ML20135B557
| ML20135B557 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/24/1997 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135B565 | List: |
| References | |
| RTR-NUREG-1431 NUDOCS 9703030102 | |
| Download: ML20135B557 (4) | |
Text
{{#Wiki_filter:Commonwealth 11hson Company e
?, liraidw ood Generating Station Route *I, Ikix Hi lirareville, IL 6(h0-9619 kp Tel HI4458 2H01 V
February 24,1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Mail Stop O-5 Cl2 Washington, D.C. 20555-0001
Subject:
Supplemental Information Regarding Application for Amendment to Appendix A, Technical Specifications, for Facility Operating Licenses: Byron Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457 Conversion to the Improved Standard Technical Specifications - January 23,1997, Meeting Action Items
References:
- 1. Gene Stanley and Ken Graesser (Comed) letter to NRC Document Control Desk, " Conversion to the Improved Standard Technical Specifications," dated December 13,1996.
- 2. NRC letter to Comed, " Summary of Improved Technical l Specirications Conmsion Meeting - January 23,1997,"
030039 dated February 18,1997. l l l l Ladies and Gentlemen: In Refererne 1, Commonwealth Edison Company (Comed) proposed to amend , Appendix A, Technical Specifications, for Facility Operating Licenses NPF-37, NPF-66, ' NPF-72, and NPF-77 for Byron Nuclear Power Station, Units 1 and 2, and Braidwood Nuclear Power Station, Units 1 and 2, respectively, from their Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) consistent with NUREG-1431, " Standard Technical Specifications - Westinghouse Plants," Revision 1, g dated April 1995. 9703030102 970224 7 l 1 PDR ADOCK 05000454' r ! P PDR 1 ) ohi.dartevpwrrespi199797014 doc l A Unicom Compan)
, N k 'o Document Control Desk 2 m
Reference 2 is a summag of the meeting held on January 23,1997, between members of ; the United States Nuclear Regulatog Commission (NRC) Staff and reprecentatives of I Comed to discuss that license amendment request. Attachments 1 - 3 provide the l information requested in Reference 2. Attachment 1, " Generic Changes versus CTS DOCS," includes a cross reference of l the generic changes included in the submittal to any corresponding CTS l Discussion of Changes (DOCS). Attachment 2, " Example Byron /Braidwood Plant Specific Justifications Which are Now in the Generic Process," provides a listing of Limiting Condition for Operation (LCO) "P" discussions which will become "C" discussions based on generic changes processed after the submittal cutoff date (October 2,1996). Byron and Braidwood are active participants in the industy generic activities and it is anticipated that more plant specific justifications may b5 converted into generic changes. In addition, it should be noted that three of these changes relate to beyond scope changes identified in Reference 1, Attachment 5. I Attachment 3, "ITS LCO versus CTS Page," provides a cross reference of the Byron and Braidwood ITS LCO versus the CTS page on which the ITS specification is discussed. In addition, to facilitate the Staffs review, Comed is providing the following information in Attachments 4 and 5. Attachment 4, " Anticipated License Amendment Requests versus Affected ITS LCO," provides a listing oflicense amendment requests forecast to be submitted during the ITS conversion review, a brief description of the change and the anticipated impact on ITS. It should be noted that the majority of these changes do not involve items which would introduce new conversion issues. Attachment 5 is a compilation of the marked-up Byron and Braidwood CTS pages, previously provid ed in Reference 1, in CTS page order. Comed appreciated the opportunity to meet with the NRC Staff to discuss the Byron and Braidwood ITS submittal. Comed welcomes any additional opportunities that may arise to discuss this matter with the NRC Staffin order to effect timely resolution of the issues and support the expeditious review and approval of this license amendment request. To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects these statements are not based on my personal l knowledge, but on information furnished by other Comed employees, contractor
1 (c., Document Control Desk 3 L) l employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable. Please address any comments or questions regarding this matter to Mr. Ilarold D. Pontious, Jr., Braidwood Nuclear Licensing Administrator, at (630) 663-7205. Very tmly yours,
}
T' , thy J. Tulon tation Manager Braidwood Generating Station Signed before me on this &/ day of kt[nurtu\. ,1997 0 i i by ---o r a v _e . u we ;; " O F F I C I A Lg= = == l= = = = = == =:l, SEAL" j ptary Public l s JACQUELINE A. SERENA l NOTARY NSUC. STATE ? OF ILUN0!5 y Attachments ll M
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cc: A. B. Beach, Regional Administrator - RIII l C. I. Grimes, Chief, Technical Specifications Branch - NRR G. F. Dick, Jr., Byron /Braidwood Project Manager - NRR R. R. Assa, Byron /Braidwood ITS Project Manager - NRR S. D. Burgess, Senior Resident Inspector - Byron C. J. Phillips, Senior Resident Inspector - Braidwood Oflice of Nuclear Facility Safety - IDNS i l
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g Attachment 1 Byron /Braidwood Improved Technical Specifications January 23, 1997 Meeting Action Item Generic Changes versus CTS DOCS (page 1 of 4) l l DOC ITS CORRELATION ITS LC0 GENERIC CHANGE CTS (DIRECT OR SECTION JFD CHANGE STATUS DOC (S) INDIRECT)") 1.0 C3 TSTF-004 Pending A13 Indirect 1.0 C7 TSTF-039 Pending L3 Direct 1.0 C8 TSTF-064 Pending A3 Direct 1.0 C9 TSTF-088 Pending M2/A12 Indirect 2.0 C1 TSTF-005 Approved LA1/LA2/ Indirect LA3/LA4 3.0 C1 TSTF-006 REV 1 Approved Al Indirect 3.0 C3 TSTF-001 REV 1 Pending L2 Indirect 3.0 C4 TSTF-012 REV 1 Approved A6 Indirect _3.0 C5 TSTF-103 Pending A4/A9 Indirect 3.0 C6 TSTF-104 Pending A4 Indirect 3.0 C7 TSTF-136 Pending A6 Ind,irect 3.0 C8 WOG-078 Pending A5 Indirect
,3.1 C1 TSTF-009 REV 1 Approved LA1 Direct 3.1 C5 TSTF-012 REV 1 Approved A18/A19 Indirect 3.1 C7 TSTF-014 REV 3 Pending M10 Indirect 3.1 C8 TSTF-089 Approved L13 Direct 3.1 C10 TSTF-110 REV 1 Pending LA9 Direct 3.1 C11 TSTF-108 Pending L17 Direct 3.1 C13 WOG-073 Pending A12/L4 Indirect 3.2 C1 TSTF-024 Pending LA4/LA7 Indirect 3.2 C2 TSTF-025 Pending L7 ]ndirect 3.2 C3 TSTF-095 Approved L10/L12 Direct (1) A CTS Discussion 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 O generic change is designated as an indirect correlation.
9703030107 970224 PDR ADOCK 05000454 P pop
i Attachment 1 l l l O' Byron /Braidwood Improved Technical Specifications ! January 23, 1997 Heeting Action Item Generic Changes versus CTS DOCS (page 2 of 4) l DOC ITS CORRELATION l ITS LCO GENERIC CHANGE CTS (DIRECT OR : i SECTION JFD CHANGE STATUS DOC (S) INDIRECT)m 3.2 C4 TSTF-097 Approved L9 Indirect 3.2 C5 TSTF-098 Approved L9 Indirect 3.2 C6 TSTF-099 Approved L9 Indirect 3.2 C9 TSTF-110 Rev.1 Pendino LA6 Indirect 3.3 C1 TSTF-135 Item 3 Pending A6/A8 Indirect A15/M7 3.3 CI 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 ; 3.3 C1 TSTF-135 Item 9 Pending L11 Indirect I 3.3 C1 TSTF 135 Item 12 Pending LA4 Indirect 3.3 C3 TSTF-091 Pending LA3/LA7 Indirect l 3.3 C5 WOG-080 Pending A20 Direct 3.4 C1 TSTF 026 Approved L36 Direct 3.4 C2 TSTre027 REV 1 Pending M9 Direct
]
3.4 C5 TF-093 Pending A13 Indirect 3.4 C6 ISTF-105 Pending LA18 Direct 3.4 C7 WOG-021 Withdrawn (2) A22 Direct i 3.4 C8 TSTF-116 Pending L21/L22/ Indirect ! L24 3.4 C9 WOG-051 Pending L16 Indirect 3.4 C10 TSTF-087 Pending L3/L12/ Indirect L23/L26 3.4 C12 TSTF-113 REV 1 Pending L8 Direct 3.4 C13 WOG-060 Pending L27 Direct l (1) A CTS Discussion 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 designated as an indirect correlation. (2) Based on withdrawal of WOG-021. NUREG-1431 Revision 1 will be utilizej for this l portion of the specification.
i l Attachment 1 O Byron /Braidwood Improved Technical Specifications l January 23, 1997 Heeting Action Item Generic Changes versus CTS DOCS (page 3 of 4) l DOC ITS CORRELATION ITS LCO GENERIC CHANGE CTS (DIRECT OR 1 SECTION JFD CHANGE STATUS DOC (S) INDIRECT)* I 3.4 C14 TSTF-153 Pending A31 Direct 3.5 C4 TSTF-117 Pending A4 Direct 3.6 C1 TSTF-052 Pending A5 Indirect 3.6 C2 TSTF-017 Pending L4 Direct 3.6 C3 TSTF-044 Proposed Pending A17 Direct REV 1 3.6 C4 TSTF-030 REV 1 Pending L14 Direct 3.6 C5 TSTF-045 Pending L11 Direct 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 J.7 C8 WOG-064 Pending L6/L7 Direct 3.8 C1 TSTF-002 Pending LA12 Direct 3.8 C5 1STF-036 REV 2 Pending L14 Direct 3.8 C6 TSTF-016 Pending L18 Direct 3.8 C7 TSTF-115 Pending L20/L21 Direct 3.8 C8 TSTF-115 Pending L22/L23/ Direct 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 G (1) A CTS Discussion Of Change (DOC) which is solely associated with the generic change is b designated as a direct correlation. A DOC which includes more information than the generic change is designated as an indirect correlation.
! l l i ! l l g Attachment 1 ; i L) l Byron /Braidwood Improved Technical Specifications i' ! January 23, 1997 Meeting Action Item l Generic Changes versus CTS DOCS (page 4 of 4) DOC l 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'8' A28 Direct 5.0 C4 TSTF-152 Pending L5 Direct l 5.0 C5 TSTF-052 Pending LA24/ Indirect A26/A36/ ' LA19 1 5.0 C6 TSTF-115 Pending LA25 Direct 5.0 C8 WOG-072 Pending A37 Direct i O I (1) A CTS Discussion Of Change (DOC) which is solely associated with the generic change is t designated as a direct correlation. A DOC which includes more information than the l 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.
[ g Attachment 2 : U : Byron /Braidwood Improved Technical Specifications ; January 23. 1997 Heeting Action Item l' Example Byron /Braidwood Plant Specific Justifications Which are Now in the Generic Process , (page 1 of 2) l l l RECENT ISTS GENERIC ITS ITS LC0 ASSOCIATED CHANGE SECTION JFD(S) ITS LCO SUBJECT NUMBER COMMENT 3.4 P38 3.4.12 Revise SR Note to exempt WOG-087
" performance" of the SR rather than exempt " compliance" with the SR i I
3.3 P29 3.3.4 Eliminate the table in the WOG-088 Will conform Remote Shutdown System LC0 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 l Change 12 identified
% in submittal j (V 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 3.1 P7 3.1.5 Eliminate unnecessary Actions WOG-094 3.2 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 5R 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 FWlVs
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 (page 2 of 2) RECENT ISTS GENERIC ITS ITS LC0 ASSOCIATED CHANGE SECTION JFD(5) ITS LCO SUBJECT NUMBER COMMENT 3.4 P3 3.4.1 Extend the time allowed to WOG-099 Eliminates perform the BOL 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 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 P1/P19 3.2.2 Frequency wording (*) ( 3.2 P1 3.2.4 L e 3.4 P14 3.4.11 Specify Separate Condition WOG-102 Entry for each pressurizer PORV block valve 3.1 P1 3.1.6 Finor 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 Editorial-12 Will conform P45 the specific activity limits to post Oct. directly in the LCO. 2. 1996 editorial changes O
l Attachment 3 O ~ i Byron /Braidwood Improved Technical Specifications January 23, 1997 Heeting Action Item . ITS LC0 versus CTS Page (page 1 of 7) i ITS LC0 Braidwood CTS Page Byron CTS Page l 1.1 1-1 1-2 1-3 1-4 1-1 1-2 1-2a 1-3 1 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
- 1-7 1-8 1-7 1-8 i 2.1.1 2-1 2-2a 2-1 2-2 )
I 2.1.2 2-1 2-1 l 2.2.1 2-1 2-1 l 2.2.2 2-1 2-1
- 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 l 3.0.6 3/4 0-1 3/4 0-1 3.0.7 3/4 0-1 3/4 0-1 i
SR 3.0.1 3/4 0-2 3/4 0-2 l 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
- 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 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 CTS pages listed do not have corres onding ITS requirements but are provided for completeness. The CTS pages contain requirements whic are deleted or relocated.
l 2 g Attachment 3 Byron /Braidwood Improved Technical Specifications 4 January 23, 1997 Meeting Action Item ITS LC0 versus CTS Pass (page 2 of 7) ITS LCO Braidwood CTS Page Byron CTS Page 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 3/4 1-17 3/4 1-19 3/4 1-17 3/4 1-19 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 3/4 1-18 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 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 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 l l3.2.4 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 3/4 3-5 3/4 3-5 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 3-4 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 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 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 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 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 3/4 9-14 3/4 9-14 ~ (( 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 O l Byron /Braidwood Improved Technical Specifications J January 23, 1997 Meeting Action Item , ITS LC0 versus CTS Page l (page 3 of 7) ! 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
- 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 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 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 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 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 4 l F 3.4.7 3/4 4-5 3/4 4-5 3.4.6 3/4 4-6 3/4 4-6 I
3.4.9 3/4 4-11 3/4 4-11 3.4.10 3/4 4-10 3/4 4 10 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 1 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 I 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
- 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 C CTS pages listed do not have corresponding ITS requirements but are provided for completeness. The CTS pages contain requirements which are deleted ce relocated.
Attachment 3 Byron /Braidwood Improved Technical Specifications January 23, 1997 Heeting Action Item l ITS LC0 versus CTS Page (page 4 of 7) j ITS LC0 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 5-6 ! 3/4 5-6a 3/4 5-6a j 3.5.3 3/4 5-7 3/4 5-8 3/4 5-7 3/4 5-8 j 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
]
- 3/4 5-10 3/4 5-10 l 3.6.1 1-2 3/4 6-1 3/4 6-2 1-2 3/4 6-1 3/4 6-2 l 3.6.2 3/4 6-4 3/4 6-5 3/4 6-4 3/4 6-5 l
! 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 6-16 l 3/4 6-17 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 ,i 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 l 3.6.4 3/4 6-6 3/4 6-6 3.6.5 3/4 6-7 3/4 6-7 ] 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 l 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 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 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 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 l i CTS pages listed do not have corres onding ITS requirements but are provided for completeness. The CTS pages contain requirements whic are deleted or relocated. 4
.)
i l g Attachment 3 l V i Byron /Braidwood Improved Technical Specifications i January 23, 1997 Meeting Action Item ITS LC0 versus CTS Page (page 5 of 7) i ITS LC0 Braidwood CTS Page Byron CTS Page l 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 l 3/4 9-16 3/4 9-16 l 3.7.14 3/4 9-13 3/4 9-13 l 3.7.15 3/4 9-13 3/4 9-13 3.7.16 Open item Ooen item 3.7.17 3/4 7-7 3/4 7-8 3/4 7-7 3/4 7-8 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 4 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 j l3.8.3 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 3.8.5 3/4 8-13 3/4 8-13 3.8.6 3/4 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 8-16 3/4 8-13 3/4 8-16
- 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 The CTSpageslisteddonothavecorreskondingITSrequirementsbutareprovidedforcompleteness.
CTS pages contain requirements whic are deleted or relocated.
1 Attachment 3 O' Byron /Braidwood-Improved Technical Specifications
- January 23. 1997 Meeting Action Item ITS LC0 versus CTS Page (page 6 of 7) 1TS LCO 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 5-1 5-2 '
4.1.3 5-1 5-3 5-1 5-3 ! 4.2.1 5-4 5-4 4.2.2 54 5-4 4.3.1 5-5 5-5b 5-5 5-5b 4.3.2 5-5 5-5 ' 4.3.3 5-5 5-5 ; 5.1.1 6-1 6-1 5.1.2 6-) 6-5 6-1 6-5 I I 5 .2.1 6-1 6-1 5.2.2 6-1 6-2 6-2a 6-5 6-2 6-2a 6-5 5.3.1 6-6 6-6 5.4.1 6-16 6-16 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 5-5a 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 The CTS pages contain CTS pages listed dorequirements not have correskonding ITS requirements whic are deleted or relocated. but are provided for completeness.
Attachent 3 O Byron /Braidwood Improved Technical Specifications January 23, 1997 Heeting Action Item ITS LC0 versus CTS Page (page 7 of 7) ITS LC0 Braidwood CTS Page Byron CTS Page 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 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.b.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 1-2 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 8-12a 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 l 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 6-4 6-7 6-15 6-23 6-24 6-23 6-24 l l The CTSpageslisteddonothavecorreskondingITSrequirementsbutareprovidedforcompleteness. CTS pages contain requirements whic are deleted or relocated.
Attachment 4 Byron /Braidwood Improved Technical Specifications g Anticipated License Amendment Requests versus Affected ITS LCO d (page 1 of 1) AMENDMENT IMPACTED REOUEST SUBJECT CHANGE DESCRIPTION DESCRIPTION OF ITS IMPACT ITS LCO* PTLR** Relocate RCS heatup and cooldown ITS submittal reflects the 5.6.6 limits and curves. coupon removal relocation of this schedule, and LTOP figures to an information with owner controlled report which appropriate discussions. includes methodology. Throttle Revise throttle and governor valve None None Valve / Governor surveillance frequency from monthly Valve to quarterly. Byron only- Revise battery specifications to Value changes and addition 3.8.4 Battery reflect new purchased batteries. of' battery specific 3.8.5 Replacement discharge test. 3.8.6 Byron only - Decrease RCS Dose Equivalent lodine Value change only. 3.4.16 Dose Equivalent allowable value to allow continued lodine operation prior to SG replacement. i allowable value , Byron only - Revise UHS basin requirements besed Value changes only. 3.7.9 l Ultimate Heat SG replacement and recent design 1 Sink evaluations. 1 Boraflex** Provide ITS Specifications which Specification development 3.7.14 I O reflect the Technical Specifications associated with the spent fuel pool invol ved. 3.7.15 3.7.16 l 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 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. 4 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 lodine allowable requirements. No 5.6.9 Program) value to standard value. additional conversion issues involved. Dose Equivalent lodine change is a value only change (affects Figure also).
- 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.
_ . _ _ _ ._.____._._____._._._..___._.._._._-_.m . _ _ _ _ . . _ - - i , h1 ( b alDM *! 4 l
- l. 0 051; AMD APPLl(A710M t
Q 1.h DEFINITIONS
-_________noye_________-__-__
@ The defined terms of this section appear in capitalized type and are applicable ,
_ throughout .._ ._these._ __Technical __ ._ SpecificationsM_ _ _ _ . u.I SneD ACTI0h hired W 4, W MQ n G ACTIO ! C/ hall be that part of a 6 Specification
- 4*4ah prescribes under designated conditions %, ,,;flM NM., T. eel i
ACTUATION LOGIC TEST i E B An ACTUATION LOGIC TEST shall be the application of vario : input combinations in conjunction with each possible interlock logic state and verification of the required loaic output. ' include a continuity checkC as a minimuma or output devices.The ACTUATION .,$ LO'
/EllEliUlh CHANNEL OPERATIONAL TEST
[ rad @ g h 9 As9BN121D CHANNEL OPERATIONAL TEST hhall be the injection of a simulated / ' signal into the_ channel as close to the/ sensor as practicable to verify OPERA 8ILITYe r -..............z.. .._ ._ __._._.a The 4 M W ) CHANNEL ! OPERATIONAL TEST shall include adjustments, as necessaiy, of the alarm, inter-W rd@ T-i;: C:t :ir.t: r,ud. t:..:. i.h* *,614,9init.= .rv wi min Lne requireo l range and accuracy. % cor m (3, ! O AXIAL FLUX DIFFERENCE e
.se,ies ,c 3 9oe wo,,
p,,4,,,,,j b w,g ,,,,
,,lppi.,,, ,,4,ga gr ,'r' -
A > i s s ..: a.n ,, u u ,,,u ,% ,,,,a ,g,d. l i O AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals i between the top and bottom halves of a two section excore neutron detector. l CHANNEL CALIBRATION GED A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known inpu@ JThe C"."TL t=LI"==m* th:: : :::_ ,:n .n: :-- = :--- =" IIn5E RT We T perrormed bys cr-- rd e!:- , d-t:-?::t ::d!:r tri;; f=c^' [Maay be Tpg . such that the' entire channel is calibrated.any series or sT40 tnt.ial, overlapping or total chan
/ Q '
09m eO @ 55riCAuteAtoJ) Sibk.}.
"~ ~
CHANNEL CHECK E D A CHANNEL CME _CK shall be the qualitative assessment,of channel behavior m Ty during operation.@y observation 7 This determination shall include, where possible, comparison of the channel indication and@ status with other indications @r status derived from independent instrument channels measuring the same parameter. O BRAIDWOOD UNITS 1 & 2 1-1
i F l Q CTS INSERT (S) SECTION 1.0 i l l Definitions 1.1 l INSERT 1-1A (A3 and A) i The CHANNEL CALIBRATION shall encompass those components, such as sensors, alarms, displays, and trip functions required to perform the specified safety ' function (s). Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. INSERT 1-1B (A3 ) l
... . including all components in the channel, such as alarms interlocks. .
displays, and trip functions, required to perform the specified safety , function (s). O i i l-l 0 Revision A
DC[meMnL l* I ! I MS 3 n s.o l A dd ress eJ 's. Sn h ea 34 hDEFINITIONS (5*. Dcc & Sube 54 i TONTA'INMENT' INTEGRITY ' % ^ ~ ' ' l I 1.7 CONTAINMENT INTEGRITY shall exist when:
- a. i All penetrations required to be closed during accident conditions are either:
- 1) l Capable of being closed by an OPERABLE containment automatic isolation valve syste.n, or {
- 2) j Closed by manual valves, blind flanges, or deactivated automatic j valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3. t
- b. j All equipment hatches are closed and sealed, I
- c. Each air lock is in compliance with the requirements of Specification 3.6.1.3, i m l d.
The containment leakage rates are within the limits of SpecificatioI 3.6.1.2, and e 8 [g " !
\ w Enc !
e. The sealing mechanism associated with each penetration (e.g. ,9swelds .o . 1 hol l nwa: . or 0-rinos) is OPERABLE. j
)
CONTP4LLEDLEAKAGE(
- 1. 8 CONTR0 )
antpum/LEDLEAKA to p seals. shall be [t at seal watdr
/ flow suplied to t[e reacth l
. CORE ALTERATION (4A, somn ,, MvWy ceMn'D .AL, I p).
( s U
@. CORE ALTERATION shall be the movemente Hp=N- of anyJcomponenQ)-
' within Suspension the reactor of CORE vessel with the vessel head removed and fuel in thj ALTERATIO component to a safOram-*@*== position.shall not preclude completion of mov I
CRITICALITYANALYSISOFSVRONANDBRAIDWO0dSTATIONFUEL/TORAGERACKS
- 1. 9a Th'CRITICALITYA/ALYSISOFBYRON d RACKS, i a document t'at provides the aximum 'NDBRAIDWOODSJTIONFUELSTOR allowab e fuel enrichme for E
storage h indiv dual Specific tions.Plant opera on within thes limits is addr sedh These limit shall be dete ned and submi ed in accordan with Specif cation 6.9.1. O. i DIGITALCHAhtkELOPERATIONA! TEST
. I'.10 AD 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.
DOSE EQUIVALENT I-131 GEED DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurf e/ 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 d'ose conversion factors used for this calculation shall be those listed in Table III of TID-34844, " Calculation of Distance Factors for Power and Test Reactor Sites." f) (> BRAIDWOOD UNITS 1 & 2 1-2 AMENDMENT tl0.18
l W '"%s n. I k C-O ?. . t. . I-O v DEFINITIONS Md"Es e e CONTAINMENT INTEGRITY Y"# ST*EY CONTAINMENT INTEGRITY shall exist when:
- a. penetrations required to be closed during accident 1tions j are e r: l
- 1) Capable o ing closed by an.0PER containment automatic I isolation valv tem, or
- 2) Closed by manual val , nd flanges, or deactivated automatic valves secured
- eir close itions, except as provided in ,
Table 3. - Specification 3.6.3.
- b. All ment hatches are closed and sealed, l ach air lock is in compliance with the requirements of Specification 3.6.1.3,
- d. The containment leakage rates are within the limits of Specification i 3.6.1.2, and
- e. The sealing mechanism associated with each penetration (e.g., welds. - I 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.
Q 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 RACKS, is a document that provider 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 dats 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, 1-132, 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 P Reactor Sites." d hM re ss ed o n Dc%.m u BRAIDWOOD UNITS 1 & 2 .5 e < Docs 12 f or Secb / c AMENDMENT NO.18 v
.~ ... . . . .- - --
DeCadicas s.: d LC O S.&.I S e c t.'c. n E , o ! i o DEFINITIONS CONTAINMENT INTEGRITY aW . ~ :. w _
-_#2 --'#
- 1. 7 CONTAINMENT INTEGRITY shall exist when:
- a. All penetrations required to be closed during accident conditions are either:
, 1) Capable of being closed by an OPERABLE containment automatic i 1 isolation valve system, or '
- 2) Closed by manual valves, blind flanges, or deactivated automatic ,
valves secured in their closed positions, except as provided in j 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 4
Specification 3.6.1.3, j
- d. ' The c6fftln * * '
o pecification 3 . I
- e. The n eling n :h:ni:: :::::f:ted "ith 2 9 peaet M an fa 0 wa W l
b:ll:w;, Or 0 rSg ) i: OPER.^3' E. . j CONTROLLED LEAKAGE ' l 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 I 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. l CRITICALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACKS 1.9a The CRITICALITY ANALYSIS OF BYRON 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." Mdmssed in Defina t.on n. BRAIDWOOD UNITS 1 & 2 Sea D OC s f,,1-2 se c+ on i.o AMENDMENT fl0.18 . U _-
. - - - . - - . - - . - . - - ~ . - - - . . ~ - - - - - - - - . - - - - - -
fehwie 1. I jl ! 6po d m W CD
@ DEFINITIONS i ,
! i I - AVERAGE DISINTEGRATIDN ENERGY- - e.uur emte ame.w w. A u,.e bo) h G E shall be the average
~
ed in proportion to the concentration of f i each energies radionuclide per disintegration in the gM,-,,.the
.. sum of the average beta and gamma ;
n mv ) for d e ::-- r : = : tr it:
- M:q l
}. , ENGINEERED SAFETY FEATURES RESPONSE TIME Yg'My) b ,@ G The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time !' i l interval from when the monitored parameter exceeds its' ESF Actuation Setpoint l i at safetythe channelfunctionsensor until the ESF equipment is capable of performing its j i.e. i discharge pressur(es re,ach their required values,Times etc. .the shallvalves include travel to t j j diesel generator starting and sequence loading delays)where applicl TFREQUENCY NOTATION **
.4 The FREQ CY NOTATION 3p6cified for equirements all correspose to the int eperformenteofSurvgt11ancei l als defins(in Table V.I. 2 ;
GDERREBiLEAKAGE G IBMHMBLEAKAGE shall be: 4.I h %dd.1.6AkA(mL !
' ' M akane f: = : --"=2 rir =: :::::: :::t-3 suchus h+M i pump sea @or valve packing i ;;;; : = r:y aptured and conducted to sump or collecting tank, @ l wuw eo n eon n e u.4 e re u .a ruaw M
\ w M aah; n ort **k A % ac.c)is 5mn i
)
% M M aj into'the containment atmosphere from sources that are both spec T cally located and known either not to interfere with the g i oerationofgeakagegetectionfystemsornottobe/RE55URE LEAKAGE, or l
)
g, ReactorCoolantSystem/eakanethroughasteamgeneratortothe g, Secondary d!isiFFisiBJSystem.
~ /b,ed.4.A LEJH(%E dehWipg Mayer kced.,
I L. \c. Frened. %ku, LEmus 9pssM M Wre. 1.15.a The maximum allowable primary containment . leakage rate, L , shall be i 0.10%oftheprimarycontainmentairweightperdayatthecalcu1Iitedpeak J Leontainment pressure (Pa). I mm - - - MASTER RELAY TEST
%e%ek (a %.bok Co 4,*g emu see pac 4- T&An f.o d
hG E.yve.e.we eks-),A MASTER RELAY TEST shall ^- "- -----'- "-- -"each l t r:-" ::tt= COPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay. !' MEMBER (S) 0F THVPUBLIC 1.17 MEMB 5) 0F THE PUB shall inclu all persons o are not occupati ally associate with the plan . This categ \ i employ s of the licen e, its contr ors or vendo anddoes not in ude 1 O the te to service uipment or t ke deliveri . persons o enter This cate y does i' i ude persons use portions f the site f recreational occupational . ) other purpos not associat with the p1 .f BRAIDWOOD - UNITS 1 & 2 1-3 AMENDMENT NO. 73
...._.--_._._._..__...~.___._.__..~____s. .-__ _ .-_ _ ._. _ .
a i i 4 . -1 3 l A' CTS INSERT (S) l lV 4 SECTION 1.0 i l Definitions 1.1- i 4 i, INSERT 1 3A (L,)_
- s. i t
' 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. '
- i !
J : a 2 ! 1 5 i I i !
- -t
. i s i i ! 1 i 5
- l, i
Q . i 1 l l i ! i i- i i i i i
- i
. J 1 i
- . -i
,'j i T i l 4-O- ) Revision A 4 _ , . , . . , , _ y - - _ _ _ - . . , . . , _ . _ .._ -- w ---
DEFINITIONS Osne:4 s.a. I - See+, e n 5 0 E - AVERAGE DISINTEGRATION ENERGY e i O 2 22 E
- 1' 6 th r e- ( $aht d $a araaartiaa ta th caac atr tiaa af 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 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that i interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel safety functionsensor until the ESF equipment is capable of performing its ! i.e. discharge pressur(es re,ach their vrequired 'alues, etc.).the Times valves travel shall include diesel generator starting and sequence loading delays where applicable. FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. IDENTI7IED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or O' 6-
'
- a iata th caat ia at
- a ah r <ra =aarc th t r 6ath specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant' System.
5 . 5. 14, 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). MASTER RELAY TEST hdbess. din Sec4.cm L0 Su pots .r., 5.a. .. t o 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. MEMBERIS) 0F THE PUBLIC
~
1.17 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors or vendors and persons who enter G the site.to service equipment or to make deliveries. This category does kJ include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. BRAIDWOOD - UNITS 1 & 2 1-3 AMENDMENT-NO. 73 .
"De % 1+;rns M .
SpexAkHon 50 DEFINITIONS -
- DFFSITE DDSE CALCULATION MANUA AMrse*L'su Sec.44aw 50 g g g. 5Mrs (4 w= w-
- 1.18 j-and parameters used in the calculation of offsite doses resulting from .
active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alars/ Trip Setpoints, and in the conduct of the Environ- ' mental Radiological Monitoring Program. Tne ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring 4 Programs required by Sections 6.8.4.e and f, and (2) descriptions of the
'information that should be included in the Anrival Radiological Environmental
' Operating and Radioactive Effluent Release Reports required by Specifications
. 9.1.6 and 6.9.1.7. I f DPERABLE - OPERABILITY (W - e qw %y
@ A system, subsystem, train, component or device sh 11 be ERABLE or
@have OPERABILITY when it is capable offied performing function (s), its spe E and when all necessary attendant instrumentation, controls electrical power, cooling'W$ seal water, lubricationB other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
@ OPERATING LIMITS REPORT (IEID 8 W" "T i
j h G:T9:E er.Ja.soea'.G<e ears s+er) h?" ) heePEPATIE LI"ITs m.%s the uni -specific document that h a providesT::: = c limits for the currenttc::rn t = reload cycle. These cycle-specific mrntelimits shall be determined for each reload cycle in accordance with Spe$fication 4' .".L M d"
- ope i
j limits is addressedlin individual cifMons. ration within these eperettmr) ( PNN) { tAvW ) l Ai '
, =m!I'=t ='=r 3 MODE l
h G At n"aT:'""" -^r:7 MODE [shallcorrespondtoanyoneinclusive combination of core reactivity condition power level, @ average reactor { coolant temperature +specifled in Table
,,,, % u ., a ., w y, m n had reacw ve*d L
- (ca wre li,(+ 44,.v q ,
4 1.20.a P i ((44.4 psi,g) for the design basis loss of coolant accident.shall J be the maxim i PHYSICS TESTS ^ #' " ' g.ei.a -r,.e bec m) C** " ) Q PHYSICS
@ nuclear chara STS shall be ose tests performed to measure the fund mental in Chapter 14 ristics of the core and related instrumentation.
f the@SAR, scribed 50.59,or,$ herwiseappro@edbytheibthorized ommission. under the provisions o 10 CFR (PRt55URY r y
- BOUNDARY LEAKAGE r
N" O e --~m === = trax ^st '= : kbody, pipe wall, or vessel wall./nabnhhrough m _ a nonisolable f J Mnek 4%vac.*beLio} , BRAIDW G 1 - UNITS 1 & 2 1-4 AMENDMENT NO. 73
. De 6 4 ;.nsa,e Spes dice 4,o. s O DEFINITIONS OFFSITE DDSE! CALCULATION MANUAL L 5.5.1., hit The DFFSITE DOSE CALCULATION MANUAL (0DCM) shall. contain the method and parameters used in the calculation of offsite doses resulting from radic- .
active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints ===8 in the conduct of the Environ-mental Radiological Monitoring Program. The ODCM shall also contain (1) the f Radioactive Ef"luent Controls and Radiological Environmental Monitoring Programs required by Sections 6.8.4.e and f, and (2) descriptions of the 5.2 information that should be included in the Annual Radiological Environmental l Operating and Radioactive Effluent Releas'e Reports required by Specifications 6.9.1.6 and 6.9.1.7. i OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or l 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 l reghed for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). OPERATING LIMITS REPORT I 1.19.a The OPERATING LIMITS REPORT is the unit-specific document that ! l O provides operating limits for the current operating reload cycle. These cycle-specific operating limits shall be determined 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 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. L .' -m Addressed in Seefoe LO I
$.L lb .
~ Sac Docain 5 cc.4 e., l.o 1.20.a P shall be the maximum calculated primary containment p (44.4 psig) for the design basis loss of coolant accident.
PHYSICS TESTS rF'[ # 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. i PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube O leakase) throush a nonisoiabie fauit $a a Reactor Coolaat System component body, pipe wall, or vessel wall. i l
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j BRAIDWOOD - UNITS I & 2 1-4 AMENDMENT NO. 73 i I
Defin.h.,a l. I
@ DEFINITIONS O . l
" PROCESS CONTAQL PROGRAM (
1.23 The PROCESS CONTROL (PCP)shallcontainthecurrentformulasd sampling, analyses, tests, and de Ationstobemadetoen processing and packaging of solid radioactwo-was on demonstrated I processing of actual or simulated wet s s W accomplished in such a way as to assure regulations with 10 CFR Parts 20, 61 M 71, State round requirements, and other requirements go emhytthe ll' { o solid radioactive waste. . PURGE-PURidNG 1.24 PU E or PURGING sha be any controlle process of disc ing air or gas from a nfinement to mai in temperature, ssure, humidity concentration
--INSERT, or ot operating condi ion, in such a man r that replaceae air or gas is tI.gA g requi d to purify the onfinement.)
QUADRANT POWER TILT RATIO O 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 excore detector calibrated output to the_ average of the lower excore detector calibrated outnuts. whichever is areater.1With one excore detector inoperable, the remaining three detectors] (shallbeusedforcomput.ingtheaverage.j Q RATED THERMAL POWER SinwJ % seau 3.:C _ d o E J , Se< 4 2.2 ee Aadv) -- RATED THERMAL POWER shall be a tota 14 core heat transfer rate to the
@ @ reactor coolant of 3411 MWt.
. REACTOR TRIP SYSTEM RESPONSE TIME dE 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. 3,
)
REPORTMLEEVENT( 1.28 A REPORT Sec ion 50.73 of LEEVENT[hallbeany['fthosecondi/ionsspeciIedin 10 CFR Fart 50. / G SH f (Conhol) GINshallbetheinstantaneous[amountofreactivitybywhich l or yould
/B'/
V the assumin@ill react r is suberitica/od dim: MigEh fluste /e suberiticAl from its present ssemblies (sh_7t2-4nd h".=fD condition are fully inserted except for the single GEE:EM5FERaiusMRof highest reactivity l worth which is assumed to be fully withdrawn. (M O @-{rmc.tr i sg BRAIDWOOD UNITS 1 & 2 1-5 AKFtDMENT NO. 35
l O CTS INSERT (S)
-SECTION 1.0 l
l \ l Definitions 1.1 ! i INSERT 1-5A (An ) )
)
PRESSURE AND The PTLR is the unit specific document that provides . TEMPERATURE LIMITS the reactor vessel pressure and temperature limits l REPORT (PTLR) including heatup and cooldown rates, and the ; pressurizer Power Operated Relief Valve (PORV) lift i settings for the current reactor vessel fluence : 3eriod. These pressure and temperature limits shall
)e determined for each fluence period in accordance ,
with Specification 5.6.6. Plant operation within i these limits is addressed in individual ' Specifications. 4 i INSERT 1 5B (L2 ) O The response time may be measured by means of any series of sequential. overlapping. or total steps so that the entire response time is measurer' INSERT 1 5C (M ) 3
- b. In MODES 1 and 2. the fuel and moderator temperatures are changed to the hot zero power temperature.
i
)
I ! O Revision A
~ __ _._ _ _ _ , _ _ _ _ _ _ _ . . . ._ _ .-_ _.__._.___ . . . . . _ _ . _ _ . _ . _ _ _ _ _ _
l Defini4 dens 1.1 d Sp*t $ c.J.on '3,3.4 { DEFINITIONS bddress*J ie Seckon 1.0 i PROCESS CONTROL PROGRAM g , poc3 .for See m ato ;
,- - u 1.23 The PROCESS CONTROL PROGRAM (PCP) shall contain the current fomulas, !
sampling, analyses, tests, and determinations to be made to ensure that ! processing and packaging of solid radioactive wastes based on demonstrated ! processing of actual or simulated wet solid wastes will be accomplished in l such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. PURGE - PURGING - l 1.24 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. QUADRANT POWER TILT RATIO 1.25 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore l 47 detector calibrated output to the average of the upper excore detector cali-l brated outputs, or the ratio of the maximum lower excore detector calibrated (satQ output to tre averaoe of the lower excore detector calibrated out>uts, whichever V s areater. With one excore detector inoperable, the remaining tiree detectors l Q $$ g t w be used for computing the average. l RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total core heat transfer rate to the reactor coolant of 3411 MWt.
.' REACTOR TRIP SYSTEM RESPONSE TIME 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 l until loss of stationary gripper coil voltage. l REPORTABLE EVENT l , 1 1.28 A REPORTABLE EVENT shall' be any of those conditions specified in ! l Section 50.73 of 10 CFR Part 50. l ; SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition l assuming all full-length rod cluster assemblies (shutdown and control) are ' fully inserted except for the single rod cluster assembly of highest reactivity ( worth which is assumed to be fully withdrawn. , Qwv -- Address ej ; o, Seef an 1, o l j,. N( S D O Cs for Sed, or 1.c / BRAIDWorsD UNITS 1 & 2 P', AMENDMENT NO. 35
l D e b .' M ,s 1.1 J
@ DEFINITIONS l O
'SITEBQDNDARYl 1.30 he SITE 80 ARY shall that line be nd which the and is neith bd.norleasedfnorotherw a controlled the licens .
SLAVE RELAY TEST G:.E A SLAVE R TE T shall
- each slave rel h & "--ir :NPERABILITY of each relay. TheSLAVERELAYTESTshaband
,a continuity checkf as a minimumD o associated testable actuation devices.
include 3SLIDIFICAI C U A t500RC/ CHECK ( 7 1.3 A SOURC CHECK sh 1 be the q itative a essment a channel re nse r the cha 1 senso is exposed a source f increas radioactiv .; STAGGERED TEST BASIS l
@ A STAGGERED TEST BASIS shall consist of [ T.h" l a. A test schedule for systems subsystems, trains, pr other desi isted]
j components obtained b divillingt specifiedteftintervali n equal ' intervals, l Q
- b. The sting of one ystem, subsy tem, train, r other designated coup nent at the ginning of ch subinte 1. -
l THERMAL POWER pumn l Q GEEP coolant. THERMAL POWER shall be the total & core heat transfer rate to the reactor Intert FL2 TRIP ACTUATING DEVICE OPE ' L TEST EEEP A TRIP ACTUAT EVICE OPERATIONAL TEST shall consist af aaaratina the w rio u .,4/R l Q /*e c l: = = = r2ripJttuating)6 ce and DEVICE he TRIP ACTUATING verifying OPERABILITY OPERATIONAL TEST shall Ginclude el- l adjustment,asnecessary,oftheJtip,Attuatinggevicesuchthatitactuates at the required getpoint within the required accuracy. UNIDENTIFIEF LEAKAGE QEigCPgeo l ewahr m3e4 l- h. Dem t'EB GmRIM3DitEAKAGE mman @GustaanMich is not JDENTIFIEf LEAKAGE g' L _- f0NRESTRICTEdARE( , 1.38 An NRESTRICTED REA shall be a area at or be nd the SITE B0pNDARY ! b access which is no controlled by he licensee fo purposes of pr ection osure to radi tion and radio tive materials or any iQ l of indi iduals from thin the SIT BOUNDARY used or residential uartersorforindustrial) (area c cial, instit ional, and/or ecreational pu oses. / BRAIDWOOD UNITS 1 & 2 1-6 AMENDMENT NO. 35
4 (]) CTS INSERT (S) SECTION 1.0 3 Definitions 1.1 INSERT 1 6A (Ap ) the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so t 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 La) ; 1
... . . including all components in the channel, such as alarms, interlocks.
displays, and trip functions required to perform the specified safety 4 { 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
(,gj is tested. l lb) Revision A ,
DeM.b:ns 1.1 4 i'
@0EFINITIONS l
4 N EXHAUST TREATMENT SYSTEM ( 1.39 A VENTILATION EATMENT SYSTEM shall be any system and installed to reduce gaseous ra e or radioactive n particulate form in effluents by passing ventilatio n st gases through charcoal 1 Ag adsorbers and/or HEPA filters for t c. ving iodines or partic-l l ulates from the gaseous exh eam prior to the r to the environment.
