4 are not applicable for entry into MODE 3 or 4. AMeese). S Seclieu 3.V set poc.Ser 6ecMm M BRAIDWOOD - UNITS 1 & 2 3/4 4-22 AMENDMENT NO. 74
CTS INSERT (S)
, SECTION 3.5 LCO 3.5.5 INSERT 3.4 22A (L )
E 250 s ,
; 225 (s .38, 25) 200 (56.91, 200) 150 (49.28, 150) l 100 __
'(40.24, 100) 5 l h (24, 63.43) ~(32, 63.43)
UNACCEPTABLE REGION ' 25 50 l c., . '
- c. 25
_E 3 0 3 20 30 40 50 60 70 U SEAL INJECTION FLOW (GPM) - Figure 3.5.5-1 (page 1 of 1) Seal Injection Flow Limits Revision A
i i . 4 i CTS INSERT (S) 1 SECTION 3.5 LCO 3.5.5 INSERT 3.4 77R (M2 and L )
- NOTE t
Not required to be performed until 4 hours after the. Reactor Coolant System pressure stabilizes at = 2215 psig and s 2255 psig. i i l, . i 1 3 i 1 i . 1 i i 4 i i i i 4 Revision A 1
i l
.-ie 4'o 3.4 l TABLE 3.4-1 -
I REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES l
-VALVE NUMBER FUNCTION S18900A,B,C,0 CHG/SI Check Valve S18815 CHG/SI Backup Check alve SI8948A,B,C,0
, Accumulator _ Check Ive 18956A,B,C,0 Accumulator Backu Check Valve 8818A,B,C,D RHR Cold Leg Ch k Valve SI 19A,B,C,0 SI Cold Leg Ch k Valve SI8 9A,B,C,D SI Hot Leg C ek Valve SI890 ,B,C,0 SI. Hot Leg ckup Check Valve 518841 B RHR Hot Le Check Valve
*RH8701A, RHR Suct' n MOV's
*RH8702A,8 RHR Suc ion MOV's l'
l
- NOTE:
- 1. Leakage rate greater than 1.0 gpm but less than or eq l to 5.0 gpm are conside ed acceptable if the latest measured rate h ( not exceeded the rate termined by the previous test by an amount tha\ reduces the margin b ween measured leakage _ rate and the maximum permi ible rate of 5.0 gp by 50% or greater, -
j
=2.- Lea ge rates greater than 1.0 gpm but less than or equal to 5. gpm are to idered unacceptable if the latest measured rate exceeded the ate termined by the previous test by an amount that reduces the. mar 'n etween measured leakage rate and the maximum permissible rate of 5. gpm
. by 50% or greater, and
. Leakage rates greater than 5.0 gpm are consi,dered unacceptable.
p BRAIDWOOD - UNITS 1.& 2 3/4 4-23 S 4
i S ech 3.4 ,
)
I i MEACTOR COOLANT SYSTEM 3/ .7 CHEMISTRY i l LIMITING ONDITION s FOR OPERATION / 3.4.7 The Rea tor Coolant System chemistry shall. be maintained withi he limits specifie in Table 3.4-2. APPLICABILITY: At 11 times. ACTION:
/,
MODES 1, 2, 3, and 4: / ' j , ! a. With any one or nor chemistry parameter i xcess of its Steady-i State Limit but with its Transient Limi)- restore the parameter to j within its Steady-Stat Limit within 24Aiours or be in at least HOT l STANDBY within the'next hours and WCOLD SHUTDOWN within 'the following 30 hours; and
- b. With any one or more chemist pa'ameter r in excess of its Transient-t limit, be in at least HOT STAN Y within 6 hours anel in COLD.SHffTDOL"1 l within the.following 30 hours.
_At All Other Times:
/
/
! WjththeconcentrationoffitherchlorideorfluorideintheReactor i Coolant System in excess /bf its Steady-State L mit for more than 24 hours l 'or in excess of its Tr 'sient Limit, reduce the. ressurizer pressure to.
- less than or equal t 500 psig, if applicable, an perform an engineering evaluation to dete ine the effects of the out-of 'mit condition on the
, structural integ ty of the Reactor Coolant Sys. tem; termine that the Reactor Coolan System remains acceptable for continue operation prior to increasing /the pressurizer pressure above 500~psig o rior to proceeding o MODE 4. I j i SURVEILLAN. REQUIREMENTS s i 4.4. The Reactor Coolant System chemistry shall.be determined to be wit n 4 t limits by arialysis of those parameters at the frequencies specified.in , able 4.4-3. l S I A i .