- Such a system is no ered to have any effect on noble
- Engineered effluents. .
estures Atmospheric Cleanup Systems are not co red to ILATION EXHAUST TREATMENT SYSTEM components. l i VENTING i i l 1 VENTING hall be any con olled process of ischarging air o gas from a i h co.40 nfinement maintain tempe ture, pressure, other opera ing condition, i such a manner t idity, concentr tion or replacement air or gas is not provided o required during ENTING. Vent, u d in system n , does not j imply a V NTING process. ' ! M HOLDUP SYSTEM A 1.41 A WASTE GAS H0 hall be an esigned and installed to j recuce racioactive gaseous efflue ., cting Reactor Coolant System off-
- gases from the Reactor ystem and prov delay or holdup for i the purpose ng the total radioactivity prior to to the en .
1 l 1 j O 3 1 BRAIDWOOD UNITS 1 & 2 1-7
1
- 1 l D36nho, a.
O '
\
TABLE 1.1 FREQUENCY NOTATION N i \ l NOTATION FREQUENCY l f S '\ At least once per 12 urs. ! i \ { l f D W
\
At least once per 4 hours. At least onc er 7 days. M At east ce per 31 days. Q At 1 once per 92 days. SA least o er 184 days. R At least once p 18 months. { S/U. Prior to each react startup. N.A. Not applicable. P templeted prior to each rel se. O As l l l lO l 8RAIDWOOD UNITS 1 & 2 1-8 . l
Def,.i. L'ons I. I 1.1- 1 TABLE A 9"EnATI^:.A0 MODES
^ anew CONDITION, K % RATED M AVERAGEE00LAN A'
- MODE TLE) eff THERMAL POWER / TEMPERATURE
- 1. POWER OPERATION > 0.99 > 5[ (z
- 2. .=;"U NA 'f c--MOnNA.,6 STARTUP ) 0.99
, < 5[
- 3. HOT STANDBY < 0.99 R NA ] >3507
- 4. HOT SHUTD0 < 0.99 /
R NA 350[> T A. [ > 200 % **9
- 5. COLD SHUTD0 < 0.99 $. NA < 200 7 j
- 6. REFUELI k (Ch @ NA h 1k N A
@ blA h 4
A- /d 7Eyeluding decay heet. '" (e.)Wsl ;c. tr.; r;;;tcr n a; ; L: n = :-vessel head closure bolts less than fully r , tens,1oned.or
;tt, tre n::: __ _ b@ Q h(bi&pe/reache ressel nr.<J closure i
bol4 s h llv den sion*{ 6
~%_
Od E -(see T.nse< f I-9 A) Se<b I.1 - L.3 J I C v - ,d.,3 Se, &- I. 3 - Crpleb E Sec k. l.4 - f~ reg.,c-< y l BRAIDWOOD UNITS 1 & 2 1-9
1
' ,T o r.e r + 1-9A y Logical Connectors
- 1. 2 '
og e. Iof 21 j Q' 1.0 USE AND APPLICATION
\
1.2 Logical Connectors 4 1 PURPOSE The, purpose of this section is to explain the meaning of logical connectors. Logical connectors are used in Technical Specifications (TS) ' to discriminate between, and yet connect. discrete Conditions. Re Surveillances, quired Actions. Completion and Frequencies. Times.connectors The only logical ' that appear in TS are MQ and QR. The physical arrangement of these connectors constitutes logical conventions with specific meanings. ; BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or 3 nesting) of the logical connectors and~ by the number i assigned to each Required Action. The first level of logic ' is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector ; 4 in the first level of nesting (i.e., left justified with the O number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical
- connectors. ;
l When logical connectors are used to state a Condition. !i 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. 1 O < continued) BRAIDWOOD - UNITS 1 & 2 1.2-1 Revision A . l 1
r 3 DW Logical Connectors I-44 1.2 Pga. 1.2 Logical Connectors @ ## #I J EXAMPLES EXAMPLE 1.2-1 LOGICAL CONNECTORS (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME ! A. LCO not met. A.1 Veri fy . . . 1 AND A.2 Restore . . . 1 In this example the logical connector A_N_Q is used to indicate that when in Condition A. both Required Actions A.1 and A.2 must be completed. ' O l l l 1 l I O ccontinued) BRAIDWOOD - UNITS 1 & 2 1.2-2 Revision A .
%wr Logical Connect ,
O 1.2 togicel Connectors adm> EXAMPLES EXAMPLE 1.2-2 MULTIPLE LOGICAL CONNECTORS (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LC0 not met. A.1 Trip . . . A.2.1 Veri fy . . . M A.2.2.1 Reduce . . . A.2.2.2 Perform . . . O 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 3erformed as indicated by the use of the logical connector @ and the left justified may be chosen.Ifplacement. Anythen A.2 is chosen, one both of these A.2.1three Actions and A.2.2 must be performed as indicated by the logical connector M . 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.
O BRAIDWOOD - UNITS 1 & 2 1.2-3 Revision A .
Q 3 Completion Ti m . 1-4 wgg 9 O 1.0 USE AND APPLICATION 1.3 Completion Times
- PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. ;
l BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The i ACTIONS associated with an LC0 state Conditions that typically describe the ways in which the requirements of the ; LC0 can fail to be met. Specified with each stated ! Condition are Required Action (s) and Completion Time (s). l 4 DESCRIPTION The Completion Time is the amount of time allowed for l
- 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 l n unit is in a MODE or specified condition stated in the () Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and l the Required Actions apply until the Condition no longer exists or the unit is not within the LC0 Applicability. l I 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 l the situation that required entry into the Condition. l l 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 no.t. result in separate entry into the Condition, unless specifically stated. The Recuired Actions of the Condition l continue to apply to each adcitional failure, with ; Completion Times based on initial entry into the Condition. l I i A U. (continued) BRAIDWOOD - UNITS 1 & 2 1.3-1 Revision A .
(MN 3 ' i Completion Times ! l-44 1. 3 ' fa.pe. - l 1.3 Completion Times [#Ul J ! DESCRIPTION However, when a subseauent train, subsystem, component, or ! (continued) variable expressed-in the Condition is discovered to be l inoperable or not within limits, the Completion Time (s) may l be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:
- a. Must exist concurrent with the .fitsi 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 c\
t U The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely se)arate re-entry into the Condition (for each train, su) system, component, or variable expressed in the 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)1y 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 i one use of this type of Completion Time. The 10 day 4 Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended. O (continued) BRAIDWOOD - UNITS 1 & 2 1.3-2 Revision A .
-~ - .-.-. . - . . - . - . - - . _ . - _ - . -. . - _ - .- -
Completion Times 1.3 Completion Times (continued) d ## M J l EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions. EXAMPLE 1.3-1 COMPLETION TIMES
. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours Action and associated M Completion Time not B.2 Be in MODE 5. 36 hours met.
O Condition B has two Required Actions. has its own separate Completion Time. Each Required Action 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 M in MODE 5 within 36 hours. A total of 6 hours is allowed for reaching N0DE 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 allowod for reaching MODE 5 is the next 33 hours because the tots! 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. O (continued) BRAIDWOOD - UNITS 1 & 2 1.3-3 Revision A .
- . - r
TtiCEAT
;_qg Completion Times ,
PS e. h ' .O 1.3 Completion Times 'T of RI J EXAMPLES EXAMPLE 1.3-2 DEFAULTED CONDITIONS / LCO 3.0.3 ENTRY / (continued) COMPL ETION TIMES ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pum) A.1 Restore pump to 7 days inopera]le. OPERABLE status. B. Required B.1 Be in MODE 3. 6 hours l Action and associated A@ l Completion , Time not B.2 Be in MODE 5. 36 hours met. , O When a pump is declared inoperable. Condition' A is entered. ) If the ! 7 days. Condition pump is not B isrestored to OPERABLE also entered status Time and the Completion within clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B 1s entered. Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated. j When a second pump is declared inoperable while the first pump is still inoperable. Condition A is not re-entered for the second pump. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop i after LCO 3.0.3 is entered, but continues to be tracked from i the time Condition A was initially entered. While in LCO 3.0.3. if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired. LC0 3.0.3 may be exited and operation continued in accordance with Condition A. O < continued, BRAIDWOOD - UNITS 1 & 2 1.3-4 Revision A ,
. - - ~ -
'1Nswr Completion Ti N
f_g , l
?qe '
1.3 Completion Times > EXAMPLES EXAMPLE 1.3-2 (continued) While in LC0 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Com)letion Time for , Condition A has expired. LCO 3.0.3 may 3e exited and l o eration continued in accordance with Condition B. The C letion Time for Condition B is tracked from the time the i Con ition A Completion Time expired. ) On restoring one of the pumps to OPERABLE status, the 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 )i 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
> 7 days. ;
t. O l l l l l l (continued) BRAIDWOOD - UNITS 1 & 2 1.3-5 Revision A
. f
- r , ,
" Completion Times
' ~* 1. 3 ' r 1.3 Completion Times d ## N J l EXAMPLES EXAMPLE 1.3-3 MULTIPLE FUNCTION COMPLETION TIMES , (continued) i ACTIONS , CONDITION REQUIRED ACTION COMPLETION TIME i. l A. One A.1 Restore 7 days i Function X Function X train ' train to OPERABLE E . inoperable. . status. l 10 days frorn discovery of -l failure to meet 1 the LC0 B. One B.1 Restore 72 hours Function Y Function Y train train to OPERABLE E inoperable. status. O- 10 deys from 1 discovery of failure to meet the LC0 C. One C.1 Restore 72 hours Function X Function X train train to OPERABLE inoperable. status. E @ l One C.2 Restore 72 hours Function Y Function Y train train to OPERABLE ! inoperable. status. l l
)
l (continued) BRAIDWOOD - UNITS 1 & 2 1 3-6 Revision A .
i r*
- Wm
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Completion Times 1-4 & 1. 3 ' l fkyt i 1.3 Completion Times f "f % l l EXAMPLES EXAMPLE 1.3-3 (continued) , .j s When one Function X train and one Function Y train are i inoperable. Condition A and Condition B are concurrently I applicable. The Com)letion Times for Condition A and Condition B are tracted separately for each train starting i 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 l situation described in Condition C was discovered). If Required Action C.2 is completed within the specified Completion Time Conditions B and C are exited. If the l Completion Time for Required Action A.1 has not expired. I operation may continue in accordance with Condition A. The ; remaining Completion Time in Condition A is measured from l . the time the affected train was declared inoperable (i.e.. l
; initial entry into Condition A).
l The Completion Times of Conditions A and'B are modified by a f3 logical connector with a separate 10 day Completion Time i V measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time. it would be-)ossible to alternate between Conditions A, B. ; and C in suc1 a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase "from , discovery of failure to meet the LC0" is designed to 3revent ; 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. O (continued) BRAIDWOOD - UNITS 1 & 2 1.3-7 Revision A . l l
L j 1 l < M*# Completion Times
- j. Id4 1.3 '
1.3 Completion Times.
- Ab EXAMPLES EXAMPLE 1.3-4 MULTIPLE FUNCTION COMPLETION TIMES
-(continued)'
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve (s) 4 hours valves to OPERABLE j inoperable. status. ) I o j 1 B. Required B.1 Be in MODE 3. 6 hours Action and l associated AND , Completion l Time not B.2 Be in MODE 4. 17 hours ! met. 1 O A single Completion Time is used for any number of valves i ino)erable at the same time. The Completion Time associated I wit 1 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. Once one of the valves has been restored to OPERABLE status. the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Com)1etion Time may be extended if the valve restored to OPEMBLE 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. If the Completion Time of 4 hours (plus the extension) expires while one or more valves are still inoperable. Condition B is entered. lO (continued) BRAIDWOOD - UNITS 1 & 2 1.3-8 Revision A . j r _ . . _ . - . _ - ,_ . , _ , . _ _ _ _ -
t F 3 NT Completion Times
!-fk 1.3' )
fept 1.3 Completion Times (I53 CE2I; l EXAMPLES EXAMPLE 1.3-5 SEPARATE ENTRY CONDITION 3 (continued) i ACTIONS ! NOTE i Separate Condition entry is allowed for each inoperable valve. 6 CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours i' valves OPERABLE status. inoperable. I B. Required B.1 Be in MODE 3. 6 hours Action and n associated AE U Completion Time not B.2 Be in MODE 4. 12 hours met. ; i I 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. 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. O ccontinued) l 4 BRAIDWOOD - UNITS 1 & 2 1.3-9 Revision A , ) 1 1
Completion Ti , l k 1.3 Completion Times 8A% EXAMPLES EXAMPLE 1.3-5 (continued) If the Completion Time asso61ated 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. 1 Since the Note in this example allows multiple Condition i entry and tracking of separate Completion Times. Completion Time extensions do not apply. ! EXAMPLE 1.3-5 MULTIPLE ACTLONS WITHIN A CONDITION / ! COMPLETION T.'ME EXTENSIONS l ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME l A. One channel A.1 Perform Once per inoperable. SR 3.x.x.x. 8 hours A.2 Reduce THERMAL 8 hours POWER to s 50% RTP. l l 1 B. Required 8.1 Be in MODE 3. 6 hours Action and associated . Completion Time not met. i O (continued) BRAIDWOOD - UNITS 1 & 2 1.3-10 Revision A .
- =. . -- . . - - - - - -
l .~C N + E A T Completion Ti l /-fA Pa Sa-1.3 Completion Times d MJ l EXAMPLES EXAMPLE 1.3-6 (continued) i
- l. Entry into Condition A offers a choice between Required l Action A.1 or A.2. Required Action A.1 has a "once per" '
l Completion Time, which qualifies for the 25% extension, per : SR 3.0.2 to each performance after the initial performance. ! l The initial 8 hour interval of Required Action A.1 begins when Condition A is entered and the initial performance of l 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 Com of 8 hours is not met. Condition B is entered.pletion Time 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.
-t r
O I i i 1 l l O (continued) BRAIDWOOD - UNITS 1 & 2 1.3-11 Revision A , I
l~AfV c.T ! j., g Completion Time . i
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Peug 4. 1.3 Completion Times 8 2'J EXAMPLES EXAMPLE 1.3-7 MULTIPLE ACT ONS WITHIN A CONDITION / - (continued) COMPLETION T ME EXTENSIONS 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour Subsystem subsystem - inoperable. 1solated. AND i Once per l 8 hours thereafter . AND 1 A.2 Restore subsystem 72 hours ; to OPERABLE status. O ! B. Required B.1 Be in MODE 3. 6 hours Action and associated MQ Completion i Time not B.2 Be in MODE 5. 36 hours i 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 per 8 hours thereafter" interval begins upon j performance of Required Action A.1. l i i i i O < continued) BRAIDWOOD - UNITS 1 & 2 1.3-12 Revision A
r 3 M6EW Completion Times 1-fA 1. 3 ' l k& 1.3 Completion Times dM b EXAMPLES EXAMPLE 1.3-7 f (continued) ! If after Condition A is entered. Required Action A.1 is not l met within either the initial I 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 i Completion Time clock for Condition A does not stop after ; Condition B is entered, but continues from the time l Condition A was initially entered. If Required Action A.1 i is met after Condition B is entered. Condition B is exited l and operation may continue in accordance with Condition A. provided the Completion Time for Required Action A.2 has not i expired. ! I 1 IMMEDIATE When "Immediately" is used as a Completion Time, the ! COMPLETION TIME Required Action should be pursued without delay and in a J controlled manner. j O l 1 i l 0 BRAIDWOOD - UNITS 1 & 2 1.3-13 Revision A v.- , - , ,r - ,
.m.
1 i g 3 Frequency 7MEST 1. 4 ' ,3 I-4 A V 1.0 USE AND APPLICATION Po.94. 1.4 Frequency b PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements. 3 l 1 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 application of the specified Frequency is necessary for compliance with the SR. 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. I Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not (j_ 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. 4 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. O (continuee) BRAIDWOOD - UNITS 1 & 2 1.4-1 Revision A .
+
l- M Frequency' 1.4 P( 0 1.4 Frequency as,ke EXAMPLES EXAMPLE 1.4-1 SINGLE FREQUENCY (continued) SURVEILLANCE RE0UIREMENTS , SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours Exam)le 1.4-1 contains the type of SR most often encountered in t1e Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent 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 Q 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 interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the <CO, and the performance of the Surveillance is not otherwise i.odified (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 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 MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4. O (continued) 1 BRAIDWOOD - UNITS 1 & 2 1.4-2 Revision A i 1 J
l J ' g*
- 3 Frequency 1-94 1. 4 '
Pip 1.4 Frequency (N# ; l EXAMPLES EXAMPLE 1.4-2 MULTIPLE FRE0UENCIES l (continued) ) SURVEILLANCE REQUIREMENTS ' l l SURVEILLANCE FREQUENCY i Verify flow is within limits. Once within ; 12 hours after :
= 25% RTP E l 24 hours thereafter ,
Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "M" indicates O that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to a 25% RTP, the Surveillance must be performed within 12 hours. : The use of "once" indicates a single performance will ! satisfy the specified Frequency (assuming no other Frequencies are connected by " M "). This type of Frequency does not qualify for the extension allowed by SR 3.0.2.
~
"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 example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.
O (continuee) BRAIDWOOD - UNITS 1 & 2 1.4-3 Revision A
_,_..-._.q I ! "# i Frequency' !
- /- @
O W 1.4 i 1.4 Frequency Wbb EXAMPLES EXAMPLE 1.4-3 FRE00ENCY BASED ON SPECIFIED CONDITION ! i .( continued) 1 l SURVEILLANCE REQUIREMENTS '
- SURVEILLANCE FREQUENCY i
NOTE
- Not required to be performed until i 12 hours after = 25% RTP.
- Perform channel adjustment. 7 days I i
4 The interval continues whether or not the unit operation is ; !. < 25% RTP between performances. ! As the Note' modifies the required oerformance of the . [ Q- 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 '
power reaches = 25% RTP to perform the Surveillance. The j ' Surveillance is still considered to be wrformed within the ,
"specified Frequency." Therefore, if tie Surveillance was ;
t not performed within the 7 day (plus the extension allowed -i i 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 i L LCO. Also, no violation of SR 3.0.4 occurs when changing i i MODES. even with the 7 day Frequency not met, provided l i operation does not exceed 12 hours with power = 25% RTP. ' 1 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.
1 j. 4-d O: (continued) BRAIDWOOD - UNITS 1 & 2 1.4-4 Revision A y --y m g s- w -
-r,- y
h N+6A C l 4 A. Freque , fa.) A i 1.4 Frequency 8*$ l EXAMPLES EXAMPLE 1.4-4 FREQUENCY BASED ON SPECIFIED CONDITION (continued) ' ! SURVEILLANCE REQUIREMENTS i SURVEILLANCE FREQUENCY 1 NOTE-Only required to be performed in MODE 1. l Perform complete cycle of the valve. 7 days t The interval continues, whether or not the unit operation is i in MODE 1. 2. or 3 (the assumed Applicability of the associated LCO) between performances. As the Note modifies the required oerformance of the : Surveillance, the note is construed to be part of the ! O " spec fied Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1. this Note allows t entry into and o>eration in MODES 2 and 3 to perform the ' Surveillance. T1e Surveillance is still considered to be l l performed within the "specified Frequency" if completed l prior to MODE 1. Therefore, if the Surveillance was not l performed within the 7 day (plus the extension allowed by l SR 3.0.2) interval, but operation was not in MODE 1. it : l 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. , l provided operction does not result in entry into MODE 1. Once the unit reaches MODE 1. the requirement for the i Surveillance to be performed within its specified Frequency l 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 l Surveillance within the specified Frequency, and tie i provisions of SR 3.0.3 would apply (as well as having had a violation of SR 3.0.4). O i BRAIDWOOD - UNITS 1 & 2 1.4-5 Revision A .
l S L 2. 0 Istd i 2.0 SAFETY L IMITS y"0 L ;M;';#0 ' MET" ;" Tr" SC' ;"3 ! o A =m
~
O ' i REACTOR CORE Q- omeO [R,,. 4 C '.
- 5 4- ,
facs)) {(DJ The y combination.[of THERMAL POWER, pressurizer pressure! i Q g: r:;i=az. loop sur%awb,tempe u ure ture(A shall not exceed the GTMH:%mo n eer = ;ee, eee, e1..e g, y,g,, 1 C""L!cra!L:$ MODES I and TJ ___ O.2 s L Wo\c h e nO- A, (AL T I um.g If CL
-% 2.2.1 re co mitetin vio\rded nce_ es,nc A.
SL -
#"2.4 ^
f9henevfr the poir)t defined y the c 1 nation the hig st operat g loop j average temperat6re and T RMAL POW has exc ded the propriate ressurizer i 5resfure line, be in HOT __ STANDBY within I hour, sad - $ rith th6 r-~'t ----t; ef S;;3I;;e:n; :.O.- REACTORCOOLANTSYSTEMPRESSURE@ 4,Tne Reactor Coolant System pressure shall not exceed 2735 psig. g-LIC AMILI'hMODES 1, 2, 3, 4, and 5] g (z. 2 2. If SL 2.1. 2 i viedoted hh O'2 "oots i ae 22 _ .; :" r n: ::: rr r u.auni ry '-- - rr :
@ '-- -----d-d 273u;j.g3 be in HOT STANDBY with the Reactor Coolant System pressure within this limit within I hour, - a c-" en ::: r= - - " e irettfic:ur;r ;,e_ a 5L 2.2.2.2.
MODES 3,4and5) l M er.erer--inr ". :ris; - ant 7 r --. ;= : rr -mawre--d-d 'm a;% reduce the Reactor Coolant System pressure to within this limit within 1 5 minutes, gz ----' run 12- --- ----"'"-----------o l sLAi@ l i 'Applicab}4 to Unit I and Unit 2 unt completion cycle 5. (Applicable to Unit 1/nd Unit 2 st tina with cv e 6. O Unit 3 - Amendment No. 56 _ _ _ _ AptdDWOOD_- UNITS 1 & 2 2-) Unit 2 - Amendment No. 55
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a 1 i. 1 i FIGURE 2.1-1 1 I i REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION j 3 Applicable to Unit I and Unit 2 until completion of cycle 5 4 4 l 5 Unit 1 - Amendment No. 56 BRAIDWOOD - UNITS 1 & 2- 2-2 _ _ gig 2 Amendment ,No. 55
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- i. HEITM/\L PbWER(fEfMNT a .1.1 - 1 A Figure,,.m. , ,a, U Reactor Core r. n-Safety 1.imitt T;r !.;;M
{. wyw.yw ,. wy m., , u. ... . m.... . .. . m. . .. s. .... . . , ... . . .,.. . .a........, . , . . . . , _.... _ _, _.._. , _ ~J (A C BRAIDWOOD - UNITS 1 & 2 Unit 1 - Amendment No. 56 2-2a Unit 2 - Amendm%t No 55
i SL lo { trO 3.3 t l O . SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2 LIMITING SAFETY SYSTEM SETTINGS, REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 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. i ACTION:
- a. With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more i l
conservative than the value shown in the Allowable Value column of ' Table 2.2-1, adjust the Setpoint consistent with the Trip 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 O applicable ACTION statement requirement of Specification 3.3.1 until U the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip 5etpoint value.
I kMrewJ ia Secb .13.t . See D o c E r 5 .r 4 3.'$.,1 l O 2-3 Amendment No. 42 BRAIDWOOD - UNITS 1 & 2
1.C.O 3.3. i Sece,i 2.o 3.3. I Reach Tr.p 5 te, .In & s m.,. g Su t ; Y LIMI: s == ;.mi:1= sat t i v sis tn su;;p
- /~}
i m -*MII: = sa L " m Tre qTil d M4 LAT I
/ fat R 90R_ TRIP SYSTEM INSTRLMENTATION SDFOINTS 2.2.1 The Reac rip System Instrumentation and Interlock Set s shall l
be set consistent wit e Trip Setpoint values shown in e 2.2-1. l APPLICABILITY: As shown for each cha 1 in Tabl . -1. I ACTION:
- a. With a React Aorip System Instrumentation or Inter Setipoint less conser AvWe than the value shown in the Trip Setpoint'cbign but more c neefvative than the value shown in the Allowable Value column f able 2.2-1, adjust the Setpoint consistent with the Trip Setpoin value.
Cood A Af. With the Reactor Trip System Instrumentation d in r;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 O. coasisteat wita the Tr4a setnoiat i e. . 1 As l l i l l l l O t l l BRAIDWOOD - UNITS 1 & 2 2-3 Amendment No. 42
~
O O. o
~ '
,l TABLE 2.2-1 c t REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS o i TRIP SETPOINT ALLOWABLE VALUE FUNCTIONAL UNIT - Manual Reactor Trip N.A. N.A. Q u, 1.
- 2. Power Range, Meutron Flux
** a. High Setpoint 1109% of RTP* 1111.36% of RTP* *
,m
- b. Low setpoint ,
125% of RTP* 127.36% of RTP* i Power Range, Neutron Flux, <5% of RTP* with <6.3% of RTP* with
- 3. i time constant i time constant l High Positive Rate 12 seconds 12 seconds Power Range, Neutron Flux, <5% of RTP* with <6.3% of RTP* with l
- 4. i time constant i time constant High Negative Rate i 12 seconds 12 seconds 131.5% of RTP*-
- 5. Intermediate Range, 125% of RTP*
Neutron Flux Source Range, Neutron Flux
. 1105 cps 11.42 x 105 cps
- 6. :
Overtemperature AT See Note 1 See Note 2 7. See Note 3 See Note 4 ;
- 8. Overpower AT 11885 psig 11869 psig
- 9. Pressurizer Pressure-Low Pressurizer Pressure-High 12385 psig 12393 psig
- 10. .3 a
ge
!* 11. Pressurizer Water Level-High 192% of instrument span
$93.5% of instrument span b"w !
I Wo f O " RIP = RATED THERMAL POWER w i L , Adams.o;- s.,v; 3 3 Ste 00c (~ Sec&, 5.3) l
.O O O a, 3.3.l-l g TABLE 2.2 1
$ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 8 - i TRIP SETPOINT ALLOWABLE VALUE hFUNCTIONALUNIT Manual Reactor Trip
- 1. .A. N.A.
M. v H 2. Power Range, Neutron Flux ;
** a. High Setpoint i 9% of RTP*
1111.36% of RTP*
- b. Low Setpoint , 12 of RTP* 127.36% of RTP*
hJl Power Range, Neutron Flux, <5% f RTP* w th <6.3% of RTP* with High Positive Rate i ti const t i time constant ,
)2 se onds
, 12 seconds 3.b M Power Range, Neutron Flux, <5% of TP with <6.3% of RTP* with '
u High Negative Rate i time o tant i time constant i i 12 seco 12 seconds.
'l .fr. Intermediate Range, 125% of P* 131.5% of R1r*
Neutron Flux ( h. Source Range, Neutron Flux 1105 s 11.42 x los eps 6I Overtemperature AT See te 1 See Note 2 7 &t Overpower AT See ote 3 See Note 4 EaK Pressurizer Pressure-Low 11 85 psig 11869 psig *
. Pressurizer Pressure-High 385 psig 12393 psig TR. Pressurizer Water Level-High _92% of instrumen <93.5% Inf-4aetamat] @a R '
" span $
z QA
" RIP = RATED THERMAL POWER ,
i nou r. . r .ontinueos - I
- n O y ReaCroa Tair svSitN ins's g taTiON TRir stir 0rNrs U I FUNCTIONAL UNIT ilt '.
TRIP SETPOINT ALLONA8tE VALUE
- 12. Reactor Coolant Flow-low 190% of loop mini- 289.3% of loop alpi-mum measured flow num measured flow
- 13. Steam Generator Water Level Low-Low
- a. Unit i 133.0% of narrow 131.0% of narrow -
range Instrument range instrument span span
- b. Unit 2 217% (Cycle 3); 116.3% (Cycle 3);
236.31 (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 -
Cociant Pumps 14920 volts - each bus each bus
- 15. Underfrequency - Reactor 157.0 Hz Coolant Pumps 156.08 Hz
- 16. Turbine Trip
- a. Emergency Trip "eader 21000 psig 1815 psig Pressure
- b. Turbine Throttle salve 21% open AIX open Closure
- 17. Safety Injection Input N.A. N.A.
from ESF >
- 18. Reactor Coolant Pdep N.A.
Breaker. Position Trip N.A. Elo OF w H
- Minimum measured flow - 97,600 gps" (92,850 gpm)' & 'O
**Appilcable to Unit I and Unit 2 untti completion of cycle 5. -
( #Appifcable to Unit I and Unit 2 starting with cycle 6. ~~ UNIT I - AMENOMENT NO. 56 BRAIDWOOD - UNITS 1 & 2 2-5 AJdrmed i" UNIT 2 - AMENDMENT NO. 55 S'd,* a 3 3=I 3 - Doc 4 An,"3.3.
enutt E b ' Q ILEACTOR TRIP SYSTEM INhinUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT y .. hRIPSETPOINT ALLOWABLE VALUE
/O M f Reactor Coolant Flow-low 2 0% of loop mini;- 109.3% for h;;; =lpli measured flow Imum-se:s;; red flow-14 13. Steam Generator Water Level Low-Low
- a. Unit 1 233. of narr 231.0%,fef :r;e.
rang Instrume t trege M t .
.;.t];
span ' 4 san _
- b. Unit 2 '
217% ( ycle 3 i 236.3% (Cyc1 4 li:;
'239.8%
= (Cicle l'C"-le'^%r,
'O .
and aft r) o Sfte-i m - 77;.;! r narrow ng frang- 3 --~-- ~ -- t instrume t pan tapan I:2 44'. Undervoltage - Reactor Coolant Pumps 25268 vol - 14920 volts - each bus each bus G 45' Underfrequency - Reactor Coolant Pumps 157.0 Hz 156.08 Hz
/ f s Turbine Trip !
- a. Emergency Trip Header Pressure 11000 psig 1815 psig
- b. Turbine Throttle Valve Closure 21% pen 11% open
/6 F. Safety injection Input N. .
from ESF N.A. il 4s. Reactor Coolant Pdep fFs co
.A. N.A.
Breaker. Position Trip T
'w
/ *Mi-t .~., :::sured flew Y97,6
\*,Wpplicabl TfAppile pm' o Unit g and Un 6 2 unt
"-"JMy ?}
comple_tlgof cyrX5. / e to UrtK 1 and# nit 2 s rting witYcycle V h ' f l, 2-5 UNIT 1 - AMENDMENT NO. 56 BRAIDWOOD - UNITS 1.& 2 UNIT 2 - AMENOMENT NO. 55 '
O O O TABLE 2.2-1 (Continued) ( REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS [ 8 TRIP SETPOINT ALLOWABLE VALUE FUNCTIONAL UNIT E Reactor Trip System y 19. m Interlocks 4 s -
>l x 10 10 amp ->6 x 10 81 amp '
- e a. Intermediate Range -
m Neutron Flux, P-6
- b. Low Power Reactor Trips Block, P-7
$10% of RTP* >7.9% to $12.1% of RTP*
- 1) P-10 input
<10% RTP* Turbine <12.1% RTP* Turbine
- 2) P-13 input Impulse Pressure Impulse Pressure t
Equivalent Equivalent ry <30% of RTP* <32.1% of RTP*
- Power Range Neutron -
c. Flux, P-8 >7.9% to <12.1% of RTP* ' Power Range Neutron -<10% of RTP* - - d. Flux, P-10 <12.1% RTP* Turbine
<10% RTP* Turbine
- e. Turbine Impulse Chamber Impulse Pressure Impulse Pressure Pressure, P-13 Equivalent Equivalent M.A. N.A.
- 20. Reactor Trip Breakers N.A. N.A.
Automatic Trip and Interlock g 21. logic g N.A. N.A.
- 22. Reactor Tr.'p Bypass Breakers Ed i'i % -
5($RTP=RATEDTHERMALPOWER
-j 9 -
0 AJarena L. sun., 3.3. ;] s - = m s s s. ,. ,
~- i o
O O O 3.3.t-l m TABLE 4-e-1 (Continued) g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 8
' (TRIPSETPOINT j ALLOWABLE VALUE FUNCTIONAL UNIT E Reactor Trip System y M m erlocks 9 >6 x e= a. Inte te Range
-> x 10 10 amp -
amp N Neutron Flu , -6
- b. Low Power Reactor rips Block, P-7 of RTP* >7.9% to <12.1% of RTP*
- 1) P-10 input -
<10% TP* rbine <12.1% RTP* Turbine
- 2) P-13 input Impuls! P ssure Impulse Pressure Equiva"en Equivalent y e P* <37. 1% of RTP*
- Power Range Neutron -<3
- c. - -
Flux, P-8
-<1G% of TP* >7.9% to <12.1% of RTP*
- d. Power Range Neut -
Flux, P-10 { (10% TP* Turbine <12.1% RT ine
- e. T e Impulse Chamber Impulse Pressure ressure, P-13 Impu e Pr(ssure Equi. alent \ Equivalent N. -
N.A. 9 Reactor Trip Breakers N A. N.A. g "l f. Automatic Trip and Interlock u r-m Logic fE Reactor Trip Bypass Breakers .A. N.A. O {f9 wW 5 *RTP = RATED THERMAL POWER , _.______..________.__._.____._____________.___1 ______.m___.___.__m--_ _ _ _ _ _ _ _ _ ____m .
l O taste 2 2- Ciaveo) O - TABLE N01ATIONS fff0TE1: OVERTEMPERATURE AT 3 l 1+t 3S) 1 1 A T-(,l+t2 S) ( 1+T s 3 S) s oA 1T [K 2 -r ((1+t,S) [T( 1+t S) -T'] 1 + t3 S) 3 +K (P-P I 1 ) -f ( AI)) Where: AT - Measured AT by RTO Instrumentation. l 1+t i s . 1+t s
- Lead-lag compensator on measured AT, r i , r, - Time constants utt11 zed in lead-lag compensator for AT, r, - 8 s, r2 = 3 s, 1
1+t 3 s - Lag compensator ori measured AT,
'e r3 - Time constants utilized in the lag compensator for AT, 3r - O s*, s2s,** l AT, - Indicated AT at RATED THERMAL POWER, K, - 1.164,* 1.325**
K, - 0.0265/*F,* 0.0297/*F** 1+t 4 s 1+t s S The function generated by the lead-lag compensator for T . dynamic compensation, t., i s
- Time constants utilized in the lead-lag compensator for T , r, - 33 s, I is = 4 s, -
Average temperature. *F, T - , t g (rA
- Applicable to Unit I and Unit 2 until completion of cycle 5. D (ApplicabletoUnitIandUnit2startingwithcycle6. j py ,
kh,l ' see yx Sc suu s.s BRA: 4000 - UNITS 1 & 2 2-7 AMENDMENT No. 66
TABLE g Q itinued) Q. TABLE NOTATIONS NOTE 1: OVERTEMPERATURE AT 9 1+t 2S) 1 1 A T ((1+t S) ( 1+t S)o sa T2 [K 2 3 i 1+t-K3S) ((1+t'S) [T( 1+t,S) 3 -T'] +r 1 (P-PI) -f ( AI)] t Where: AT - Measured AT by RTD Instrumentation. l 9 ,
, f'ITgS-yS
---- M' Tag compeMa6 measured AT, ;t r,, r, -
Time constants utt11 red in lead-lag compensator for AT, r, - 8 s, ; r: = 3 s, , l Nw __.-1 1+t S_ Lag-compel H Fe m__-meast Q' r3 - Time constants utt11 red in the lag compensator for AT,3r - sis, l j h AT, - Indicated AT at RATED THERMAL POWER, K, 1.32 Ay l K .- [0.02 Si T C 0.0297/*F ! I 1+t sg ___dynamir._rompensaHen,
- Tb_e functlenh._ generated. _by_the lead-lag _compensaterf ;
( r,r3 - Time constants utilized in the lead-lag compensator for T , f4 = 33 s, r3-4s, - T - Average temperature, "F, i i a O
~
( 3;;i s. eie te exit i =e e=n-a-st.rtina-with-cycie-se-- [, 9 i
.~ .
r BRAIDWOOD - UNITS 1 a 2 2-7 AMENOMENT NO. 66
~
i
.. . -- _ _ . . - . - . - _ . . . . . . - . - - . ~ ~ . - .. . - .- - - .- - . . -. . . .- O O O TABLE 2.2-1 (Continued) U d M M ' A J,3,1 Sea WC Gr h+1k 5,3 - 2 TABLE NOTATIONS (Continued) [ NOTE 1: (Continued) 3 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, - P'
- 2235 psig (Nominal RCS operating pressure),
S - Laplace transfom operator, s", ' and fdal) is a function of the indicated difference between top and bottom detectors of the , power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that: (t) for q - q,, netween -32%', -24% and +13%*, +10%** f (al) - 0, where q and 3 RATED, THERMAL POWER in the top and bottom halves of the core respect [vely,g are percentand q total THERMAL POWER in percent of RATED THERMAL POWER; (11) for each percent that the magnjtude of automatically reduced by 1.74% , 4.11%,,q, o f its value at RATED THERMAL POWER.- g exceeds 13 for each percent that the magnitude of (111) automatically reduced by 1.67% , 3.35%,,q, o f its value at RATED THERMAL POWER.- g exceeds -32%' {E
*P NOTE 2: Thechannel's,,maximumTripsetpointshallnotexceeditscomputedTripSetpointbymorethan 'y b 3.71% , 1.33% of AT span. -
- Applicable to Unit I and Unit 2 until completion of cycle 5.
( ,Appitcable to Unit I and Unit 2 starting with cycle 6. y , BRAIDWOOD - UNITS 1 & 2 2-8 , AMENOMENT NO. 66 .l
_-. . - .- - .. - .- - -.-. - -.._... ._. .. - . .- u O - JO. O. : 3.3. l-l .i
,. TABLE M-4 (Continued) . j
^
- TA8LE NOTATIONS (Continued) ,
NOTE 1: (Continued)
- 1 8I j
- r. - Time constant utt11 red in the measured T , lag compensator, t. = 4 s ts, r
T' s 588.4*F (P inal T , at RATED THERMAL POWER), ! K3 - @.G;i34 .00181 P = Pr'essurizer pressure, psig, t P' - 2235 psig (Nominal RCS operating pressure), ! S = Laplace transform operator,-sd , and f;(AI) is a function of the indicated difference between top and bottom detectors of the ' :. 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 - g between -24 and +1 f AI). - O, where q, and RATED, THERMAL POWER in the top and bottom halves of,(the core respectively,g are percentand total THERMAL POWER in percent of RATED THERMAL POWER t (11) for each percent that the maar - g exceeds +105 the AT Trip Setpoint shall be automatically reduced by G-MC. ttude 4.1 of q,o f its value at RAT ERMAL POWCR. Tm (111) for each percent that the maan ude o - g exceeds the AT trly setpoint shall be : automat 11y reduced by(h4ft-2 .3 ,of 1ts value at RATED THERMAL POWER. I NOTE 2- Th annel' aximum Trip Setpoint s all not exceed its computed Trip Setpoint by more than
, 1.33 of AT span.
l n j i
;pp)$ cob 2 IG 'vC!I I AN; m m := te : i-= # v.u 2 a.ru r w tr. <,a e :.
ve eb6 Uw b Ub b UMU 5 .N, . p p -. o I BRAIDWOOD - UNITS 1 & 2 2-8 , AMEfWMENT NO. 66
.i
O o' O - TABLE 2.2-1 (Continued) ~N to i b TABLE NOTATIONS (Continued) b o MOTE 3: OVERPOWER AT l (1 + t S) i i ( t:5 ) ( 1 } - i 1 [T 1 + teS
-) - T"] - f (AI))
AT (1 + t:5) Il + T3 5) $ AT,[K '- Ks 1 + t,5 1 + tes , l9 e-Where: AT = As defined in Note 1, 1 + 1:S = As defined in Note 1, 1+tS tg, ta = As defined in Note 1, I = As defined in Note 1, T I+153 e is
= As defined in Note 1,
= As defined in Note 1, AT, K.
= 1.072,
= 0.02/*F for increasing average temperature and 0 for decreasing average Ks temperature, ,
t,S The function generated by the rate-lag compensator for T8 dynamic
=
compensation, [ 1 + tys t,
= Time constants utilized in the rate-lag compensater for T ,,,, t, = 10 s.
I = As defined in Note 1, 1+ 5 t,
= As defined in Note 1 MJren*J i s Seeb 3.3.1 See Doc & S.
5.3,
O o O . l - 3.3.1~ \ TA8LE 64=1 (Continued] g -
.TA8LE NOTATIONS (Continued)
NOTE : DVERPOWER AT ; ( t,S ) g y (1 + t:5) AT (1 + t:5) Il + ts5) $ AT, M. '- K S 3 1 + t,5 1 + te5 - 4 [TIf5 l te
~
~ I8IAIII e-
" Where: AT = As deffned in Note 1, i
1-+ T35 ,
= As defined in Note 1, 1 + t:5 1,13 3
= 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
= 0.02/'F for increasing average temperature and 0 for decreasing average i Ks temperature, ,
t,$ The ' unction generated by the rate-lag coupensator for T,,, dynamic
=
1 + t,5 compensation, t, = Time constants utilized in the rate-lag compensator for T,,,, t, = 10 s.
= As defined in Note 1, hE 1 + tes in [ 1 to = As defined in Note 1, h O ,
i
O O~ . . O TABLE 2.2-1 (Continued) TABLE NOTATIONS (Continued) D NOTE 3: (Continued) , 0.00170/*F*,- 0.00245/*F** for T > T" and K - 0 for T $ T", Kg - T - As defined in Note 1, T" - Indicated T a instrumentaITon,ts RATED 588.4*F),THERMAL POWER (Calibration temperature for AT i S - As defined in Note 1, and f,(al) - O for all AI. NOTE 4: The channel's , maximum Trip Setpoint shall not exceed its computed h 1p Setpoint by more thanj . 2.31% , 3.65% of AT span. g l s Yh aW hl 55, b lhk n3 ) h* rm h $V
))
SN Y
,,' App 1tcable to Unit I and Unit 2 until completion of cycle 5.
( Applicable to Unit I and Unit 2 starting with cycle 6.
*h-BRAIDWOOD - UNITS 1 & 2 2 AMENOMENT NO. 66
. _ _ . _ _ . - _ ___m. . _ _ .-..,m __.um_.m.__._____..-___.____m.-_____--.___m-____ _ _ __--m__ov _____r,--___w,*- __--,-r-e-e-w~ -e-ew-. ---
- O O . . O. ;
I
- 3. 3.1- l -
TABLE 4,4-4 (Continued) , , IABLE' NOTATIONS (Continued) . NOTE : (Continued) K. - @,.eGi7;/"T 0.00245/*(for T > T* and K. - O for T $ T*, A, ; T - As defined Not 4 1 ; T" - Indicated T a h S - instrumentaITon,ts RATED As defined in Note 1, and 588.4*F),THERMAL POWER (Calibration temperature for AT . i e , f,(AI) = 0 for all A1. ' ' MOTE A: g Av Th c annci' haximum Trip Setpoint shall not ext.ced St. computed Trip Setpoint by more than , _, 3.65 of AT span. g ! I b l s __ g a m - hh (EU b th v b a bbw w b u m (...,- = ON y A wa
;#p::c.u a t; ca:t : aae catt : st.rtlag witt cyde-s-- t : >
- ?* i' O
BRAIDWOOD - UNITS I & 2 2-10 AMEMOMENT NO. 66 -
. . - - - . = . . . . . . - - . . . - _ - - - .- . . . . . .- - - - _ .
j CTS INSERT (S) !