.BRAIDWOOD - UNITS 1 & 2 3/4 4-24 ..
a 4 4
-g, - .+ . , - . - , , , , - . , - -- - _ , , ----3 -
R 5scwea 3 + TABLE 3.4-2 2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS l
/
STEADY-STATE ,NANSIENT PARAMETER y N LIMIT
/
/ LIMIT j
Dissolved Oxygen
- l \N $ 0.10 ppm ,/ $ 1.00 ppm ;
' i Chloride \ $ 0.15 ppm $ 1.50 ppm !
Fluoride 1 3 1.50 ppm l N s
/ .
y - N '
,/' N y
/ N p .
p . p"Eimit not applicable with I,yg less than or equal to 250*F. 4 t' BRAIDWOOD - UNIIS 1 & 2 3/4 4-25
5een 3A TABLE 4.4-3 ,- REACTOR COOLANT SYSTEM i i CHEMISTRY SURVEILLANCE REQUIREMENTS l l SAMPL AND l PARAMETER ANALYSIS' FREQUENCY Dissolved Oxygen * / At leas once per 72 hours Chloride At east once per 72 hours Fluoride \ At least once per 72 hours N
\s\
/
/"N # required with T,yg less than or equal to 250*F 4
e 4 4 BRAIDWOOD - UNITS 1 & 2 3/4 4-26
I L.co o,%/w 3,4 REALTOR COOLANT SYSI.E (Ac6) , cA.\& ! C /4 . 4. "J SPECIFIO AGTIVITY. LIMITING CONDITION FOR OPERATION
',6 i .
SMB The specific activity of the reactor coolant shall be G ; ned t pww.w h 4 j s A s.4./G. 2 .4 Less than or equal to 1 microcurie per gram DOSE EQUIVALENT I-131**, and l M JA.I6.l K Less than or equal to 100/E microcuries per gram of gross radioactivity. APPLICABILITY: MODES 1, 2,C. 4. ...J 54 ACTION: bod 3 * "" "" "" ") * ') 1 MODES 1, 2 and 3*: i WP A RA A. A y. With the specific activity of the reactor coolant greater than i 1 1 microcurie per gram DOSE EQUIVALENT I-131** for more than I j _48 hours during one continuous time intervaljor exceecing the listt ; line snown on Mgore 3.4-1, be in at least HOT STANDBY with T. l r (e @ B ess than 500*F w1hin 6 hours; andf I C.M p C. .K With_the specific activity of the reactor coolant greater than 100/E microcuries per gram, be in at least HOT STANDBY with T, less than 500*F within 6 hours.- (Add t.co 3,4th Ca,.ct,3 u A A>ert }
& l'
_-_ _ _ _ worr - -
. L,co 3,0, L( (s acd App //t'd!C .
l _ __ u i. d Lco 3.*l,Ib t,rrocs w M _ , [ *With Tm greater than or equal to 500*F.]
#**For Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35]
microCuries per gram.f S A 3..t.14.,2 Y 4 BRAIDWOOD - UNITS 1 & 2 3/4 4-27' AMENDMENT NO. 69
._ - - - _ _ . . . _ _ . . _- - . - - _ . . - - - _ -. - _ _ ~ _ _ _ .