.O SECTION 2.0
, BASES a
- 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. j E
a
)
.I 1
4
- i I i 1 I 1
O i 1 I 1 4 1 l j l O Revision A .
LCO APplicabd*+/ 3.O i j ('/' L:"T:"CCC+5:TIONSf^"0"bP^TIO".%:: SURVEfttANGE- RE0'.'!"5""9} . , , M ;[APPLICABILITYl-LIMITING CONDITION FOR OPERATION (LCo h l ('EaPud, w/ImuT) I
, o .g A)
- ;o 3.0. Incompliance with the Limiting Conditions for Operation contained in the)--
A (succeeding specifications is required durira the OPERATIONAL MODES or other / l (conditions specified therein; cr ::t th;t Xpon failure to meet the Limiting
- (Conditions for Doeration, the_maanciated t resce n a., n.*
ACTION r:cai m r.ts shall be met,
% 3' T 7 M):nn d t ;;; .;ft' e --- meeti-- m u_entet.rat:: os a . uo .r o 5
...s 1
tte n y r;;t: :<
'the Lir! ; C ndit h: *r- ^ etiaa e-d :::ee4eeed AGHON-cequirements-eae A2 -*==*''W t.b e : M 05 S';n:h.
l If the Limiting Condition for l " *"" * / kompletion of the ACTION reauirements is not required %=8m *~= **'OOperatio 1
- j. EN u3.o_is ,
4 i fLs0 3.0.1 When a Limiting Condition for Operation is not met, except as provided ! in the associated ACTION requirements, within 1 hour action shall be initiated 3 i to place the unit in a MODE in which the specification does not appi placing it, as applicable, in: rhpm @ a. i i At least HOT STAND 8Y within the next 6 hours, 2 Dhar i
- b. AtleastHOTSHUTDOWNwithinthefollowing6 hours,an@
c. L 3.0 lC. ) j At least COLD SHUTOOWN within the ubseauent 24 hours.] t , Where correctiva measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the.specified time limits l i Q as measured from the time of failure to meet the Limiting Condition for Operation.
. Exceptions to these requirements are stated in the individual. specifications. )
(ThisspecificationisnotapplicableinMODE5or6. CLSQ 3.0.4) Entry into an OPERATIONAL MODE or other specified condition shall no [ utmca @ i fbe made when the conditions for the Limiting Conditions f Operation are not Qs Ay met and the associated ACTION requires a shutdown if the are not met within . specified time interval. Entry into an OPERATIONAL MOD or specified conditio ! may be made in accordance with ACTION requirements when conformance to then
- permits continued operation of the facility for an unlimited period of time.
This provision shall not prevent passage through or to 0PERATIONAL MODES as i required to comply with ACTION requirements. Exceptions to these requirements
- are stated in the individual specifications.
i M Limiting Conditions for Operation including the associated ACTION ragutrf-mentsbg ly to each unit individually unless othentise indicated"affollows}.
- a. Whenever the is Qing Conditions for Operation refers to systems or
/
components which ar) red by both uni , ACTION requirements i will apply to both units ta y. l t.A i b. WhenevertheLimitingCfo ons ration applies to only one ! unit, this will b tified in the AP)M ILITY section of the [ specificat , nd I I c. W er certain portions of a specification contain eting param-eters, Setpoints, etc. , which are different for each unit, thu 2 , ! 6 ia ati'i a ia_a " ata 'aat"*' ' ** 6 ar '" " a"ir Nw"ill' ' O @THD W ] %es +(170 % s- M BRAIDWOOD - UNITS 1 & 2 3/4 0-1 AMENDMENT NO. 3B 1 ; i
-Q CTS INSERT (S) SECTION 3.0 j LC0 3.0 j INSERT 3.0 1A (A3 ) ; LCOs shall be met during the MODES or other specified conditions in the , Applicability, except as provided in LC0 3.0.2 and LCO 3.0.7. l l I 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 LCO 3.0.5 and ! LC0 3.0.6. ! If the LC0 is met or is no longer applicable prior to expiration of the specified Completion Time (s), completion of the Required Action (s) is not required unless otherwise stated. o ! i O Revision A
~
- ('d' - CTS INSERT (S)
SECTION 3.0 , LCO 3.0
. INSERT 3.0 1C (A3 and L ) 3 (Aa)
When an LC0 is not met and the associated ACTIONS are not met, an associated I ACTION is rtot provided, or if directed by the associated ACTIONS the unit shall be placed in a MODE or other specified condition in which the LC0 is not i applicable. Action shall be initiated within I hour to place the unit, as applicable, in: (L3 )
- a. MODE 3 within 7 hours:
d 4 b. MODE 4 within 13 hours; and
)
- c. MODE 5 within 37 hours.
1 Exceptions to this Specification are stated in the individual Specifications. (Aa) O 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
,~
l ~ l ~ O I Revision A I
)
i 1 Q- CTS INSERT (S) SECTION 3.0 1 l l LCO 3.0 ; INSERT 3.0 1D (4) ! When an LC0 is not met, entry into a MODE or other specified condition in the ! Applicability shall not be made except when the associated ACTIONS to be i 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. Exceptions to this Specification are stated in the individual Specifications. s These exceptions allow entry into MODES or other specified conditions in the l Applicability when the associated ACTIONS to be entered allow unit operation i in the MODE or other specified condition in the Applicability only for a I limited period of time. l, l jySERT3.01E (L2) 1 O Equiment removed from service or declared inoperable to comply with ACTIONS may )e 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. l l l O l Revision A l
O cts INSERT (s) sECTION 3.0 LCO 3.0 I I 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 assor;tated with this supported ! system are not required to be entered. Only the support system LC0 ACTIONS 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 accordance with Specification 5.5.15. " Safety Function Determination Program (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. When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the a)plicable Conditions and Required Actions shall be entered in accordance witi LCO 3.0.2. l O IwSERT 3.0 18 (A.) Exception LCOs allow specified Technical Specification (TS) requirements to be changed to permit performance of'special tests and operations. Unless otherwise specified. all other TS requirements remain unchanged. Compliance with Exception LCOs is o)tional. When an Exception LC0 is desired to be met but is not met, the ACTIONS'of the Exception LC0 shall be met. When an Exception LC0 is not desired to be met, entry into a MODE or other specified l condition in the Applicability shall be made in accordance with the other ' applicable Specifications. l
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I ! 1 Revision A i I
i l 5 R App 1/cJ,.14 3.o - i b ym od toad M I {APPLICA81 LIT) O i j SURVEILLANCE REQUIREMENTS (510 SR M M ) Surveillance Requirements shall be met during the OPERATIONAL MODESl I 7 (or other conditions specified for individual Limiting Conditions for ,hed 1 (Operation unless otherwiss stated in an indivisin=1 fueveillance3.o-2 Raouire A
@8MJEach surve111ance nequirement shall be performed within the specifie l me interval with a maximum allowable extension not to exceed 25% of the r oecified surveillance interval /
4 ,u m o,,,3,, % , g , % ,, ,, g L1R Jg.0.33 Failure to perfom a Surveillance Requirement within the allowed sur. r h l ance interval, defined by Specification 4.0.2, shall constitute noncompli F9Ww ! nee with the OPERABILITY reautrements for a Limiting Condition for Dooration. sa er j The time limits of the ACTION requirements are applicable at the time 't is h zo 1 identified that a Surveillance Requirement has not been performed. The ACTIO j i requirements may be delayed for up to 24 hours to permit the completion of th
' surveillance when the allowable outage time limits of the ACTION requirements W
i re less than 24 hours / Surveillance nequirements ao not nave to be performed) g on inoperable equipment.J (g.,,a % ge u,,,3, w ,g 3, g , ,,g g i i 6RV.0.1Yntry into an OPERATIONAL MODE or other specified condition shall not uscar hade unless the Survalliance Requirement (s) associated with a Limiting Conditio #* for Operation has been performed within the stated surveillance interval or as j O otherwise specified. This provision shall not prevent passage through or to PERATIONAL MDDES as reouired to comply with ACTION requirements. 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME ! ICode Class 1, 2, and 3 components shall be applicable as follows: ! i i 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 l shall be performed in accordance with Section XI of the ASME Boiler , ; and Pressure Vessel Code and applicable Addenda as required by. l t 10 CFR Part 50, Section 50.55a(g), except where specific written 4 i relief has been granted by the Commission pursuant to 10 CFR Part 50, l \ Section 50.55a(g)(6)(1); i \ j b. Surveillance intervals specified in Section XI of the ASME Boiler and i Pressure Vessel Code and applicable Addenda for the inservice inspec-I tion and testing activities shall be applicable as follows in these ! Technical Specifications:
- kddrenec!b M4 g, See Occ4 sec% 3,o, lO
'f ,- BRAIDWOOD - UNITS 1 & 2 3/4 0-2 AMENDMENT NO. 38 . 1 I
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Q' CTS INSERT (S) SECTION 3.0 : SR 3.0 l INSERT 3.0 2A (A7 ) SRs shall be met during the MODES or other s)ecified conditions in the I Applicability for individual LCOs. unless otlerwise stated in the SR. Failure i to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, l shall be failure to meet the LCO. Failure to perform a Surveillance within ! the specified Frequency shall be failure to meet the LC0 except as provided in ' l SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. ; ( I!GERT 3.0 2B (As M , and L3) 3 (A,) The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from O the previous performance or as measured from the time a specified condition of the Frequency is met. l (M3 ) For Fre ; apply. quencies specified as "once." the above interval extension does not : (L3 ) If a Com)1etion Time requires periodic performance on a "once per . . ." basis, t1e above Frequency extension applies to each performance after the initial performance. (A,) Exceptions to this Specification are stated in the individual Specifications. n ! b Revision A ,
l O CTS INSERT (S) SECTION 3.0 ; SR 3.0 INSERT 3.0 2C (M2 and L ) (L4 ) i If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of : l the specified Frequency, whichever is less. This delay period is permitted to l l allow performance of the Surveillance. I (M2 ) If the Surveillance is not performed within the delay period, the LCO must l immediately be declared not met, and the applicable Condition (s) must be entered. l When the Surveillance is performed within the delay period and the I Surveillance is not met, the LCO must imediately be declared not met, and the -l applicable Condition (s) must be entered. l 1 l m
- U l
l 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 l specified Frequency. This provision shall not prevent entry into MODES or l other specified conditions in the Applicability that are required to comply with ACTIONS. l l 4 O Revision A
. .- - - . _ ~ . - . - . . = . - - - _ - . - - . _ . - . - . - . - - _- .
- SR Anh,Jbli43 3.o q
! .5 p u . 4.X, 5.5. y APPLICABILITY . O e AeldrewcA '.- Sub 3.0 i SURVEILLANCE REQUIREMENTS h Doc b SaF. 30 j
.. ~ _ _-
l
- 4. 0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES
! or other conditions specified for individual Limiting Conditions for j Operation unless otherwise stated in an individual Surveillance Requirement.
- 4. 0. 2 Each Surveillance Requirement shall be performed within the specified i
time interval with a maximum allowable extension not to exceed 25% of the
- specified surveillance interval.
) 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. 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 j requirements may be delayed for up to 24 hours to permit the completion of the j surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. i 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition } for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to I OPERATIONAL MODES as required to comply with ACTION requirements. l 5.5 8 dEE5p Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows: ] i 4
- a. its~ inspection of ASME Code Class 1, 2, and 3 compon M inservice of ASME Code Class 1, 2, and and valves f shall be performe ance wit n XI of the ASME Boiler
- and Pressure Vessel Code Addenda as required by-
} h 10 CFR Part 50 reli 0.55a(g),excep een granted by the Commission pursuant cific written A Part 50 l . ection 50.55a(a)(6)(i): N, i : . 5.5.9.o Jr. Surveillance intervals specified in Section XI of the ASME Boiler and i ' Pressure Vessel Code and applicable Addenda for the inservice inspec-tion and testing activities shall be applicable as follows in these Technical Specifications: i ) i i O i I BRAIDWOOD - UNITS 1 & 2 3/4 0-2 AMENDMENT NO. 38 .
5AAwbad.g5.o - Pro $m.s ..d bd5 5 hPPLICABILITY SURVEILLANCE REQUIREMENT (Continued) l ' ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICA8LE ADDENDA - - PERFORMING INSERVICE TERMIN0 LOGY FOR INSERVICE INSPECTION AND TESTING i INSPECTION AND TEST!hG ACTIVITIES ACTIVITIES l 7 Weekly At least once per 7 days Mdrused ,) Monthly At least once per 31 days Se.cnn 5.5 Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days See 00C 6 ;- I Every 9 months At least once per 276 days (Sube 5.0 / Yearly or annually At least once per 366 days
- c. The provisions of Specification 4.0.2 are applicable to the above I
{ required frequencies for performing inservice inspection and testing activities;
- d. Performance of the above inservice inspection and testing activities
,t 11 he ir, cddi tic.. L. cu.s. 74aci f!ad *... 6 .4..ce ;,yu ;. . ..n . .ieu
- e. Nothing in the ASME Boiler and Pressure Ve'ssel Code shall be construe to supersede the requirements of any Technical Snecificatian f4.0.6 Surv 111ance Requi nts shall apply / each unit indivi IIyunlelss otherwise ndicated as s ated in $pecificati 3.0.5 for indivi ual soecificad Lg, tions or enever cert n portions of a sp ification contain urveillance parame rs of fferent j r each unit, which ill be identified in parentheses. )
(oct es or body of he recuirement.
,;.. /
ll l l i I l lO ( BRAIDWOOD - UNITS 1 & 2 3/4 0-3
SR Appluebild.g 3 O Sper St. % 5 5.E g APPLICABILITY V ' g SURVEILLANCE REQUIREMENTS (Continued) ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA - PERFORMING. INSERVICE i ' TERMINOLOGY FOR INSERVICE INSPECTION AND TESTING INSPECTION AND TESTING ACTIVITIES ACTIVITIES Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or *very 3 months At least once per 92 days Semiannually or -very 6 months At least once per 184 days
- Every 9 mor.ths At least once per 276 days Yearly or annually At least once per 366 days
' Bi e nn ally er ever, 2 veers M teca+ one per 73 I cla .4 s 3
.5. E. E . h #1 The provisions of specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing ;
activities;
- . I;rfe x n;; ;f th; :t;;; 'n;;.rvi;; in;;;;ti;n nd t;; ting ;;ti.-ities a ' - '* '
. ... : L. :.. ;ddi t!;n L., ;': c ;ee;! f .
L. .e !!!o..m L, ; . _,.. a . dj S.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 SurveillanceRequirementsshallapplytoeachunitindividuallyunlessf otherwise indicated as stated in Specification 3.0.5 for individual specifica-
)
l tions or whenever certain portions of a specification contain surveillance l parameters different for each unit, which will be identified in parentheses, j footnotes or body of the requirement. / A ec
- g oot 4. Se q.- y 65.9. c. : The p iio.it of SP_ J.0.3 are applcalle E Jurv;ct g,
~ m em .a i
f 4 O ! BRAIDWOOD - UNITS 1 & 2 3/4 0-3
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d
i i I l 1
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l ! l l t l- , (1 v CTS INSERT (S) ! SECTION 3.0 i L ! t BASES ! i l' ; The Bases of the current Technical Specifications have been replaced in their i entirety by Bases reflecting the format and applicable content of NUREG-1431 i Bases and proposed Byron and Braidwood Technical Specifications. l l i . I l I l i
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l I i
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i O i i. i i i i i J l O ! Revision A f l
. _ = _ _ _ _ - - _ __ ,. , __ _ . . _ , _ - . _ _ . - _ _ . , , _
.Be b. b s 1. l Lco 3.1l .
Lc o 3.1.2. . 3/4.1 REACTIVITY CONTROL SYSTEMS gg)A 3/4.1.1 BORATION CONTROL L co 3. l. E
>200*F L c o 3 .1.f.
SHUTDOWN MARGIN - TS Adrew.J 2Se.e4.a.a.1 LIMITING CONDITION FOR OPERATION ^ 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k
- for four loop operation, j
APPLICABILITY: MODES 1, 2", 3, and 4. ACTION: i' With the SHUTDOWN MARGIN less than 1.3% Ak/k, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppe boron or equivalent until the required SHUTOOWN MARGIN j is restored. SURVEILLANCE REQUIREMENTS l f ' 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be creater.-than or equal to 1.3% ak/k: ~ O a. Within 1 hour after detection of an inoperable control rod (s) and at
)
I least once per 12 hours thereafter while the rod (s) is inoperable. gg f If the inoperable control rod (s) is immovable or untrippable, the above
.. / requiredSHUTDOWNMARGINshallbeverifiedacceptablewithanincreased}i allowance for the withdrawn worth of the immovable or untrippable cq, g control rod (s);
b. When in MODE 1 or MODE 2 with K,ff greater than or equal to 1 at i least once per 12 hours by verifying that control bank insertion is l within the limits of Specification 3.1.3.6;
- c. When in MODE 2 with K df less than 1, within 4 hours prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6;
- d. Prior to initial operction above'S% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4
4.1.1.1.le. below, with the control banks at the maximum insertion limit of Specification 3.1.3.6; and "See Special Test Exceptions Specification 3.10.1. I O Et s ""'
- u. 60; & s s .,.33.
BRAIDWOOD - UNITS 1 & 2 3/4 1-1
.. _ __ _. ~ ~ ~ .. _ _ . _ _ _ _ . _ .._. _ .._. . ._ -_ . . _ . _ _ . _ _ _ . _ _ . _ . . _ _ . - . _ _ _ _ .._ _ .
^
LCo 3.1.1
. LCO 3.1.1 i
LCO 3.1.4
- i. "g LCo 3.15 l v 3.1 9 REACTIVITY CONTROL SYSTEMS LCD 3.I G Sputf:calon f.i I,
3.l.I SHUTDOWN MARGIN ( T ;=;: _] (SOM) av_w I j .LIMITINT; CONDITION FOR OPERATION wihn 4he' lindt. spect6ed so Ille COLR- . i LCOC;c 3.1.8 The SHUTDOWN MARGIN shall be r="-- a-- a- -~ - ' M L " " N ?
;_c :::; :;;r = ::a APPLICABILITY: MODES
/Mede 2 weh kesr A t.o R /fA l + 3, and 4. O ACTION: .
LA j
~ wibn lentit - a. amino +es - U coNO A With the SHUTDOWN MARGIN '-- "=a ' " " % -d 9-'_ initiate and continue boration.l(t-greater /than or e al to 30. gps /bf-a sc:utiof containin greater / '
than or Aqual to 7f00 ppm be n or equivalfnt until the/ required 5 TDOWN MA) GIN
- is respred.( ,
- SURVEILLANCE REQUIREMENTS a
SR 3.1.l.l .
; w;4%N 1:, t45 smified eih Col.R.
O . ; .1.1. 0 The SHUTDOWN MARf4IN shall be determined to be ; ;=c 2:n n ud i le 1. % ai/ .; - oc 1 h e rw o a . l f,ab,g ,n sWbn i.. If the inoperable control rod (s) is immovable or untrippable, the above '. i (see coc kr M' ens.t.' required SHUTDOWN MARGIN shall be verified acceptable with an-increased allowance for the withdrawn worth of the immovable or untrippable q control rod (s); ; !. 5 8 3 .l. (,. 2 _ .b.. Whe in MOD or MOD 2 with ff great than or qual to at j - - - - - ast onc per 12 urs by v ifying at contr bank i ertion i l , within e limit of Speci cation .3.6; i - S R 3 .l. G .I Whe in MODE with K f less th 1, wit 'n 4 hour prior to ! e,
~
I q (,3 i,h4eving eactor c ticality y verify' g that predic d cri'i [ control d posit n is wit n the li ts of 5 cificatio 3.1.3.6-2 Ce.m/.u mate t A i d e
- Pri o r to% ' - ' ' ---- " -- -"- - "~ " ~ "'" ' "~ "" l a f te r e ach fuel loadina.[:y n :n s = :: :: =: n:n ; ;? ;;;;;":::t 2n i M *I'A'I -- R.1.1.1.12. M S. /.;tti 0% n:tr:1 t_nu :: th: =;i r 'n;:rtical j G .. ; t .,f sw. ;; k.:-: c. 2.1. 2. 5. uS LAj
(
"'.a s
( Luci : T.;t L u.,0 en; R u:'t:::::n 2.!".L2 i . O' i n - I BRAIDWOOD - UNITS 1 & 2 3/4 1-1 1 1 l } 4 i
. . . . . . . . . . . ._ . _ _ _ _ . _ . . . _ _ = _ . . - - . - . . .-- 4
.. LCO 2J.I lI f
'l L ( 0 3 .1 2.
Lf'O 3 .l. 4 REACTIVITY CONTROL SYSTEMS L C C 2 .l. 5 L co 3.14 j SURVEILLANCE REQUIREMENTS (Continued) ( Mwk 2 weti. k,o ' n 0 and in ! SR 3.l.1.1 + When in MODE 3 or 4. at least once per 24 hours by consi ration of l t 'following factor . l h- 1) Reactor Coo nt System boron neentration,
\
- 2) Control ro,d position, ,
' i
- 3) React r Coolant System verage temperatu ,
- 4) F 1 burnup based o gross thermal en rgy/ generation,
- 5) Xenon concentrat n, and LI8 Samariumconcfntration.
$p,3, g , A, p AleTEl : _T.N4 ca:r 5. t -21 ) ,fmeA+ure4)
;h3122 (4.1.1.1.2 Jihe (;.;r;MItore reactivity (behned shall be compared to predicted values to demonstrate feceeemene within t 1% Ak/k at least once per 31
[*fective Full Power Days (EFPD)./This g#mparisA shalj1 tonsider at/least
$<?f acto,# stan6d in jrn et fi,sHan af 1 !M e ..I I The ;rc::ictc reactivity core valuesprior conditions q-J be adjusted (normalized) to correspond to the actual
'to exc ding a fuel burnup of 60 EFPD after each fuel Q '
Ioading, g (lNSECT 3.1 - 2.A ) _ I 1 i e O i BRAIDWOOD - UNITS 1 & 2 3/4 1-2
i i- CTS INSERT (S) l- Q SECTION 3.1 LCO 3.1.2 INSERT 3.1-26 (Anand M,) 3.1 REACTIVITY CONTROL SYSTEMS ? . 3.1.2 Core Reactivity ! LCO' 3.1.2 The measured core reactivity shall be within 1% Ak/k of-predicted values. APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME O 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 acceptable for continued operation. 6NQ 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. ( O l Revision A
I
? 'Q CTS INSERT (S)
SECTION 3.1 l' LCO 3.1.2 INSERT 3.1 *dQ (La) , SURVEILLANCE FREQUENCY ; SR 3.1.2.2 NOTES
- 1. Only required to be performed after 60 Effective Full Power Days (EFPD).
- 2. ...
l ~ i l O ! i
)
l I O Revision A i
h l ] SpE.CaMn i.I
- Lco 3.1.1 Q IAEACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,,, < 200*F A di re .,a a k d . 5.i.
See Doe Le s'r a% sg . l LIMITING CONDITION FOR OPERATION 4 3.1.1.2 The SHUTDOWN Mr.RGIN shall be greater than or equal to 1.N Ak/k. l 1 i APPLICABILITY: MODE d. ACTION:
- a. With the SHUTDOWN MARGIN less then 1.N Ak/k declare both Boron Dilution Protection System subsystans inoperable and apply Specifi-cation 3.1.2.7.b.
b.. With the SHUTDOWN MARGIN less than N Ak/k, immediately initiate and I continue boration at greater than or equal to 30 gpa of a solution l containing greater than or equal to 7000 ppe, boron or equivalent I until the SHUTDOWN MARGIN is restored to greater than or equal to N Ak/k. i SURVEILLANCE REQUIREMENTS O ! 4.1.1.2 The SHUTDOWN MARGIN shall be detemined to be greater than or equal to N Ak/k:
- a. Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (s) is inonerable.
,' i If the inoperable control rod (s) is immovable or untrippable, the guno ,a SHUTDOWN MARGIN shall be verified acceptable with an increased Maaw u allowance for the withdrawn worth of the immovable or untrippable ;
control rod (s): and l
- b. At least once per 24 hours by consideration of the following factors: l
- 1) Reactor Coolant System boron concentration, l
- 2) Control rod position,
- 3) Reactor Coolant System average temperature,
- 4) Fuel burnup based on gross thermal energy generation,
- 5) Xenon concentration, and
- 6) Samarium concentration.
g L AJdrev b Te,L 3.1.
- s. 4 s .+ s. ]
~
BRAIDWOOD - UNITS 1 & 2 3/4 1-3 Amendment No. 40
u co 2 . l . I ! L t.o 5. I A \ spu.. f.r.4. .., I,l 03iatacTiv2Tvco" Tao'sv5TE"5 3.1.tSHUTDOWNMARGIN{T,,gi b (gogj s LIMITING CONDITION FOR OPERATION wal..o +he lioh ree med ni fl.e. ColB. LCO 3.1.1@ The SHUTDOWN MARGIN shall be PTE the er ec=1 tr L n AVU l APPLICABILITY: MODE S. g, ACTION: ,
- a. Nith he SHUTD0 MARGIN ig(s' than 1.K Ak/k defare both B on Di tion Prote ion Systesi subsysted inopera, nte and appl occifi-ion 3.1.2 . b. I sief wiin..r. iin.d wA n is n.. nde
+. With the SHUTDOWN MARGIN ce:: the n IA'u (ix:ci:te!v) nitiate and gg continueboratinn.latgreatertanorequalto gpm of a solu on containing ater than or e al to 7000 ppm oron or equival nt until the S OWN MARGIN i restored to gr ter than or eq 1 to 1% Ak/k. l L.A p SURVEILLANCE REQUIREMENTS ~
U En 3.1.n win..n u.e hir.ie genned i'i de cm.M. !
' 4.1.10 The SHUTDOWN MARGIN shall be determined to5be' rT:ter th:r Or c;;12 l lto S tuiG o 2 er rod~
s ab If the inoperable control rod (s) is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased h=@=2((O',7l? allowance for the withdrawn worth of the . immovable or urd.rippable
" ~ - -
control rod (s); and _ m 3.1.1.1 -b. At least once per 24 hours by considerati of the followi factors: g 1 Reactor Coolan ystem boron con ntration,
- 2) Controlrod'hosition, f'
- 3) Reactor Coolant System average temperature,/ / f
- 4) Fuel burnup based on gross thermal energy generation, ,/
- 5) Xenon concentration', and !
i 6,)' Samarium concentration. 3/4 1-3 Amendment No. 40 BRAIDWOOD
- UNITS 1 & 2
LC4 31.3 s O 3.t REACTIVITY CONTROL SYSTEMS 3.i.3 MODERATOR TEMPER 6TURE COEFFICIENT LIMITING CONDITION FOR OPERATION l 1' 3.1, 3 (Core) @ L G ( L l 1 3T The moderator temperature coefficient (MTC) shal1Jhe within the limits specified in thew 0perating Limits Report f0LR). The maximum upper limit shall be less than or equal to that shown in FigureQ'T 3.1.3 -1 ( , ther MTc APPLICABILITY:G;esinning et .;fr ac:.nlimit - MODE $ 1 and' o ly . F" c' M*-tm limit - MODES 1, 2, and 3 . N Lemer MTC ACTION: uwer MTc. ' coNO A &. With the MTC more positive than the dE B limit 0e2:17:20 in the m D, l operation in MODES I and 2 may proceed provided: c m 7 g, g.e h Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than the BOL i coso e limit specified in the 0 R_yithin 24 hours or be inmel s ! "=I, l These thdrawal limits shall be in . h within addition thetonext 6 hours.'n limit the iFisit]o of Specificati'on 3.l.3.6; ! 0
+. /hecontrolrosaremaintain'dwithinthewithdrawallimits established a ove until a s sequent calculation verifies /that
(@ the MTC has een restored within its limit for the al)/ rods withdrawn c ndition: and /
- 3. A Special Report is prep 6 red and submi ed to the Commission pursuant to Specification 6.9.2 withi 10 days, describing the ;
value o the measured C, the inter'm control rod sithdrawal '
@ limits and the pred ted average c re burnup necessary for resto ing the positi)ve MTC to with n its limit for the all rods with rawn condition'. ]
h 4. (The erevisiens ei SDistion-Jff3trLuvi. app 3 inb COWL C 4. l With the MTC more negative than they limit specified in the LR, be in HOT SHUTDOWN within 12 hours. we 48 *With K,u greater than or egual to 1.]
% nee Seecist-T3st-Exceptisiis;5tiicifi~catjon-3m.J. )
O BRAIDWOOD - UNITS 1 & 2 3/4 1-4 Amendment No.65
L cc,3.t .3 O REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE0VIREMENTS I
~
l (4.1.1.3) The MTC shall be determined to be within its limits during each fuel cycle as follows: Wh kupr hmd l G6 3.t.3.1 +. The MTC shall belmeasured an compared to t BOL predicte MTC to AstE517sh adspnistrative ro withdrawal li ts, as necess y, to - LA assure that fhe BOL limit ecified. in th OLR, is met t oughout !
. core life,l prior to initiat operation aboveG vi "eT ED T;;E""X )
POWER, after each fuel loading, and s R 3.1.3:2-tr. The MTC shall be measured (;t =; .E""/.L "L':"Jand compared to the
. 300 aps surveillance limit specified in theG9LR (all rods withdrawn, cue ei >-cu:: m"r am_r erremer) within 7 EFPD a'ter reachina an equilibrium boron concentration of 300 ppm.l In the event this comparison indicates the MTC is more negative than the 300 ppm cm 2 )_ surveillance limi specified in tha@LR, the MTC shall be remeasured, at least once peand c spared 14 EFPD to the @'the remainder of the fuel cycle.MT during l Uwer !
.h d LCOlimN)) ,
l O OWTE 3 Insert 3.1-5A
. l
.O
,I BRAIDWD0D - UNITS 1 & 2 3/4 1-5 ,
Amendment No. 65 ~, -
i-i O'- CTS INSERT (S) SECTION 3.1 LCO 3.1.3 INSERT 3.1 5A (L3 ) 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-AR0 boron concentration of s 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.
O 4 O ~ Revision A
i LCD 3.I.3 F l J J 1 0 l l
- 1 10 l-
,9 -
Unacceptable Operation f . g8' . Y 7 .' f :
)6 y
- u :
5 L 2 e j : e : i {d [ Acceptable Operation 3- h . l s - , w : i 5 2 - , 1- - i e ,,... t .1 t i g # . . 1 O 10 20 30 40 50 90 70 80 90 100 A i . j Percent RTP 3- ,
- 3. i . 3 - 1 FIGURE O MODERATOR TEMPERTURE COEFFICIENT vs. POWER LEVEL BRAIDWOOD - UNITS 1 & 2 3/4 1-Sa AMENDMENT NO.65 O
O
-.. . .. -. .~ -.- . .. .-. , . . . . - , - - - - . - .-. . - _ ~ _ . . - . - . - - .
* $ f
%h 3, \ '
LCO 3,#,1 Aclciresseci in Sechon 31 ; Lq REACTIVITY CONTROL SYSTEMS s= cot for sechen 34 ] MINIMUM TEMPERATURE FOR CRITICALITY f l , LIMITING CONDITION FOR OPERATION i
]
. 1 b
3.1.1.4. shall beThe Reactor greater thanCoolant or equal System lowest operating loop temperature (T"'9) to 550*F. 4 APPLICABILITY: MODES I and 2#*. . l ACTION: With a Reactor Coolant System operating loop temperature (T,yg) less than 550*F, restore T,,, to within its limit within 15 minutes or be in NOT STANDBY within the next 15 minutes. SURVEILLANCE REQUIREMENTS 4.1.1.4 The Reactor Coolant.5ystem temperature".(T**9)'shall be determined to be greater than or equal to 550*F: I a. Within 15 minutes prior to achieving reactor criticality, and
- 1
- 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,,g-Tref Deviation Alann not reset.
l
#With K,77 greater than or equal to 1.
"See Special Test Exceptions Specification 3.10.3.
O~ s BRAIDWOOD - UNITS 1 & 2 3/4 1-6 9
1
. -~ M e i See u 3. \ ^
i 3.9 ggu.rog coesAni styrsA (es) - ' Q <.y,7 F.c.6 MINIMUM TEMPERATURE FOR CRITICALITY l l l LIMITING CONDITION F'OR OPERATION l LCO 3A. A NshallThebe Reactor Coolant System lowest operating loop temperature (T**9) greater than or equal to 5 1 *F . APPLICABILITY: MODES 1and2d . i ACTION: I CONP4 With a fleactor Coolant System operating loop temperature (T,yg) less than 550*F,O=::=r; ,
.= u;;n"- i;; ::i: ::n"
== ::n=:=: :n be in %
l }ET^"DS")withinthenext15 minutes. 4 Mapt 2, or.+t k'vGE < t.o] L.4 SURVEILLANCE REQUIREMENTS ) 6 A 3.4.11 (*-t-tc The Reactor be greater than or Coolant equal to:550*F: System temperature '.(T*"9) 'shall be determined to 3 O <=- - te - :t = : == == = :- = = := == r = = =2 ==== t= ==:t:==: t> . = ==4
- b. ' At least once oe/MO minut when e -rea ter is ritic and' the l fR ctor olant ystem T g is le s than 557*F w th th T,yg-Trefj eviat' n Ala not ce t.f ;
i f [lL h o u r.$ . g4
. l
.D r."pk c.F WN
#With K,ff greater than or equal to 1.
{}5mm Svu .I Tw.i Encvi.un. Svu ;' koiivu 3.1^. 0 g 5 O BRAIDWOOD - UNITS 1 & 2 3/4 1-6 9 0
. _ - . - . - -- - -- - - - . .. _ . - - . - ~ .
l a
~
Mah. 3,1 , l O l EACTIVITY CONTROL SYSTEMS 3 1. 2 BORATION SYSTEMS , FLOW TH - SHUTDOWN I LIMITING CONDITION FOR OPERATION I
- 3 3.1.2.1 j
- beOPERABLEandca(pableofbeingpoweredfromanOPERABLEemergencyp j source: j
. a. A flow path qom the Boric Acid Storage System via a bori acid transfer pump and a cent,rifugal charging pump to the Reactor Coo ent System if the Boric Acid Storage System is OPERABLE as given in pecification 3.1.2.5a. for MOD 5 and 6 or as given in Specific ion 3.1.2.6a.
for MODE 4; or
- b. The flow path from thegrefueling water storage ank via a centrifugal charging pump to the Reactor Coolant System i the refu,eling water .
storage tank is OPERABLE 'a.s given in Specif ation 3.1.2.5b. for !
- MODES 5 and 6 or as given in Soecificatio 3.1.2.6b. for MonF a O. APPuCABluTv: M= ES A , 5 ane e.
ACTION: l d With none of the abo e flow paths OPERABLE or capable of being powered from an OPERABLEemergencypowersource,suspeng'alloperationsinvolvingCORE ALTERATIONS or positive reactivity changes. l SURVEILLANCE REQUIREMENTS
?
4.1.2.1 At least one of t aboverequiredflowpathss\ hall be demonstrated
)'
OPERABLE:
- a. At least on e per'7 days by verifying that the tempergture of the '
, heat trace portion of the flow path is greater than o equal to
- 65'F whe a flow path from the Boric Acid Storage System is used,
- and 4
- 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 loc'ked, ealed, or otherwise secured in position, is in its correct position.
4
\ !
5 "A ximum of one charging pump shall be OPERABLE, and that pump shall be a ntrifugal charging pump, whenever the temperature of one or more of the C5 cold legs is less than or equal to 330*F. ! BRAIDWOOD - UNITS 1 & 2 3/4 1-7
i
~
, 6ttEie61 3.I i O s xREACTIVITY CONTWOL SYSTEMS
\ l FLOWsPATHS - OPERATING '
\ \
LIMITING CONDITION FOR OPERATION
/
\ /
3.1.2.2 At Ikast two of the following three boron injection flow paths shall l be OPERABLE: - j
- a. The flow' path from the Boric Acid Storage System via a borir acid l transfer 1 sump and a charging pump to the Reactor Coolant ystem, and
- b. Two flow pat'hs from the refueling water storage tank 'via charging pumps to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2 nd 3. ACTION: j With only one of the above required. boron injectiop/ flow paths 'to the Reactor Coolant System OPERABLE, restore atN1 east two borpn injection flow paths to i the Reactor Coolant System to OPERABLE status w) thin 72 hours or be in at l 1eastHOTSTANDBYandboratedtoaSHUTDOWNMfRGINequivalenttoatleast l 1% Ak/k at. 700*F within t.h* a'ist~T hodi'skrpsto}e 3t I. :t h:: I M- . ".L., *
) ' to OPERABLE status within .he next 7 days r be in COLD SHUTDOWN within tne !
next 30 hours. SURVEILLANCE REQUIREMENT! N < i 1 /
! 4.1.2.2 Atleasttwooftheaboverequiredflowpytsshallbedemons'trated a !'
OPERABLE: , a. At least once per 7 days by verifying that the emperature of the heat traced greaterthan,p-6rtionoftheflowpathfromthebor\cacidtanksis or equal to 65'F when it is a required water source;
- b. At least nce per 31 days by verifying that each valv (manual, power-operated, or automatic) in the flow path that is ot locked, i sealed, or otherwise secured in position, is in its corre position; c.
At 1 east once per 18 months during shutdown by verifying t each fautomatic valve in the flow path actuates to its correct pos ion on a Safety Injection test signal; and d
- j. At least once per 18 months by verifying that the flow path requ (ed
/ by Specification 3.1.2.2a. delivers at least 30 gpm to the P::Sctor '
Coolant System. o BRAIDWOOD - UNITS 1 & 2 341-8
s 4 ~ % % . F,( .I 4 LO
~
O EACTIVITY CONTROL SYSTEMS CH GING PUMP - SHUTDOWN N LIMITING. CONDITION FOR OPERATION I
\
N . . l 3.1.2.3 One ' charging pump in the boron injection flow path required by ! 3' 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. ! . A.CTION:
\
1 With no charging pump OPERABLE or capable of being powered f, rom an OPERABLE emergency power source, sus),end all eperations involving CORE ALTERATIONS or positive reactivity changes. 1 O , SUavEIttANCe REoVIREaEN1s x N i 4.1.2.3.1 The above required charging pump \shall be demenstrated OPERABLE by
- verifying, on recirculation flow, thpt a differential pressure across the ;
4 pump of greater than or equal to 2 96 psid is de'veloped when tested pursuant to Specification 4.0.5. l 4.1.2.3.2 Wheneve? the temperJture of one or more o the RCS cold legs is less than or equal to 330*F . OPERABLEpump,shallbedepo/allchargingpumps,excluingtheaboverequired 1 nstrated inoperable"* at le t once per 31 days, ! except when the rv.utor (ssel head is removed, by verify' g that the motor . circuit becakers a e s ured in the open position. i
*A maximum of one charging pump shall be OPERA 3LE, and that pump shai' be a centrifdgal charging pump, whenever the temperature of one or more of .he
- RCS cold legs is less than or equal to 330*F.
**An operable pump may be energized for testing provided the discharge o the 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.
BRAIDWOOO - UNITS 1 & 2 3/4 1-9 1
^
s MW L 1 O CTIVITY CONTROL SYSTEMS h CHAR PUMPS - OPERATING LIMITING CD TION FOR OPERATION
/
5 i 3.1.2.4 At least two harging pumps shall be OPERABLE. APPLICABILITY: MODES 1, and 3. l ACTION: With only one charging pump OPERA , restore at least we charging pumps to
' OPERABLE status within 72 hours or b in at least H STANDBY and berated to a SHUTDOWN MARGIN equivalent to at lea 1% Ak/k 200*F within the next 1 6 hours; restore at least two charging p st PERABLE status within the next l 7 days or be in COLD SHUTDOWN within the ne 30 hours.
d O*
. j SURVEILLANCE REQU MENTS I 4.1.2.4 At least two charging pumps shall be demonstrated by. I verif ng, on recirculation flow, that a differential pressu. ,5 each p of greater than or equal to 2396 psid is developed when ic51.ec pursuant ;
Specification 4.0.5. - a . Os BRAIDWOOD - UNITS 1 & 2 3/4 1-10
(RhACTIVITYCONTROLSYmrs 3 ' }. 40R ED WATER IQPRCE - SHUTDOWh 3 ! O uMn h C0 0 0pE mTIO. . t 3.1.2.5 M i OPERABLE: A\aminimum,oneofthefollowingboratedwatersourcesshall I
- a. A Bo ic Acid Storage System with:
1
- 1) A nimumcontainedboratedwaterlevs1of7.05, l
j
.c.-. 2) A minimum boron concentration of 7000 ppe, and
- 3) A minimum solution temperature of 65*F.
j b. The refuelingwater \ 1) A minimum c\ storage tank (RWST) with: on ined borated water level f 9.05, i 2) a) 1 *A minimun g baren concentration f 2000 ppa, b)' **A boron con tration betwe n 2300 and 2500 ppe, and 3 3) Aminimumsolutionteperature f 35 F. APPLICABILITY: MODES 5 and 6. i
) ACTION:
=
i l l With no borated water source OPERABLE susp d all operations involving CORE i ALTERATIONS or positive reactivity anges. i j 'SURVEftLANCE RE0UIREMENTS 1 i 4.1.2.5 The above required [' 6 9PERABLE: rated water source sha 1 be demonstrated
- a. At least onc per 7 days by:
i j
- 1) Verif ing the boron concentration of the wa r,
- 2) V ifying the contained borated water level, a
.?,) erifying the boric acid storage tank solution t
!- erature when it is the sourr.e of borated water. I 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 1
'less than 35'F.
i I ' i
- pli' cable to Unit I and Unit 2 until completion of cycle 5.
} Applicable to Unit I and Unit 2 starting with cycle 6. l . i ~ i BRAIDWOOD - UNITS 1 & 2 Unit l'- Amendment'No. 56 1 3/4 1-11 Unit 2 - Amendment No. 55
_ _ - ~ . _ . - . _ . _ . . - . . . . _ _ - . _ . . . _ . _ _ . . _ . _ . . . . _ _ _ _ _ . _ _ . . . _ _ . _ . .
% c % 3el i l
REACTIVITY CONTROL SYSTEMS 5 BORATED WATER ens:P_CES - OPERATING LIMTING CONDITION FOR OPERATION ! 3.1.2.6 s'a minimum, the following borated water source (s) shall be OPE L . db LE i-
' 3as require's y Specification 3.1.2.2 for MODES 1, 2 and 3 and one 1.2.1 for 4:
! i j- a. A Bori cid Storage System with: 1)- A mi mum contained borated water level of 40%,
- 2) A mini boron concentration of 7000 ppa, a i
- 3) A minimum s ution temperature of 65*F.
i l
- b. The refueling wate torage tank (RWST) wit .
t i 1) A minimum contai ed borated water 1 1 of 89%, '
\
- 2) a') *A minimum bor'on concentra on of 2000 ppa, b) **A boron concent a on tween 2300 and 2500 ppm, O- ') ^ '"' '#tia"
- a r *=
q r 25 r d i
- 4) A maximum solution temperature. of 100*F. 4 I' '
j APPLICABILITY: MODES 1, 2, 3, and 4.
/ \g j i
! ACYION- \ l I a. With the Boric Aci Storage System inoperable and being used as one k i 1
- j i oftheaboverequJfedboratedwatersourcesfgMODE1,2,or3, l restore the systda to OPERABLE status within 72ghours or be in at i
i . least HOT i MARGIN equi Y within the next 6 hours and bor ted to a SHUTDOWN ! ent to at least 1% ak/k at 200*F; r tore the Boric Acid Storag System to OPERABLE status within the n t 7 days or be l in COLD 5" within the next 30 hours. .. 1-f b. With t e RWST inoperable in MODE 1, 2, or 3, restore th tank to
- OPE I
th next LE status within I hour or be in at least HOT STANDB within 6 hours and in COLD SHUTDOWN within the following{30 hours. ,
~c .
ith no borated water source OPERABLE in MODE 4, restore one orated water source to OPERABLE status within 6 hours or be in COLD S' DOWN within the following 30 hours. ; l
\
. Applicable to Unit I and Unit 2 until completion of cycle 5.
Applicable to Unit I and Unit 2 starting with cycle 6. l Unit 1 - Amendment No. 56 BRAIDWOOD - UNITS 1 & 2 3/4 1-12 Unit 2 - Amendment No. 55
6e<Mok .5,( N - - - - -. O REACTIVITY CONTROL SYSTEMS j SURVEILLANCE REQUIREMENTS l
'N .., l
- 4.1.2.6 Each borated, water source shall be demonstrated OPER : !
N i At least once per 7 days by: a.
- s. -
, '1) Verifying the boron concentration the water,-
- , 2) Verifying the contai or ed water level of the water 1 source, and ;
Verifying the Bor* Acid Storage stem solution temperature i 3) when it is th ource of borated wa .
- b. At least onc er 24 hours by verifying the temperature when the outsi air temperature is either less than 3 or greater than 100*F nd
- i c. st once per 24 hours by verifying the RWST vent path erature i to be greater than or equal to 35'F when the outside air tempe ure
! is less than 35*F. t
~
O O BRAIDWOOD - UNITS 1 & 2 3/4 1-13
_ .~. _ __ _ _. _ _ __ -_._ _ _ _ _ _ _ Weh 3s \ W 5.~5,9 1 Add ] he.esed insecha 3 3 coc Er Grchon 3 3 REACTIVITY CONTROL SYSTEMS
; BORON DILUTION PROTECTION SYSTEM
. LIMITING CONDITION FOR OPERATION 3.1.2.7 Two independent Boron Dilution Protection System (BDPS) subsystems shall be OPERABLE.* APPLICABILITY: MODES 3, 4, and 5.
, ACTION:
- a. With one BDPS subsystem ineperanie, restore the inoperable subsystem to OPERABLE status witMn 72 hours or within the next hour, and at
- . least once every 31 days thereafter, verify valves CV-1118, CV-8428, i CV-8439, CV-8441, and CV-8435 are closed and secured in position.** c
- b. With both BDPS subsystems inoperable, within I hour, and at least
- j 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 O, specificetiaa 3.1.1.1 or 3.1.1.2, as app 14cabie. ,
. l I
l 1 1 l l
.:;9 ] l ***TheThese BDPS Flux Doubling signals may be blocked during reactor startup.
valves may be opened on an intermittent basis under administrative control when required to support plant evolutions. j BRAIDWOOD - UNITS 1 & 2 3/4 1-13a Amendment No. 40
1 LCD 3.3.9 . l 3.3 In.* m.,e A n. 6 Se.e.E 3. t
/20f,0TIV!"' 00'""*L = T = j
- 33. BORON DILUTION PROTECTION SYSTEM [80P5) l LIMITING CONDITION FOR OPERATION t
! Leo J.JM 4:t:P:P) Two independent Boron Dilution Protection System (BDPS) subsystems shall be OPERABLE. Q APPLICABILITY: MODES 3, 4, and 5. l ! ACTION: l Co,4 4 ,af With one BDPS subsystem inoperable, restore the inoperable subsystes to OPERABLE status within 72 hours for w1 thin the next hour, and at 1 i r 31 days thereafter, verify valves ;V 1113. CV M ;J '
- b Jeast onceEUever
,_U "'ta ^_1 _ - d EU ^2"-l are closed -- ' --- --- i r - iii-- M Co.,a D .F.' With both BDPS suosystems inoperab hin I hour, and at least i once every 12 hours thereafter:
i .Ft Verify valves C"-111", CV- M ", CV M30. OV 0'"1. e..d OV M3% are closed) em reer ed #- ; nit'e..**i, and { X Verify compliance with the SHUTDOWN MARGIN requirements of i Specification 3.1.1.1 or 3.1.1.2, as applicable. 4 O yp c. H sawe-r 2.1-13aA ; h I LCO u4e Mhe BDPS Flux Doubling signals may be blocked during reactor startup. , A O cbaf*These
" 4e controi sen valves may reauired to sugPortbe opened piant evoiutions. on an intermittent basis under adminis ,
i l BRAIDWOOD - UNITS 1 & 2 3/4 1-13a Amendment No. 40
l l O cts INsERTcs) sECTION 3.3 LCO 3.3.9 j INSERT 3.1-13aA (M,) CONDITION REQllIRED ACTION COMPLETION TIME C. Two trains inoperable. C.1 Close and deactivate 8 hours due to an unisolated unborated water unborated water source source isolation frorp the refueling valves. water storage tank. l 1 0 - l 1 i j O , Revision A
l M g Adclrer. sect in Secit on 3.3 @ '5,7.9 l See Doc for sec4:en 3 3 i
]
C REACTIVITY CONTROL SYSTEMS i SURVEILLANCE REQUIREMENTS i; I 4.1.2.7 Each BDPS subsyst.m shall be demonstrated OPERABLE: I a. .At least once per 12 hours by:
- 1. Verifying that its associated nuclear instrumentation source i range detector is OPERABLE and indicating greater than or equal' l
- l. to 10 counts per second. ;
- 2. Verifying that all reactor coolant loop stop isolation valves are open, and ;
- 3. Verifying that at least one reactor coolant pump is in l operation. -
- b. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, I
sealed, or otherwise secured in position, is in its correct position.
~
l
- c. At least once per 92 days by verifying that the BDP.S Alars 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 aimulated BDPS Flux Doubling test signal valves CV-112D and CV-112E
- open and valves CV-1128 and CV-112C close in less than or equal to
, 30 seconds. '
l i l 1 1 1 o BRAIDWD0D - UNITS 1 & 2 3/4 1-13b Amendment No. 40
ICO 3. 3. Cr l Scc h 3.1 REACTIVITY CONTROL SYSTEMS O i SURVEILLANCE REQUIREMENTS l
- MEI;3 Each BDPS subsystem shall be demonstrated DPERABLE
l l p. At least once per 12 ho s by: SR 3.3.i. 8 No4e. hNa r%T 3.1 -13 bA in SR 3. 3. 9 i E. Verifying that its ssociated nuclear instrumentation source range detector is OPERABLE and indicating greater than or equal to 10 counts per second. . l SR y. 3.9,3 .2f Verifying that all reactor coolant' loop stop isolation valves. are open, and SR J.3.9.2 3' Verifying that at least one reactor coolant pump is in operation. SR133.5 K At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position. SR3.31.6 g. At least once per 92 days by verifying that the BDPS Alars Setpoint is less than or equal to an increase of twice the count rate within . a 10-minute period. r e .3 %,,, '
%c coere + p a A. o [ a athl u 12:;
SR J.3 ct.8 CK At least once Der 18 mone.hs when shutdown by vehifyina that on a/ simulatedlbDP7 Flux Doutf ing tesbanal valves >tv-1 and CV-11A 1 (oper}/and val /es CV-1127 and CV-11/C close An less th or equal go J l30 Aeconds.f LAs 1 I l l l lO ! l BRAIDWOOD - UNITS 1 & 2 3/4 1-13b Amendment No. 40 l 1 l
1
'i c .
i O CTS INSERT (S) SECTION 3.3 . LCO 3.3.9 i INSERT 3.1-13bA (L33 ) l
.) <
! SURVEILLANCE FREQUENCY I 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 after entry into MODE 3. O i l l l i O Revision A
too 3.154 l 1 3.1 REACTIVITY CONTROL SYSTEMS g m , . 2. s . .- m .......-,, mms, 3. . 4 Rod Group Abgnmerd Limdr. LIMITING CONDITION FOR OPERATION
+
LCO 3.1. 6 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step counter demand position. APPLICABILITY: MODES 1 . ACTION: ' ~ cono A + With one or more full-length rods inoperable /Wue/to beincr immovable) R A A.i.i as A resulf of exofessivefrictioff or mec,hanical/interfefence of kn6wn to Me untrippable/aetennine that the SHUTDOWN MARGIN require +' h Q RA A t.2 ment.'n G;;- ;;e;;en .;. l.1. ;' satisfiedittithin I hour andAe in U l HOT STANDBY within 6 hours. A' c rum s. i- M A QA cowo B .b.. With one full-lenath rod pfippable/butingerable/ueto'c/uses /l [sither thpfi addregsed by)fCTION af above,forl misaligned from its h group step counter aemana neight by'more than i 12 steps (indicated position), POWER OPERATION may continue provided that,within 1 l
,] hour-s .estored to hin the bove
//4
- 1. RABi.E tus herod[trequy,ements lignmen or G. inopeyablean'therepiinder the rods in fT)[erod1 he growith / decla are al einoppabler whilem/gnedtaintainigther/
ithin ) i 12 s eps of e inopprable r od Al v seq ce and nsertion limits of n = 2.M/ The THERMAL P R levpi shall Spec , on ... 4 ; dgingsubs/berestyictedpyrsuant) equent/peration,or / 5=ac2 M k3 % / p s.u 3, The rod is declared inoperable and the SHUTDOWN MARGIN - requirement of Specification 3.1.1.1 is satisfied.I POWER gg , OPERATION may then continue provided that: t mqsj,.,q s 7 RA e.2 .a-) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER-within' the next'houriano spIthin getpo'ntisp)educedAoless/thanorfequaltp85%ofhe TED fo ' lowing h THE, L POWER.] b} The SHUTDOWN MARGIN requirement of Specification 3.1,1.1 RA B.3 is determined at least once per 12 hours; i (*See Speciel Test Oceptiene Specific;tiens 3.10.2 end 0.10.0.) h !O 1 BRAIDWOOD - UNITS 1 & 2 3/4 1-14 Amendment No. 32
1 l O CTS INSERT (S) SECTION 3.1 l l LCO 3.1.4 l INSERT 3.1 14A (A7 ) CONDITION' REQUIRED ACTION COMPLETION TIME.' i A. ... ... 2 A.1.2 Initiate boration to I hour restore SDM to within limit. i INSERT 3.1 14B (A7 ) CONDITION REQUIRED ACTION COMPLETION TIME f l B. .. B.1.1 ... ... l 2 B.1.2 Initiate boration to I hour restore SDM to within limit. l l l l l l O ! ! Revision A I i
4 1 L L o s t.4 1 . i REACTIVITY CONTROL SYSTEMS i !' o 1 LIMITING CONDITION FOR OPERATION ; l ACTION (Continued) LAs Rg g,y .s.) A pown disty1Dutton/ nap tr/obtaijsed frosithe marvable) l R A 6. 5' Li"""0 *t aAnet/and F (Z) and F" are verified to be l withintheirlimitswiIhin72 hours;and i i g RA&(a 4) A reevaluation of each accident analysis bf T:.m 2. -11.is i performed within 5 days; this reevaluation shall-confirm ) { that the previously analyzed results of these accidents ! remain valid for the duration of operation under these conditions: l
- CoWo( fow~M be in m.oe 3 wim (, hwrs)
With more than one full-length rod /trippab/e Dut/inopetable due to/ b rh ) ' Cowo D s ' M b~_ causer otner Anan soaressed by ACMON a. 4bove/or/ misaligned from
~its group step counter demand height by more than 12 steps
< (indicated posit 1on),
} POWER OPE ON may continue ovided that: 1 i
- 1. Within our, the rem der of the rods ' the group (s) with O M e n av isa ,,
the i perable rods e aligned to wit n 12 steps of the ino rable rods w e maintaining t . rod sequence and ? ) g i ertion limit f 4 1 hall be rest cted pursuant
>-1 he THERMAL POWER lev
- 3. 3.6 ring i
j subsequent eration, and ' 4 l 2
- 2. The in rable rods shall e re oreiio BruAB status within
- 72 h rs. . j i
I L0ther se,[beinHOTSTANDBYwithin6 hours. 0 l L ! 4 ~ SURVEILLANCE REOUIREMENTS
- sR3.i.u.t a-+--+-+-M 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 oer 12 hours cept duringfime intervalywhen the rod position deviftion mojdtor is in erable. therr verify the oreuo notitions A least on
- cer/4 hours //
2 5R3.1A.2. NT Each full-length rod not fully inserted in the core shall be j determined OPERABLE by movement of at least 10 steps in any one direction at l least once per 92 days. i 1 4 O BRAIDWOOD - UNITS 1 & 2 3/4 1-15 AMENDMENT NO. 74
- ~ . _.. _ - - - - . ..
l- i g q ! i i G CTS INSERT (S) i- O SECTION 3.1 ; , LCO 3.1.4 2 ! INSERT 3.1 15A (M ) . ! )
- CONDITION REQUIRED ACTION COMPLETION TIME I i i D. ... D.1.1 Verify SDM is within 1 hour l l the limits specified j- in the COLR.
I i 2 't D.I.2 Initiate boration to I hour l' restore required SDM
- to within limit.
i
- bND 2 '
D.2 ... j- O-i i l O Revision A 4
4 1 1 Lt.o 3, t.4 1 O Tast'E 3.1-i ! ACCIDENT ANALYSES REQUIRING REEVALUATION i j IN THE EVENT OF AN INOPERABLE 4ULL-LENGTH ROD Rod Cluster Control Ass Insertion Cha eteristics.
' I Rod Cluster Control Assembly su i Loss of' Reactor Coolant from Spa 1 R M
red Pipes or from Cracks in Large Pipes Which Actuates M Emergency re Cooling System. j Single Rod Cluster Co 01 Assembly Withdrawal ! Full Power. l MajorReactorCo ant System Pipe Ruptures (Loss of lant Accident). Major Seco ary Coolant System Pipe Rupture. 1 Rupt e of a Control Rod Drive Mechanism Housing (Rod Cluster con A ly Ejection). 01
. l O
i l 0 BRAIDWOOD - UNITS 1 & 2 3/4 1-16
l g LCO 3.1.'7 l 4 1 LLO 9.l.Q i 4 1 3l REACTIVITY CONTROL SYSTEMS l { l ' 2.L~T POSITION INDICATION SYSTEMS - OPERATING l i LIMITING CONDITION FOR OPERATION l LCO 2.1.7 (0.1.3.0 The Digital Rod Position Indication System and the Demand Position '
. Indication System shall be OPERABLE (:nd :::el: c' ::::mi e r.: th: ::=r:1 L
.f
;oositi:r.; withir, ; 1 ets;.
-l LA. I APPLICABILITY: MODES 1 and 2. @yBy C Irm + 3.i -na 3 I "'#6 O " " * ' '
ACTION: coND A L CONF 4 g / tycup coND E 4, With(a maximum of one) digital rod position indicator per' inoper- ' able either: ! Lei i 43 Determine the position of the nonindicating rod (s) indirectl by the movable incore _ detectors at least,once oer 8 hours _a motion g the n indica]# fig rod wh' F1mmedia y after a l A excee 24 steps ~ one direction s cethe)(stdeterm'ation)
- of e rod's p tion /lir
. 1 f A A,2 -2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER l O
~
itai" a a="r - OlO 9 -b: With a maximum of one bank demand position indicator inoperable I either: f g ,, g
$h hl.l -h Verify that all digital rod position indicators for the affected gg p',,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 pec 8 hours, or f ft ),2. 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER .
within 8 hours. . (_2n er4 3. i - n e_ ' > cewo p SURVEILLANCE REQUIREMENTS 7' 1 ' 4 l " 1. 3. 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 uring time in rvals wnen the o position oeviption alarm 1sfinope q l ble, hen compare t e Demand Positi Indication Systen and the Dicftal Rod / ) osi ion Indicatio System at least nee per 4 hours./ l LAq lO l BRAIDWOOD - UNITS 1 & 2 3/4 1-17 I
Q. 1 CTS INSERT (S) SECTION 3.1 LCO 3.1.7 j INSERT 3.1 17A (Au ) i ACTIONS NOTE Separate Condition entry is allowed for each inoperable Digital Rod Position Indicator (DRPI) and each demand position indicator. i ,
- INSERT 3.1 17B (Mn )
CONDITION ' REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours O associated Completion Time not met. ' i O ' Revision A
I l I i O CTS INSERT (S) SECTION 3.1 1 I d LCO 3.1.7 ) t INSERT 3.1 17C (L,) . I l CONDITION' REQUIRED ACTION COMPLETION TIME - I
)
B. More than one DRPI per B.1 .. ... group inoperable for - one or more groups. Atgl B.2 Restore inowrable 24 hours DRPIs to OPERABLE status such that a maximum of one DRPI per group is inoperable. O . 1 l 1 l l j O Revision A !
h
' l (CD 3.t.'1 1
O %mv!Tv CONT.0t Sv5TE S @ POSITION ATION Sv5 TEM - SHUTOOWN LIMITING CONDITION F0 'CPERATION / N
\
3.1.3.3 One digital rod position indij:a or (excluding bank demand position
~
i indication) shall be OPERABLE and cafablesof determining the control rod l position within 1 12 steps fo prih shutdown or control rod not fully inserted. l APPLICABILITY: MODES 3*g /4"# and 5"#. \ ' I ACTION:
/ -With les3 4han the above required position indicator (s) OPERABLE, immediately open ttie Reactor Trip System breakers. /
O . SURVEILLANCE REQUIREMENTS t e 3.1.7.1 (4.1.0.23 Each of the above required 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; ;nt er.s m 10 ee. i.t.;. priot to c.r'.M (.d h fy Q oner end . f c o it vn) of ihd reachr Leod,
*Witn tne Reactor Trip System brearers in the closed,fosition. #See Specia st Exceptions S ification 3.10.
4 O BRAIDWOOD - UNITS 1 & 2 3/4 1-18
- Lco 3.i.4 ItEACTIVITY CONTROL SYSTEMS h
- ROD DROP TIME 1
LIMITING CONDITION FOR OPERATION ER 3.1.4 3 @ I 6 The individual full-length sh lens utdown and control rod crop time from he fully withdrawn position shall be than or ecual tol2 4/secon46 ' t 2,7 secondsI(Wiit 1 C&cle 3 And _ ! nit 1/ ycle t 7and Up1t 2 Cydle 1)/and e fter/ Unit 1/ Cycle I and afterDifrom neginning of decay of stationary gripper coil voltage to dashpot entry w'.th:
- a. T,y, greater than or equal to $50'F, and
! b. All reactor coolant pumps operating. ApPLICABILITI MODES I and ACTION:
& With the rod op time of any ull-lengthrodIterminedtoa eed I
the above li it, restore the rod drop time to'within the abov6 limit
/ /
O arier to or c dias to aoo 2 or 2.
- time within 1 'its but deterpined with three/
&. /iththeroddro
/reactorcoolan pumps operatin , operation may' proceed provided Q ,
5 THERMAL POWER s restricted lessthanorfqualto66%o RATED THERMAL POWER. SURVEILLANCE REQUIREMENTS I 5R 3.I.+.5 (4.L .43 The rod drop time of full-length rods shall be demonstrated through censurement prior to spoester) criticality: t. For all rods following each removal of the reactor vessel head, For sp cifically affec d individual to s following any aintenance %
/ b.
on o modification to he Control Rod rive System whi aff et the drop tim of those specif c rods, and could
+. I At least/ nce per 18 monftis.
o i 1 Amendment No. 23 l
-- -~ ~ . twTTc 1 & 2 3/4 1-19 l
i Ltp 5.t.S~ 1 8@ i 3.1 REACTIVITY CONTROL SYSTEMS 6ANK n'" W ^ i SHUTDOWN 6 INSERTION LIMIT \tryii}cdgg) og C CO! 80f ef YiOO I c.ic coccdied er 4he OfE**DNta l Ae 4 LIM (14 SLMr M 1
%%w # ,
LIMITING CONDITION FOR OPERATION 1 1 lorks. ! Lto 3.1.$5 @M shutdown @ shall be feliv withere c; ; 4 I APPLICA81LITY: MODES 1 and2$. < , . . . . . ACTION: h5 soterfeel be and 4he' ene or more rhundown Li, c A
'"T-biby' l-@ No+E
- U Withec - ' e ene et..tdan re4%et ";,;!:r v;tt.;r;.;;, except for surveillance ' j (winnn P hoort,s itestino g.ursuant to mfemefi'!;e;ien a 4.2
,. .. . ..%.ewithin 1 hour either:
- .%4o,, u,e W h wiihin the interison Im. C l RA A.F. e g FvHv witt.4, e. tr.e red. ed ._ceeafie,d ..QOtu.4nte peurg
, l g p.[.{ &. Declare the rod to be inoperable and apply Specification 3.1.3.1. l 1
4 j g coND E Wdli Ccquired Ad Oh cnKl ci:sociatec( Coropleboo Time noi mc+ , , Lc ni Macle 2. wnb ail coHrol bank fully irrerf ed wd his i fe licure. ! SURVEILLANCE REQUIREMENTS
.gR 3 l.5.1 . . . . . ~
4 g (to Le with . 4he ince (".1.3.5) Each shutdown @ shall be determined ce!!w .iins - J. w Nn. hm* - - - A i
* /Within 15 minu}4s prior to wit rawal of any r s in Control
} Bank A, B, C./br D during an proach to reac or criticality, nd f 1 h At least once per 12 hours y =e==M ay i e I i 1 (" Lee Leeeie'. Ieel Caseeliehi LPeeifleellen. 3.10.2 anG 3.10.33 h i AghcoLihty v . .. . .. . . ... ...... .. . .... .. .., bang conhl bank. not full 9 ~nwkd Q ' 1 O BRAIDWOOD - UNITS 1 & 2 3/4 1-20 1
s l L CO 3 1 -(* 4 i O $.1'REACTIVITYCONTROLSYSTEMS I 1 4 CONTROL R00 INSERTION LIMITS
- l LIMITING CONDITION FOR OPERATION reooence a a overino i.im+sD Leo 3.1.06 The control banks shall be limited in phys)caJ,_ insertion,as (ttgren-4*~
7, e., . 3. ; L !sf'-..'e.ci.fTedu 'ni Re.. 'CEER'5tiNei (lMiT'E RE[ oft T' A
. m. mmw APPLICABILITY: MODES 1 and29.'
ACTION: A LCO t4eie. l _W ith the control banks inserted beyond the above insertion limits Cexceot for: 1 l l surveillance testino oursuant to Specification 4.1.3.1.Zt ' i j COND A 8 A A. 2. 4. Restore the Control banks to within'the limits.within 2 hours, or
-tr. Redu e THE L POWJR wit n2h rs to ess th or equd1 to tha '
fr tion f RATEVTHER POWE whic is pank itio Au , ing )..s . . , . i ,; . el e ,- 3 dc^e Tr i b m,411o ic d,by,t Jied i *Le ,
/ / / -RA 6 tgCi ,LilW T REPC 23 % 7
, l j -
CoHD C. c. Se in at least m . . . . , . - vwithin 6 hours. ( MODE 2. with ke*6 'I.o j cet4D A
.g (Incer+ 3.1 - 2 A (i nic. t 5.i-2 s ) cag 8 a
SURVEILLANCE REQUIREMENTS b i, j SR 3.1.6.2 (c. l.3.cl The position of each control bank shall be determined to be within the insertion limits at least once per 12 hourslexcep during time 3ntervals w)(n the Rod J(sertion LimivAlarm is inpferable, t n verify the f ndividuay * , M od positiopf, at least o e per 4 houry. ( l LA9 ER 3.l.6.3 ( Incer + 3.1 - 2 i c-l ("',ee ;p c , e ; Tes t Lceeti e..5 Lee c i f i ceti er.3 0.10. 2 are 3.10. 3.3 h AgAtC.obdiN \/ #With K,ff greater than or equal to 1.
. BRAIDWOOD - UNITS 1 & 2 3/4 1-21 l
l 1
i i l 1 Q CTS INSERT (S) SECTION 3.1 l i-4, 2 LC0 3.1.6 j
- INSERT 3.1-21A - (M,)
i 1-
.J i
CONDITION REQUIRED ACTION COMPLETION TIME l : 1 I A. ... A.1.1 Verify SDM is within 1 hour the limits specified i in the COLR. i l' @ i ! A.1.2 Initiate boration to 1 hour i restore SDM to within 4 limit. i l a m 2
- n ...
iU i 3 i 4 1 i i
)
i l l l l O Revision A i s
. . - . . . . - _ _ . _ - - _ . . ~ - - . - . . - - . . . - . . .- _
]
i CTS INSERT (S) , L i
'Q SECTION 3.1 l
v ! LCO 3.1.6
~
~'
INSERT 3.1 21B (M7 ) :
, CONDITION REQUIRED ACTION COMPLETION TIME ' )
I l B. ... B.1.1 Verify SDM is within 1 hour the limits specified in the COLR. 1 l 2 ' B.1.2 Initiate boration to 1 hour restore SDM to within limit. MD B.2 Restore control bank 2 hours O sequence and overlap to within limits. l, O Revision A
Q CTS INSERT (S) SECTION 3.1 4 LCO 3.1.6
- JNSERT 3.1 21C (M7 )
i SURVEILLANCE FRE0VENCY SR 3.1.6.3 'lerify each control bank not fully withdrawn 12 hours from the core is within the sequence and averlap limits specified in the COLR.
~
O l O Revision A l 1
i g tv2.t. h a W t , s (7k. , , s n.4 v%) ) S O %_<_\ _ _ A_ __ W ,, k
- :" .:n; ./:(29%,228) ~ '~~ ~" ' "M:2 /:I79%. 2l29)---- -
; : :11-
- .z:.::---- ~!f: s.-
200 ,\:_..._..[:
, ,g, , , g , . , _ - f,,,,
.: : . .b- _. - .BANKB' 4
0 .-,
].. .-e-
- .i.~ ' - '
(100%.161)- I 160 ( (0%.162):.:=x.-
/- .
4 g - f . N, g ::iE.1 '.'-
,f .
~
.=.
- .-! :=:g- - :.: :
t
-- - - + - - - - .:: . .
BANK C
~
.= .. ..._
g N . :..;[E
,- a.- + -\-- '
. :. = _/- -.,
1 2
,y .... - - .
-r
/
4 o ==:-+ ...-- ' f. p . . . . .
..--- . : .y . g - '-
. . . ..s.._.. ,
, s.
m .- - . --
; Q . ..;d i= ~jf_,*:,~ =~ _ l ~~~ /-
O t .
; =
< SO i:: int z9 ---
so _ a BANK D , f' .a:- : . :. - { . . . . (' 8
= 60
.: /; .!.gr. =-- - '
'.A
/
.=....._,. .-
3 . ... . - (0%,47) :: ..t- ' 40 . :.. - ' I 4
- i.::flE -"-* - [.. --
,/
. . .. . : 0 -- --
.e '
\
20 s.
.:. n;
- 2.
+
r f- .
. g j E:jg:;-f ,--(30%,0) ;; * *' -
)
. . s ,
0 0 20 40 60 0 100 RELATIVE POWER (Percent)
)
i i i s\ FIGURE 3.1-1 [ . KOD BANK INSERTION LIMITS VER5US THERMAL POWER FOUR LOOP OPERATION /" i, p O k x-
. -~ --e -
+H BRAIDWOOD - UNITS 1 & 2 3/4 1~22 i
l
0 l Lco 3 2.3 'j i I l I i O @ } '3.2 M POWER DISTRIBUTION LIMITS ~ 3.n c' :a Ax!At FLUX DIFFERENCE h E.,,e+ lwaJ s 6% h2
- A1 I.u+,*,pasiat-n j LIMITING CONDITION FOR OPERATION _ePNTIN6 GMTS hpgr i _
] l.CO3.g lhe indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the l l target band (flux difference units) about the target flux di_fferenceM l A a. C cle 1 core average accumulated burnup of less th ' 4 equal to and
/
l A b. + R , -95 for Cycle 1 core ._,_ e eunulated 'burnup of greater than ') j 5000 MWD /MTU / i . -12% for each subsequent cycle. b ) f Nird than or equal to 50% but less than 90% of di' E ' r'ee
- THERful POWER meny.ided the indi-i catedAFDiswithintheAcceptableOperationLimitsErrn--e2sprandthe cumulative penalty deviation time does not exceed 1"f*W*i -- - a -* = h- =
l t 24 hours. - A* * ' h'd * -* #'M77"6 RPUT5 LEO 3.2.1 ^^
* = ' - -
TheindicatedAFDmaydeviateoutsidethe t r ==L less than 50% of RATED THERMA
. required target band at
'1?= D OWER,W ;.:::: tr.; ; n ::t;.;
; re. i., . n u . 3, .
c.-..- i. _. ; a , -, i ;_ ; . ,,,,; .ae.; ; : ci,
' APPLICABILITY: MODE I above 15% of RATED THERMAL POWER N l ACTION:
l Co,v.) A .at With the indicated AFD outside of the required target band and 4 with THERMAL POWER greater than or equa 90% of RATED THERMAL l POWER, within @nutes, eitner: y l S. Restore the indicated AFD to within the required
- target band limits, or fed E 2. Reduce THERMAL POWER to less than 90% RATED THERMAL POWER.
f C. ,a C. p. With the indicated AFD outside of the equired target band for more than I hour of cumulative penait tion time during g'ous 24 hours or outside the Acceptable Operation Limits Pl; :==- Gand with THERMAL POWER less than 90% u
~Pi' iter 71faii 50% of RATED THERMAL POWER, reduce: A2. wMed s > ur OTERhTJ'4- i LTtATTs R EPoe r
- 2. THERMAL POWER to less than 50% of RATED THERMAL ruw q y h I
30 minutas, and e u. H L e r r'5:: 12::W T::t E::: ti n: irc:!'!ratten2,20.2) h T urveillance testing of the Power Range Neutron Flux channel may be performed pursuant to Specification 4.3.1.1 provi d the Jrut.iratatt AFD is maintained within the Acce: table Operation Limit :- ':=- : r vj A al of 16 hours f operation may be accumulatea with the TTdTile of7tte uired target i banc during testing without penalty deviati'on yn'h.h ERA:Da* ODD - UNIT 5 1 & 2 3/4 2-1[GATZwa L'nc': iific _ _ .
_~ - - - , - . - - . . . . . - . - - - - . . - - - - . . - - . 7.. Lcc .3.2.2 { LIMITING' CONDITION FOR OPERATION
- O ACTION (Continued)
I f c. more than indicated AFD outside of t umulative penalty M preguired tar *+ E%.. or j at uring the 1 4 previous 24 hours and w ess than 50% but greater i than 15% of RATED T ^'
.%n, t POWER shall not be j
g1 increased or greater t of RA 5 POWER until j E cated AFD is within the _ Wequired target ba . SURVEILLANCERE001REMENTS i l N The indicated AFD shall be determined to be within its limits during L POWER OPERATION above 15% of RATED THERMAL POWER by: L i El Monitoring the indicated AFD for each OPERABLE excore channel: 5R .3.2.3.1 .33 At least o'ce n per 7 days when the AFD Monitor Alarm is OPERABLE, and o 1 P L s n and logging the indicated AFD for each DPERAm r g us M channel at er hour for the f rs and at least LA, once per 30 minutes ther AFD Monitor Alarm is inoperable. Th: %e values of the nai.M O M exist durino the interval precedino each o shall be uo-Me i15t 'lThe indicated AFD shall be considered outside of its target band ~\ when two~or more OPERABLE excore channels are indicatina the AFD to be outside) ithe taroet band. I Penalty deviation outside of the quired target band shall be accumulated on a time basis of: Ifb Abk Z s. One minute penalty deviation for each 1 minute o POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and - lioAMe3 b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER. _5R 3.2.3 SR.3.2 33 3MeD
~ > /The initial determination of target flux difference following a refuel-)
(ina outaae shall >e >ased on desian pre fictionsJ Otherwise, the target flux !
'trifferenceiof ear 5QERAKE MarveWwD shall be determined by measurement I L 7 at least once -- " M "-- FrE 9---- ----& M WiEmaa h heduG 3 l St. 313. 2- " ~
e -*w The target flux difference shall be updated *at least once ner 31 Effective Full Power Days /by either determining the taroet or .;.ierence 1 pursu m. ;; Symention 4.2.1.3 above or T 'i. . interpolation between the g most recently measured v e : ...u 6. ;;r:9+.d value at the end of the cycle ilif. --_ ) 1 O M m e u km -oh3adw[ u k e. BRAIDWOOD - UNITS 1 & 2 3/4 2-2 AMENDMENT NO. 38 I
. i
a
- tco 3 2.3 q i
!O t , (Tha Route b nef med ) Aa
- FIGURE 3.2-1 y ~m - _ r--
! -AHAk6 i ! FWGHON-6F-ME9-ME#h+WER i ! I
?u ei _
i :s j : .g _ i i ) j -
. i i
G
*! +I l
! w0 _- i ! igggUNACCEPTABLElk1)AO):~ (11,90)5 ABLEjE i WJ5.A,TJON - - - -
- ~ =::r . TION ,-*:: !
g __- ~- lO 4
=
- e
/ --
A -_. j !
~
j ( -
- l l _
j = M:CEPTABLEj f0PERAh0N M_ < SO _- : - i _- _ l i ( 31,50) -- t31 AO) 1 l 4 e - i ; ; l 1 _- f -
- y
- -
s. 1 - 3
- j __ . -
g ,/ i . < 1 0 i j ^
-40 30, 20 -10 0 10 20 30 40. W i 1 FLUX OtFFERENCE (All 5 <' -
} j >
% __ w w W ', -
5 ) - 1 1 RAIDWD00 - UNITS 1 & 2 3/4 2-3
g LCO 3.2.1 3.21 e '" ' o HEAT FLUX HOT CHANNEL FACTOR - - LIMITING CONDITION FOR OPERATION ' 3 mm.+,d by LCO b F (Z) shall be "trtier r; in:Fs(d aad F# ldh 4"b*
M g ::::= r: r : : i :""- - -- >
q 1- [K(Z)] for P > 0.5, :nd (Unit 1 Cy:h 2 P greJ/' W "a4+ ? Cye1= 1) Fg (Z) 5 . K(Z)] for P < 0.5. b F 9(Z) ; [2.50] [K(Z,, 'a-
"'O.5)n. ....t Cfcle 2 :nd P ef te ; L'nf t 2 Cyck 2 7)3 <m o< ,_
2nd Oft d i Where. - Fa,= & p , THERMAL ER . ) J RogoMN RAT HERMAL POWER tcun, me)..,o,;,gg g,cerprN
- __ am1rs v.npo r.a c is the functio t ::A:-he h- 'iEre 3.2-Sfor a i height location. - see;f,yj ;,, +ecornatut, Lisf6 hif'g '
~ ~ ~
APPLICABILITY: MODE 1. ACTION: Ff M With - exceeding its limit: pg[g) L Coacl A X. Reduce THERMAL POWER at least 1% for each 1% exceeds the limit A A*I within 15 minutesland similarly reduce the Power Rance Neutron /
- 6. J A ILA A.2.M1ux-Hiah Trip Setpoints within the next@ hours:/ POWER OPERATION c.,a A RA 4.3 may proceed for up to a total of 72 hours ( subsequent POWER OPERATION may proceed provided the OverpowHr al Trip 5etpoints g {,,
have been reduced at least 1% for each 1% exceeds the limit; and
~
g Jr: 'Id tify nd cor ett thf cause Af the jrut-of-/1mit cynditiph priofl iner asing ERMAL 70WER Co6ve the reduced limit /reaui/ed by / / 5 CTIO a. ab ve:JTHERMAL POWER may then be increased provided Gd A R A 4.4} is demonstrated (Dtousn tocoreAhappino)to be within its limit. ,@, Co.u) A N& II(1)Q i . LJ5Eltr J.2 - 4A }-Q N$ O BRAIDWOOD - UNITS 1 & 2 3/4 2-4 Amendment No. 23
4
~ CTS INSERT (S)
SECTION 3.2
, LCO 3.2.1 INSERT 3.2 4A (L,)
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME. B. Es(Z)notwithin B.1.1 Reduce THERMAL POWER 4 hours limits. below the Allowed Power Limit (APL). 8ND B.1.2 NOTE Required Action B.1.2 ; must be completed if : Required Action B.1.1 is implemented. Perform SR 3.2.1.2. Prior to O- exceeding the THERMAL POWER limit of Required Action B.1.1 08 B.2.1 Reduce- AFD limits = 1% 4 hours for each 1% F#(Z) i exceeds limit l SS i B.2.2 NOTE . 1 Required Action B.2.2 1 must be completed if Required Action B.2.1 is implemented. Perform SR 3.2.1.2. Prior to restoring AFD limits O - l Revision A
kq J LTS INSERT (S) SECTION 3.2 i LCO 3.2.1 i INSERT 3.2 4A (continued) (L,) . i 1 i CONDITION REQUIRED ACTION COMPLETION TIME. C. Required Action and C,1 Be in MODE 2. 6 hours associated Completion Time not I met. O l O Revision A
.- ....._.--.---...-.-.--_.-.--.-..--.......---_...u .
~ - ~ . - . _ - . .
t s e O < l l3 Fict,re is ,so4 osed I At l W ~ syfL $nk & __ t
}
IN N g' / f 4 $. E I
/
l
' ~
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li { e a I L . . . 2"""1 _ 5= l rr- .im.- 4 I d .
,c ,
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,a,yj h o" na ..
4 { --
. _ e n s J es s,
i 1 I J i .cr}t Jc > L ~, t C 43 4 C 1 \. F 4 4J t > 3 < l' $ sa n a j .n =.: - j," '
]
, (. si ~~'i ' - j l h, j sl s.: ., . :.m
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_ J !d
.s l3 i . . . ,
- g. - =..._,-r,_ -
_ s. ...
.a_ . - :.wm.rer.a.w.e.. _..a+ e=_ as - - ;----
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,a l=LF M1- :ifd-AF44itislEmif: 4. aliliitMIE.T.W5'Hr4EM ' ;;
1 a
)I I:mi Im.. =-
-+!.c i ?"-irnah ;E. Z
- - " =. f ,s :r___ _ '.=_ . .;h.Wi='ir=_t'gHgyC TE--
rs. : __ . - =n a m . , w m r - -u - =
- . ,.u w -- - -
iso..
. -r,-4 ad ..un . ..a =1 s . _ . . . . . . . . _ =. . r.
{ ( hi;lt :1 Eld 1] WI.MhadEDM-#. fit.MdfM*MMEi"4FIM , ) b= 2 ::1 t/t!E*W"3tiWd.+-4e4f.riGdsF.mimih---- _._
=._,_,
- , ...- - n .---v--- --
\
_ n' . 4
. 9 _ . =r . _ . . - -
q e e e e g e
. 4 ei si al e 4
i i - El 4032nVWWON*EIM D 1 1
\sb Q BRAIDWOOD - UNITS 1 & 2 3/4 2-5 -
Amendment No.23 4 J
- . _ - - . - _ _ - _ _ . . - - - - - . - . . - . . - - - . - - - . _ - . - . - . - ~ . _ _ . . - .
4 i LC o .T.2 f ' I ) ' SR @_ POWER DISTRIBUTION LIMITS , f Replea w/ ~ SR 3.2.1.1 h SURVEILLANCE REQUIREMENTS
^
- 22 4 M 3.21.1 4 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:
- a. Using the movable incore detectors to obtain a power distributio i at any THERMAL POWER greater than 55 but prior to exceedin 50E 1 RATED THERMAL POWER following a refueling outage. The 24 our letion time provisions of Specification 4.0.3 are not
- c licable;
- b. Increa ing the measured F component of the power dist bution map 9
by 35 to ecount for manufacturing tolerances and fu r increasing l the value 55 to account for measurement uncertai ins; , i
- c. Comparing the computed (F,C) obtained in 5 ification 4.2.2.2b.,
[ above, to: RTP
- 1) The F !
3 xy limits for RATED THERMAL POWE (Fxy ) for th appmpriah i measured core p1 es given in Spec cations 4.2.2.2e. and f., l below, and 4 j 2) The relationship: Q j F = F,RTP [1+0.2(1 ) i l Where F*Y is the limi for fra tional THERMAL POWER operation ! j expressed as a fun ion of F,RTP y d P is the fraction of RATED l j THERMAL POWER a ich F,y was meas d,-
- d. Remeasuring F,y ording to the following s dule: l C
- 1. When F is greater than the F,RTP limit for he appropriate .
i meas ed core plane but less than the F,f rela onship,. additional ! p r distribution maps shall be taken and F C e ared to F,RTP l nd F,y: ! a) Within 24 hours after exceeding by 20% of RATED TH L l POWER or greater, the THERHAL POWER at which was F,C st i determined, or i b) At least once per 31 EFPD, whichever occurs first. 1 I LO i BRAIDWOOD - UNITS 1 & 2- 3/4 2-6 AMENDMENT ND. 38 [ . l -
l Lco 3.2.i POWER 0,ISTRIBUTION tIaITS --
.ra h
]Ne.Phesa)[
h iO suavelttaNce aEouraenenTS < continued) r- rsua Sg,pg si< 2.t i.2.
- 2) When the F is.less than or equal to the F RTP limit for the x
i appropriate measured core plane, additional power distribution maps shall be taken and F compared to F l xy at lea and F i once per 31 EFPD. i ! e. The RTP limits for RATED THERMAL POWER (Fxy )~shall be wi in the j limits rovided in the OPERATING LIMITS REPORT for all re planes i containin Bank "D" 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 toe of the fuel
I a
- 1) Lower core regio from 0 to 15%, inc sive,
{ 2) Upper core region f 85 to 10 inclusive, f 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
( j 4) Core plane regions wit ni of core height (* 2.88 inches) about the bank deman osition the Bank "D" control rods.
- g. With F exceeding F[ the effects of on Fq (Z) shall be evaluated to deters' e if Fq (Z) is within s limits.
4.2.2.3 When Fq (Z) is m sured for other than F xy 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
, _ _ . -,_._:-s
~ .,a+ > - - - - - A O CTS INSERT (S)
SECTION 3.2 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.
- SURVEILLANCE FREQUENCY SR.3.2.1.1 Verify Fj(Z) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling M
@ Once within 12 hours after achieving equilibrium conditions after exceeding, by
= 20% RTP. the THERMAL POWER 1 at'which Fs(Z) was last verified i
S 31 Effective ! Full Power Days l (EFPD) , thereafter 1 (continued) O l Revision A
. - ~ . . - = . - .