Lco 54. t4 REACTOR COOLANT SYSTEM .. . i LIMITING CONDITION FOR OPERATION ACTION (Continued) MODES 1, 2, G. 4. ...J Ignoos s v,4s ncs &~.3r,-rarawre (r <4) ? foo'F. O c.oup g e4 4.s With the specific activity of the reactor coolant greater than 1 _ microcurie per gram DOSE EQUIVALENT I-131*j:r gr;;ter it.;r.1;;/:. 4 i =i;recerieU;r ;r::,l perform the sampling and analysis requirements of 7 tem 4.a) of Tab' e 4.4-4 until the spec'ific activity.of the reactor - 1 coolant is restored to within its limits. ,
, I l
SURVEILLANCE REOUIREMENTS 1 M The specific activity of the reactor coolant shall be detennined to be within the limits by performance of the sampling and analysis program of Table 4.4-4. l
. S e. 3.4. la . I s c. s.9.II.. $
' t, y, s q.IL. 5 l
l 6 4 M. /4,. 2
'*For Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35)
- _microcuries per gram.f BRAIDWOOD - UNITS 1 & 2 3/4 4-28 AMENDMENT NO. 69
___ - _ _ _ _ _ . . . . . . _ - . . - - . - - - . . . _ - . _ _ _ . . _ - . - - . - - - ~ . . - . - - - - - - - - - L.f 0 3.*l.lb E f 4 4 4, . . t
, i t
i 't 22 ' t
~
1 n
- \ja i
'k
{ t 5 . T j l ' k i i
, t - unccEMar i- 3 OPDiafloN l i t l
l h ' L I s
- W
-L -
j h t y \
,, 't 1
l-150 % ' t
- i j u k -
3
$ t -t a t ,
i i i T L ('L l i 5* \'< AccarTAms OPetATioN PcR UMTa \ I
.! UNACCEPTARE OPGIATioN FOR UMT 1 '
t I - i 3
- 5 '
s y % s 3 . L 1 (
" 3 , tm 2 tur --
i 4 w i, k I MM o I T I o ( ___ h ! ___ AcctmstE \ i ___ CPERATioN 'L i UNIT 1 LW- -- B i 0 20 .10 40 50 so l 70 ao so 100 ,, PDtCENT OF RATED TERMAL POWER i 6 c.v. u. - o FIGURE (h4-IN i DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY i LIMIT VERSUS PERCENT
...__.-.m.
( w_w_w_i.rwi . OF RATED THERMAL..P0WERf"..;.T.;.;..T:::
. . . . . . - - - - . . - - - - - - - - - ".;".;T."." . wr e.w a s a w sw s a v a 31 #asswaf ervirs uva6 Lgwa une.a.n s a aea. A, I
. I k ( e.t _.-. .n 4.+. 1, .n_ _.g gg_ __. r 1. .g e-,. .- a. s.. a . a.6 4. o. a. a m, a...s w w.._e, rws.er ra,.n s. r u.ma- r .a.ry
. .v .i .s .i )
[ BRAIDWOOD - UNITS 1 & 2 3/44-29
- AMENDMENT NO. 69 i
i
, . . - . . _ . , -- . -.,.,.-- . .- --. . . - . , - - ~ , , . . - , -
TABLE 4,4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT O AND ANAL.YSIS SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE FREQUENCY AND ANALYSIS REQUIRED ;
- 1. Gross Radioactivity Set 3.4.to. 4 [At least once per G2 t.au--d Determination ** -
1,2,38 tg 50.4.t6.2 Qg ya
- 2. Isotopic Analysis for DOSE EQUIVA- Once per 14 days 1 LENT I-131 Concentration SK s.t.tc. 3
- 3. Radiochemical for E Determination *** Once per 6 months
- i 1
- 4. Isotopic Analysis for Iodine .at (Once per 4 hours, Including I-131, I-133, and 1-135 whenever the specific If, 2f, 3f[ if, 5f] L3, activity exceedsf1 '
hA N -131**** i 5 E J'Y' A I Wr 100/E $ t/grir lefgreerrdter-*ivity.], t L,3 gand ,
.b7 f0ne sample between 2 1,2,3 and 6 hours following a
! THERMAL POWER change
~
s( s.v.I( s ' exceeding 15% of ftheRATEDTHERMAL POWER within a 1-hour-(period. ~ r [ :
.t BRAIDWOOD - UNITS 1 & 2 3/4 4-30 . ?
AMENOMENT'NO. 69 i e e
- - ~ . - . - - - . - - - . - . - . _ . . . . - - -. . . - . ~ - - -
D e % s % ns 1. \ - TABLE 4.4-4 t8'a=tinuad) p, g TABil NOTATIDMS I- [f Until the specific activity of the Reactor Coolant System is restored I 1 within its limits. i Sample to be taken after a minimum of 2 EFPD and 20 days *of POWER j OPERATION longer. have elapsed since reactor was last suberitical for 48 hours or A gross radioactivity analysis shall consist of the quantitative measurement of the total specific activity of the reactor coolant ~ except for radionuclides with half-lives less than 10 minutes and all radiciodines.
~-
The total specific activity shall be the sum of the degassed beta-gamma activity and the total of all identified gaseous 4 ! activities in the sample within 2 hours after the sample is taken and extrapolated back to when the sample was taken. Determination of the contributors to the gross specific activity shall be based upon those i enerity peaks identif: able with a g55 confidence level. The latest i
._ (.
avai able data may be used for pure beta-emitting radionuclides. '
% A radiochemical analysis for E shall consist of the quantitative measurement of the specific activity for each radionuclide, except for radionuclides with half-lives less than-10 minutes and all radiciodines, Q
v which is identified in the reactor coolant. The specific activities these individual radionuclides shall be used in the determination of for the reactor coolant sample. Determination of the contributors'to ! devel.tshall be based upon these energy peaks identifiable with a g55 confidence) I****For Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35 i microcuries per gram. see Doc-4 Jun,3.4j 9** e 4 4 4 0
. BRAIDWOOD - UNITS 1 & 2 3/4 4-31 AMENDNENT N0 69
i 4 Co 3.4.Ho TABLE 4.4-4 (Ct,ntinued) - - TABLE NOTATIONS wpn RA A.I. f Until the specific activity of the Reactor Coolant System is restored within its limits. a 54 s.v.16.3
- Sample to be taken*fu+u zu 6w of 2 EFPD and 20 days of POWER after a minimum Mh OPERATION have' elapsed since reactor was last subcritical for 48 hours or i longer. l NA gross radioactivity analysis shall consist of the quantitative menurement of the total specifit activity of the reactor cool )
cept i for radionDel- with half-lives less than 10 minutes 9d ' h radiciod*: m The taLJpecific activity 11 M s's of the degassed beta-gama activitMheAta- of all identified gaseous activities in the sample wi.thi l t o ter the sample is taken and extrapolated backJIurhefi'the sample was ta
. termination of the contributors-ttrthe gross specific activity shall be u on those e y peaks identifiable with a 95% confidence level. The
( available data may be used for pure beta-emitting radionuclides. [*** A. radiochemical analysis for E shall consist'of the quantitatjve 3
' measurement of the specific activity .for each radionuclide, except for radionuclides with half-lives less than'10 minutes and all radiciodines, which is identified in the reactor coolant. The specific activities for these individual radionuclides shall be used in the determination of E._
for the reactor coolant sample. Detemination of the contributors to E ] , shall be based upon these energy peaks identifiable with a 95% confidence ( 1evel. j , l
****For Unit 1, reacto oolant DOSE EQUIVALENT I-131 will be limited to 0.35)
_ microcuries per gram./ l , : 3R 3.4.16. ~.3. .- Addreased W ifedian /.I < j Gu poc.4.- See 9 9 < BRAIDWOOD - UNITS 1 & 2 3/4.4-31 ANENDMINT NO. 69
.. ~ . . _ _ . . _ . . _ . .. _ _ . _ _ .. _ _ ... _ _. .. _ ._ . _ .__ _ _ . _ _ .-_ - _ - _
4 1 Leo A%5
; Syed Scah% C4h I. S,81 REACTOR COOLANT SYSTEM (Rc6') '
S.4.7 c/0.0 O PRESSURE / TEMPERATURE LIMITS ' ff/d l . LIMITING CONDITION FOR OPERATION J' 1. c o 3 A..(svnet M weA w;W, w 6 e b =o++ #ae.m 4 h 44. PrtR..) ! G;T?F D The Rea or Coolant System t:::::: tt: : ;;;;;ruern temperature and oressure shall b i imited in accordance with the l'ait lines shown on rigures j '3.4-2a and 3.4-3a fo. Unit 1 (Figures 3.4-2b and 3.4-3b for Unit 2) during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with: f
- a. A maximum heatup of 100*F in any 1-hour period,
! b. A maximum cooldown of 100*F i.i any 1-hour period, and
- c.