'Q CTS INSERT (S) SECTION 3.2 LCO 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 F (Z): *
- a. Increase Fs(Z) by the appropriate factor specified in the COLR and reverify F#(Z) is within limits Q specified in the COLR: or
- b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive flux maps indicate F8(Z) maximum over z K(Z) .
has not increased. Verify Fs(Z) is within limit specified in Prior to the COLR. exceeding 75% RTP after each refueling AND (continued) O Revision A i
CTS INSERT (S) SECTION 3.2 LCO 3.2.1 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 last verified O a 31 EFPD thereafter O-Revision A l
.3.2. POWER DISTRIBUTION LIMITS . L C D 3.2.7_
.32.7. = = r 7 .C ; = m : t Lco 3.4.1
, 3 NUCtEAR ENTHALPY RISE HOT CHANNEL FACTOR
- O usmNo CoNomoN roR o,ERmoN +
Iwh ne li; .h sonaf'id in N CoteJ
/ Indicated Reactor
,_....___...,_1,_._ Coolan". System (RCS) total flow rate andF", shall be
___ ___ ...__i $ I a. 1) 'RCS Total Flowrate 2 390,400 gpe,and) a.Sa<M fA d ! j 2) ,,RCS Total Flowrate 2 371,400 spa, and \ i 15ea poc. b SuL 3 4.; c b. 5 Q [1.0 (1.0-P)) ('-F ".@
~. , - -
e F1 7 fM 1 Km U Ahf7 A f* f E #
- f. U., 1... .A. A..9 ~#. 1. A.._
,, _ , . a nni h where: Pfau=ihe Fli' s %e Fs",, I:
w hilarro 1 ~" peedied in A Th ed in % opranz"" am s Measured oy 'usi T the lhovanie incore O detectors. An appro,p,r shall then be ap a uncerta f 4% (nominal) or greater compared to to th red va f F", before it is requirement
.. . _!n . . ;~ . . .,
na r[n v unUSSuro Gi m O 4entICA8ItITv: M00E 1. ACTION: With (RCS total flow rate or) F", outside the regi_on of acceptable operation: 4 L. bAd:lren.J i Sutis 3.4II.
- p. Within hours either: See Doc. kr Se& 3 4.
E. (wlRCS total flow rate and.C., t; ;;ith'- th: 2:;: _ 'i-f td Cond A PA A. I y. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER an CW A AA A.3 "f reduce the Power Range Neutron Flux-High Trip Setpoint to less an or equal to 55% of RATED THERMAL POWER within 5 --m L hours. /
@G A&lreaed E Sec_Ga 3 4. l.
See Doc. b Secs 3.4.
^9914cibie to uait 2 ad uait 2 oatii co pietiaa or cycie 5-O i..~
/ Applicable to Unit I and Unit 2 starting with cycle I
- 6. .
l 4 Unit 1 - Amendment No. 56 BRAIDWOOD - UNITS 1 & 2 3/4 2-8 Unit 2 - Amendment No. 55
3.A
'.""."?encrn. toot.or surnot (,e.cs) u o 54. I
- O!!?"!!"'I^^' L !"'Ti) ;
3A. t 3 C ".?.1) RCS FLOW kATE C_ LEAR Ennu^i ; :;E ;;;T C;;- ;;;L r^cTGR) LIMITING CONDITION FOR OPERATION Leo 3.4.1.c. f b e-4) Indicated React _ 1 r:::;- . :::: :: :::: .;. :or Coolant ;r ::;-System
- ; . (RCS) ;m-.. total flow rate (and F",)shall be
- g. t
_n, % ,...,. n.... ..-
.. . ---. . .....,...,,.,...n
; Aurmel h Sacam 12.2 2 , ,
c 2) kCS Total Flowrate371,400 it gpm..and [b. FI, s 1.55 [1.0 + 0.3 (1.0-P)] for OFA fuel I D FI, s 1.65 [1.0 + 0.3 (1.0-P)J for VANTAGE 5 fuel where: i Measured values of F", are obtained by using the movable incore detectors. } shall then be applied to the measured value of F", before it compared to the requirements, and P= ( THERMAL POWER RATED THERMAL POWER . j i D U APPLICABILITY: MODE 1. 4
\'
l ACTION: 1 1 With RCS total flow rate (or F",)outside the region of acceptable operation:
% w _
, % sea'om fu n 3.2 1 X Within 2 hours either: '" D " #'
- t coup A E.
Restore RCS total flow rate (and F" )to within the above ,'imits, or mpB r ;
-Reduce THERMAL POWER tol k:: th:: 5'"' ef PfTED ".EPyf.L P9E!EP an:0 fred e it:
(thin :r :;;;;j t; 55% ef RAT 0 I;j:";.;;r ",enge %; ;tr;;, Fh- l'igh Tri; Set;; i urs. EL CERh!ithin the next A. 2 a :==::: O (z.:e.pplacu a::::.:=:= t; =it : ::e =:::=== mit : = :t:rtir.; c; .ent::= :th ;ycn =f .1;:e4.)' BRAIDWOOD - UNITS 1 & 2 Unit 1 - Amendment No. 56 3/4 2-8 Unit 2 - Amendment No. 55
i Lco 3.2. 2. LCo ~' t ' i i 4 POWER DlSTRIBUTION LIMIT! . o Q LIMITING CONDITION FOR OPERATION ACTION (Continued) M i j (mjA(Ag2 F Within 24 hours of initially being outside the above limits, v_erify 1 asrouaN Incore "luf Maind and RC5 total flow rata ca=a=rinnalthat thecombinationofF"fandRCStotalflowrate[arerestoredto g Q& 4 wi".hin tie above limits./or reduce THERMAL POWER to less than 55 of)
!RA"ED THIRMAL POWER within the next burs; and / g g .
- p; fl ntify correct the cause o the o -of-1 it naitiop priori incresingTH)RMALPQWER e the uce L POWER lis 41 '*8 by ACTEDN a.2/and/o
- 5 i auf b. =__.e
- Isubsequent POWER OPERATION b A M may proceed provided that th'e combination'of g F" fand (indicated RCS L
{ @otal flow rate /are demonstrated. Q.hfm e neofe
- M indland ) ,
i ft;,gh -Q , JtCS total flow rate comparisonJto be with' n the ' ;;;;r. ;7 --- ^ Mej - i i
'\ n +M- f-L ::: = 1; 0;7t R C lre % ;171;;^1 2 2 E prio to exceeding the fol-i ' lowing THERMAL POWER levels:
M i l U 1: A nominal 50% of RATED THERMAL POWER, (AdreueJkSLhie14.Q l ( s u bcx'. 4 [u G 3 4. J 2: A nominal 75% of RATED THERMAL POWER, and l j X Within 24 hours of attaining greater than or equal to 95% of l Cond 4 RA AA bh- ED HERMAL M . ( MaMAL powat doenot hue h be rulweJ 4e A ( I Q SURVEILLANCE REQUIREMENTS 3 M M 6 Reen,: erd Ah . l 5. .3.1 '
;- ;= := : ::::: n-_un 1. ':. : := ::- -- ' ::":, _',
i
.5R 3 2 2.l -
l l = Theiconcination or inoicatea acs totai riow rate anaiFN shall be determined to be within the,- - QH ___ __ _ _ _
')
~
1 [A h i.S.L3.4tl l i u r::t't::tten 3.2.3:1
,a" (h;.as .souLd ta & cout.)
Prior to operation above 75% of RATED THERMAL POWER after eac_h fuel i h (See bOC bSed a 3D j loading, and i X. At least once per 31 Effective Full Power Days. I 4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specificatiori 3.2.3 at least once per 12 hours whenthemostrecentlyobtainedvalueofFh,obtainedperSpecification4.2.3.2, is assumed to exist.
- 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 j 4.2.3.5 The RCS total flow rate shall be determined by precision heat balance t 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. j The measurement instrumentation shall be calibrated within seven days prior to
; t Prior to the precision
*het6iac performance of #rthe calorimetrictta=<throar<dtrfia flow measurement.
4 O at.ti venturis shall be visually inspected and, if fouling.is found, all venturis tr j shall be cleaned. I j BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AfENDMENT N0. 38
j I ~.2.~. a o s. 4. l l POWER DISTRIBUTION LIMITS _- fw" .. -w ,. J; i / LIMITING CONDITION FOR OPERATION / Q 'u=^=^^^^ Doc. &* S M *atr.x) l ACTION"(Continued) j . Within 24 hours of initially /being outside the above limits, verify .
- through(incore flux mapping and)RCS total flow rate comparison
! t ombination of F" g and[RCStotalflowratearerestore o l $ within above limits, or reduce THERMAL POWER to ess than 5% of RATED THE - R within the next 2 hours; and - !
- c. Identify and cor thecauseoftheout-ofNdiitconditionprior t to increasing THE R above the re,dve'ed THERMAL POWER limit j required by ACTION a.2. or b. ; subsecuent POWER OPERATION j may proceed provided that the ination of and jindicated RCS g _ _ {
l total flow rate are demo ated, t ugh ncore flux mappingJand ! RCS total flow rate comparison, to be w in the region of acceptable ! operation defined.ji(Specification 3.2.3 p ist to exceeding the fol-l lowing THERMAL R levels: L 8 l 1. A inal 50% of RATED THERMAL POWEP., i 2 A nominal 75% of RATED THERMAL P0WER. and l 3. Within 24 hours of attaining greater than or equal to 95% o 1 RATED THERMAL POWER. SURVEILLANCE REQUIREMENTS { . Cf:f:3FDCTn: ;rnei:= :1 i;nifi::ti:n t.0.e n; nt ;; heu., - t [ i (. The combination of indicated RCS total flow rate and F s determined to - t n the region of acceptable opera'ti
- Specification 3.2.3
Li
- a. Prior to operatio 5% of'IfATED4 Welt!AL POWER after eat.h fuel j loadin
( . t least once per 3'1 Effective Full Power Days. j WJ 8 q.2.1:D The indicated RCS total flow rate shall be verified (t: bc z'th'- th:2 Tr:;tr :f ::::p' 91: :;:r:tt:n:!5;= tit::tt:n2.2.}atleastonceper12 hours , i en th: 1 m ==d e:=t =m., nnntly dt ind nin Of Th, etOind ,;r7 'r;,;;ificatier, 4.2.3.2,[ fN..). hd b =O O) f)6w~ IA A iist CA Oi$ Abd ) urd Aubidd O O$hI b (Jt i (CtL '"".TIO" et lee;t u.;e ;;- 10 n:W./ gv l 5r.s.4t.4 - (4 7:FF) The RCS total flow rate shall be detemined6 -,w : .--<--._..a b g p;= w e = ;== = ;._== 2r == = m-- =5
- = --%-r<. e - ,3
, t= x;=1 :;= ==i= . . : = -= =: me m. h; n:nnnnt i=teunentat40n-shal-1-be-sal 4brated-within === d:y: p-4cr.-tth
- f %f[te p=f:- == -f te =wri=t-e n= === =t. -i-- e te p = ei=
qr O == = :: = = = == =t . = t ' == t = = f t* <=- < = = *= te e * *- * > e=u ul e-i=uy<=,est:e=e.i,=f=m;ef=e. e :=t=u f g Q b?? t: :h:=d./ le BRAIDWOOD - UNITS 1 & 2 3/4 2-9 AMEN 0 MENT NO. 38 I i
LCO 3.2.4 l b
- O n POWER DISTR 1.uTIO uaITs j .3.1.4 w OUADRANT POWER TILT RATIO i
LIMITING CONDITION FOR OPERATION i ! ICO J.2.4.' i 15i333 l The QUADRANT POWER TILT RATIO shall not exceed 1.02(above 50% of RATED [THERMALPUWtR.) '
'--oAreIkaWI:ps APPLICABILITY: MDDE 1 .
- ACTION
(r.4wM.xll.O s: g the QUADRANT POWER TILT RATIOH---
-- ---- Q- - _ '
l C.aJ A RA A.2 E. Calculate
'unt et the QUADRANT POWE.r TERATIO at least once per digg%
4 G h M & TH N m u H W R fu e au k ( i e4 Q Prff > f.00. itd f Coad B .Wt l THERMAL POWER. POWER is reduced to less than 50% of RATED THERMAL i I i E Within 2 hours either:
/ o t
j Co.J A RA A.I .Wf i Reduce THERMAL POWER at least 35 from RATED THERMAL POWER ! for each 1% of indicated QUADRANT POWER TILT RATIO in I oexcess
.. .m a v.4. of 1,;-; c..
-i;i::r:, 7::::: =: = =;;;; n.treal 4... m4*w4. .w.
( ; Polm W/Jusu4) g j
" ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
.... m~ ~~~ ~ ' ""- ~~l
! / .3."L-10 A fy y;7;g ;;,;; ;;g ;"., ,;,,; - ,,3 7;;; =;;; ;; ,,i;t,;a ;;; ;jajtj j zl'- 2' 5 ::: c j g- r cr- :d!= '1: 'fri'. Tor reduce THERMAL g POWER i i q hours to paa less than 50% of RATED THERMAL POWER within the next r uce r r Ra neut n r1 M1g 1p Q Mtpo s to ess no equal 55% f RAT THE L withi the ext 4 ours and I i A I . Cc.ed A P.A A.4 prior to inc nd correct the cause of the out-of-limit c THERMAL POWER; subse OPERATION C cl A RA A.5 above 50% of RATED oceed provided that the I 4 CandARAA.6} QUADRANT POWER TILT ve ithin its limit at less once per h hours or until veri table at 95% er RATED THERMAL POWER. jO h Reduce w/ IMER.T 3.2-103 M j
=..=== = ===:=.==u:=4= m.e g
? l
- BRAIDWOOD - UNITS 1 & 2 3/4 2-10 i
s ! O CTS INSERT (S) SECTION 3.2 i
^
- LCO 3.2.4 i INSERT 3.2 10A and INSERT 3.2 10B (L7 and Lu)
CONDITION REQUIRED ACTION COMPLETION TIME ' i' A. OPTR not within limit. A.2 ... M A.3 Perform SR 3.2.1.1 24 hours after and SR 3.2.2.1. achieving equilibrium conditions with THERMAL POWER ' reduced by Required Actions A.1 or A.2 O m : i Once per 7 days ) thereafter ! 4
.M A.4 Re-evaluate safety Prior to analyses 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
.AR (continued) l O
Revision A
-Q- '
CTS INSERT (S)
' SECTION 3.2- *
- )
- LCO 3.2.4 l INSERT 3.2-10A and INSERT 3.2-10B (continued) (L7 and Lu) i l CONDITION REQUIRED ACTION COMPLETION TIME t
A. (continued) A.5 NOTE Perform Required Action A.5 only after j i Required Action A.4
-is completed. j Normalize excore Prior to I
- detectors to exceeding the eliminate tilt. THERMAL POWER
, limits of > Required Actions A.1 i
- Q and A.2
]
3 SM i A.6 NOTES ! Required Action A.6 ! j must be completed i when Required Action A.5 is ; implemented. i Perform SR 3.2.1.1 24 hours after ! and SR 3.2.2.1. achieving equilibrium , . conditions with THERMAL POWER exceeding the ) limits of ' Required Actions A.1 and A.2 O Revision A
I Lco 3.z.+ - l ~ 1 O POWEa DIsTRIRuTI0a LlaITs I LIMITING CONDITION FOR OPERATION l l l 4 l kCTION(Continued) N b With the QUADRANT POWER TILT RATIO determined to exceed 1.09 d misalignment of either a shutdown or control rod: ' i j Calculate the QUADRANT POWER TILT RATIO at least once er hour
- j until either:
The QUADRANT POWER TILT RATIO is reduced to ithin [ its limit, or l ,
) b) RMAL POWER is reduced to less than of RATED THERMAL R. j
- 2. Reduce TH L POWER at least 35 from TED THERMAL POWER for !
I each 15 of' icated QUADRANT POWER LT RATIO in excess of 1, within 30 nutes; i li
- 3. Verify that the RANT POWER ILT RATIO is within its limit i
! within 2 hours aft exceedi the limit or reduce THERMAL l
! k POWER to less than 2 hours and reduce t of P
ED THERMAL POWER within the next r Range Neutron Flux-High Trip !
' Setpoints to less than equal to 55% of RATED THERMAL POWER within the next 4 hou ;
i j 4. Identify and cor t the cau of the out-of-limit condition ! prior to increa ng THERMAL . R; subsequent POWER OPERATION i above 50% of RA ED THEPF1.L POWER y proceed provided that the , 1 QUADRANT P TILT RATIC is veri d within its limit at least once per h r for 12 hu ct or until rified acceptable at 95% l j or great RATED THERMAL POWER. exceed 1.09 due to l
- c. With the RANT POWER TILT RATIO determined causes o er than the misalignment of either a s tdown or control i rod:
- 1. Calculate the QUADRANT POWER TILT RATIO at least a per hour until either:
a) The QUADRANT POWER TILT RATIO is reduced to withi its limit, or THERMAL POWER is reduced to less than 50% of RATED THE L b) POWER. O @ BRAIDWOOD - UNITS 1 & 2 3/4 2-11
i j O POWEk DISTRIBUTION LIMITS - Lco 3.2.4- !O
- LIMITING CONDITION FOR OPERATION
~
4 AD191L (Continued) ! 2. Re HERMAL POWER to less than 50% of RATED L POWER ! within 2 s and reduce the Power Range n 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
! prior to incre THERMAL POWER; quent POWER OPERATION l above 50% TED THERMAL POWER may proc rovided that the l l QUAD POWER TILT RATIO is verified within imit at least
- e per hour for 12 hours or until verified at 9 rester i RATED THERMAL POWER.
i \ t j SURVEILLANCE REQUIREMENTS dFFF:4 b The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by: O_TR314.1 x . Calculating the ratio at least once per 7 days tr.; . ^.;; e;; ;.
}::"E". = . ;..O I. 0:0 ;;; ;;;7 lZ 0;;r; 0 717:g ;t;;dy ;tet-'
g.[Cel;ulatir.sth;7;ti;;t1:
- r t' n d:: th: :!:= ': '::::re':. ,-
SR 3 2 41 3 %) ,M *m- }
=--- -
The.wuADRANT POWER TILT RATIO shall be dete eined to be within the J.igj.t'G";S;.; 5"D of RATED THERMAL POWER with one* Power Raque c iannell
-linnparab.lalby using the movable incore detectors lt.o co tra at t no lize s y. .. ic p r ai riouyon, oppaineaprom T.wp sets f fo s ric imb loc ions af -corr flux map. iskonsist4nt wi the ndic ed 0 RA e PO R TIL RATIOJat least once per 12 hours.
s 5R 3.2 4.1 Na+c wm i2 we a+w 2 h) O ! i BRAIDWOOD - UNITS 1 & 2 3/4 2-12 - AMENDMENT NO. 38 l l
, LCO 3A.) see .3.2.
,-- - ~ - _ _
POWER DISTRIBUTION LIMITS l Nd . SecL[31i. 3/4.2.5 DNB PARAMETERS "[ k k"f** 3 4-LIMITING CONDITION FOR OPERATION .i l 3.2.5 The'following DN8 related para e'.' shall be maintained within the limits shown on Tabla 3.2-1: .
- a. Reactor Coolant System T,yg, aM ,
l b. Pressurizer Pressure. 4 APPLICA8ILITY: MDDE 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 RATED THERMAL POWER within the next 4 hours. j glRVEILLANCEREQUIREMENTS 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 i
- o BRAIDWOOD - UNITS 1 & 2 3/4 2-13
4 h ~ L.C.o 3.4. I
&sen 3 2
~ ~
(3.4 ke.acTom. cooLMT SWerut (rc.5))
~
(^0Z DISTRIOUTIO , LI"IT';) (.,.,,,.,,
. . . . , . .....,-.,,...-,..c,,9 u.n u.sr m ,s w _,a d Flea M ar w A S,4ut<_ w.(e ( M B) ue= A LIMITING CONDITION FOR OPERATION G.2.'O The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:
J 1.2.0 3,01.6 x Reactor Coolant System T,yg, and L c o 3,*l.l. a. X Pressurizer Pressure. APPLICABILITY: MODE 1. ; ACTION: 59 h With any of the above parameters exceedino its limit restore the parameter to I ga.sNp 15 within its limit within 2 hours orf reduce THERMAL POWER to less than 5% of) ; (RATE 0 THERMAL POWER within the next@ hours.f 1 SURVEILLANCE REQUIREMENTS sk 3.4.t.I a 4 SP. 3.s l.R W) Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours.
?
O BRAIDWOOD - UNITS 1 & 2 3/4 2-13 I
. . . - . . .-- _. . - _ _ _ - ~ _ . - - . . . - . . . . . . . _-_. .. ___-. . _. -. O O O m TA8LE 3.2-1 b DNB PARAMETERS E e PARAETER- LIMITS g Indicated Reactor Coolant System T avg -< 591.2*F
-4 g Indicated Pres.surizer P.ressure _
> 2219 psig*
e-n u .
> 3 U; i ,L oa 3 i b
1 0 Xi n c. i
>*4 i I iD W 4 pR' ln :t,
'? s Nl i y l j
WA ' pL ) l V
- Limit'not app 11 cable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL G F' POWER step in excess of 10% of RATED THERMAL POWER. 'A
+.
Q 1
- . - . . . . (A >
t f
o O O , TABLE 3.2-1 E D DNB PARAMETERS o , 6 O PARAMETER LIMITS E Leo J.4.f.b a Indicated Reactor Coolant System T,9 $ 591.2*F 1 LCD 3 4 l . A- Indicated Pressurizer Pressure > 2219 psig* s t M z i R ~ h (pressure tra,s;e,d3 fy 4,{ t W N#T8 " l'* Limit not applicable during*either a THERMAL POWER ramp inD excess of 5% of RATED THERMAL POWI.R per minute or a THERMAL (POWER step in excess of 10% of RAlED THERMAL POWER. y , LA - , R r
. .;+ t :
J 0 h rJ - _._________._____-__-_____-..________-.-_._____.-._m_.___.___ _______-__._.__________________m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
. _ . _ _ ~ . _ _ _ _ _ - _ _ _ . _ . _ _ . _ _ _ - - _ - _ . _ _ _ . _ _ . _ . _ - . _ _ . . _ _ _ _ _ . -
A 4 i 1
- CTS INSERT (S)
O. SECTION 3.2 1 BASES The Bases of the current Technical Specifications have been replaced in their
- entirety by Bases reflecting the format and app'licable content of NUREG-1431 j Bases and proposed Byron and Braidwood Technical Specifications, i
i d i i 4 I 1 i ? I .1 i O 4 i a l l l 4 4 i ) O Revision A f
LCo 3.3.( . l 3.3 6M"h INFTRUMENTATION i 15.;r.'I'.:.n REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION Leo 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. I 1 f ACTION:
- As shown in Table 3.3-1.
AcH n3 AMe 4 lIusse.T 13-1A ' I SURVEILLANCE REOUIREMENTS SR NOTE A N Each Reactor Trip System instrumentation channel c"c '-te-M _ a the automatic trip logic shall be demonstrated OPEFSLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1. i SR 341. l4 . I i Q #2.FEB The REACTOR TRIP SYSTEN RESPONSE TIME of each React:r trip function shall be verified to be within its limit at least once per 18 months. leach "verifica verifie aton shallonin ude at least ne train suc that both tr 'ns are i t ' least per 36 mont 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 j l 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. ? )
. O BRAIDWOOD - UNITS 1 & 2 3/4 3-1 AMENDMENT NO~ 76
l l 2 1 h i ! O CTS INSERT (S) SECTION 3.3 , i LCO 3.. 1 . ) INSERT 3.3 1A (A) i t-NOTE . ! Separate Condition entry is allowed for each channel. t l l O
)
O Revision A
O O O i m.s. i _ o
/ ITh le %ed 4+ c.
~
REACTOR TRIP iNTRUNENTATION ! Re4 ered 1 MINI h(4F-CHANNELS TOTAL !!O. C ANNELS - CHANNE APPLICABLE q FUNCT10NAL UNIT ( j T TRIP OPERAB E MODES... ACTION 6:wpiTera
.1
- 1. Manual Reactor Trip 2 1 2 1t 47 .
2 2 3*, 4*, 5* g) :: r. g / c -
- 2. Power Range, Neutron Flux
- a. High Setpoint 4 2 3 1, t / $h/6-
- b. Low Setpoint 4 2 3 Ifff, 1 g gp/G.
6,4 .E 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 p/6 High Negative Rate g, ,
.Lf, tr. Intermediate Range, Neutron Flux 2 1 2- l###, 4 F KE Source Range, Neutron Flux '
y; Startup 2 1 2 2ff 4 7 gg
.tr. Shutdown
- 2 1 2 3*, 4*, $* , Sit .) ,
LcoJ.19 - M Shutdown ** NA 1 3**, 4**, 5** ,$ti D/E 3"'338)
- 6. Z Overtemperature AT 4 1, t 5 h/E
- 7. 9. Overpower AT 4 2 3 1, 2 # P/tf-T.4. E Pressurizer Pressure-Low panm(ggAbove P-7D 4 2 3- 1 g J/R
~
-* IV h BRAIDWOOD - UNITS 1 & 2 3/4 3-2 AMENOMENT NO. 72 Wb
_9 W
-b -
' O EO . O 3.3.1 - ! . .
TABLE W (Continued) ! REACTOR TRIP SYSTEM INSTRUMENTATION ! hu;nd CHANNELS MINIMUM CHANNELS MPLICABLE FUNCTIONAL UNIT h@-TOTAL F CHANNELS "O.TO TRIP OPERABL MODES ACTION CoNo
%b.MK Pressurizer Pressure-High 4 2 '3 1, 2 X b/6 9 R. Pressurizer Water Level-High 3 2 1 p JIK EAneet(ch((Above P-7))
V) Jr. Reactor Coolant Flow-Low ggg a. Single Loop.(Above P-8) ) 3/ loop 2/ loop in ny 2/1 op in each 1 -X J/K operating op op rating loop .
- b. TwoLoops(AboveP-7and/ 3/ loop 2/ loop in t / loop in each 1 y M below P-8) i sperating loop perating loop
\4 Jr. Steam Generator Water Level- 4/sta. gen. 2/sts. gen. In 3/sta gen. 1, 2 y bM Low-Low any operating each operaing sim. gen. sim. gen.
lN)(. Undervoltage-Reactor Coolant 2 3 ,1 g 'J}Rl WeQPumps((Above P-7)) [perhia) 5-1/bu}s j 13 E. Underfrequency-Reactor Cool (4-1/ bus; 2 3 1 y JfR F4dt(*L Pumps ((Above P-7)) (per4vo.. ggTurbine Trip ((Above P-8)) , M *
- a. Emergenc Tr H ader dIT7aTiD Train 2/Tra 1 .y Pressure e ts
- b. Turbine Throttle Valve 4 1 1 g '
LlM ; Closure (p.citsy .- i r- i O BRAIDWOOD - UNITS 1 & 2~ 3/4 3-3 AMENDMENT NO. 44
O O I O 33.1-1 i TABLE 9-9-F (Continued) . E REACTOR TRIP SYSIEM INSTRUMENTATION
$ E41 g
p"setd 10 fi "J' .
~
5 MINIMUM h ~ r ANNELS CHANNELS APPLICABLE c FUNCTIONAL UNIT p CHANNELS TRIP z _ OPERABLE MODES ACTION M , 3 14 Jr. Safety Injection Input _; y from ESF 2 . 2 1, 2 Jr NIQ ! e )) 36'. Reactor Coolant Pump j N Breaker Position Trip 4 ,
,Gd d fe,Rhove P-7) (per4%a)
- 6 2 1/br ker 1 .R .1/R {
per erating - loo
- 1. eactor Trip System Interlocks' -
- a. reediate Range '
q Neutr lux, P-6 2 1 2 2N 8
- b. Low Power Re '
, T
- Trips Block, P-7 P-10.Inp .
4 2 1 8' l or , P-13 Input 1 2 1 8
~
- c. Power Range Neutron f Flux, P-8 4 3 1. 8 !
- d. Power Range -
Neutron Flux, P-1 4 .,- 2 3 1, 2 i 8
, e. Turbi I u se Chamber '
$ ssure, P-13 2 1 1-hl7/192tr. Reactor Trip Breakers
~
2 1 .2 I ~2 g O/P/G 3 2 1 2 3g , 4*, 5* .34- Ris , 519X Automatic Trip and Interlock Logic 2
^
2 I 2 # N/G [ 2 2 3g, 4* , 5* J6 R/S l7lflM., Reactor Trip Bypass Breakers . 2 1 1 9,* ),3 - OlP/GL $ DI i
~
. i
! LtO 3,M b LLD 3:Sil O ; . . i~ '-W4O ' 4y ' e
. ..,. m . e n
! . TABLE 3.5-1 (Continued) ! 4 Mew ++dd W 68<+1% F,3,I l TABLE NDTATIONS $se. PAC Or' 6dt:4ieh 7,3 i ! *With the Reactor Trip System breakers in the closed position and the l- Control Rod Drive System capable of rod withdrawal. i **With Reactor Trip System Breakers in the open position. In this condition, i source range function does not provide reactor trip, but does provide input
- to the 8eron Dilution Protection System (Technical.5pecification 3.1.2.7) .
i and indication. , ! MBelow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. j i MNelow the P-10 (Low 5etpoint Power Range Neutron Flux Interlock) Setpoint. ; 9Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypassing a Reactor Trip ~ Breaker. ACTION STATEMENTS i ACTION 1 - With the number of OPERABLE channels one less than the Minimum . Channels OPERABLE requirement, restore the inoperable channel to l ! ' 0PERABLE status within 48 hours or be in HOT STANDBY within the
- next 6 hours. .
1 i l ACTION 2 - With the number of OPERABLE channels one less than the Total Number j of Channels, STARTUP and/or POWER OPERATION may proceed provided i the following conditions are satisfied: l l a. The inoperable channel is placed in the tripped condition within j 6 hours; i .. . . .
- b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for ;
- surveillance testing of other channels per specification 1 4.3.1.1
- and than ' Fl= " ^rip'75%
SK 8'2Si < #l [Either, THERMAL POWER is restricted to less%=tr= ! (of RATED THERMAL POWER'rf t.5: ":rr ".r: A
- NC TS;;;; tat i: 7:frd t: 1e:: tM e :-"i;:te !!E' ef P^.TED 1 %L9 I ,
i i '"E"".l. "0"E" dt'r ' trr::/or, the QUADRAN' POWER TILT RATIO l l gg 3. 2,6 2 is monitored at ' east once per 12 hours per j 4gyg g specification 4.2.4.2. ! ACTION 3 - With the number of channels OPERABLE er,e less than the Minimum Channels OPERABLE requirement ar.J with the THERMAL . POWER level:
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status 3 prior to increasing THERMAL POWER above the P-6 Setpoint; and i i b. Above the P-6 (Intermediate Range Neutron Flux Interlock) O SetPoint but 6eio 2a5 r a^Tro Tataaat rouca. rest re the inoperable channel to OPERABLE status prior to increasing l THERMAL POWER above 10% of RATED THERMAL POWER. - 8 3 BRAIDWOOD - UNITS I & 2 3/4 3-5 AMENDMENT NO. 72 l
t . LC.O 3,2 4-5 f c.O 3.3,! a i -- . ts. 3. t - U -
- O -
. n -as~m. ._. .m.m. w s. .
~
" W '"-lY " ~ TAtt F _._ . fCanti -4 4
} TABLE NOTATIONS gg 4 g l ( Ally har4*k l M*ht@ *With thec.sta 3:e L;;= Rur.r; : tu chu. ;nitia ud tM1 j ! r= ten 1 as Dr' we System e===hle o" rod w' thdrawa' , , f**WithRe ange' or Trip System kers in the n pos'. tion, this condi on,
- function not provide actor. trip does provi input),
! . to tems D11sti taction Sy (Technical cification .1.2.7) ) . j i - indicatian./ j SW9 Ntelou the P-6 (Intermediate Range Neutron Flux Interlock) actpint. i fiubMG)#N8elou the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.- LA f, m g 0Whenever the Reactor Trip Bypass Breakers are racked in and closed for i bypassing a Reactor Trip ~ Breaker. , hu+w s.2-rA ACTION STATEMENTS l 4 B.2 EEffMFB- With the number of OPERABLE channels one less than the Minimus j Channels OPERABLE requirement, restore the inoperable channel to
, 0PERABLE status within 48 hours /or be in HDT STANDBY W1 thin the) l gg y ,,
-..rt 6 tours. /
(mee.Ar is-st T j RA P.'2 N- With the number of OPERABLE channels one less than the Total Number l Q CMP 6 +---(the followinc conditions are satisfied:of Channels./STARTUP and/or POWER OPERA l !- .r/ The iroperable channel is placed in the tripped condition within ! 6 hours; ! Af The Minimum Cha'anels OPERABLE requirement is met; however, the j C.oNP P A+e. j inoperable channel may be bypassed for up to 4 hours for i surveillance testing of other channels per Specification ! 4.3.1.1; and i Addrewed _in Se Aios 3.2 c. Either, THERMAL POWER is restricted to less than or equal to 75% g pyg,. .r,,, of RATED THERMAL POWER and the Power Range Neutron Flux Trip j - aw 2,2 Setpoint is reduced to less than or equal to B5% of RATED !- THERMAL POWER within 4 hours; or, tha QUADRANT POWER TILT RATIO l 1s monitored at least once per 12 hours per i Specification 4.2.4.2. ! EETINF9- With the number of channels OPERABLE one less than the Minimus j - Channels OPERABLE requirement and with the THERMAL . POWER level: ! 10 l A4 E2,2 & k x Below the P-6 (Intermediate Range Neutron Flux Interlock) l Setpoint, restore the inoperable channel to OPERABLE status l Fbeholc, (.bM(c) l RA R AI d .K Above the P-6 (Intermediate Range Neutron Flux Interlock) i Setooint but below 10% of RATED THERMAL POWER,frestor Q LA F. 2. 2 [ inoperable chap 41 to DPERAlyf status prjaf to iner sing ] he ) L;g pgg (THERMAL POWEVabove 10% op1 LATED THERMAC POWER.g usser s.3-tc.- )- O'" W 3 1 - R - 3 gn y,2 gg I BRAIDWOOD - UNITS 1 & 2 3/4 3-5 AMENDMENT N0. 72 i -
. . - . - .. - . ... - - . ...- .-..---.-._.- - --.- -. - ....-..= .-. .-...~.. -
4 n
- .Q -
CTS INSERT (S) SECTION 3.3 i i ! LCO 3.3.1- :
- INSERT 3.c ji6 _ (A3 )
f 4 i CONDITION REQUIRED ACTION COMPLETION TIME ! h i . j B. As required by B.1 Restore one channel 1 ho0r from
- Recuired Action A.1 to OPERABLE status discovery of j :anc referenced by when two channels are two inoperable Table 3.3.1-1. inoperable. channels l 2 ,
- E
j B.2 ... j l ! 4 4 i i O ,
\
1 I l j l i O Revision A !
i i i O CTS INSERT (S) SECTION 3.3 , LCO 3.3.1 INSERT 3.3 5B -(A13 ) L
- CONDITION h00IREDACTION COMPLETION TIME D. As required by D.1 NOTE Required Action A.1 Performance of and referenced by Required Action D.1 Table 3.3.1-1. may be delayed for up 4
to 4 hours for- ! surveillance testing ! + and setpoint adjustment provided . trip capability is j maintained. Restore all but one 1 hour from l.. ' channel to OPERABLE discovery of i
'O status when two or more channels on the two inoperable channels on the !
same Function.are same Function inoperable- : AND D.2 ... : O Revision A
' Q CTS INSERT (S) SECTION 3.3 LCO 3.3.1 ' INSERT 3.3-5C (L 4 and L3) f CONDITION REQUIRED ACTION COMPLETION TIME f F. As required by F.1 , Suspend operations imediately . Required Action A.1 involving positive- from discovery and referenced by reactivity additions. of two - Table 3.3.1-1. inoperable i channels S \ F.2.1 Reduce THERMAL POWER 2 hours to < P-6. j l 08 i F.2.2 NOTE O - 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 i i O Revision A
i w o,o., t.co s.s.9
'c""*'"""
O. @ i i ACTION STATEMENTS (Continued) ! SEMIPT)- With the number of OPERABLE channels one less than the Minimum j M4.2 Channels OPERABLE requirement suspend all operations involving AA 4.l' r - f "'
*$ (%MEAr 5,1- M J j j RA H.2 GNNIP'5D- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to L ;
i OPEPARlE status within 48 h0urs o p tu - tM M M-rrer !M ) i M Li AA AAT.%e-C---t: tM b-" 2./wita no mannels .urtuABLE. immed q+ y open M 4,1 < ithe reactor trip breakers M = Arm __a ,< w:. 9 , b w w q l 4 i GGHil EE 'With no channels OPERABLE, immediately suspend operations invo' vinal 4 te.e 3,3,4 AA g.l+--mositive reactivity additions And within I hour verify valves N [
- Lu s,31 AA p.i : : _ ::. :: ::::. :: 522. CY en. =r' c -=3Dare closed. Also, ithin 1 hour and at least once per 12 hours thereafter, verify le s L2 ' 34 M D*d compliance with the SHUTDOWN MARGIN requirements of Specification l i
U T'I % 1 n e
- r u - 6 5 23.1.1.1 or 3.1.1.2, as applicable. 0 l
i u y,q N With the number of OPERABLE channels one less than the Total Number l 4 5.2 4 4 h L.R of Channels./5TARTUP and/or POWER OrtNATION may proceed provided)
- . Mthe follow < n'a' conditions are satisfied
i conp uup xr$ 8 i u N p ti g The inoperable channel s placed in the tripped condition within i 6 hours; and y g e t , g _- n u,esst S.s -6c. conP D Nan. X The Minimum Channels OPERABLE requirement is met; however, the j U cdp J /WE. inoperable channel may be bypassed for up to 4 hours for ! c.cep L t&M. surveillance testing of other channels per Specification 4.3.1.1. i 6 j less than th inimum Numbe f Channels RABLE, with i (ACTION _8 - W hour determi y observati of the asso ted permiss } i 4 annunciator ' dow(s) that e interlock ~ in its req ed state
- for the er tina olant c ition. or y Soecific on 3.0.3. )
isuse.Rr 3 3-1,D 3 a 4 With the number of OPERABL annels one less than the Minimum O N' Channels OPERABLE requirement, restore the inooerable channel to OPERABLE status within 6 hoursfor be in at least HOT STANDBY ) GbHP G :. (within the next 6 hours Jnowever, one channel may be bypassed for up to 4 hours for surveillance testing per Specification 4.3.1.1, l UMP /4142 provided the other channel is OPERABLE. RA na SCTMEPM)- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to W a a Ae R.2 4 gg c,4 ggf y g,,g h u,,s,3 *-(DPERABLE within the next hour. status within 48 hoursfor open the Reactor trip br j Rh C GUTWE"TD- With the number of OPERABLE channels less than the Total Number of
! Q coup p Channels.Joperation may continue previo the inoperable channels are placed in the tripped condition within 6 hours.
--hs u.T 3 3- E.Fj g BRAIDWOOD - UNITS 1 & 2 3/4 3-6 AMENDMENT NO. 72 y
O' CTS INSERT (S) SECTION 3.3 LCO 3.3.1 INSERT 3.3 6A (L3 ) CONDITION REQUIRED ACTION COMPLETION TIME I. Required Action and 1.1 Initiate action to Immediately associated Completion fully insert all Time of Condition H rods. not met. 8ND I.2 Place the Rod Control I hour System in a condition . incapable of rod ' withdrawal. ' (2) l l s l l 1 i 1 O Revision A ! 1 I
l l O cts 1" SERT (s) SECTION 3.3 l l LCO 3.3.1 INSERT 3.3 6B (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME J. As required by J.1 NOTE , 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 provided trip capability is maintained. Restore all but one 1 hour from channel to OPERABLE discovery of status when two or two inoperable O - more channels on the same Function are channels on the same Function inoperable.
~
M J.2 ... P 1 O Revision A j
CTS INSERT (S) SECTION 3.3
. LCO 3.3.1 INSERT 3.3 6C (A3 )
CONDITION REQUIRED ACTION COMPLETION TIME L. As required by L.1 NOTE Required Action A.1 Performance of and 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 all but one 1 hour from channel to OPERABLE discovery of status when two or two inoperable O more channels on the same Function are channels on the same Function inoperable. MQ L.2 ... l i i O l Revision A l
. . . . - . . . - . . - - _ - . . . . - - . - - . - . . _ = _ - . . - . - . - _ . _ - - . . . - - - , . - .
i i .
.Q' CTS INSERT (S)
SECTION 3.3 LCO 3.3.1 INSERT 3.3 6D (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME N. As required by N.1 Restore one train to I hour from Required Action A.1 '0PERABLE status when discovery of i and referenced by two trains on the two inoperable Table 3.3.1-1. same Function are trains on the inoperable. same Function AND N2 ... O O Revision A
O. . CTS INSERT (S) SECTION 3.3 i l LCO 3.3.1 l INSERT 3.3 6E (Lu) i CONDITION REQUIRED ACTION COMPLETION TIME ! l 1 C. Required Action and C.1 ... associated Completion t Time of Condition B 6HD i not met. ! C.2 Initiate action to 6 hours . fully insert all rods. bE : C.3 Place Rod Control 7 hours System in a Condition incapable of rod t withdrawal. ' O , 1 l
}
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 Place Rod Control I hour ; System in a Condition I incapable of rod withdrawal. , 1 O i Revision A
l u r O CTS INSERT (S) SECTION 3.3 LC0 3.3.1 INSERT 3.3 6F (A3 ) i ! CONDITION REQUIRED ACTION COMPLETION TIME I !, O. As required by 0.1 Restore one train to I hour from , Recuired Action A.1 OPERABLE status when discovery of l anc referenced by two trains are two inoperable ! Table 3.3.1-1. inoperable. trains M O.2 ...
**1 l
CONDITION REQUIRED ACTION COMPLETION TIME P. As required by P.1 Restore one tria 1 hour from Required Action A.1 mechanism to OPERABLE discovery of and referenced by status when two trip two inoperable Table 3.3.1-1. mechanisms are trip mechanisms inoperable. AND P.2 ... l lO ! Revision A
O CTS INSERT (S) SECTION 3.3
.LCO 3.3.1 l
INSERT 3.3 6F (continued) (A3 ) l l I CONDITION ' REQUIRED ACTION COMPLETION TIME i
~
R. As required by R.1 Re' store one trip 1 hour from i Recuired Action A.1 . mechanism to OPERABLE discovery of i anc referenced by status when two trip two inoperable , Table 3.3.1-1. mechanisms or two trip mechanisms ; trains on the same or trains on t Function are the same , inoperable. Function j M i R.2 ... . i i O ! l INSERT 3.3 6G (M;) l l CONDITION REQUIRED ACTION- COMPLETION TIME l l G. As required by G.1 Open Reactor Trip Immediately 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 M G.2 ... O i Revision A i I 1
l LCo 3.3.1 i O- Taa'r 2 3-' 'caatiau d' ACTION STATEMENTS (Continued) RA 9.2. W- y. With_one of the diverse trip features (undervoltage or Shunt)
. (Tri) Attachment)) inoperable, restore it to OPERABLE status 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 triD features is Cend O Se 24 ___ inoperable, except for'"
' " )for performing maintenance and testing to restore theM iverse trip feature to OPERABLE status.1 .
y ., . j Cond G X. With one of the Reactor Trip Breakers otherwise inoperable,
. be in at least HOT STANDBY within 6 haurs;lhowever, one
' Reactor Trip Breaker may be bypassed for up to 2 hours for Cong g hlotel z 1 surveillance testing per Specificati en 4.3.1.1, provided th
\other Reactor Trip Breaker is OPERABLE.i
@CTIO" 135 '.With the Reactor Trip Bypass Breaker inoperable, restore the.
e Conac tJdels(Reactor Reactor Trip TripBypass Bypass Breaker Breaker to OPERABLE to bypass status a Reactor Trip prior toIfusing Breaker. the Reactor Trip Bypass Breaker is racked in and closed for Gord C / bypassing a Reactor Trip Breaker and it becomes inoperable, be in cond 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. O O AMENDMENT NO. 44 I BRAIDWOOD - UNITS 1 & 2 3/4 3-6a l l i l
Sec4. 3.3 - O /
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i i I l i i RAIDWOOD - UNITS 1 & 2 3/4 3-7 AMENDMENT NO.12
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/
/
O . BRAIDWOOD - UNITS 1 & 2 3/4 3-8 AMENDMENT NO.12
O O O J T I-I ' IABLE E 3 % REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS b SR marnops,ely yhe 4.,6 I ' nu,4w h h , it.. , TRIP l - :) SR 3.3. r.1 w ANALOG CHANNEL ACTUATING DEVICE MODES FOR WHICH 7 J>_ s a s. s' ' 7 e4 "
- CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCF CHECK CALIBRATION TEST TEST LOGIC TEST 15 REQUIRED _
FUNCTIONAL UNIT I. Manual Reactor Trip N.A.