- A maximum t'emperature change.of less than or equal to 10*F in any j- 1-hour period during inservice hydrostatic and leak testing operatioris ~
above the heatup and cooldown limit curves. j APPLICABILITY: At all times. 2 ACTION: Mao l m., y % j 1 OO tth sny of the above limits exceeded, restore the temperature and/or pressure
?: within the limit within 30 minutes perfo n engin
- [det ine the f,Fects of e out- imit c dition o(p(ring the eyafuation stxTctural pr 1 isfienritvl lo he Reactsf Coolan vstem
- ee ine that the Reactor Coolant System remains j
RA 4,2 acceptable for continued operation r/be in at least HOT STANDBY within the I next 6 hours and reduce the RC5 Tavg and pressure to less_ than 200*FEsir? d4NP 5 ,[3D9'ppfg,() respectively, within the following,'30 hour . ' (.ogp g:. am ss Ar s,* - 12 A 7
- SURVEILLANCE REQUIREMENTS 1
1'
- SR SA,3, \
! N The Reactor Coolant System temperature ar.d pressure shall be i i Ms.hl(heatup, cooldown, and inservice leak and hydrostatic testing operations, j deter J NarE j t 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens i j shall be removed and examined, to determine changes in material properties, as required by 10 CFR Part 50, Appendix H, in accordance with the schedule in Table 4.4-5. The results of these examinations shall be used to update Figures 3.4-2a and 3.4-3a for Unit 1 (Figures 3.4-2b and 3.4-3b for Unit 2), 4 _and 3.4-4a for Unit 1 (Figure i.4-4b for Unit 2). kb $r& % db **H S k h4 See poc.Aer- Grol% S*O BRAIDWOOD - UNITS 1 & 2 3/4 4-32 , AMENDMENT NO. 30
. CTS INSERT (S) SECTION 3.4
- LC0 3.4.3 .
, INSERT 3.4 32A (Mn) l' . $ CONDITION REQUIRED ACTION COMPLETION TIME
- - C. -
NOTE C.1 Initiate action to Immediately
- ReqA red Action C.2 restore parameter (s) shall be completed to.within limits.
whenever this l Condition is entered. _AND j ^ C.2 Deter.mine RCS is Prior to. Requirements of LC0 acceptable for entering MODE 4 i not met any time other continued operation. than in MODE 1. 2. 3. - l or 4. i i 1 i i Revision A 9
3 3 .
~'
1 c o '3 A .3
! REACTOR COOLANT SYSTEM 5pe40 cd' aa 5 6 6 i
j 3/4.4.9 PRESSURE / TEMPERATURE LIMITS $ REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION s p as.4".. ) ys % f1L Adelres.J ia Lco ?.4.~1 b a a ha.+se a...re o.us.~e r.res l s 4. , s <.t . sp s.4 4.e 3. ' a.1 The Reactor Coolant System kexceot the cressurjer) l' temperature and
.pressureAshall be limited in accordance with the limitsJ = cmra ^^ n;res 3 '
O.' 2: M L '-3; fe, Ur.it 1 (T;i,. ;; 2. '-2b ;;;d 0.4 L fe.- Ln H. 2) durir+
. Heatup, cooldown, criticality,'and inservice leak and hydrostatic testing wthi w ts b< l.e. 4< I h a ce s aj o w v:4 > +v PTL R .
T imum heatup of 100*F in any 1-hour period, . i b. A maximum cooldo O'F in any 1-ho i %2 .~ , and ! c. A maximum temperat ge of less { 1-hour equal to 10*F in any" uring inservice hydrostatic an sting operations he heatup and cooldown limit cur'ves. APPLICABILITY: At all times. j ACTION: l j With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to t determine. the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains !- acceptable for continued operation or be in at least HOT STANDBY within the 3 next 6 hours and. reduce the RCS T,yg and pressure to,less than 200*F and j 500 psig, respectively, within the follMngg m Addressed in L.c.o 3.4:3 ! SURVEILLANCE REQUIREMENTS s,e Docs 4.,Sech-3A i y _ I v 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be j determined to be within the limits at least once per 30 minutes during system heatup, cooldown,' and inservice leak and hydrostatic testing operations.
- j. . . . The reactor vessel material irradiation surveillance speci
- shall be rein examined, to determine changes in mate erties, i as required by 10 CFR Appendix H, in a ned with the schedule in
! Table 4.4-5. The results of thes ns shall be used to update i i Figures 3.4-2a and 3.4-3a (Figur - and 3.4-3b for Unit 2),
- an t -T"TFigure 3.4-4b for Unit 2).
i n s e r t- 3_.4 ss
,g
~
b
- j. BRAIDWOOD - UNITS 1 & 2 3/4'4-32 AMENDMENT NO. 30 -
L 1
CTS INSERT (S) SECTION 5.0 Specification 5.6.6 INSERT 3.4 32A (LAn ) 5.6.6 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR).