~
N.A. N.A. 12- R(14) N.A. 1, 2, 3* , 4* , 5*
- 2. Power Range, Neutron Flux -
- a. High Setpoint t-5 J- 0(2,4) 7- Q N.A. N.A. 1, 2 ll- R(4, 54) !
N.A. M.A. 1", 2 !
- b. Low Setpoint I- S u- R(4) St - Q N.A. N.A. 1, 2 !
g.h Power Range, Neutron Flux, High N.A. 11- R(4) ~1 - Q Positive Rate FJbPower Range, Neutron Flux, High N.A. 11- R(4) 7+ Q N.A. N.A. 1, 2 l Negative Rate J.4 Intermediate Range, Neutron Flux I- S 1-1 R(4,Sa) ?-Q N.A. ,M.A. 1", 2 l 2*', ,8'.5 Source Range, Neutron Flux y ,5 Ig4,5b) f(}) N.A. N.A. 3, 4, 5 l I Zb0vertemperature AT t- S to- 7-Q N.A. N.A.. 1, 2 X.7 Overpower AT I-S 10- R 7- Q N.A. ~ N.A. 1, 2 l I- S so- R 7-Q N.A. M.A. 1 l 5.faPressurizer Pressure-Low , (Above P-7) JefbPressurizer Pressure-High I-S io- R 7- Q N.A. M.A. 1, 2 l Ef.9 Pressurizer Water level-High 1-S so- R 7- Q N.A. M.A. I r- r-(Above P-7) gQ l
** u M i, a-BRAIDWOOD - UNITS 1 & 2 3/4 3-9 AMEN 0 MENT'NO.44
O O O
- 3. B.1- l .
TABLE (~537 fContinued) REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE ! FUNCTIONAL UNIT CHECK CAllBRATION TEST TEST LOGIC TEST IS REOUIRED X.roReactor Coolant Flow-Low l-S lo-R '7 - Q N.A. N.A. I b ; e t- S to- R 7- Q N.A. N.A. 1, 2 ! J!rJ4 Steam Generator Water Lt.el-Low-Low
)(.lIUndervoltage-Reactor Coolant N.A. 10- R N.A. 9 - Q(10) N.A. I !
Pumps (Above P-7) 15J3Underfrequency-Reactor Coolant N.A. 10-R N.A. 'i- Q(10) M.A. I
- Pumps (Above P-7)
NJSTurbine Trip (Above P-8) l i
- a. Emergency Trip Header N.A. lo-R N.A. 13- S/U(1,10) N.A. 1 Pressure
- b. Turbine Throttle Valve M.A. krR N.A. 13-5/U(1, 10) M.A. 1 Closure ,
R )foSafety Injection Input from ESF N.A. N.A. N.A. 12.-R N.A. 1, 2 JII.li Reactor Coolant Pump Breaker N.A. N.A. N.A. IZ-R - N.A. 1 Position Trip (Above P-7) -
' ~~~
'19. Rea for Trip Sys'em Interlocks .
- a. Intermediate Range Neutron M.A. R(4) R .A. .A. 2 l Flux, P-6
. Low Power eactor Trips N.A. R(4) R N.A. N.A. -
Block, P-7 Kl
- c. Power Ra e Neutron Flu , P-8 N.A. / R(4) R f N.A. N.A. I 8l
/ ~ . / . _ _ -
. _ . _ _ . j BRAIDWOOD - UNITS 1 & 2 3/4 3-10 AMENDMENT NO. 44 f
- - - _ -- - - - - - . - - _ . - - - - - - - - _ _ - _ - - - - - - . - - - _ _ - - - - - - - - - - - _ - _ - - - _ _ - _ _ _ - - - - - _ - _ - ' - - - - - ~ a-\ a -- u- -- _ -,.e _-__--_--.--_-u-,,---'-----.------n- -- - _ _ . - - -
I O O O 3.3.l-l . TABLE E --fContinued) REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIREMENTS
~
TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH ! CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED l 19. Redctor Trip System Interlocks (Continued) ~T - : d LowSetpoin(PowerRange N.A. R(4) R !'N.A. N.A. 1, 2
/ Neutron F1,sx, P-10 ,/ ,
f
/
/ e. Turbine [mpulse
/ R / R N.A. . N.A. 1
'l Pressure, P-13 Chamber /
/ N.A./ '~ / ~~ ~ ~ ~
1 , 2 ,' 3* , 4*, 5* 20D/gReactor Trip Breakers N.A. N.A. N.A. 4 - N(11) M.A. 3tJ9 Automatic Trip and Interlock N . A .- N.A. N.A. N.A. 5- N(7) 1, 2, 3*, 4*, 5* Logic : 20.fl1ReactorTrinBypassBreakers N.A. N.A. N.A. 12.-(15), R(16) N.A. 1, 2, 3*, 4*, 5*
. 1
. I O
J BRAIDWOOD - UNITS 1 & 2 3/4 3-11 AMEN 0 MENT NO. 44
. . - . - . . - - - _ . - - . - ~ . ~ . - - . . - . - . - . - - _ - - . - . . . - - . - - . _ _ - -
2.3. i.; Lex 3.5.1 f l TABLE 4:3:% f Celinued) O.M"4 With the !n:::t;r Tri; 0;t;; tre;L ; ele ed .J i.;.el Control Rod Drile " '^ "5
- System capable of rod withdrawale av auem e W inm v Q '
l WMdd MBelow P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Mnk(b)sN8elow P-10 (Low setpoint Power Range Neutron Flux Interlock) Setpoint.
If not perforined in previous 31 days. I j SR33.1.13 M i sg33.1.2 W Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistant with calorimetric l cower if absolute difference is creater than 2%. /The previ:i;n: ;f1 'g Ng 'L 4---(5pec i f i c.u un 4.G . 4 .. . uvi. .pyl i 6.L's ivi .. i.. , l..;.. r;;LE 2 1. ., ! SApt.4$43) The initial single point comparison of incore to excore AX1AL FLUX sg 3,3,i 3 g7g DIFFERENCE following a refueling outage shall be performed prior to l 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 per 31 tie previ:t::: Of Ep;;ific:ti;; 4.0.31 har:EFPD. ::t :::11::51:. IThe 2' he:r cr-detic M M.I. i t .W) Neutron detectors may be excluded from CHANNEL CALIBRATION. O IP% (.5s') fivritial plateau-curves-shall-be measured-for--each. detecter _ S*equent1 A' " pl:te:: ::r;;; :h:11 5: ;ttained. evehated--and-costaredio-the-initfal/ I s m es,ff:r th: ::t:c ; dict: 5;;; ::d P :: 5 ;;; = ;tr;; FI;; j dannel: th: pr;;i:i::: Of Sp::ift;;ti;n 4.0.4 :r: act-eppli;;ble f;r- ! (, .::try St: "^0E : ;r 1. / (5b)tWith he high v tage setti g varied a recommended the manufdcturer, an itial dis riminator b'as curve s 11 be measur for each detector. Su sequent di criminator ias curves hall be obtai ed, evaluat d and n i ktmparedto he initial urves. g IitI.I e ,{frf /Inte - Extere Calibr-at40n, &v: 75% Of ".",TED T"E".".".L P0"ER. Th T previ:i::: Of Speci'itat-ic 4.0.4-are-not :;;1icetle fer entry into_J'- - M00: 2 v, :./ For the purposes of this surveillance, quarterly shall mean at least once per 92 EFPD. Ins
,}
5m.i. i (7) Each train shall be tested at least every days on a STAGGERED TEST BASIS. A 3i (*) tt 5:d. (9) Surveil, lance in MODES 3*, 4 , and S* hall also/ include perification that permissives'P-6 and P 10 are it;/their req 6 ired state for exilting plany conditions by obseryation of jfhe permissive annunciator wi/dow. ~ s a 2.u.7 e4.t O 30 S.J.f 3 SIe 3R 3.3.1.s AMe I t Alofe 2. L I'A3ssa r .3.3 -l'2.c} 1 n BRAIDWOOD - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 44
4 i O CTS INSERT (S) SECTION 3.3 , . LCO 3.3.1 INSERT 3'.312A -(M3 ) f SURVEILLANCE FREQUENCY SR 3.3.1.2 5'OTE Not required to be performed until 12 hours after THERMAL POWER is = 15% RTP. INSERT 3.3 12B (M3 ) SURVEILLANCE FREQUENCY SR 3.3.1.6 NOTE Not required to be performed until 24 hours after THERMAL POWER is a 75% RTP.
'l
-O Revision A
.I
- -. . - . . . - -. . . . . _ . ~ _ -. . - . - . . .-
r 4 O CTS INSERT (S) SECTION 3.3 LCO 3.3.1 INSERT 3.3 12C (Ln) ! SURVEILLANCE FREQUENCY SR 3.3.1.7 NOTE ...
- Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours after entry into MODE 3.
SR 3.3.1.8 NOTES ... !
- 1. Not required to be performed for power i and intermediate range instrumentation i
. O.. Ontil 4 hours after reducing power below P-10.
- 2. Not required to be performed for i source range instrumentation until 4 hours after reducing power below
'P-6.
j I l l 1 O Revision A , i
.- _-.- . . . - . . ~ . . - .. - . - . - . . . . . . . . . . . . . . . - . -.
~
Q CTS INSERT (S) SECTION 3.3 : LCO 3.3.9 j INSERT 3.3-12C (continued) (Lu) : i SURVEILLANCE FREQUENCY , 4 SR 3.3.9.7 NOTE ... t Not required to be performed for source i range instrumentation prior to entering ! MODE 3 from MODE 2 until 4 hours after : entry into MODE 3. , i O l l 1 I l i O Revision A
- s. 7 M 3*I I O
3.5.1-1 TAVE E"E"D (Continued 1 TABLE NOTATIONS S A,11,1,11/4 ate. 947 Setpoint verification is not applicable. # SRs,1,s at Qt7 The TRIP ACTUATING DEVICE OPERATIONAL TEST shall be performed such that each train is tested at least every Ddays _on a STAGGERED T 3T BASIS'and
- 'ol 4Wina sfaintesince olfadjusDent #1 theAeactpf Tr<4 Breaders/an 1 d u n r r sJ ggggggg) k7 l
d: ) c:r=L =L::=T:= ;t 11 '= ::: th: m t;;=: ! =:: m e --te." %! f(14) Veri that the- repriate gnals rea the Unde tage an unt Tr' T r ys, for bo the Reac r Trip an ypass Bre rs from e Manua l l ( witches. rip)I v IJete. SAJ,3,s.4(M7 Manual Shunt Trip prior to the Reactor Trip Bypass Breaker being racked
- in and closed by bypassing a Reactor Trip Breaker. j
!O ai v uto m c . # -ows,e w . 4
. l l
O - (*This =tc i; :pplic:bi: 1; Unit : =d Unit 2 =til :Rel: tin ;f cicli 5-) l BRAIDWOOD - UNITS I & 2 3/4 3-124 AMENDMENT NO. 66
- i O. .
33 INSTRUMENTATION 3.5.2. ! .!f.3.2
},
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l LIMITING CONDITION FOR OPERATION tc.o 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE /wlth + heir-gf
'r, i.im irip 5etpoint column o g j ae6puinR = trMutant with the vaAec ehr: -
\ Table 3.3_ 4 I .
APPLICABILITY: As shown in Table 3.3-3. gg , ' ! Nait- ' ACTION: [a. thanESFAS%dstrumentat'onorInter kTripSetpintlesscc/i-\ re ervative thar/the value hown in the ip Setpoint column but [ i conservative han the va ue shown in t e Allowable Value colu Table 3.3-4 adjust the 3'etpoint cons ' stent with the Trip Set int of )M value. / , _ , _ , ,
. j{ _, , ,,,,/,,_,,_.
Cond A y. With an ESFAS Instrumentation orQr.terled' Trio setooint less con- i Q a L servative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable! h's- ACTION statement requirements of Table 3.3-3 until the channel is O restored to OPERABLE status with its Setpoint adjusted consistent } __.w lth.the_Tr_ip..Se_tpoint value. ~i l C x.d A r. With an ESFAS instrumentation channel 6- ilwC inoperable, take the ACTION shown in Table 3.3-3. t 4 AMENDMENT NO 42 BRAIDWOOD - UNITS 1 & 2 3/4 3-13
_ _ _ . ~ _ . . . _ . . . _ _ _ _ . . . _ _ . _ . _ _ . ._. _ ._ ___ ...___. _ . _ _ _ . _ .. _ .. .... .. _ _ . . t
.O cts rascatcs)
SECTION 3.3 , LCO 3.3.2 t INSERT 3.3 13A (A) r NOTE Separate Condition entry is allowed for each channel. i i s i F O : i I i e O Revision A
Lc0 3,5. .R. - i .. i !O INSTRUMENTATION g 1 j SURVEILLANCE RE0VIREMENTS ' SK m i i N Each ESFAS instrumentation channel and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance l of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2. SL S.S 2 ll ' M.L? M The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function 6R7,3.3.12 shall' 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 cha els are verifi at least once pe times 18 mon s where N is t total r of redunda channels in a sp ific ESFAS fu ion as shown i he Total No. of C nnels" Column of ble 3.3-3. 1 hit O
1 l i O BRAIDWOOD - UNITS 1 & 2 3/4 3-14 AMENDMENT NO. 76
' b O "
O O TABLEt.,.h,2-!, y[ d 00 geit ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Q , S I MINIMUM
& 0
~1 Requeed TO,n NO. CHANNELS CHANNEL APPLICABLE o FUNCTIONAL UNIT t9F CHANNELS TO TRIP OPERAB MODES ACIloti cond
- 1. , afety In.lection '(ReactorTr ,
t dwater Isolat'on, Sta Dies enerators, C inment . , Cooling , Con' Room Isolation, P "A" Isolation,
' Turbine Tr , Au ary Feedwa , Containme ent Iso) lon, and Essential vice i Mer),
- s. Manual Initiation 2 1 2 1, 2, 3, 4 X B/E
- b. Automatic Actuation Logic 2 1 2 1,2,3,4 X c/6 and Actuation Relays
- c. Containment Pressure-High-1 3 2 2 1,nt, 3 X FlJl
- d. _ Pressurizer Pressure-Low 4 2 . 3 1, 2, 3' E K/LI MokWA-{(Above P-II)]
- e. Steam Line Pressure-Low 3/ steam line 2/ steam ine 2/ eam line 1, 2, 3' Jr k/d Fodnokla)4-4(Above P-ll)) any ste line .
- 2. Containment Spray LAs '
- a. Manual Initiation 2 pair 2p r 1, 2, 3, 4 .38- BlE
- b. Automatic Actuation Logic 2 1 2 l', . 2, 3, .4 jf clE and Actuation Relays
- c. Containment Pressure-High-3 4 .2 3 1, 2, 3 16' GlJ o :
BRAIDWOOD - UNITS 1 & 2 3/4 3-15 AMENDMENT NO. 44 Y i t _ _ . - _ _ _ . _ . . . - -__m_.. _ - _ . - . _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ . _ . . _ _ _- _ _ _ . _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
O D O 33.2-/ es TABLE 3.M (Cont inued) b ENGINEERED SAFETY FEATURES ACTUATI(N SYSTEM INSTRUMENTATION i l h fleym eI T0TAL-NO: m t.Ad ANNELS MINIMUM CHANNELS h3
' APPL.ICA8tE FU$tCT10NAL UNIT -GF CHANNELS T TRIP
- g ' -
i OPERABL M00ES ACTION Co.d M' in 3 Containment Isolation , e
- a. Phase "A" Isolation -
- 1) Manual Initiation 2 1 /2 1,2,3,4 K R/E !
- 2) Automatic Actuation 2 1 2 1,2,3,4 )4- cl6 Logic and Actuation Relays .
- 3) Safety Injection See Item 1. above fcr all Safety Injection initiating functions and t requirements. / ,
$ b. Phase "B" Isolation -
LAag /
$ 1) Manual Initiation f
2 1 pal I 2 pair 1, 2, 3, 4 #
- 2) Automatic Actuation 2 i 2 1,2,3,4 ,,14' Cl' Logic and Actuation f
Relays ,
- 3) Containment 4 2' 1, 2, 3 Gb,8.
Pressure-liigh-3 )( D 'i3 Jet.' Containment Vent Isolation i 7 ,4 Automatic Actuation 2 1 1,2,3,4 Logic and Actuation 2 JT' - t Relays
- l 27 Manual Phase "A" See Item 3.a.1 for all mami Phase "A" Isolation initiating Isolation functions and requirements.
r- r 2 ,M Manual Phase "B" See Item 3.b.1 for all manual Phase "B" Isolation initiating y$ Isolation functions and requirements. 9g i M Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements. .
O TABLE -3,4 (Continued) uD O ENGINEERED SAFETY FEATURES __ ACTUATION SYSTEM INSTRUMENTATION gr r > ~i W ' MINIMUM k lh TOTAL-NO: CHANNELS CHANNELS / APPLICABLE . FUNCTIONAL-UNIT OF CHANNEL'S TO TRIP OPERABLE / MODES- ACTION .Cc.; d.
- 4. Steam Line Isolation
- a. Manual Initiation j
'l) Individual 1/stees line /stee line 1/opdra,t;ing-- --1;- 2, 3- ~23
( 21 Sy:t= 2 1 7
/
2 1 "2, 3 El H/J
- b. Automation Actuation Logic 2 1 /
2 1, 2, 3 2f 7/J M
- 0-) and Actuation Relays ,/
- c. Containment Pressure-High-2 3 2 ,' 2 1, 2, 3 l'[Jl k#2.lSteamLinePressure-Low 3/ steam line 2/steamline/ 2/steamline 1, '2, 3' f 24 K/L!
%gg -((above P-11)) any steam 11,ne ,"
M rAx5 team Line Pressure-Negative 3/ steam line 2/ steam 1 1he any steam $1ne 2 team line j - )f. o/Pl g g g Rate-High((below P-11))
- 5. Turbine Trip & Feedwater '
I= b k 6}) Isolatton 4) ,
- a. Automatic Actuation Logic 2 1 2 1, 2,) ,2( 'l/J and Actuation Relays
- b. Steam Generator Water Level- 4/sta. gen. 2/s m. gen. In 3/sta. gen. In 1 J9' f f3 High-High (P-14) ariy operating each operatt j s,tm. gen. stm. gen. \
- c. Safety Injection See Itea 1. above for all Safety Injection initiating functions and requirement.s.
r-F Y e BRAIDWOOD - UNITS 1 & 2 3/4 3-17 ANENOMENT NO. 44
- - - - - - - - - . - - - , - , - - - - - - - - _ _ _ _ - - - - - - _ _ - - _ _ _ _ _ _ _ - - _ _ - - - - _ _ - _ - _ _ . - - - - - - - - - _ - == + --
_ ._.__..-.._m - - _.. _ _ . . . . _ _ _ . . _ . . ~ _ . . _ . _ . _ _ _ . _ - ~ - _ _ . . . - _ . _ . . . . . - _ .._-._. _ O O O 33.2-I '
, TABLE 3.0 3-(Continued)
=
E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (l re I m h .- - MINIMUM
, ,, - " " "a HANNELS CHANNELS APPLICA8LE
! FUNCTIONAL UNIT (9F CHANNELS TRIP OPERABLE MDOES ACTION Cord d 6. Auxiliary Feedwater k
~
\-- - - ~ ~ ~ r e --
e- .. . . e ,. ' u, _. ,. ,u, ._ , , . . (. c 1 7 ._ 1.7 . 3. - - - _. 22. m a. A Automatic Actuation Logic and Actuation Relays 2 T~
~ ~ ~
2 1, 2, 3 Af I/J b .e. Stm. Gen. Water Level- ' Low-Low
- Start Moto '
Driven P 4/sta. gen. 2/sta, n. 3[im. s gen. 1, 2, 3 g F/3 w in any era- i each A ting sta gen. rating i - w ._ to. gen. W 2) Start Die 1-Driven Pump 4/sta. gen. 2/sta. gen. 3/sta. gen. ' 1, 2, 3 g flJ , in any in each !
. operating operating sim. gen. sim. gen. !
t i Undervoltage - RCP 4-1/ bus X-e .C Bus t MotoF 's 2 3 1, 2 Qil l i Hven.P nd 1 0 ElesEl-Driven i
- c. x. Safety In.lection -
k T4t 8-- See Item 1. above for all Safety Injection initiating functions and ! g m h p .:rt S t;r Dr k::d Dir c' "Thenrequirements. Qj}
/
( 5 dE W(Dittion21forision11forUnity]2) '
= it ,-.
. I ESF Bus r tage- Le O ,
w i Start Mo - iven - 0
" Pum ( art as li g )),G sequencing) (
2 2 2 1,2,3 - J5er F/J ,'" i g Lc56 et OfQrte Dese_e . t
~vo E o.
- O 33.2-l
. TABLE .: 3-(Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION Required as e 42 \ MINIMUM T0!n ;;;. $1ANNELS CHANNE APPLICABLE FUNCTIONAL UNIT . WFCHANNELS . 11 TRIP OP F BEDES ACTION fond _
- 6. Auxillary Feedwater (Continued) .
fg. Auxiliary Feedwater Pump 1/ Train 1/Tr in I rain 1, 2, 3 ,15er M/4l Suction Pressure-Low ( E::::ti:1 8 (.ITr:::f:rt:
- 7. Automatic Opening of Containment Sump Suction Isolation Valves ,
- a. Automatic Actuation Lo'ic g 2 1 2 1, 2, 3, 4
.14' k6 I and Actuation Re, lays
/
- b. RWST Level - Low-tow 4 2 / 3 1, 2, 3, 4 )!r b)El -
Coincident With Safety '
- Injection See Item 1. above for Safety Injection initiating functions and !
requirements. , ' Co73 5 A: Loss of Power g 3,,,,g ;
- a. ESF Bus Undervoltage 2/ Bus / Bus 2/8 1, 2, 3, 4 g A/BfC i
- b. Grid Degraded Voltage A/8/C, 2/ Bus 2/ Bus 2/ Bus , 1, 2, 3, 4 J5tr f
i r- r i BRAIDWOOD - UNITS 1 & 2 3/4 3-19 AMENDMENT NO. 44 8g 9?.9* ;
"3 i 4
~
y O . O O 331-1 1ABLE -h+4- (Continued) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL No. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
~
- 9. Engineered Safety Feptures
/
Actuation Syster In erlocks ,/ ,/ / ' l 2l
# # i 20 a.
b Pressurizer Pr ssure, P-Il Re nior Trip, P-4 3 4-2/ Train l 2/ Train l 2 2'/ Train i , 2, 3 1, 2, 3 2'2
. Low-Low T P-12 4 2 3 1, 2, 3 jo'h i
o S 9 Y BRAIDWOOD - UNITS 1 & 2 3/4 3-20 AMENOMENT NO. 44 w
. a
{ . L.co 3 4.1. j 3.3.1-1 Lco 3.3 t. TABLE 5:3 4 fContinued) Q.
- TABLE NOTATIONS -
~
Fodde(d Wrip' function may be blocked in this MODE below the P-11 (Pressurizer
, Pressure Interlock) Setpr.t. ,
binole64 ~NTrip function automatically blocked above P-11 and may be blocked below F-11
- when-Safety Injection on low steam line pressure is not blocked.
~
l _. ACTION STATEMENTS - . l- ' 8A C.I i---frggT 5.3- 2i A S(h i RAQ.'l(ACT:=j- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inopera>10 channel to ! OPEtABLE status within 6 hours. lor be ia at least 40" STANDBY \ 1 witsin the next 6 hours and in COLD SHUTDOWN within the followinh condE.f30 hours:1 however, one channel may be bypassed for up to 4 hours . (for surveillance testing per Specification 4.3.2.1, provided the
- CondC Metother channel is ERABLE. - '
- #A D.) ' cissen 3 5- 2i s l RAD.2. (A;T = I!)- With the number o ERABLE channels one less than the Total M 4 ""=8=r of rhnnels.foperation may proceed until performance pf) f
! Ithe next reautred ANALOG CHANNEL OPERATIONAL TEST orovideddie. inoperable channel is placed in the tripped condition within 6 l j Q . Cond C) Note; hours. %sCM 3.3 Al6 M
.' CoNiM 'ACT:= %)- With the number of OPERABLE channels one less than the Total l QL7 -(astr M-zickNumber of Channels,Mdeclare the associated pump INOPERABLE and j Cc*i N H take the A ION 1 red by Specification 3.7.1.2.
i RA 6.l : %segt 53-2: 0 (wwn (o wd, L l PAG.2 {ACT = 10]- With the n ro PERABLE channels one less than the Total bd 'I , Number of Channels A operation may proceed providedithe inoperable
' channel is alaced in the bypassed conditio.m....
'Cr.;; : t 0" ;""."' ! ;;;t . .; 0 : ;;.; One additional channel 'Raf
. . . . . . . . . , Q bd6Me be bypassed for up to 4 hours for surveillance testing per l j Specification 4.3.2.1.
l LC03'3%A;T 3 :D- With less than the Minimum Channels OPERABLE requirement, l operation may continue provided the containment purge supply and ftA614--GNse.RT 3 3 2: u
+"r ves are maintained closed.
)
- 8AB.1 - With the r of OPERABLE channels one less than the Minimum
! Channels OPERABLE requirement, restore the inoperable channel to j OPERABLE states within 48 hours /or De in at least HOT STANDBY \
'within the next 6 hours and in COLD SHUTDOWN within the following\
i ftM.P RA bf.nd C
,30 hours.>
4 RAo. fete udf'Lnwg1 53-zis q i pg,yn,,,;,fMff6 IRE- With the'1(umber of OPERABLE channels one less than the Total 1 Number of Channels./STARTUP and/or POWER OPERATION may proceed \ l n U 2) RAG.2Cond 3 ; I7' Drovided the followina conditions are satisfied: f l
.) ,
# CondL', .
Ca c a ? ,Co e d R b l BRAIDWOOD - UNITS 1 & 2 3/4 3-21 AMENDMENT NO. 44 1 l
i Q' CTS INSERT (S) SECTION 3.3 : LCO 3.3.2 l
- l. INSERT 3.3 21A ' (A3 ) l' l I l 1 l CONDITION REQUIRED ACTION COMPLETION TIME C. As required by C.1 Restore one train to I hour from :
Recuired Action A.1 OPERABLE status % en discovery of l anc referenced by .two trains on the two inoperable t Table 3.3.2-1. same Function are trains on the ! inoperable. same Function AND ! C.2 ... ! O ! J ! .O Revision A
, -- a I
I ! 1 : i l I i Q CTS INSERT (S) SECTION 3.3 i l LCO 3.3.2 !
- INSERT 3.3 21B (A3 and L ) .j J- !
! CONDITION REQUIRED ACTION- COMPLETION TIME ; 2 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 - to 4 hours for surveillance testing l ! provided actuation-- ; capability is , maintained. ; 4 , i Restore all but one 1 hour from . 'i
- channel to OPERABLE discovery of l status when two or two. inoperable j O- more channels on the same Function are channels on the same Function i
inoperable.
~
! 6@ D.2 ... I 1 j 4 Revision A i I i
l O CTS INSERT (S) SECTION 3.3 l- LCO 3.3.2 4 INSERT 3.3 21C (L,) li CONDITION REQUIRED ACTION COMPLETION. TIME M. As required by M.1 Res' tore channel (s) of 1 hour from i Required Action A.1 one train to OPERABLE discovery of and referenced by status when both inoperable Table 3.3.2-1. trains on the same channels on i Function have both trains j inoperable channels. within the same Function 8!iD M.2 Restore channel to 48 hours OPERABLE status. O 1 l l I O Revision A i
i
- 1
.O CTS INSERT (S)
SECTION 3.3 LCO 3.3.2 INSERT 3.3 21D (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME l. 1 G. As required by G.1 NOTE Required Action A.1 Performance of i and referenced by Required Action G.1 i 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 O more channels on the same Function are channels on the same Function inoperable. 4 Alf G.2 ... i l l l 1 1 i i J
. j Revision A 4
- , . ~ . .. - . - , ., ..- a ,,, . ,
, 4 O- CTS INSERT (S) SECTION 3.3 LCO 3.3.2-INSERT 3.3 21E (Au ) CONDITION REQUIRED ACTION COMPLETION TIME B. As required by B.1 Restore all but one 1 hour from Required Action A.1 channel to OPERABLE discovery of and referenced by status when both two inoperable Table 3.3.2-1. channels on the same channels on the Function are same Function inoperable. 8!iQ B.2 ... O 1 4 O Revision A
I l O- cts instaT(s) SECTION 3.3 LCO 3.3.2 INSERT 3.3 21F (A3 ) ! CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 NOTE Required Action A.1 Performance of ;
.and referenced by Required Action F.1 '
Table 3.3.2-1. may be delayed for up t to 4 hours for , surveillance testing provided actuation : capability is ! maintained. ; Restore all but one 1 nour from channel to OPERABLE discovery of status when two or two inoperable . O more channeis on the same Function are cnannels on the same Function inoperable. MD F.2 ... i t l lO Revision A
... .= ..~-- - - . . . _.- - . _ - . . _- - . ..
1 D V CTS INSERT (S) SECTION 3.3 LCO 3.3.2 INSERT 3.3 21F (continued)(A) CONDITION REQUIRED ACTION COMPLETION TIME
~K. As required by K.1 NOTE Recuired Action A.1. Performance of-anc 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.
Restore all but one 1 hour from channel to OPERABLE discovery of status when two or two inoperable O more channels on the same Function are channels on the same Function inoperable. AND K.2 ... O , Revision A
O- CTS INSERT (S) SECTION 3.3 LCO 3.3.2 INSERT 3.3-21F (continued) (Au) CONDITION REQUIRED ACTION COMPLETION TIME
- 0. As required by 0.1 NOTE 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 O more channels on the same Function are channels on the sa:ne Function inoperable. AliD 0.2 ... O Revision A
- l 1
a O CTS INSERT (S) SECTION 3.3 , LCO 3.3.2 ! l I F RT 3.3 21F (continued) (A3 ) [ , t 4 t CONDITION REQUIRED ACTION COMPLETION TIME l j _ O. As required by 0.1 . NOTE i d Required Action A.1 Performance of and referent.ed by Required Action 0.1 Table 3.3.2-1. may be delayed for up , to 4 nours for surveillance testing
- provided actuation
{ capability is maintained. 1 Restore all but one 1 hour from j channel to OPERABLE discovery of status when two or two inoperable l O more channels on the same Function are channels on the same Function 1 l inoperable. AND l 0.2 ... . i , 'l i i 1 i i I O 4 Revision A i
k , l J
- l I LCD 3 3,5 1 3.2.2-1 g 3,3,2 TABLE G (Continued) i ACTION STATEMENTS (Continued) s .
l pl The inoperable channel is placed in the tripped condition within 6 hours, and 4 Cond F t40tc.) y. The Minimum Channels OPERABLE requirement is met;'however, l j cond gtJote; the inoperable channel may be bypassed for up to 4 hours i ; ! Cond 0 idoit ; for surveillance testing of q}her channels per Specification con 4 E dott 4.3.2.1. l ,
- ACT 20 - Wi less t n the Mi mun Numbe of.Chann s OPERABL , within
- - r date ne.by obs rvation o the assoc ated pera sive }
{ nunciat window (s that the nterlock in its quired s te g4 I i l . for the e sting p1 t conditi n, or app Specific tion 3.0. . I RAI.I 4--4TusERT L5-22A i ggI,1 mur: n 1- with the r of OPERABLE Channels one less than the Minimum i Channels OPERABLE requirement, restore the inoperable channel to i .0PERABLE status within 6 hours, for be in at least HOT STANDBY \ i Cord 3', 'within the next 6 hours and in at least HOT SHUTDOWN within the\
- followina 6 hours
- newever one enannei may ne nypassed for up to l
CO g g d 4 (hours nrovided t for surveillance testing per Specification 4.3.2.1 her channel is OPERABLE. }. (4A H.l( rInwR.T 5.5- 12 e> l gA g,2. !ACT!:"! S - With the n r of OPERABLE channels one less than the Total
- r^s .
Number of Channels, restore the ' inoperable channel to OPERABLE i () status within 48 hours /or be in at least NOT STANDBY within 6 \ l Cond J4--ihours and in at least HOT SHUTDOWN within the following 6- hours). ' > ACT DN 23 - 64th the n r of OPE BLE chann s one les( than the otal j umber of C nnels, r tore the operable tannel to PERABLE status with 4B hour or decla the asso ated valv inoperal; e lam i
- \ and take t ACTION equired by pecificat n 3.7.1.5 /
4 RAI.1 < !rasen w5e ,, i RAI.1 : ==: a ;- witn the r of OPERABLE channels one less than the Minimum i Channels OPERABLE requirement, restore the inoperable channel to l OPERABLE status within 6 hours, for be in at least HOT STANDBY A. L 0.ord < 'within the next 6 hours;fhowever, one channel may be bypassed for l CondTtdo4{ up to 4 nours for surveillance testing per Specification 4.3.2.1 LCo 3 3.5 Cond 4 (provided the other channel is OPERABLE. !
!ACT::"' 25}- p: With the number of OPERABLE channels one less than the Minimum t e o g,g,g g na gg/g ,' Number of Channels.ISTARTUP and/or POWER OPERATION may proceedl j .
lorovidedithe inoperable channel is placed in the tripped i L co s,1,2. Coq p/7 condition within.I hour. The inoperable channel may be . bypassed for up to 2 hours for surveillance testing of the 9 j OPERABLE channel per Specification 4.3.2.1. %, g.,, m,
- j. LCo 3.3 5 Cond A X With the number of OPERABLE channels one less than the Minimum 2 - Numher of Channels.(S"ARTUP and/or POWER OPERATION may oroceed LCO 3 3.5 Cm:lfh brovided ithe inoperable channel is placed in the tripped O condition within i hour. -
I ,) ' BRAIDWOOD - UNITS 1 & 2 3/4 3-22 AP.ENDMENT NO. 44 4 a -
r \ .
-Q CTS INSERT (S)
SECTION 3.3 i LCO 3.3.2- i l INSERT 3.3 22A (A35) ' l CONDITION REQUIRED ACTION COMPLETION TIME l 1 j I. As required by I.1 Restore one train to l' hour from i Recuired Action A.1 OPERABLE status when discovery of- ! anc referenced by two trains on the two inoperable , Table 3.3.2-1. same Function are trains on the I inoperable. same Funct1on AND i i 1.2 ... ! I l i O INSERT 3.3 228 (A33) j CONDITION REQUIRED ACTION COMPLETION TIME H. -As required by . H.1 Restore all but one 1 hour from Required Action A.1 channel to OPERABLE discovery of and referenced by status when two or two inoperable Table 3.3.2-1. more channels on the channels on the same Function are same Function inoperable. hE H.2 ... l l O i Revision A 7 .. _ _ . , . , _ . _ _ w. . _ . - -
.O - CTS INSERT (S) SECTION 3.3 LC0 3.3.5- 'i INSERT 3.3 22C (L,) l l CONDITION REQUIRED ACTION COMPLETION. TIME l B. One or more Functions- B.1 Restore one channel - I hour i with two channels on for tt' Function on one or more buses the affected bus to ; inoperable. OPERABLE status. i 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 t O instrumentation. l P 3
+
1 W e O ; Revision A l
.. -. - - - - - - . . ~ . . . . - . .. - - - - . - -
O O O . 3 '5.2 - I
, TABLE-0.0 " -
C
~ ENGINEERED !!/ETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 5 i g ,
TRIP ALLOWABLE
, FUNCTIONAL UNIT SETPOINT VALUE i
! 1. Safety Injection g (Reactor Trip, Feedwater !
y Isolation, Start Diesel _
,, Generators, Containment .
. Cooling Fans, Control ,
Room Isolation, Phase "A" . Isolation, Turbine Trip, Auxiliary,Feedwater, Containment Vent Isolation and Essential ! Service Water) 4
$ a. Manual Initiation . N.A. N.A.
T b. Automatic Actuation N.A. N.A. ! O Logic and Actuation Relays j [ , [
- c. Containment Pressure- .
l High-1 5 3. sig i 4.6 psig ,
- d. Pressurizer Pressure- i Low (Above P-11) 1 29 ig 1 1813 psig
- e. Steam Line Pressure-
- i Low (Above P-11) 1 40 ps 1 614 psig* [
= 2. Containment Spray -
l
$ a. Manual Initiation .A. N.A.
3 I 5
- b. Automatic Actuation I r- l 2 Logic and Actuation $ !
O ' Relays N.A. M.A. w ! J \
- c. Containment Pressure- \ p High-3 Q 20.0 psig JS21.2psig l
-- a..
O O O -
- 3. 3. 2 - i
, TABLE t 3-t (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS f o
, FUNCTIONAL UNIT g- TRIP SETPOINT ALLOWABLE VALUE I
l , h 3. Containment Isolation d a. Phase "A" Isolation g 1) Manual Initiation N.A. N.A.
- 2) Automatic Actuatio'n
[ 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 "8" Isolation ; s N.A. N.A.
- 1) Manual Initiation
@ 2) Automatic Actuation N.A. N.A. ,
Logic and Actuation Relays
- 3) Containment .
Pressure-High-3 $ 0,0 sig i 21.2 psig
- LCO3 34 s. Containment Vent '
Isolation , J E Automatic Actuation (2 Logic and Actuation Relays N.A. N.A. ku I E Manual Phase "A" N.A. N.A. ! [ Isolation Z J7 Manual Phase "B" N.A. N.A. Eb oO O Isolation Ww l 5A) SafetyInjection See Item 1 above for all Safety Injection Trip Setpoints MS ! and Allowable Values. rJg
O 33.z.,O O . TABLE -3.3 " Wontinued) . 4 . ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
~
E TRIP ALLOWABLE-
- g. SETPOINT VALUE g FUNCTIONAL UNIT e
, 4. Steam Line Iso' J. ion ,_
N.A. M.A. ! a. Manual Initiation N b. Automatic Actuation Logic and Actuation N
- Relays .A. N.A.
- c. Containment Pressure-
.2 psi 19.4 psig High-2 d.) .d: Steam Line Pressure-
> 0 ps g*i
>614 psig*
Low (Above P-11) ' d 2.e: Steam Line Pressure , Negative Rate-High w (Below P-11) il si**' 1165.3 psi **
)
y 5. Turbine Trip and y Feedwater Isolation
- a. Automatic Actuation Logic and Actuation Relays N. . N.A.
- b. Steam Generator Water Level-High-High (P-14)
- 1) Unit 1 81.4% f <83.4% of
_W Lg arrow ange l instr it ins span n g 47
<78.1% ( t:1e 6,,.,,._s.,...,,,, "3 2) Unit 2 3); <80. <sz.syft : : " - >
3 of 5 narrow ra instrument r-span 8 . O .tn N
O 3.u_, 0 O TABLE 3.3 ' Antinuid) - ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP S TPOINTS I b TRIP ' ALLOWABLE SETPOINT VALUE o FUNCTIONAL UNIT L ' 7 5. Turbine Trip and Feedwater Isolation (continued)
- c. Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and i
< m Allowable Values.
",, 6. Auxiliary Feedwater .
"k. [ " A. _j
[e. "e.. eel h ii h t h , aK Automatic Actuation Logic and Actuation Relays N.A. M.A. bg Steam Generator Water - Level-Low-Low-Start Motor-Driven Pump and
$ Diesel-Driven Pump k 1) Unit 1 >33. of >31.0% of L_g-nar ange ow ins r nt inst t spp
- 2) Unit 2 > % (Cy le Q15. 5 : .e' e =,P., Ar
>36. >34. ,07 3( yc
; Te 4 nd .
i ter) of Ma rA arrow ra le ' inst nt-nstrument 's a span g z E e .df Undervoltage-RCP Bus- >5268 vol s ->4920 volts y Start Motor Driven Pump and Diesel-Driven Pump o r (, pf Safety Injection-C Start Motor- 8 Driven Pump and See Item 1. above for all Safety Injection Trip Setpoints and u Diesel-Driven Pump Allowable Values. 9 b8
f-
.. O .
O o
- 3. 3.1 - I ,
TABLE 9-4 (Continued) as 5 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS g TRIP ALLOWABLE SETPOINT VALUE
, FUNCTIONAL UNIT Auxiliary Feedwater (Continued) N E 6. 7 d Lee MMw_ 7,aer-ol % v sion on11 21 for for Unity) g ,, (D 12 m ESF Bus tage-Start -
en 287 vo ts 2730 volts P f.g: Auxiliary Feedwater Pump Suction Pressure-Low (Transfer to w Essential Service vac " Hg vac Water) 1.2
}
T U 7. Automatic Opening of Containment Sump Suction Isolation Valves Automatic Actuation N. A. N.A. a. Logic and Actuation Relays i
- b. RWST Level-Low-Low Coincident with
/ 46.7% 44 4.7 %
Safety Injection See Item 1. above for Safety Injection Trip 5etpoints and Allowable Values. g B' B
'+ ,
- o. F S
v W 08
O Ta8tt 3.3- Ontinuedl ENGINEERED SAFETY FEATURES ACTUATION .4 TEM INSTRUMENTATION TRIP SETPOINTS O- i TRIP ALLOWA8tE FUNCTIONAL UNIT SEIPOINT VALUE ,
~ '
SR335k Loss of Power
- a. ESF Bus Undervoltage 2 0 volt! 2 0 volts w/ 8s d 'ay w/sl. del
- b. Grid Degraded 3804 vo s 1372 Its @
Voltage w/31 lay 0 i 30s de _
^
9 Ineered Safety FealiiM4 tuation f-System Inte a. P-Il s Pressurizer Pressu s 93JLpsig
/'/
$1936 psig
.e ,
- b. Reactor Trip, P-4
./ .A. M.A.
- c. Low-low T,,, P-12 ,.7"\ 2550*F 2 547.2*F',1 546.9'F**
-l
- d. Steam Generato ate 5.b. above for all SteamEe'PaterJater Level Trip '
Leve Setpoints and Allowable Values. - i p M h-High) '
~. '
... t
^
r- N ________ - .~ - - - . - - . - - h <
**pp11 table io Unii i nd Uiitt-2 tmitWietten-of -cyc4e-5. ,.
Q' g 14 ta .