- a. ...
1
- b. The analytical methods used to determine the RCS pressure and ,
, temperature limits shall be those previously reviewed and approved ' by the NRC, specifically those described in the.following dccuments:
.. WCAP 14040-A, " Methodology used to Develop Cold Ov'erpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Revision 1. December 1994. Approval provided by NRC Safety Evaluation Report, dated October 16, 1995.
- 2. Comed letter to NRC. " Initial Pressure and Temperature 4
Limits Report." dated . Approval provided by NRC Safety Evaluation Report, dated : and [0 pen Item -- see Justification fo,r Differences Pp ]
- c. The PTLR shall be provided to the NRC upon' issuance for each l reactor vessel for each reactor vessel fluence period and for any
- revision of supplement thereto.
1 . Revision A 9 9
i AYMA. %. fuk%n CO "'f Mun " su. %c. .c t-. m,, go
- . 6. c,,,. g.
l armYE1m PRCPERTY BASIS - - l
- CONTROLLING MATERIAL
- CIRCUFERENTIAL WELD ~ )
INITIAL RT,,: 4 0*F- ,[' l l ART AFTER 32 EFPY: 1/4T, 1597 -
,, i l 3/4T, 135T ,
I i I These curves are applicable for heatup rates up to 100T/hr for i the service period up to 32 EFPY and contain margins of ICT and , 60- psig for possible instrument errors. i 4 s +
- *: :=.-= o .6 3 r. 7 i . 4
- i I 6 r e , i , ,
i I s . . . . t t .
- M gggg g '_ '
, i '
i e i - e e *6 J t T - 6 1 . . i
- l t 4 * . 8 *' ' ' * *
'I e p # f i i e l 4 f i i t t * ' I i I 6 . 6 !
t , u..f0 . . , .. . . . . i r. , , , ; , , l
' * ' 3 * !
t I I_ i i e [ t 6 , i e ; , ' I
- 1 i I g. t y ;
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- I i .
i I I I 6 I 4
..
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j
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- I f a f. e i ,
l.
- g. i . . t
# 1 a
- , . . i 1 1 t ! . - -
r r l i t 6 6 ) t
*= **
! 7 1500 f f f l 1 I G . ; r r
- c. i h eeptablg I I 3 y .:: ' ' Operettee '
~ ~ ~ 0 ' ' i+
) E acctPTAstt j - . t 't 6 . i 4 I I ggggygg j . i , ef e 6 e < 1 , g j y ? . ee ' 'L I 61', I
- 2. .... a i t . . Ft .I I e b * * * . -
r i e t , n .. .A . I I
- t
. i . s .. ,
v.t r ,.
. . 6 -
J i > ## i i t-
' # N(ATUP RAT [3
~
l ' ' '
.. UP 70 100*Fpa F F -
w go'I ' ' ' ' I r '
.1
. e i e f . I t / I. -
t C 2 e i a . I e 1 i i f
>F .
i Q+ j" I i
}
. . . . . f i ei ii i . . 6 i r 500 . , . .e / Criticality Limit.Saeed se l
. . . s' , laservies tydesstatic test .
' ' for the seressa
{ w. Persed 004*F)32.Errfap to. ' l 150 . . t , l
. . i i
. i , i l e a . l l 4 i l i l I t l
i t t
- r . . , l 0 50 100 150 230 250 300 350 400 450 500 ?
IN0l W 2D TEMPERATURE (DCC.F) 1 l i FIGURE 3.4-2a '
}
REACTOR COOLANT SYSTEM EEATUP. LIMITATION 8 APPLICABLE UP TO 32 EFPY (UNIT 1) 6 i i BRAIDWOOD - UNITS 1 & 2 3/4 4-33 AMENDMENT No. 53
. . _ - - . . . . ~ . - . . - . - . . - - - - . - - . . . . - ~ . . - . . . - . . . . . - . . . - - - . . - . . ~ . - - - - - . - . . . - . _ . . -
. ( ~' --" S e c + ;.., 2.4
,Soet;S.1.,,+,om 5. L .c .
l MATIKIAL PROPERTY BASIS _
., e .