** Applicable te Un!t ! :nd Unit-2-start ing-with-eyele-6r i I 68 fd i
I FM BRAIDWOOD - UNITS I & 2 3/4 3-28 AMENOMENT NO. 66
_ _ . _ ___ ..- . . . ._. . . _ _ _ _ _ _ _ . ~ . . . _ _ _ _ _ . _ . _ . _ _ _ _ . . . _ _ . _ _ _ . . _ . _ . . i
, s Lco 3.5 2, l ,
TA8LE 3.3-4 (continued)
,,/ TABLE NOTATIONS l
l Mete (b)41me constants utilized in the lead-lag controller for Staas Line Pressure-Low are T, > $0 seconds and t. < 5 seconds. /r"":'. E^'- "am" c'en e ce e 1 6 l {t'rt t':n " r ::::- rt: 2 ; d' :' " '- : 2 :: h n. I FEMC) **The time constant utilized in the rate-lag controller for Steam Line Pressure . m,- L Ou^^ e4 Neoative Rata - Minh .is. armatar than no =aa=1 tn 50 seconds. i _m_,. .u_ _ _ _ . _ _ .m_. .,______...,,m....a .. ,,,,3.. 1 e i d ( a 4 t e O... ,.) ( - i i. f 4 i 4 O. . R ' BRAIDWOOD - UNITS 1 & 2 3/4 3-29
, 1 Sec% 33 p
p-
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, BRAIDWOOD - UNITS 1 & 2 3/4 3-30 AMENDMEllT NO.12 d 9
$ m (p 4A 4ea h,4 ear . mwd 44M+_,ey.A& M -sw6Ss4 . 44 e4 Aor 4 ,4d hW.aA,.A4 ,ssNh4MJp.e e . A 5hde-em44.&,AJ.4weaA w A , m .a# ._42.4@4 eA4&64 4.J 4 abe 4 6 _d-._wp,g Q, e s[ mwae Aah.4Ah adJ 4.. # 4 d 4m.A.
1 I i 4 *i < ) . ~ Sectb 3 3 l 9 k 1 , 9 9_ r *
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s O BRAIDWOOD - UNITS-1 & 2 3/4 3-31 AMENDMENT NO. 12
. ,- . . . . . . . . ~ . . . + . . . ~ . . - . . - . - . . . . . - - - - . , , . . _ , _ - . , . _
1
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s_-........., 1 ! /, TLI T C Tantr t..r u..ny
.. n..e.yj en s z
9 = $ ./
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Q '\, BRAIDWOOD - UrtITS I & 2 3/4 3-32 AMENDMENT $0.12
4 ( 4* *
.... e ,
O
* ,_,ir__.,_.._n
- -- m m ---
s- --...---, 4 i (Tute Tantr te unv neens 't
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cO - 2 BRAIDWOOD - UNITS 1 & 2 3/4 3-33 AMENDMENT NO. 12 i i 3
O O O 93.1.- t 5, 9 mr .e y 4. (g 3,.6,- a h p, ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION
/ SURVEILLANCE REQUIRENENTS
\_ => S R 3.3'2.1 =~l }
C- g =-) qR 3 3.13 eb- g ANALOS TRIP AttunflWS IISES CNANNEL DEVICE ACfM fl65 MASTER SLAVE FOR WillCN CNANNEL CNANNEL OPERAfl0NAL OPERATIONAL LONIC NELAY RELAT SURVEILLANCE FUNCfl0NAL Ulitt C81ECIL __ Call 9tAflO4 1EST 1EST TEST E E 15 REWIRED _
- 1. Safety injectlen (Desctor felp, '
Feeduster feeletten, Stort 91eeet Generatore, Centeltenent Costirg Fene Centret Room feeletten, Phase "A" feeletten, furbine frlp, , Aunillery f eedseter, Centeltenent Vent f eeletten and Essentlet i Servlee Weter)
- e. Menuel inittetten N.A. N.A.
N.A. 9-R N.A. N.A. N.A. 1,2,3,4
- b. Autenette Actuellen Logle N.A. N.A. W.A. W.A. f/-fl(1) 3"-N(1) 7-9 1,2,3,4 and Actuotten Releye ,
- t. Centeltsment Pressure Nigh 1 1-9 lp-R 6-0 N.A. N.A. N.A. N.A. 1,2,3
- d. Preeevrlier Pressure Leu l- S 10-R 6-e N.A. N.A. N.A. N.A. 1,2,3 (Above P-11) ,
- e. Steese LIne Pressure-Lou l- S /p., a ge a N.A. N.A. ,N.A. N.A. 1,2,3 (Above F 11)
- 2. Contaltseent Sprey
- e. Nenuel Inittetten ll. A. N.A. N.A.
fR N.A. N.A. - N.A. 1,2,3,4
- b. Autenstle Actuellen Legle N.A. N.A. N.A. N.A. Y -N(1) Mp(1) '/-a 1, 2, 3, 4 and Actuetten Relays
/O R S-e
- c. Centeirament Pressure NIsh-3 1- S N.A. N.A. W.A. N.A. 1,2,3
- 3. Centalesment f eeletten .
- a. Phase "A" leeletlen
- 1) nonuel Inittetten N.A. N.A. N.A. T-R N.A. N.A. N.A. 1, 2, 3, 4 8
- 2) Autenette Actuetten M.A. N.A. N.A. N.A. *f-N(1) p p(1) '74 1,2,3,4 Logic and Actuetten teleys h
O 14
'I W
a BRAIDWOOD - UNITS 1 & 2 3/4 3-34 ANENDNENT NO. 44
O O O 3 5 L-1 TABLE -4r3-E- (Continued) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION , SURVEILLANCE REQUIREMENTS TRIP ANALOC ACTUAflNG MSES CNANNEL DEVICE ACTUATitNI MRSTER SLAVE ffNt initCR CNANNEL CNANNEL OPERATIONAL OPERAil0NAL LostC RELAY RELAT SURVEILLRNCE , FUNCTIONAL UNIT CNEtt . CALISNAfl0N TEST TEST TEST TEST _ Hil. It RENUIRED ; 3.0. Phase "A" leeletten teentinued)
- 3) Sofety injectlen See item 1. above for ett Safety injectlen Survelttence Regstrements.
- b. Phase "S" leetetten
- 1) penuel Inittetten N.A. N.A. N.A. i-- R N.A. W.A. R.A. 1, 2, 3, 4
- 2) Automette Actuation N.A. N.A. N.A. N.A. Y -M(1) [-M(1) ~7 6 1,2,3,4 Logic Actuellen teleye
- 3) Centelrument Proeeure. I- S /O- R [p- 0 N.A. N.A. N.A. N.A. 1,2,3 l Mish-3 I LCO 3 'de g Contalrument Vent leeletten Autountle Actuetten N.A. N.A. N.A. N.A. .3. 6.1. pggy g3,3.1,.3- nggy se,gge 1,2,3,4 3 _W Leste end Actuellen Releys j .Je Manuel Phase *A* See Item 3.e.1 above for ett manuel Phase "A" lootetten Survelllence Regstremente. .
teolation
- 2. M- wenuel Phese asa See item 3.b.1 above for ett sunuel Phase asa footetten Surveittence Regstremente.
leetetten [.A f Safety Injeetten See Itse 1. ebeve fee 911 Safety injection Survelltence Regstremente.
- 4. Steam Line testation
- e. Menuet Inittetten N.A. N.A. N.A. I" R N.A. N.A. N.A. 1, 2, 3
- b. Automelle Actuotten Lecle N.A. N.A. N.A. II . A. (-N(1) f N(1) 7-6 1,2,3 and Actuetten Releye ,
- c. Centelrunent Pressure Nigh-2 l- S /d' R dr* e N.A. N.A. N.A. N.A. 1, 2, 3 ck,l ,d' Steen Line Pressure-Lou l- S M*R (a - e N.A. N.A. N.A. N.A. 1,2,3 80l (Above P 11)
Id ; W . h 6' ' BRAIDif000 - UNITS I & 2 3/4 3-35 AMENDMENT No. 44 t
O O -O 3.32-1 TABLE-4-9-f (Continued) . ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVElllANCE REQUIREMENTS TRIP ANALOS ACTUATINS INNES CNANNEL DEVICE ACTURTitpl NASffR SLAVE Ftut lAlltN 1 CNANNEL CMANNEL OPERAll0NAL r#ERAfl0NAL LOBIC RELAT RELAY SURVEILLANCE FUNCfl0NAL UNIT CNECE CALIBRAf ttpl TEST TEST TEST ILII__ E IS REWIRED
- 4. Stees Line feeletten (contlemmi) d,2 p Steam Line Pressure - 1- S NR I-e N.A. N.A. N.A. N.A. 3 Negettve Rete - Nigh (Below l P-til
- 3. Turbine Trip and Feeduster feeletten
- e. Autemette Actuellen Legle N.A. N.A. N.A. N.A. Y -N(1) f- N(1) 7-5 1, 2 eral Actuetten Reley
- b. ,Stese senerater Water Levet- l- S @ -R 4-8 N.A. f-N(1) - S N(1) 7- N 1, 2 ,
Nigh-Nigh (P-14)
- e. Sofety injectlen See item 1. above for ett Safety injection Surve litance Reapsiremente.
- 4. Ateilttery Feeduster
- . n Mn444et?r N. A.+ -
N.A. N A. ...e ea m,g, g , m, ~j~'jIjT 41 M Automette Actuetten Logle N.A. N.A. N.A. N.A. T--M(1) 5* M(1) 7- N 1, 2, 3 ' and Actuation Relay , b pr Steen Generator voter Levet I- S JD-R gae N.A. N.A. N.A. W.A. 1,2,3 Low-Lew e .ht Undervettege RCP Bus N.A. b-R N.A. E-6(3) N.A. N.A. N.A. 1, 2 l *
- c. p: Sefet tess &y injntten0 % s06 Ver&Ods~
See Item 1. above for ett Sefaty inlectten turve'ltIenee Respalremente. dg Il for W ll. A. /d - R , N.A. 8-N(2,3). N.A. N.A. N.A. 1,2,3,4 j (Olvlel it 2) ESF . rvettene {g Atatillery Feeduster Ptsup l- S 88 - R 2- N N.A. N.A. N.A. W.A. 1,2,3 Suellen Pressure Lew
- w G t b
BRAIDWOOD - UNITS 1 & 2 . 3/4 3-36 AMENDMENT NO. 44
. _ _ . _ _ _ _ _ . _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . . _ . . _ _ _ . _ . _ . _ _ . _ _ . _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ ~ _ _ _ _ _ . _ _ _ _ _ . __ - ,.-m -
e new - -.w,_
O O O '
.3.3. Z 1
. TABLE 4+f- (Continued 1 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP !
ANALDG ACTUATING MWES CnANNEL DEVICE ACTUnil04 MASTER SLAVE Fet INilCN l CNANNEL CNANNEL OPERATIONAL OPERAtlONAL LOBIC RELAY RELAY SURVEILLANCE ! FUNC110NAL U41T CNECE _ CAllBRAfl0E TEST TEST TEST HEI._ IEH_ IS REGUIREN T. Automatic Opening of Contalenent Sump tuetten feeletten velves ,
- e. Automatic Actuetlen Legle N.A. N.A. N.A. N.A. k-R(1) 6- R(1) '/- t 1,2,3,4 and Actuetten Releye
- b. Rv5T Level-Low-Low l- 3 /O- R 4-4 N.A. N.A. N.A. N.A. 1, 2, 3, 4 telncident With Safety injectlen See Ites 1. above for all Sofety injectlen Surveillance Reg iremente
,Cr. Lees of Power
- o. ESF Bue Undervettese N.A. R-SR 3.3.T.1 N.A N(2, 3)-5+t 4 LS. 8 N.A. N.A. N.A. 1,2,3,4 ;
- b. trid Begraded Voltese N.A. R 'A *. 3. ". . L N.A. M(3)-SA k3.5 1 N.A. N.A. N.A. 1,2,3,4
~~ ~ ' ~~~~ " ~
- 9. E Ineered Safety Featur's l tuotten Systne in clocks +
. Pressurfter P escure, P 11 N.A. . N N. . N. . N. . N.A 1, 2, 3 1
. y J :
- b. Reseter Trl , P-4 N.A. .A. .A. R N h. N.A. N. . 1, 2, l 7
d.A. Il.A. 1,23 !
- e. Lev-Lee T , P.12 N.A. R S N.A. N.A.
. . . . _ _ _ _ . ___ _ _ . _ . _ ; __ _ . . i j
bb TABLE NOTATION ; W Each train shall be tested at least every days on a STAGGERED TEST BASIS. ; (27 Undervoltage relay operability is to be verified independently. An inoperable channel Niay be bypassed for up to 2 hours t for surveillance testing of the OPERABLE channel per Specification 4.3.2.1. I W Jetpoint veriffration is not applicable. R 3.3.5.l Nc3 t ) . l A 5. s. 2,5 tete >> It 3. 3. 2.8 Ocr+1' ,_ , wn i TC OO l
** ("
Leo 3QS RA A.I NOLL O 2.#.2 P A F.I t W 4 )' - SR 3. 3 2.1 MOTE e -1M5EET 3 3 - 37A BRAIDWOOD - UNITS I & 2 3/4 3-37 AMEN 0 MENT NO. 44
,= - .
l l
.l 1 l 1 - O- CTS INSERT (S) l SECTION 3.3 '
l LCO 3.3.2 ,. I INSERT 3.3 3/A ~ (Ap ) i i SURVEILLANCE FREQUENCY ,i i SR 3.3.2.9 NOTE ... 1 i Verification of setpoint not required for ~ 4 manual initiation functions. ,
- i 1
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Revision A r - . . , , - . - - - .m. 7
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! tco 3. 3.t. . ! Lc o 13 7 INSTRUMENTATION - C1/L 2 3 MONITORING INSTRUMENT 5 TION t- .
@IATIONMONITORINGFORPLANTOPERATIONS J.IMITING CONDI, TION FOR CPERATION l
3'34 kO331 I:F:34 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE M'th tMi *!a m.5 -f; Set;rint: eithin T LLO3.3,3 (*M 5pectf 4ed44a%
. APPLICABILITY: As shown in Table 3.3-6.
ACTION: monitoring channel Ala tpoint-ftr plant l operations excee ng n e 3.3-6, adjust the Setpoi n jt ton-t t wi lare the channel' 1 O perable. - c.-d A g. With one or more radiation monitoring channels for plant operations cw e inoperable, take the ACTION shown in Table 3.3-6. c.
! TS previsiers ef Speci*icatier 3.0.3 er: r.et ;;11::b1:. @
be dok -.- (mt:r .3.1 2 A - (t.co33') . l SURVEILLANCE REQUIREMENTS 68 )Je+c ( Uo 3 3.b e 1C0 3 3.7 ) - 4:dh2EE Each radiation monitoring instrumentation channel fnr plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3. lO BRAIDWOOD - UNITS 1 & 2 3/4 3-39 AMENDMENT NO. 38
O
\J CTS INSERT (S)
SECTION 3.3 LCO 3.3.6 INSERT 3.3 39A (6,) NOTE Separate Condition entry is allowed for each Function. i j N l l
- O Q -
O. .
, -TA8t4-8+6 C
RADIATION MDNITORING INSTRUNENTATION FOR PLANT OPERATIONS l:
\ CHANNELS /
hY9 iCHANNELSi APPLICA8LE ALARN/ TRIP
$ FUNCTIONAL UNIT \TO TRIP / ALAR 5 \0PERA86El M00ES
~ '
SETPOINT ACTION co J gLoo3.ss g X: Fuel Building Isolation- , Wr-
,, J ? 8-I criticallty
, Radioactivltp g a .":; High_a 2 _ g/_ f @ 1 2 * <5 mR/h / A/s Lcos 3 6
.t containment Isolation-Q 7ab* WContainment Radioactivity- 1N"U34 M *W High "
** A/8/c
~
T a)pntt_ J (IREyAItuu/1ZT 1 2 28' ' (byUnlV2 (2RE-AR011/12 LA" 1 2 **
.F A/a/c.
~~ ~ "- - ~ ~ ~ ~ ~
$ 3. . Gaseous Radioactivity- -
RCS Leakage Detection - - - ~ ~ T a) Unit 1 (1RE-PR0118) N.A. 1 1.2.3.4 N.A. 28 A4km 43* Sed *a34-8 b) Unit 2 (2RE-PR0118) N.A. I 1.2.3,4 N.A. 28 See Occ 4 N H Particulate Radioactivity-
- 4. l RCS Leakage Detection '
a) Unit 1 (1RE-PR011A) N. . I 1, 2, 3. 4 N.A. 28
. b) Unit 2 (2RE-PRO 11A) , _
N. . _ 1 1.2.3,4 N.A. 28
'"' W Main Control Room Isolation-T4hsa.y.I A.
Outside Air Intake-Gaseous - Red eactivity-Hf di _
- 4) " fain LA" 1 2 All < 2 mR/h M Als/cl o (b)/frain'A 8 (ORE-PR0338/348 (ORE 4R0318/328) 1 2 All 32mR/h JT A/B/FJ V(E 4 r-n n on 0 000 .
LA7
. MM" A %Y Y g q@1C G
- - . _ . - - _ _ . - - - - _ . _ . - . . . _----._.-.----__.__.------.-_._.-.--n_--__ . - . - -
-w .- --,n- r, w an n-.,- - n . , - , - - --n-w. - - --
b i
.. 1 l-i i
O' cts rascaT(s) SECTION 3.3 i 1 r LCO 3.3.6 ) 4 : i INSERT 3.3 40A (La) 'i I ! 1. 2. 3. 4. (a) When Item C.2 of LC0 3.9.4 is required. 1 i i-l~ 4 i t-l- 4 i i l 4 O i . 3-i 1 i 4 i ! . I 3 e. i-4 a ,1
- t. :
i 1 i
- s. -
O . Revision A l
O O . 03 ,
. TA8LE 3.3-6 C ~ RADIATION MDNITORING INSTRUMENTATION FOR PLANT OPERATIONS Y NINIMUM CHANNELS CHANNELS APPLICABLE ALANN/ TRIP w
FUNCTIONAL UNIT TO TRIP / ALARM OPERA 8LE -MDOES SETPOINT ACTION [ 1. Fuel Building Isolation-
,, Radioactivity-High and fA u,,mJ :,4t u Criticality (ORE-AR055/56) 1 2
- u <5 mR/h 29 q g % g.,
t=
- 2. Containment Isolation-Containment Radioactivity-Nigh ;
1 2 ** 25 a) Unit 1 (1RE-AR011/12) All b) Unit 2 (2RE-AR011/12) . 1 2 All 26
$ eo.3 ~. Gaseous Radioactivity-
.RCS__Leakaan netmettaa m
'{tJ.4.tS"' ) t jt i gg;7;;;;g}l [g 27 N.A. 1, 2. 3. 4 N.A. 28 N 8 o y) Wit 21,fRE-PR9HB) ; N.A. 1, 2. 3. 4 N.A. 28
- 4. Particulate Radioactivity- L,,
Lc4 M'8@ RCS Lemk- Detection _:) Wit-1 N.A. (100 = 11A) '
~
- 1. 2. 3. 4 N.A. 28
. ;b)-Unit 2 ( OC O 1M) ; M.A. 1, 2. 3. 4 N.A. N
- 5. Malr: Control Room isolation- pr Out41de Air Intake-Gaseous -
ooO Padioactivity-Hi &u a)TrainA(0REpR0318/328)
! 1 2 All < 2 mR/h 27 gp L b) Train 8 (ORE-PR0335/348) 1 2 All ?2mR/h 27 s3 ,k _A-_ '
h
.,- [A4&eess,J se u;. 2.3. $gg{
isee het A*r ' >
. b* '"
e em ;
-l l
i LCO 3.h Q Lc 0 3. 3.~) Lcn .U s TABLE NOTATIONS t.c.o 3,4 35- {N"T 3(3-" o % _ f 1.4. . .=.1.m.. m =-. .. f ml.s
** 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 or vent the Setpoint value may be increased Asp twice . maxi concen a' in the tainse ned'by e analys perfo d- I
/tJ. on activ1 in - - g.,O data val does) prior to ch role ge Tab 1 4.11-2 rovided !
inot exc d 105 of eeubentli ts of cific ion 3. .1.alin accord- i
, ance with the methodology and parameters in the DDEN.
ACTION STATEMENTS l 'I.NSEKT 3.3 414 [, ' Leo 3.3.4 g dEffpFi!E) - Wit 7hss than-the Minimum Channels 0PiiiABLEleq'uirementmEtTon C.ad A ,.C..J B i may continue provided the.conta,inment purge valves' are ' - maintained Coad C. (c1Dsed ~)
# 3#= n= m -
With the number of OPERABLE channels less than the Minimum CW A / Ceed 8 Channels 0PERA8LE 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
.J0/0/E) or isolate the Control Roon Ventilation System and initiate <
bsem.r 3.3-41B}- operation of the Control Room Make-up Systan. (Restors .thF rs to 0PERABLE status withifr-3(FHays or submit i
/Inoper w r m ,.s w i f,.. 3 &. T a Special Report M*
W:-desion ~ pursuant
~
ng 30 day'i'Tn.;. FFtoidti. Specification - 6, s. 4,,, s +J g.9.2 Jtability_and.1ht_ plans for_. restor _ation. the cause of f4g _, TION 28 - MustsatisfytheACTIONrequirementforSpecification3.4.6.1.[ tco3.3.8 A m 0N:29 With the number of OPERABLE channels one less than the Minimus Channels OPERABLE reautrement, FACTION a. of Specification 3.9.12\ ~ buil_be_ satisfied. )With both channels inoperable.Jprueit.; ;; v ep-?ste pe-+ ^1: :: tier = reiter dth the ^1er; Set = 2' i Sintinth '=1 ;xi ;r;;lwith one FueLHandl_ing Budding Exhaust filter plenum in operation. @therwise satisfy ACTION b.'
! of Specification 3.9.12. T
" i StC C o!' e s p o. O s'n N W k-@
e4 Lco act.1 l l l l O . BRAIDWOOD - UNITS 1 & 2 3/4 3-41 AMENDMENT NO. 37
t
.{
i (~~) CTS INSERT (S) v SECTION 3.3 )i LCO 3.3.6 j INSERT 3.3 41A (Lu) l l CONDITION . REQUIRED ACTION COMPLETION TIME ) l A. One radiation A.1 Restore the affected 4 hours monitoring channel channel to OPERABLE inoperable. status. B. NOTE B.1 Enter applicable Immediately Only applicable in Conditions and i MODE 1. 2. 3 or 4. Required Actions of ! LCO 3.6.3.
" Containment -
One or more automatic Isolation Valves." actuation trains for containment purge inoperable. valves made inoperable by
@ isolation instrumentation.
Two radiation i monitoring channels inoperable.
@ l Required Action and associated Completion Time of Condition A not met.
l l O
- Revision A
O 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 Irmediately Only applicable when containment purge Item C.2 of LC0 3.9.4 valves in the closed is required. position. Two radiation monitoring channels C.2 Enter applicable Immediately inoperable. Conditions and Re utred Actions of 08 LC 3.9.4.
" Containment Required Action and Penetrations." for associated Completion containment purge O T =e of coadit oa ^
not met. va'ves made ino erable by iso ation instrumentation. O Revision A
O- CTS INSERT (S) SECTION 3.3 LCO 3.3.7 l INSERT 3.3 418 (M3 ) l i 1 CONDITION REQUIRED ACTION COMPLETION TIME I l C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion j Time of Condition A 6HD ! or B not met in i MODE 1. 2. 3. or 4. C.2 Be in MODE 5. 36 hours ; i l i CONDITION REQUIRED ACTION COMPLETION TIME i O :l D. Required Action and D.1 Suspend movement of Immediately ; associated Completion irradiated fuel i Time of Condition A assemblies. ; or B not met during ! movement of irradiated , fuel assemblies. l i
'0 l Revision A
I > l : O cts instar (s) SECTION 3.3 - 1 LCO 3.3.7 ! L l INSERT 3.3 41B (continued) (M3 ) . j CONDITION I REQUIRED ACTION COMPLETION. TIME ,; I E. Required Action and E.1 SusbandCORE Immediately [ associated Completion ALTERATIONS. : Time of Condition A or B not met in MODE 5 AND i or 6. : E.2 Initiate action to Immediately ! restore one VC . Filtoation System i train to OPERABLE : 1 status. 't j O 1 i t I O Revision A
-.. - . . - - . . - _ - - - _ ~ . - - - . . - _ . . . . - - - . - . . . . . _ . ...- - - .... .
L l
.- 3 i
t n U CTS INSERT (S) SECTION 3.3 i i LCO 3.3.8 l 1 INSERT 3.3-41C (Ls_and i LA3 )- i l (a) During movement of irradiated fuel assemblies in the fuel handling ! l building. i ! (b) During. movement of irradiated fuel assemblies in the containment with the equipment hatch not-intact.' ; (c) During CORE ALTERATIONS with the equipment hatch not intact. , I \ i l
.i
( L i
-i r
I l f
- I O
Revision A
_ . = - - .
"93.4.6
. .IAdeesied k See A '3.3 Sece, . 3 t TABLE N01AT10NS see hoc,4,e se,rl~ 3.]
O With new fuei or tradiated fusi in the fusi stora.e areas or fusi suiidin,.
** Trip Setpoint h. to be established such that the actual submersion dose rate would not exceed 10 mR/hr in the containment building. For containment purge 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-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 00CM.
ACTION STATEMENTS 1 ACTION 26 - With less than the Minimum Channels OPERABLE requirement,' operation may continue provided the conta,inment purge valves are maintained closed. ,
- ACTION 27 -
With the number of OPERABLE channels less than the Minimum ! Channels OPERABLE requirement, within I hour switch to the redundant train of Control Room Ventilation, provided the - j redundant train meets the Minimus Channels OPERABLE raquirement ! or isolate the Control Room Ventilation System and initiate operation of the Control Room Make-up System. Restore the inoperable monitors to OPERABLE status within 30 days or submit a Special Report to the Commission pursuant to Specification l 6.9.2 within the following 30 days that provides.the cause of - the inoperability and the plans for restoration. - l ACTION 28 - Must satisfy the ACTION requirement for Specification 3.4.6.1. ,
, ACTION 29 -
With the number of OPERABLE channels one less than the Minimum
*! Channels OPERABLE requirement, ACTION a. of Specification 3.9.12 must be satisfied. With both channels inoperable, provide an appropriate portable continuous monitor with the same Alarn Set-point in the fuel pool area with one Fuel Handling Building l
Exhaust filter plenum in operation. Otherwise. satisfy ACTION b. of Specification 3.9.12. IA15 esse /NSubew I- ! 4 \ See bots L $re % L3 A l L 1 1 l 1 O . BRAIDWOOD - UNITS 1 & 2 3/4 3-41 AMENDMENT N0. 37
O O ' O Sc s p, wrlsp,. Re _e_o T"a'l4.23-N gep p ,,% m 4 (( RADIATION HONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS 1.e.. -fo - L c o 3,;3.1 , L - 4 s et. 3,3 8, I, e+c- .. FUNCTIONAL UNIT CHANNEL LHECK CHANNEL CALIBRATION OPERATIONAL TEST WESFORWHICH / SURVEILLANCE IS REQUIRED tc.oy,y,% Fuel Building Isolation- - Radioactivity-High and ' g y,y,g , i Criticallty (URL4RU55/5513 (-S 3-R 2-Q l i l c.o 3,3,4#. Containment Isolatlon- / g),q yg,g.g Containment Radioactivity / -
##d it 1 ( -AR0ll t-S 4-R All 2 )' V-Q it 2 -AR 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-PR0llA) S R Q 1, 2, 3, 4 b) Unit 2 (2RE-PR0llA) S R Q 1, 2, 3, 4 Lc4757#' Main Control Room Isolation-7Ekte s.3,7-( Outside Air Intake-Caseous Radioactivity-High .
/a -l- S 1-R :z- Q 1 l,)frainA(PRE-PR0318J52B)} I- S s-R st-Q 11 M Train BA0RE-PR0335/348))
me, s See 3bc.%- se+ekses s.v 3.y j "&m)z w y l ;, , (*Wi th r. W Sal Or !-- d!:ted f'fel 4" th? f"?! !!^*!"? 3r?!! Or f"Ol b"!!d!"" ' BRAIDWOOD - UNITS 1 & 2 3/4 3-42 AMENONENT NO. 74
~
O O O TABLE 4.3-3 ' RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVElLLANCE REQUIREMENTS DIGITAL CHANNEL CHANNEL CHANNEL OPERATIONAL FUNCTIONAL UNIT MODES FOR WHICH CHECK CAllBRATION TEST SURVEILLANCE IS REOUIRED
- 1. Fuel Building Is91stion-Radioactivity-High and Criticality (ORE-A3055/56) S R Q
, , i t
- 2. Containment Isolation--
Containment Radioactivity-High a) Unit 1 (IRE-AR0ll/12)
~
S R Q All O b) Unit 2 (2RE-ARoll/12) S R 0 All '*$ ti ;; SR ayS,/ \
- 3. Gaseous Radioactivity- SR 14.ts.4 .se s.g.ir.7. I gE X
RCS Leakage Detection _
'a) Unit I (IRE-PR0llB)1 6 S [R '
.5, I
p Q I, 2, 3, 4
.b) Unit 2 (2RE-PR0llB). .
wi l 4 S R Q 1, 2, 3, 4 ({g i
- 4. Particulate Radioactivity-RCS Leakage Detection- f f[u a) Unit I (IRE-PR0llA) S R Q~ 1, 2, 3, 4 9 ,$k i b) Unit 2 (2RE-PR0llA) @j R Q 1, 2, 3, 4
- 5. Main Control Room Isolation-Outside Air Intake-Gaseous "
Radioactivity-High a) Train A (ORE-PR0318/328) S R. Q All b) Train B (ORE-PR0338/348) S R Q All E $ EN o O OO l
^
p 9PM _A rPP q ao J P
*With new fuel or irrr lated fuel in the fuel storage areas or fuel building.
ERAIDWOOD - UNITS 1 & 2 3/4 3-42 AMFNOMFNT NO. 74
i l ! 5 8 ., 3.5 hNSTRUMENTATION { M00ABLEINCOREDETECTORS LIMITING' CONDITION FOR OPERATION j/ ! 'N l
\
3.3.3.2 The Movable Incore Detection System shall be OPERABLE with: N l a. At leasf.\75% of the detecto'r thimbles,
- b. A minimum two detector thimbles per core quadrant, an8
- c. Sufficient mov'able detectors, drive, and readout e paent to map these thimbles. 'N j APPLICABILITY: When the Novab Incore. Detection System s used for:
- a. Recalibration of the ex re neutron flux tection system, or
- b. Monitoring the QUADRANT P x '
TILT RA
, or l c. MeasurementofFh,F(Z)and ./
g ACTION:
/ \
l C With the Movable Incore Detection System inoper'able, do not use the system for the above applicable monitoring or.talibration functions. The provisions of Specification 3.0.3 are not app 1,idable. *
./
K -
,/
N', 4
\
SURVEILLANCEREQUIREMEkTS \ f/ 4 ' , !4.3.3.2 Th'e Mofable Incore Detection System shall be demonstrated' OPERABLE at l l least once per 24 hours by normalizing each detector output when required for:
./ ;
- a. ,/Recalibration of the Excore Neutron Flux Detection System, or 1
- I if
- f. Monitoring the QUADRANT POWER TILT RATIO, or \,
; / *
,' c. MeasurementofFh,F(Z),andF q yy. \
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- O BRAIDWOOD - UNITS 1 & 2 3/4 3-43 AMENDMENT NO. 38
. , S eat 4*a 33 IWSTRUMENTATION O \
SEISMIC INSTRUMENTATION LIMITIIG CONDITION FOR OPERATION
\
3.3.3.3 T seismic monitoring instrumentation shown in Table 3.3-7 shall be l OPERABLE. APPLICABILITY: t all times. l ACTION:
- a. With one orwre of the above required seismic monitoring instruments to the Consdsshn pursuant to. Specification 6.9.2 withiji the next 10 ino l days outlining th cause of the malfunction and the pmns for restoring l the instrument (s) OPERABLE status.
- b. The provisions of Specification 3.0.3 are not app cable.
i SURVEILLANCE REQUIREMENTS \ ~ 4.3.3.3.1 The seismic monitoring ins't[umentation s 1 be determined OPERABLE:
- a. At least once per 31 days by ' verifying erable status indications of the seismic monitoring instrumentatio .
- b. Atleastonceper92daysbyverily59 that:
Q 1) The triaxial acceleration s s s and the time-history accelero-l graphs properly process the' equi nt internal" test signals.
- 2) The response spectrum an/alyzer prop rly executes its diagnostic routine. j/
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- c. At least once per 184 daps by verifying tha 'i.he triaxial acceleration i
sensors and the time-history accelprographs peqperly record the equipment internal test. signals. The test may be d in lieu of the test ; requiredbySpeepication4.3.3.3.1.b.1)perfo , and , j d. l Atleastoncepr18monthsby: i 1) Verifyingtheelectroniccalibrationofthetinea istory acceylographs.
- 2) Installing fresh magnetic recording plates in the tr' xial peak accelerographs.
/
4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the eq ~ nt l listed in Jable 3.3-7 shall be restored to OPERABLE status within 24 hour g following'the seismic event. Data shall be retrieved from actuated instr nts and ans1yzed to determine the magnitude of the vibratory ground motion. A , Specp1ReportshallbepreparedandsubmittedtotheCommissionpursuantto . Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum l an'd resultant effect upon facility features important to safety. O BRAIDWOOD - UNITS 1 & 2 3/4 3-44 AMENDMENT NO. 38 m e--
l SecG 13 l l0 at l TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION I NIMUM ; MEASUREMEKT INSTRUMENTS : INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE- , 1. N : Time - History Accelerographs '
- a. Aux. Elect. Ra, 0 02 N.A ~1
- 2. Triaxial Peak Accelerographs I
- a. Cont./ Reactor Eq. Accumulators -
2 g to +2 g 1 l b. c. Cont./ Reactor piping Aux. Bldg./ Cat. I piping h 2 g to +2 g s-2 g to +2 g 1 1
)
- 3. Response-Spectrum Analyze i Aux Elect Re, OP 2J None 1
; 4. Triaxial Accele tion Sensors -]
- a. Cont./ - 377' -2 g to +2 g 1 j
- b. Con DW - 502' -2 g to +2 g 1 '
- c. Cot (t./10X - 426' -2 g to +2 g 9 l d/.ree Field /38 + 015, 34 + ISE -2 g to +2 g IN I
- e. Aux. Bldg./ISN - 426' -2 g to +2 g 1 \s l f'f.
3 Aux. Bldg./18L - 338'
-2 g to +2 g 1 ' s.,
x
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BRAIDWOOD - UNITS 1 & 2 3/4 3-45 Amendment No. 28 , 1 l
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O-l- i l-1 BRAIDWDDD - UNITS 1 & 2 3/4 3-46
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$ e cff. 3.3 3
LO INSTRUMENTATION ' N LIMITING CONDITION FOR OPERATION / 3.3.3.4 The meteoro' logical monitoring instrumentation channels giv in Table 3.3-8 shall be OPERABLE)
\~
APPLICABILITY: At all times. ACTION:
- a. With one or more required teerological nitoring channels inoperable for more than 7 days, prepare 'and su a Special Report to the Commission pursuant to Specificatio .9.2 within the next 10 days outlining the cause of the malf 4on and the plans for restoring the channel (s) to OPERABLE sta . \ 1
- b. The provisions of Specifi n 3.0.3 a enot applicable.
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SuRvE1LtANcE ReouratNtNTS .
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4.3.3.4..Each of the above meteorological monitoring instrumentation ch nels shall bb demonstrated OPERABLE by the performance of the CHANNEL CHECK an ! CHANNEL CALIBRATION. operations at the frequencies given in Table 4.3-5. l l l e O 1 BRAIDWOOD - UNITS 1 & 2. 3/4 3-47 AMENDMENT NO. 38
-. . . _ - - . _ ~ . .- .-
Sess a 3.3 l @ 1' n V TABLE 3.3-8 l ) , METEOROLOGICAL MONITORING INSTRUMENTATIO l l i MINIMUM l INSTRUMEN1 LOCATION OPERA 8LE
- 1. Wind Speed nel Elev. 34 ft 1 1 Elev. 203 ft. 1
- 2. Wind Directi n Moeinal Elev. ft 1 Nominal Elev. 203 ft 'N 1
- 3. Air Temperature - AT Nominal Elev. 30 ft/199 ft S
O ., . e e l l l l t BRAIDWOOD - UNITS 1 & 2 3/4 3-48
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. 5 '* a 3.3 O k .
'T , TA8LE 4.3-5
.i METf0R0 LOGICAL MONITORING INSTRtMENTATION SURVEILLANCE REQUIREMENTS ..
CHANNE CHANNEL INSTRUMENT CH . CALIBRATION
- 1. Wind Speed
- a. Nominal Elev. ft 0 SA
- b. Moeinal Elev. 203 ' O SA
- 2. Wind Direction
- a. Nos Elev. 34 ft 0 SA
- b. inal Elev. 203 ft D SA
. Air Temperature - AT Nominal Flav. an ft/199 ft 0 5
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j 8RAIDWOOD - UNITS 1 & 2 3/4 3-49 i
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3.3 INSTRUMENTATION j
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23.4 REMOTE SNUTDOWN(4esstemesesM4ew) LIMITING CONDITION FOR OPERATION . LCO .2.3 4 . i E'I:1.T/ The remote shutdown monitorine instrumentatiotr channels alven in -*- { Table 3.:1-9 shall be OPERA 8LEMe cr = OS;hy; ea u rr.;i = = ; ;e. v . O APPLICABILITY: MDDES 1, 2, and 3. ACTION: Cona A p. With the number of OPERABLE remote shutdown monitoring channels less than the Minimum Channels OPERA 8LE as required by Table 3.3-9, rastort the inoperable channel (s) to OPERA 8LE status witttin vssor ne7til l Gdg . /at least NDT STAND 5Y within the next 6 hours andj in@ ' Iwithin the followinc 6 hours. I p dcT10t6 Note ) p. The provisions of Specification 3.0.4 are not applicable. ACTom Oote 2. ; .Inster .3.3. co A $ SURVE!LLANCE REQUIREMENTS [+h d is n3 m all ecca,e i 5R .3.3 4.1( SE339 Each remote shutdown monitoring instrumentation channelbhall be
.SR .3.3 4.2 demonstrated OPERA 8LE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operatichs at the frequencies given in Table 4.3-6.
.se. 3 3.4.2 mic. ;
/2me.r a2 soa
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. SRAIDWOOD - UNITS 1 & 2 3/4 3-50 .
o 4 i' CTS INSERT (S) _ O)- SECTION 3.3 2 i ! LCO 3.3.4 ; INSERT 3.3 50A (As) !
- -NOTE :
- 1. ... .
4 2, Separate Condition. entry is allowed for each Function.
- I
( 4 )- + - I INSERT 3.3 50B (Au )
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- SURVEILLANCE FREQUENCY. !
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-SR 3.3.4.2 NOTE ...
i Neutron detectors are excluded from CHANNEL h-
- CALIBRATION. j s
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i TA8tE 3.3-9 - REM 0iE SHUTOOWN MONITORING INSTRUMENTAT10N - I o TOTAL NO. MINI i .
. READOUT OF L5 g INSTRUMENT LOCAll0N CHANNELS ERA 8tE 3 1. Intermediate Range Neutron lux. PLO6J 2 1
- e. 2. Source Range Neutron Flux PLO6J 2 1 u
- 3. Reactor Cealant Temperature -
Wide Range
- a. Hot Leg PLO 1/leep 1/leep
- b. Cold Leg $J 1/ loop 1/ loop
- 4. Pressurizer Pressure PLb6J 1 1:'.
s .
"f 5. Pressurfrer Level PLO6J 2 1 .
5 . 6.. Steam Generator essure PLO4J/PLO5J 1/ste gen sie een
~
- 7. Steam Ge ator Level PLO4J 1/ste gen 1/sta
- 8. RH emperature LOCAL 2 1 ,
. Auxiliary Feedwater Flow Rate PLO4J/PLD5J 2/ste gen 1/sta gen ,
. 9 A
G
. . _ _ _ _ _ _ _ . _ . ~ ___ _ ..___m _ ___2___.__ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ ._ + -e v t-----
O O O
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, T/8tE4.3-6/
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h /REMOT SHUT MONITORI INSTR NTATION
/ SURVFJLLANCE R60UIREMENTJ ,
8 . SA 33 4.1 - LMMtL' 5R H 41- CHANNEL
, INSTRUMENT CHECK CALIBRATION e -
5 1. '-Intermediate Range Neutron Flux M l # j
- 2. Sourte., Range Neutron Flux #
[I 3. ReactorAdolantTemperatur - Wide Range M [
- 4. Pressurizer Pressure M [ '
- 5. Pressurizer Lev N M [
I
- 6. Steam Gener or Pressure- M #
- 7. Steam nerator level M R[
$ 8. R Temperature -
M R
$ . Auxiliary Feedwater Flow Rate .
M R
'_.:n bel = "-S
'The ;p;;f fied 1" ;; nth interval =y b0 extraid t0,3_2 Entht-fGT CV;le 1 Galv-)
E h 5 e 5 n u O W
.h
... .. . . - . . . . ft.o 3,3_3 ... .. .
5' 5 pet A m 4i.- 5 4 . 7 O 3~, .23 INSTRUMENTATg , , .3 3.3 A4 ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION i tco3.1.2 l M The accident monitoring instrumentation channels shown in Table 3.3-10 2 shall be OPERA 8LE.
- APPLICA8!LITY: MODES 1, 2, and 3.
ACTION:
$30
- C.-J A ,a With the number of OPERABLE accident monitoring instrumen ion chan-
- C..a S nels less than the Required Number of Channels shown in Tab 3.3-10 j restore the_ inoperable _ channel (s) to OPERABLE status within days:
g^g g ctherwise. It: ' :: ::::i r n. -:: re a - :M r: : :: ; : : ni M P
- 0 . T wi c i.. 2 : f:1?: wing 5 5:r :. Lg g i X. 'With the number of OPERABLE accident monitoring instrumentation' CuJ D channels, except the containment high range area radiation monitor, Coad E asin steam line radiation monitor, and the auxiliary buildi.ng vent .