CONTROLLING MATERIAL: CIRCUTERENTIAL WELD
,.[~'/ -
i
- NITIAL RTum
- 4 0'F- l 9
T AFTER 32 EFPY: 1/4T, 159'F -
,, i j 3/4T, 135'T ,
I Thes curves are applicable for heatup rates up to 100' /hr for i the a vice period up to 32 EFPY and cr.,ntain margins f 10'F and ,
! 60- psi for possible instrument errors.
a .
... t E Y O_ .. a F.; A \ '
j 4 i , 6 ii .. . / 6 , i g gggg gg ' J j e t . T.
- t t e i
*/ 6 e t ! i i , . . N. e i 6 6 6 I /. I t ! .
- 6
} t i 4 e 6 .\ e i . 8 ! *
- ff 6 I/ t I 6 6 .
g
. ! I t ti e . ' I f 6 s i e i ;
EE 0_ 4 . ! e e A e i i e r- e /J 2 ee j ii ) j ' e i i 6 .
. N. fg , y . 1 1 . t . + 8 . I * < r J > 'Il t 1 i j i '
l ... i ..I
. 6
\
# # ** I I
/
i r6 6 r i il e e :\ i ) t 4 4 Eb : e e , , \ s # ' . / J j . t 6 , j f . 6 6 ei$T
- i i ! 2 er I e , ;
5 i 6 .e A. 4 4 e r .I f , 6 4 ,
. . \. t t / I e fe e 6 e >
- ....e . 6 e s .. '
/ . ! 88 Ed , e , , . I N 2 j g
- , . . . \ r , , --
t i 6 e i ( -
/ r r 1 i , ii, 1 3 s - - O 1500 t t i \ / I I l $ ' '
Y
/ r r
- c. J J f \ h '
I 1 u *~~o' rat i ' ' ' ' ' ACCEPTA8t! ' ' E,
. e !
i
. # 6
. , ,i. e
; e i
f\ / _ gggygg g , ( , . i . y , e s , / i 3 - I, l 6 p- l 3 .... . 6 e . . s \' Ft e ii e L -. i .,, , . , , .. v . i i .
. . i r . . rA i r . .
i + . 6 * / NEATUP MTES ' a > ' ' i ' i i e i . > ' ' *-P * ! '
- g. a . . o , UP 70 100'F/m / e rv
.u. i i . t . .r i e s ,
O * . I I t i / 1 / \ . l 3 i . . .s i f se i
. . . . . r f X i i 500 !.,'l'.[ f f CritMey Limit.saaed sa ,
. . 6 , s e e Inaswise Bydreetatic Test i
' / ' fer the Santee
/ Temp.
Persed (304*F)32.EFFT op To. '
-.o
=c ,
. . is f l 6
, .f i , i i i i u. ., l
, a t t I i i
- e 0 50 100 150 200 250 300 350 400 450 500 .
INDICATED TCuPERATUAC (OCC.F) 1 . FIGURE 3.4-2a ' REACTOR COOLANT SYSTEM EEATUP LIMITATIONS - APPLICABLE UP TO 32 EFPY (UNIT 1) i e
. l BRAIDWOOD - UNITS 1 & 2 3/4 4-33, AMENDMENT No. 53 -
- Sec h 3.4
' ~
$$E
!- 4 d k nc e v.1 % 6 sc M a x 6 0 % Sa-we.%ssakacof i i v ( l ! CURVES APPLICABLE FOR HEATUP RATES UP TO 100*F/HR FOR THE S ' 16 EFPY. 1 CONTAINS MARGIN OF 10*F AND 60 PSIG FOR POSSISLE INSTRUNEl 1 j 25 0 3,u !.., , ) . 1 i>ii,eie iieie, , ,, ,,, , l ,, 2250 Leak Test y ,' l l, L im, i t, e ,
. i , ,
i , 2000 ' i n . , i i ,' i
, i j . .f g e .i. ... i , ,, , . . .
*ii , i 4
13
. e , , ,
' i ,, ,
! , i '.; 1 , , , j g :5,:- ;,;,,' * ! Acceptable' ,'; ;
/ Operation 3
c
+i4 .i
, i e,
',;,' f , .- .
1 <
<<,,.1 ,,
[ gii ll ,_ , 1 , l Unacceptable ,' i ' g ' Operation
,, , l l l, g
I .* - y >i i, ,,, s t I J f 4 g je:e a is ie
,,i i
,i e - ,
w
. Heatup Rates C '
vi ,i .. .... 3, Up To ',' , i M ~50f',' .' im *F/Hr '
.i i i. ,
l m } I ' ' ' l ;
'l' l,'
' Criticality Limit I j 500
' i . I Based on Ir. service I
" Hydrostatic Test --
- Teraperature (292*F) "
l a ^ 250 for the Service Period up to 16 EFPY-0
- 0 50 100 40 '200 - -
250 300 350 400 450 500 f eelcaft0 TruPERaTINtt (StG.F) FIGURE 3.4-2b REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 16 EFPY (UNIT 2) BRAIDUOOD - UNITS 1 & 2 3/4 4-34 AMENDMENT NO. 30
i i I
,2 2- Oe.<.4 ion 5.0 i
4 S e c4i on 3.4 i CURVES APPLICABLE FOR'HEATUP RATES UP TO 100*F/HR FOR THE S , 16 EFPY. l
- .. . CONTAINS MARGIN OF 10*F AND 60 PSIG FOR POSSIBLE INSTRUl .
50 l t
, E s.; 2 q- '
ii ,i,,, . . , , ,,,, , ,
, , i'+ti + t i e # # ,i a i
, , , , , , , , , , j i .. ,,,,,,,
! 2250
' Ledk Limit Test x ,' ,
1 l,'
,q l ,
- s
- w ,> o ,, , , , ,
- 1 , i , ,
,, ' r )
.ns ,, 1 i
r i i<
< i ,,,
1 , ,,, 2000 ' llSJ;j I mi it j , 1 j l {ll
,,u , ,
' , ,,, ,1, , ; '
'2 , ,
,'l, ' ,' ,' ;'
- 750 e ir , , , , , ,
,. 1 -
-, o , , , . . , ,'
3, , , ,' ' /r ' i e 4 , , ,,
, , c 1 ,1 , , ,
i , , ,,, E ;5% i, . ,
/ Acceptable- ' ' ' '
! l > , , , l ; , ,' ' ' e , ,,,,, .. s s y Operation - - ' - b, ' l'l'l ;' h
<- 7 1
,,,,,c
, ,,'lll, '
w 5:250 e
,: ',' l
' Un ceptable _;
Ope tion iet J l
, , ' ,l ; ;,
e * ,i i ; , ,, si ,
,e, ,,
g - i *i s , ei. .r ,.r
,,,, {
u 2000
- * *, .n , ,, , ,, .
- x ,_.c - r. ,,
llll,l, Heatup Rates ^ '/ ' ' ' e i , ,
-t ,1> 1 ,'
Up.To e ,. ri t' 750 { l 4 ,' m 'F/Hr 1 , , , ,
/ '
m
/
N',
' Criticality Limit I s00 i a i , s s . Based on Ir. service- +
2 - s Hydrostatic Test - '- Temperature (292*F) Z 250 / for the Service -
, eriodUpto16'EFPY{
' ' ~~
0 ' 0 , " -" 50 100 160 200 ~ 250 300 350 400 450 500 f eelcAfto TCasPCRATURC (DCC.F) FIGURE 3.4-2b REACTOR COOLANT SYSTEM HEATUP LIMITATIONS \ APPLICABLE UP TO 16 EFPY (UNIT 2) \s s e 4
.BRAIDWOOD - UNITS 1 & 2 3/4 4-34 AMENDMENT N0. 30
l . he %s 3 4. . AbknesskWoacken CO \ l
- - - .3Nc hiL y, g g -
see. 'poc.Aac kc Mh .MO v ww - 4 MATERIAL PROPERTY BASIS . i CONTROLLING MATERIAL: CI'RCUMFIRENTIAL WELD INITIAL RTmn: 40*F. " i ART AFTER 32 EFPY: 1/4T, 159'T
- 3/4T, 13 5'T i
i These curves are applicable for cooldown rates up to 200'F/hr for the service period up to 32 EFPY and contain margins. of 10*F and
'60 psig for possible instrument errors.
l 4 ! 1500 may, wu i ' i 1 -
, i ' - i 7 .
i a250: , ! 1 :. i . , acc0 ' ,
- - i .}}