- s. tack wi & range.natie g1: cr. t te r , 1..;, " - ' ~ * * - - ;;.'.s. 1 a
? j O. % aP RaR'< r aut t f T hi 2 2-20. re t r ta in chanev1(s) to OPERA 8LE status within f MJtherwise, be in at \ ai-1
'j ' CJ G. Tea E MOT STAND 8Y within the next 6 he urs and in HOT SHUT 00WN within\
l the followina 5 hours.\
- ,i? ckndL k,w %.+.Am, y im ,
9p p. With the number of OPERA 8LE channels for the conthnt s higt/ range 2 ! area radiation monitor. or main steam line radiation monitend lee-the-4 M3 it tier, Lildia;; een ned wit.; r;;;; 7.Ok ;;; :. niterliess than the Minimum Channels OPERA 8LE reavirements of Table 3.3-10. linir.iate\ i en alternate method of monitoring the appropriate parameter (s) within) i gg ?? ""**iana ettner restore tne Inoperable channel to OPERABLE status ] within 7 days,lor prepare and suestt a special Report to the , ! g f* Commission pursuant to Specification 6.9.2 within 14 days that provides i 1 actions taken, cause of the inoperability and plans and schedule for l [" (h festering the channels to OPERABLE status.) A4[M.4,. .d The provisions of Specification 3.0.4 are not applicable. i 4
$URVEILLANCE REQUIREMENTS
.S E. 3.3 3 FMEach accident. monitoring instrumentation channel .sha-11 be demonstrated SR 3 3 7 2. OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations tat the freauencies shown in Ttble 4.3-7./
, $8 thte
_/ . BRAIDWOOD - UNITS 1 & 2 3/4 3-53
O CTS INSERT (S) SECTION 3.3 LCO 3.3.3 l l I INSERT 3.3 53A (La) r CONDITION REQUIRED ACTION COMPLETION TIME ! C. Required Action and C.1 Initiate action in Immediately associated Completion accordance with l Time of Condition B Specification 5.6.7. ' not met. 4 4 j l O : i l l O Revision A
- 4.
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- 1 L.co 33.3 SpecM;c.4,.. g 53,7
!.O t f 3 , INSTRUMENTATION e . i ACCIDENT MONITORING INSTRUMENTATION a 4 ! LIMITING CON 0! TION FOR OPERATION i
- 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
} APPLICA81LITY: MODES 1, 2, and 3. l l ACTION: i a. With the number of OPERA 8LE accident monitoring instrumentation chan-l 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 HDT STAN08Y within the next u hours and in NOT SHUTDOWN within the following 6 hours.
l b. With the number of OPERA 8LE accident monitoring instrumentation - ! channels, except the containment high range area radiation monitor, j main steam line radiation monitor, and the auxiliary building vent . stack wie range.actle su ll:er.!ter,1..:. th;;; the 'i! .i;l;;. . .. . 14
- i. O. s, aaraaa'r r a ir t < taai 2.>-2a. t r ta ia P r ai-channel (s) to OPERA 8LE status within 48 hours; otherwise, be in at O..
i ', - least NOT STAND 8Y within the next 6 hours and in HOT SHUTDOWN within
- the following 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 i auxiliary building vent stack wide range nc/ ole gas monitor less than j the Minimum Channels OPERA 8LE reavirements of Table 3.3-10,Irait;:::
l ,.1;... ;w ;'.J ;f _c! --'- tt: :::7;;ri;;; ::r: ::::N ith% i . (, . 7 ' ? i::aland either mtere the ' nonerahla chmaami to OPERABLE statusJ f within 7 days,lor prepare and submit a Special Report to the - ! C ""ission pursuant to specification 6.9.2 within 14 days that provides A/dr<.ssedia ux3.3.3 =n _ x.^ cause of the inoperability and ' plans and schedule for l .5,i Docs Ag -13 restor <ng the channels to 0PERA8LE status. l i
- d. The provisions of Specification 3.0.4 are not applicable. ,
l 5 [ ,,Qn Okl.nr ok Aho ff tylemS t i a f hanada enened a f snoe.ier..s i SURVEILLANCE REQUIREMENT 5 i a i 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. i . j . 3 BRAIDWOOD - UNITS 1 & 2 3/4 3-53 . _m.__ __._. _ _ _ . _ _ . _ a -
O O O . L. .s
.9 3 3-t TABLE 1.+4e -
ACCIDENT MONITORING INSTRtMENTATION i h fREQUIRED INIRSt INSTRlMENT dBIND i HANNELS
, ,CHANNELSj ERABLE o
'T E Containment Pressure 2 41 .
g 2. Reactor Coolant Outlet Temperature - THof (Wide Range) 2
- 1 1
g 3. Reactor Coolant Inlet Temperature - TCOLD (Wide Range) 2 g IA Reactor Coolant Pressure - Wide Range 2 1 e (o F. Pressurizer Water Level
" 2 1 8.t. Steam Line Pressure !
2/ steam generator 1/s eaa se erates 5K Steam Generator Water Level - Narrow Range ', 1/ steam generator 1/st as g eratoi , 4 .8' Steam Generator Water Level.- Wide Range 1/ steam generator
; 1/st a neratoi-
- 9. Refueling Water Storage Tank Water Level 2 1 hr ' 'l R r Feedater flow Rate -
2/ steam generator 1/ste genefEToi [ 11. PORY Position in c - Closed) , 1/ Val.ve _ 1/Valv h 12. PORV Block Valve Position Indicator ** (0 pen 7Cl alve 1/Valv
- 13. Safety Valve Position _Indicater-T0 pin 7CIosed) ,N 1/Vai e 1L. -Gent 1rtniliiiFt Floor Drain Sump Water Level (Harrow Rance3 2 D ,
t 015. Containment Water Level (Wide Range) 2 1 13 Mr. In Core Thermocouples 4/ core quadrant 2/c re quad nt ; 11 17. Containment High Range Area Radiation
~~ ~ 14GD 1
[!" . I^.5Nillary-8ellding-Vent-Stach-Wided[ng[Nehke-Ge: .% A. 1,l,:15h 11 17. Main Steam Line Radiation I ([ED/.5% I;at sta line 1420' Reactor Vessel Water Level ~ 2 t-2L1-Reactor-Ecolant-Subcooling Eargin Monitor ~ - - - - 2**' [1*** h O v
*No / applicable'If the ass ated block va'Ive is in t closeil posJ(lon.
**N(t appIlcable if the b} ek valve is ve'rlfled in t closed pas tion and poidr/is remov f
h
. va OU" **lisemonitpiingchanne)((10highestgveragecoref xit tessera res)incopfunction .
with RCS' Pressure (Jtem 4 above) tgdetermineffie subcoolin margin. f ., ]
O O O. (4/M"'.!' T ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREpiENTS g INSTRUMENT y33.3., SHANNEL CHECKj fiiANNEL CALIBRATION b Sn a 3.3 z 1 is 14. Containment Pressure M pF
- 2. Reactor Coolant Outlet Temperature - T HOT I"Id' "*"9') M 8' !
- 3. M plP
. Reactor Coolant Inlet Temperature - TCOLD (Wide Range)
E l 4- Reactor Coolant Pressure - Wide Range M M P i;! $ t. Pressurizer Water Level M M P , N e.
- 84. Steam Line Pressure M R P ;
u 5 -7. Steam Generator Water Lgvel ~- Narrow Range M R P
- 44. Steam Generator Water Level - Wide Range M R P
- 9. Refueling Water Storage Tank Water Level M R P t
f10. Auxill Feedater low Rate M R ! t
- 11. PORV osition I cator* (0 pen / losed) A.
. 12. PO BlockValv[PositionIn cator** (Ope / Closed) M N.A.
w 13. afety Valve osition Indt tor (0 pen /C1 .ed) M N.A. E- 14. Containmen Floor Drain Water *Lew (Narrow nee) M Rf / J 1o45. Containment Water Level (Wide Range) M fil
- 1546. In Core Thermocouples M fil
'8 47. Containment High Range Area Radi? tion M '
R***
~
- 10. Mi t iary-Betfding-Vet *t-Steck- WIiji~llange-fioble-Ges M "" 1 1119: Main Steam Line Radiation M .RII kz lif f9. Reactor Vessel Water Level .
M RI g - fthe/ associated'blockvalveisinfheclosed osition. . m *Not plicabi l
** applica f block y va is v dified V the close itio Dower remov k gg.3[gk***~CHANNELCALIBRATION#:y:=?tOf:
~ =w :=== == 1 n,-.nd+0n.--Int-m,eu 4ert.conie-eal-lbration-of-the-channel,k-not includingw the w tm e = ;=te c .t .
~U
/ !!he :: es4f-teiFI" = nth Mte--01 = 7_50 ext::::: te 32 ;;;th: . ,. . 13.is __. . 1 v-L- g t
s 1
Sech 3.3 O 1.kTn4*:atul0N MONI RING INSTRUMENTATION 4 LIMITING NDITION FOR OPERATION ; s .
-3.3.3.7 (This wwwiiissi.ivn nu-uvr is net used.', ,
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f' ! l O l BRAIDWOOD - UNITS 1 & 2 3/4 3-56
e Secf*= 3 3 O. 4 4 l s..u..._....-.
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BRAIDWOOD - UNITS 1 & 2 3/4 3-57 AMENDMENT NO. 35
s Su.foa 33 N , INSTRUMENTATION i O t00Sg.png7 ogisc73on sys7gg - Ru f LIMITINGChNDITIONFOROPERATION 3.3.3.8 The Loose-Part Detection System shall be OPERABLE. APPLICABILITY: MODES I and 2. , ACTION:
. a. With one or.nore Loose-Part Detection Systes e nels inoperable for more than 30 days, prepare and submit a SpecWI 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 are not applicable.
Q SURVEILLANCE REQUIREMENTS
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4.3.3.8 Each chann of the Loose-Part Detection Systems shall be demonstrated OPERABLE by perfo nce of:
. \
- a. A ANNEL CHECK at least once per 24 hours, l
- b. An ANALOG CHANNEL OPERATIONAL TEST except for verification of s'etpoint at least once per 31 days, and
)
- c. A CHANNEL CALIBRATION at least once per 18 ronths. \ x-l O
BRAIDWOOD - UNITS 1 & 2 3/4 3-58 AMENDMENT NO. 38
I l l
$seWen 3 3 / \
hSTRUMENTATION RAD ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMIT CONDITION FOR OPERATION 0.0.0.9 ( is specification number-is-not =:d.') i
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O BRAIDWOOD - UNITS 1 & 2 3/4 3-59 AMENDMENT NO. 35
e bet.Mo9 STRUMENTATION - EXP IVE GAS MONITORING INSTRUMENTATION LIMITING C DITION FOR OPERATION I
~
1 1 l 3.3.3.10 The exp ive gas monitoring instrumentation cha'nnels shown i able 3.3-13 shall be OPE BLE with their Alare/ Trip Setpoints set to ensur that the limits of Specifi tion 3.11.2.5 are not exceeded. APPL!CABILITY: 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 entat n to OPERABLE 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 i p explain why this inop ability was not co ected in. a timely manner.
V
- c. The provisions of pecification 3.0.3 are not pp.licable. ;
. 1 SURVEILLANCE REQ EMENTS y s 4.3.3.1 Eacn explosive gas monitoring instrumentation channel shall be l demon rated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRAT N and/IGITALCHANNELOPERATIONALTESTatthefrequenciesshowninTable4.3-9.
O BRAIDWOOD - UNITS I & 2 3/4 3-60 AMENDMENT NO. 38
O O O N
,, y TABLE 3.3-13 9 ~
EXPLOSIVE GAS MONITORING INSTRUMENTATIONI l MINIMUM CHANNELS INSTRtiMENT OPERABLE APPLICA81LITY ACTION
- 1. (Not Used)
--e '
- 2. (NotUsed)
[ '
- 3. Gaseous Waste. Management Syst
[ ,
- a. Hydrogen Analyzer (OAT-GW8000 1 ** . 38
- b. Oxygen Analyzer (OAT-GW8003) ** 38
- c. Waste Gas Compressor Olscharge i
Oxygen Analyzer (OAIT-GWOO4) *** 38 R* Y. TABLE NOTATIONS p .
*(Not used) .
**During WASTE GAS HOLOUP TEM operation.
***0uring Waste Gas Comp sor Operation.
All instruments r red for Unit 1 or Unit 2 operation. i ACTION STATEMENTS ACTION 3 With the number of channels OPERA 8LE less than required the Minimum Channels OPERA 8tE 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 urs k* during other operations. . u 9 i
. h m
(#1 i i
O O O t
, N TABLE 4.3-9 b '
, EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS R N 5 N DIGITAL
\ '
' CHANNEL ES FOR WHICH
' CHANNEL SOURCE CHANNEL OPERATI SURVEILLANCE
@ FUNCTIONAL UNIT CHECK CHECK CALIBRATION T IS REQUIRED j u
[ 1. (Not Used) l [ 2. (Not Used)
- 3. Gaseous Waste Management System
- a. Hydrogen Analyzer (OAT-GW8000) D N. Q(4) 'M ** !
- b. 07.ygen Analyzer (OAT-GW8003) D N.A. Q(5) M ** '
R c. Waste Gas Compressor Discharge 's 0xygen Analyzer (OAIT-GWOO4) N.A. Q(5) M *** [ e l IO TABLE NOTATIONS -
*(Not used) ,
**During WASTE GAS HOLOUP SYSTEN operation.
***DuringWasteGasCompreporOperation. '
A11 instruments requirtfd for Unit 1 or Unit 2 operation. (1) (Not Used) 7 ' (2) (Not Used) g (3) ( ded) ; E
! J ,((4 e CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and ni The CHANPSL CALIBRATION shall include the use of standard gas samples containing. oxygen and nitrogen, en.
{t - 5 I 5 u
'e N l i
t'
, - _ _ _ _ _ _ _ __ _ _ _ . _ _ _ _ _ _ _ _ _ . . . _ _ m. _ __ _ . _ _ _ _ MSTRUMENTATION - HIG ENERGY LINE BREAK ISOLATION SENSORS i N Rs LIMITING CONDITION FOR OPERATION j
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3.3.3.11 The hi 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 the inoperable instrument (s) to ERABLE sta within 7 days, or suspend the supply of auxiliary steam to Auxil' ry Building, or establish a 1
continuous watch in the affected are s ntil the inoperable sensors are restored to OPERABLE status.
- b. With the number of OPERABLE stea generato blowdown line isolation instru-ments less than the Minimum C 1s OPERABL as required by Table 3.3-14, restore the inoperable inst nt(s) to OPERAB status within 7 days, or limit the total steam ge ator blowdown flow ra to less than or equal to 60 gpm or establis continuous watch in the a eted area (s) until the inoperable sens are restored to OPERABLE stat O c. The provisions Specification 3.0.3 are not applicable. ,
SURVEILLANCE QUIREMENTS s 4.3.3. 'Each of the above high energy line break isolation instruments all ; be d onstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONA TES and CHANNEL CALIBRATION at least once per 18 months. l i N~ - l O BRAIDWOOD UNITS 1 & 2 3/4 3-63 AMENDMENT NO. 38
.- . . . _ - .- - - _ _ - . = _ . . _ . - . _ _ _ - - . - _ . . - . - - . - .
3 - 5 cc 4 3 3 TABLE 3.3-14
- HIGH ENERGY LINE BREAK INSTRIMENTATION i
- ^ '
150 !0N INSTel.2NT MINIMUM CHANNELS APP LE FUNCTIM CNAhWEL OPERABLE .
~,
ADDES
- 1. Auxil. ry Steam 1
- l* OTS-AS031A Iso'1sti ,
OTS-AS032A -
~
l OTS-A50318 1
. OTS-A5032B 1 *
- 0TS-A5031C ..
j - OTS-AS032C TS-A5031D 1 ~
- 0 -A5032D' - -
~ ~
! OTS- 31E- *
' 1~
OTS-AS 2E
- - OTS-AS031 1 * ;
- - OTS-A5032F . O
- 2. Ste re-rator. 15-SD04sA 1 1, 2, 3, 4 Blowdown Line TS-SDQ45B
! Isolation / ' l TS-SD046A 1 1,'2,3,4 j T -50046B i' TS-SD045C
- 1 1,2,3,4 TS-SD0450 TS-SD046C 1 1, 2, 3, 4 TS-SD0460 1
q
/
i / Required when auxiliary steam is being supplied, from any source, to the Auxiliary Building. O. O BRAIDWOOD UNITS 1 & 2 3/4 3-64 AMENDMENT NO. 35
INSTRUMENTATION c.e
" c h . 3 .5 l 3/b.4 TURBINE OVERSPEED PROTECTION S LIMITbCONDITIONFOROPERATION s 3.3.4 At\eastoneTurbineOverspeedProtectionSystemshallbeOPERABLE.
APPLICABILI MDDES 1, 2, and 3. ACTION:
- a. With one hrottle valve or one governor valve per high ssure turbim l steam line inoperable and/or with one reheat stop val or one l l reheat inte apt valve per low pressure turbine ste line inoperable, i restore the y perable valve (s) to OPERABLE status ithin 72 hours, i ~ or close at.lehgt one valve in the affected steap line(s) or isolate the turbine f the steam supply within the 6 hours. -
- b. With the above req ' red Turbine Nerspeed P taction System otherwise inoperable, within 6 urs isolate the tu ne from the steam supply.
~
l i
; SURVEILLANCE REQUIREMENTS :
4.3.4.1 The provisions of Specificati n s4 .4 are not applicable.
\
4.3.4.2 The above required Turbine Ov s d Protection System shall be ! demonstrated OPERABLE: l 1
- a. During turbine operation t least onc per 31 days by direct obser- l vation of the movement f the valves ow through one complete cycle from the running posi ion
- 1) Four high pre ure turbine throttle v ves,
; 2) Four high p ssure turbine governor va es, l 3) Six turbi reheat stop valves, and j ,
- 4) Six turbi reheat intercept valves.
i b. Within 7 da prior to entering MODE 3 from MODE by cycling each of the 12 xtraction steam nonreturn check valves on the closed position
- c. Durin turbine operation at least once per 31 da'ys by " rect observa-tion of freedom of movement of each of the 12 extractio steam non-re rn check valve weight arms,
- d. least once per 18 months by performance of CHANNEL CALIB TION 4 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 stems and verifying no unacceptable flaws or corrosion. BRAIDWOOD UNITS 1 & 2 3/4 3-65 AMENDMENT NO. 35 L . _ _ , ._ __ _ _ _
L.w 3.4 4 . 3 9 (t/*-@ REACTOR COOLANT SYSTEM [Acs) O G/ . 0.1 OCACTO 000LAMT LOOP 0 ^!:0 CO^LAt;' CIRC"LAT!0 0 i-6- .= P ": Or ;;.T;0:ys,q,9 acs g_up, - Mope and a) i LIMITING CONDITION FOR OPERATIONS Lco 3.4 4 optRasts e.J } j N All reactor coolant loops shall be1in operation. j APPLICABILITY: MODES 1 and 2. ACTION: CoHp A With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within 6 hours. 4 Y 4 O
~
SURVEILLANCE REQUIREMENTS
- $ A 3.'t.4 1 M-+:4-H The above required reactor coolant loops shall be verified in operation tnt :t r: 1: tin; :e;;;r cecle ,U at least once per 12 hours.
( % Oym..; in t 6.t ..... ;ym ; : c.u.. 2. lc.4.) O BRAIDWOOD - UNITS 1 & 2 3/4~4-1
, _,,,,,3
' =- C -
s M html fpwm 'io } 3.8f REACTORCOOLANTSYSTEM(RCC t cardle of nd ardLA a lf ] c:= T :T C / L (MS Rc6 Loops-NPE 3) tA .l 8 LIMITING CONDITION FOR OPERATION l 1 i j M At-least two of.the reactor coolant loops shall be e . j ,0PERABLE with two reactor coolant loops in operation when the'":::t r ' = ; i - ; ;nt:: tr :t:n ::: _ S and one reactor coolant loop in operation when the j ' '":::t:r ' = :::t:r inct:= 27; ::: L*-fy wgg m w ,, g g,foggal,h,=Q { Reactor Coolant Loop A and its associated steam generator r coolant pump,- LJ 1 ! b. Reactor Coo op B and its associat am generator and j reactor coolant pump, I
- c. Reactor Coolant Loop ts ated steam generator and U i reactor coolan , and~
2
- d. Rea oolant Loop D and its associated steam ge r and j y actor coolant pump.
APPLICABILITY: MODE 3. b4 c,,,u,t wa i ACTION: _ M' '#
- cowD C IImr + 2.4-18 i- (.oNP P E 6H
- h le?? thin the ebeve ret;uired reacter coelent 100ps OPERABLE, i
restore the required loops to OPERABLE status within 72 hoursf or De} cup f_ 'in MOT sMuluowN within the next 12 hours. J f ! v Co@ h ./ ,With only one reactor coolant l'oop in operation and the '":::t: '-t:f _ j ,'0=t:: t x t: n '- th: cl:::' : n ttt: ] within 1 hour r e r: N:::::ri m% , t_(zmay y,4.ag) j _ ,, i '-:: := t:: tr::i:ng m%waaugw,g.,; g
- g. With no reactor coola'nt loop in operation,tsuspend all opera ions "jfM,(j c
involvino a reduction in boron concentration of the Reactor Coolant-System /and immediately initiate corrective action to return the) I
- ; g F tJ.s.t
! Jew ' 4 C 3 M required reactor coolant loop to operation.f l t.o W D f IZ n sed I A *M k j . SURVEILLANCE REQUIREMENT 4 !. S.445 E'l:F'E At least the above required reactor coolant pumps, if not in l l operation, shall be determined OPERABLE once per 7 days by verifying correct
- breaker alignments and indicated power availability.
! u M G- (49-t-t-B The required steam generators shall be determ'ined OPERABLE by { I 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. 1 l 3F 'L 3 , l 9.3.4.El A,TFFE required coolant loops shall be verified in operation e ' ' = ', 4
.. ;__ __ _ _ _ _ ---,45D at least once. per 12 hours.
g per s W PerW 3 (40t#TL *All Reactor Coolant pumps may be c:n ;;nd for up to 1 hourhprovided: ! 4 j (1) no operations are permitted that would cause dilution of the Reactor l 6araa ca"c atratiaa "' (2) car aat' t t a r tar 's ! i O' caa' "' syst maintained at least 10*F below saturation temperature. i f (**;n 0;nir.' int 5;,aptics 0;nifistin 2.10.4.) , i i-l BRAIDWOOD - UNITS 1 & 2 3/4 4-2 4 :
,--....--c- ,,e.- -,, -
O CTS INSERT (S) SECTION 3.4 LCO 3.4.5 . INSERT 3.4 2A (L3 ) r a CONDITION REQUIRED ACTION COMPLETION TIME + A. One required RCS loop A.1 Place the Rod Control I hour 4 not in operation with System in a condition Rod Control System incapable of rod . capable of rod withdrawal. withdrawal. INSERT 3.4 2B (Lu ) CONDITION REQUIRED ACTION COMPLETION TIME C. Two required RCS loops C.1 Initiate action to Immediately not in operation with place the Rod Control Rod Control System System in a condition capable of rod . . - incapable of rod withdrawal. withdrawal. QR AND Required Action and C.2 Suspend all Immediately assoc 1cted Completion operations involving Time of Condition A a reduction of RCS not met. baron concentration. AND C.3 - Initiate action to Immediately restore RCS loop (s) to operation. i l O Revision A 2
t l
-O CTS INSERT (S) l SECTION 3.4-f LCO 3.4.5 -
3 INSERT 3.4 2C . (Ln) -
- i . j 3 j t
. CONDITION REQUIRED ACTION COMPLETION TIME ^ l F. Two required RCS loops F.1 Initiate action to Immediately l inoperable. place the Rod Control ! System in a condition , incapable of rod i ! withdrawal. - MQ F.2 Suspend all Immediately I
- . operations involving .;
a reduction of RCS i j boron concentration.
]
r
] .
AND ! F.3 Initiate action to Immediately 4
. restore one RCS loop l
, to OPERABLE status. l 1 O Revision A-
, - e,w ;l 3M REACTOR C0QANT SYSTEM (Rc.5)
("0T 0""T00ZO (3.4.6 Ec.5 Loors - MODE. Si) LIMITING CONDITION FOR OPERATION _ . . - ._ , , - . _ ,, _ m._. - _u , ,, GM"T3P) At least two of the loopst ut:d Mk,.3 shall be OPERABLE and at least one of these loops shall be in operation:* Reactor Coolant Loop A and its associated steam' generator and reac ^ lant pump,**
- b. Reactor nt Loop B and its associated steam ge or and reactor
- coolant pump, U c. Reactor Coolant Loop C a ts asso ed steam generator and reactor
, coolant pump,** I d. Reactor Coolant Loo and its associate eam generator and reactor coolant pump,**
- e. RHR A, and M L RHR Loop B.
- i i
APPLICABILITY: MODE 4.
)
O ^CTion: E: With less than the.above required reactor coolant and/or RHR loops C. odd B tA 8.1 OPERABLE, immediately initiate corrective action to return the
- W C E A CJ- _ required loops to OPERABLE status as soon as possible;/if the]
ces ut.2 AJp3t(remaining OPERABLE loop is an RHR loop,)be in COLD SHUTDOWN within co,a g ga B1 24 hours. E. As CodPA"*lh(WithnoreactorcoolantorRHRloopinoperation,suspendall operations involving a reduction in boron concentration of the ca9 C KA Cl) LReactor Coolant Systemfand immediately initiate corrective action to 40t40 A M A.t. return the required coolant loop to operation. (tiba b opaq Per 8 6 ' M *d l/.o ML i #All reactor coolant pumps and RHR pumps may be i ;c/_ p d forupto1 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. ' Leo HoTL 2 #*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. O BRAIDWOOD - UNITS 1 & 2 3/4 4'3
u w s . ,. . . REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS sk s.t& 3 N The required reactor coolant pump (s) and/or RHR pumps, if not in operation, shall be determined OPERABLE nnce per 7 days by verifying correct breaker align s'~and indicated power availability.
. 6K J.44.A ls .
C4. 4.1. 2. D
- e. qui team generator (s) shall be determined OPERABLE by verif i secondary narrow range water level to be greater than or equal tol 4th or Unit 1 ( for Unit 2)'at least once per 12 hours.
M s.4.t.. I 33 % _ fue re n t e,O i ( L L M 71 1:=t :n3 react
. oolant or RHR loop shall be verified in operation t .d :t r: 1: tin; r ::::r :=12.Dat least once per 12 hours.
O i O - 1
)
e O. BRAIDWOOD - UNITS 1 & 2 3/4 4-4
~ l Lco s.n. r \ Q
~
_ 3 4 REACTOR COOLANT SYSTEM (Rcs) - (0^LO 0=T00= LOOPS TILLEQ3.4 7 Rc6 Loops - tiope..r, t p Rile.[] LIMITING CONDITION FOR OPERATION Lt.D M.7 (ih+&4-H At least one residual heat remeval (RHR) loop shall be OPERABLE and i in operation *, and either: Lco M.7. 4. K.' One additional RHR loop"shall be OPERABLE #, - Ld) 3 47,b S L5 Y. (The secondary side _ narrow range w4ter levell at ast two steam generators shall b creater than G for Unit _1 ( W for Unit 2).)
- SR 3 M.7 2. < .
openests WA APPLICABILITY: MODE 5 with reactor coolant Toops filled ##. I ACTION 3 g 3g.,,
- s. [WithoneoftheRHRloopsinoperableandwithlessthantherequired (pnp 1 RA 1.l k steam generator level, immediately ini.tiate corrective action to
, .j
. treturn the__ inoperable RHR looo to OPERABLE statusfor restore the coNp 13 MrE.2. required steam generatorflevellas soon as possible.
l*o ofttrA GL.E s+sk HD E [WithnoRHRloopinoperation,suspendalloperationsinvolvingja cos) A R A A.Q treduction in boron concentesliun of tiw Twector Cooiant systemlano
- 4q immediately initiate corrective action to return the required RHR )
loop to operation. l t SURVEILLANCE REQUIREMENTS !
- St,3M.7. 2.
g, krf oC'. '.1. '.1.12 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours. ' 6F 3A.7.1 BNY 0 I P '.1.'.1.2) tit 1::n ;QRHR loop shall be determined to be in operation
/ cig;ul: tin; 7:::ter :::1:nt)at least once per 12 hours, my 5 tt. M 7. = M 5est 3A-5A 2 49, g
) LIC "- l "The RHR pump may be d---- ;;idd for up to 1 hour ovided: (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. Lto sort. 2. #0ne'RHR loop may be inoperable for up to 2 hours for surveillance testing provided the other RHR loop is OPERABLE and in operation. 2 Lto MafE.3 ##A reactor coolant pump shall not be started with one or more of the Reactor j Coolant System cold leg temperatures less than or q.;cl 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.
1 O=e we- =a O . 4 BRAIDWOOD - UNITS 1 & 2 3/4 4-5
i
?
~
(]). CTS INSERT (S) SECTION 3.4 LCO 3.4.7 : INSERT 3.4 5A- (Mn ) t I CONDITION ~ REQUIRED ACTION COMPLETION TIME ! t 1 C. Two required RHR loops C.1 Suspend all Immediately ! inoperable. operations involving
- a reduction of RCS l QB boron concentration.
! Required RHR loop AND ino)erable and one or ! l boti required SGs C.2 Initiate action to Immediately ! inoperable. restore one RHR loop : to OPERABLE status. ; t C:) l r INSERT 3.4 5B (M ) 3 SURVEILLANCE FREQUENCY SR 3.4.7.3 Verify correct breaker alignment and 7 days indicated power are available to each required RHR pump. i f l-() Revision A !
1-i
- h CTS INSERT (S)
SECTION 3.4 l: 4 LCO 3.4.7
- INSERT - 3.4 5C (Lp) f .
4 -NOTE I 4. All RHR loops may be removed from omration during planned . ,. heatup to MODE 4 when at least one RCS loop .is in operation. i 4 i-5- 1 I O O Revision A
l LCO 3. 'i, 8 . dJ.4 ' REACTOR COOLANT SYSTEM (stc(,) (COLD 5"" TOM - L^0P; MOT TILLE:"d&'t,T R45. Laep+-MOPE- 6 4**f+ Net AlI8 4) . LIMITING CONDITION FOR OPERATION Lco 3.8f.T N Two' residual heat removal (RHR) loops shall'be OPERABLE
- and at least one RHR loop shall bF in operation.** ~ ~~
APPLICABILITY: MODE 5 with reactor coolant loops not filled. i ACTION: p5W X. With less than the above required RHR loops OPERABLE, immediately cogp c Aa d.,a. initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible. Jr. f CsO 4 RA A. (WithnoRHP,loopinoperation,suspendalloperationsinvolvingja reduction in boron concentration of the Reactor Coolant Systemfand immediately initiate corrective action to return the required RHR l csHPA #4 A.A loop to operation. Coup C l Ins e r 4 'A-GA SURVEILLANCE REQUIREMENTS 6 R 5.4.t.l ( % e resutee / 7 , G.4.L4.0 ^.t !:::t en:;RHR loop shall be determined to be in operation ' pi cel: tin: r:::ter ::: lor.3 at least once per 12 hours. , sR. 3.44 > <---(Ims.str sA- 6 B) h Lco wrs. A "One RHR loop may be inoperable fc,r up to 2 hours for surveillance testing provided the other RHR loop is OPERAB!.E and i peration. Cre-o<ev 4,o., op .wse A,3 i Azo Nars. I **The RHR pump may be t h - W M for up to I ho provided: si) 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 l below saturation temperatur i i
/ stera b , nas s*J A M d Q (3) 16 draArekne. %k tics Wahr ) Molume 1
o i BRAIDWOOD - UNITS 1 & 2 3/4 4-6 l l
i CTS INSERT (S) -Q- SECTION 3.4 l LCO 3.4.8 -. INSERT 3.4-6A- (Mu ) 1 CONDITION' REQUIRED ACTION COMPLETION TIME
.C. Two required RHR C.1 Suspend all operations Immediately loops inoperable. involving reduction in RCS boron concentration.
AN_Q C.2 Initia'te action to Immediately restore one RHR loop to OPERABLE status. O INSERT-3.4 6B (M ) 3 SURVEILLANCE FREQUENCY SR .3.4.8.2. Verify correct breaker alignment and indicated 7 days power are available to each required RHR pump. i l l J O Revision A
. . L4D 3A.I7 .
a l < A 3.4 REACTOR COOLANT SYSTEN (hc5) .
. I 3.9,f 7 LOOP !$0LAT!0N VALVES ..
I- g - LINITING CONDITION FOR OPERATION O LCO 3A. l 7 i . . l (Fe4-1-k+) All RCS loop-isolation valves (hot leg and co1'd leg stop valves) . j shall be open and power removed from the isolation valve operators. Ai
" APPLICABILITY: _ES 1, 2, 3 'and 4. 'U cm.ee r s.*-7e Is Acuous nors.-Odsur 3,-74 g g g,, o,,4
, %, 4 : m , cmp 3 AGHON With any RCS loop isolation valve closed,c " - - - - - - - - - " " " " P and be in at least NOT SHUTOOWN within 6 hours and in at least COLD' ! ithin the following 30 hours. i e h
~
CAHb s NorE. 4 (Insar a,#- 70 ", l
- >
- ;L*::VCILLAt:C:'.::EO:M::ENCCS n..':;. :n.. *:
Ili i" " SP, 3.4.n. t . l ' C4 EE'ED All RCS loop isolation valves shall be verified open and power l removed from the isolation valve operators at least once per 31 days. . I h' . t: ]* . -
- i. .
1 1 i,
- i. !
4, ;
. 1 qh 4:
Or.e , U. BRAIDWOOD - UNITS 1 & 2 3/4 4-7 U
~I 5
Q CTS INSERT (S)- SECTION 3.4 LCO 3.4.17 INSERT 3.4 7A (L.) j ACTIONS l NOTE : Separate Condition entry is allowed for each RCS loop isolation valve. ; i INSERT 3.4 78 (L ) ; CONDITION . REQUIRED ACTION COMPLETION TIME ; A. Power available to one A.1 Remove power from 30 minutes or more loop isolation loop isolation valve O va ve operators- operators. . INSERT 3.4 7C (Au) l CONDITION REQUIRED ACTION COMPLETION TIME
]
B. - NOTE ... ... j All Required Actions i shall be completed whenever this Condition is entered. O Revision A i
4 to .I.V./S d I a.4 REACTOR COOLANT SYSTEM [AM) s.q.t g (L^^r 00LAT:0% VALV ';k_ _fRc.s L..rs ' Is.\a4ed ) l i i i LIMITING CONDITION FOR OPERATION 1.c.o '3.4 1g l C-3:T:E2EE If an RCS loop is isolated, maintain the hot leg and cold leg stop valves closed until: 6 tom.ecA .sho44om more a is
- a. The boron concentration o cthe isolated loop is greater than or equal {
l g boron concentration of the ;;; := : 'rerj,and ' I wu coda.& u&A o
- b. The temperature oretne cold Tag of the isolated loop is within 20*F l of the hiahest cold le temperature of the 6 g )
APPLICABIL Y: E5 5 n 5. . t u"iS*I*A*d P *#"* * ! MA
)
l
/ ACTION: With the requirements of the above specification not satisfied, do not) '
(open either the hot leg or cold leg stop valves.1
.g L4 )
l O SURVEILLANCE REQUIREMENTS 1 I i l a s.n.a. I __ G.,.1.L.2.11 The isolated loop cold legttemperature shall be determined to be
} "***O& '
i within 20*F of the highest cold leg temperature of thegeperet4ao-leop4within 30 minutes prior to o ning the cold leg stop valve. .gg gg S A %'/.If. R long ccolad ad 1 ^ .1. 5. 2. 2) The boron oncentration oftan isolated loop shall,,be determined to be grea er than or equal to the n boron concentration of theter r:tta; :;eed within hours prior to opening either the hot leg or cold h g stop valves of an isolated loop. rwguired shWh mar 4d 4 i I l i !O l l I l BRAIDWOOD - UNITS 1 & 2 3/4 4-8
_ . ~ . ._ -.. _ _ _ _ _ _ Sec 4 3.4 MEACTORCOOLANTSYSTEM 3 4.2 SAFETY VALVES, i SHUTD0 U l LIMITING CO TION FOR OPERATION 3.4.2.1 A minim .of one pressurizer Code safety valve shall be OPERABL ith a lift setting of 2485 psig i 1%.* t \ lAPPLICABILITY: MODES h and 5.
\
ACTION:
; With no pressurizer Code safety valve OPERABLE, immediately #6 spend all opera-tions involving positive reactivity changes and place an 0.PERABLE RHR loop into
. . operation in the shutdown coolih mode. j
\, ,'
/
s\ / O.
~ \
x.'
'x \,
SURVEILLANCE REQUIREMENTS -' 's i .. \
- ./ \
4.4.2.1 No additional requirements'other th4n thoshs re
\quiredby Specification 4.0.5.
, l 4
N
\
< \ ;
/ s, l
/ ',
\ >
/
, 1 i
l e lift setting pressure shall correspond to ambient conditions of the valve
~
- i"
! t nominal operating temperature and pressure. . O I
l BRAIDWOOD - UNITS 1 & 2 3/4 4-9 .
l i l O Lt.o 8. st. IO O s.* "cac'oa coo'a"' svs'e" race) - 3.4.10 Pre +5ar1 car Safe 3y Valvas M" LIMITING CONDITION FOR OPERATION LCo J.4.10 l M All pressurizer Code safety valves shall be OPERABLE with a lift setting of 2485 psig i IL F APPLICABILITY: MODES 1, 2, and 3. ACTION: Gosp 4 With one pressurizer Code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes orfbe in at least HOTT CON 9 8 [ STANDBY within 6 hours and in at least HOT SHUTDOWN within the following ]
\ 6 hours.I CMT B = (rNsu 7 3.9.uos) ~
SURVEILLANCE REQUIREMENTS l ( A 3.8.10.1 6 No additional requirements other than those required by Specification 4.0.5. i l l LCO HoTL = (rusLr 2.4-wn)
~
'*Thelift[ettingpressureshallcorrespondtoambientconditionsofthevalve) i at nominal operating temperature and pressure.f l
O BRAIDWOOD - UNITS I & 2 3/4 4-10
t 1 CTS INSERT (S)
=Q SECTION 3.4 l LCO 3.4.10' !
1 l INSERT 3.4 10A (Mp ) NOTE i l The lift settings are not required.to be within the LCO limits during i
- MODE 3 for the purmse of setting the pressurizer safety valves under
- hot conditions. T11s exception is allowed for 54 hours following l
, entry into MODE 3 at normal operating temperature and pressure j provided a preliminary cold setting was made prior to heatup. j d
- i i i INSERT 3.4 108 (MS )
i- , [ CONDITION REQUIRED ACTION COMPLETION TIME Q- B. ... B.1 Be in MODE 3. 6 hours i , \ QB .E Two or more B.2 Be iii MODE 4. 12 hours t pressurizer safety
- valves inoperable.
O Revision A 1 l
- - - -_._ - - - - - .- ._- _ .- - - - _- - _ ~ - . - - - - . . Lco 3.'I.9
~
I.4 REACTOR COOLANT SYSTEM [RCS) 3,q.9 "_l'. .21 PRESSURIZER LIMITING CONDITION FOR OPERATION LCD 3 0 fm The pressurizer shall be OPERABLE with at least two groups of
~ pressurizer heaters each having a capacity of at least 150 kW,and a water level of less than or equal to 92%. T APPLICABILITY: MODES 1, 2, and 3. a.d capak ed lie:S vowered (em an engineeeea scJe43 bhtes powersqpig ,
E.IIDff: 1 Coe 5 g. With less than two groups of pressurizer heaters OPERABLE, restore at ; least two groups of pressurizer heaters to OPERABLE status within i 72 hoursfor be in at least HOT STANDBY within the next 6 hours and in) : Coon C 4-{ HOT SHUTDOWN within the following 6 hours.J gar levet not w;&tw hit Au 1 Co . A #- With the >ressurizer str. = t:: ':::: :M e; be in at least HOT STANDBY d:r. tr.:- ';;.n ;r tr 4 :,r n t: : n =lwithin 6 hours and in HOT SHUTDOWN within the following 6.1ours. l
, Lhg 'mserb c.n rds., ad Ace Ro6 Cam +rol ) j O
S.p+em k a. c.whikins Weapb\e af to& wihdrawal @ SURVEILLANCE REOUIREMENTS S R 3.LI.9. 8
- .:.U The pressurizer water level shall be determined to be within its limit at least once per 12 hours, a 2.4.9.2 (f.t.3.2) Th'e capacity of each of the above required groups of pressurizer
, heaters shall be ferrifiid b7 es e. g .o ne U.s ..6 cia . . .u .. . .....; a r m d,
;=r;r.t' at least once each [ refueling interval. ' g' S R 3 A .9.3 l e s pa 6 1.' +y c4 Md 2A M . 4. 3._3' The ---- --lT tWpressurizer heaters tithe ESF power supply
, shall be demonstrated OPERABLE at least once per 18' months ---- " -- -- ,'
[4ete.H __ j ' g oc ewens vg BRAIDWOOD - UNITS 1 & 2 3/4 4-11 AMENDMENT NO. 74
, . . _ _ _ . . _ . _ _ __ . . _ . . _ . . _ . _ . _ - _ . ~ . _ _ _ _ . . _ _ _ _ . _ _
L.-c 3.i,ei 3,1 REACTOR COOLANT SYSTEM (nc.d u.n c/:.:.: = xr =.r M P 7. - or r. e ia % ( =v.)) LIMITING CONDITION FOR OPERATION tt.o3M.it 6 Both power-operated relief valves (PORVs) and their associated block l volves shall be OPERABLE. l l m,rw.8 u _ APPLICABILITY: MDDES 1, 2, and 3.
~ ACTION: C " "'8*'" I h
, [and ca>We d beWatty cycleo coadA y With one or more PORV(s) inoperablee-- e :: r r xire :en 1:25r:
within 1 hour r- - r r: -- ---- -) -- - == = H c or close the associated block valve (s) with mwer maintained to the block ~~ valvefs):1otherwise be in at least iDT STAnus" within 6 hours and)
- (m] D n HD" 5HUTnnWW within the followino 6 hours.
0 5wmai.,.tanau,mmeva .faWi*0 wi ho , ! !'or)close the associated block valve and remove power from the block ! ' valve; restore the PORV to OPERABLE status within " f WM } 72 hourslor be in HDT STANDBY w1 thin the next 6 hours and in MT) Coul 0 u ,-ww g l ce0E Jr: , With HUTDOWN both PORVs inoperable within the & ^ followina
. : --- : cr:6 hours. I gN '$$x= : n:t?l within I hour (;i'J.= rn'n. :t h=t x:
l
;, W ,r close
,e4etenJo its associated block valve and remove power fros'""! t 0" '
u "'"LE ock valveland be in HDT STANDBY within the next 6 hours and) l Q h 'the in HDTb' 5HUTDOWN within the followino 6 hours. I An i Wit storu'the# l l t.oND C/F d'd r=h: one r :r:1 or more block valves inoperable, within 1 hourn _F r e r ? "! - ' J manual centro'. Restore at ' east one block valve to OPERABLE status ! restore l vi iiisi Tid i.at hour it isoth block v&ivo div inoperable;ithin 72 any remaining inoperable block valve to OPERABLE status w i hotrs:Iotherwise, be in et. ivas.t HD15TANDBY within the next 6 hours)
- ccm o 0/ (.ani.110T. SHUTDOWN within_the, fo11owina.6 hourA/
M .. ,4 u, ie, The provisions of Specification 3.0.4 are not applicable. i SURVEILLANCE REQUIREMENTS N C: dditix 0; tr.: 7;;ic. nt; ;f Ocifi;;ti= '.0.5.ych PORV shall be demonstrated DPERABLE at least once per 18 months by: 4 Fer ";r7;- := Of : C"'?""'t C^LIEP*TE" Of t': =-tuation - LA
- L in;tra.utti
- . WJ i
se s.v.si.3 .tr.' Operating solenoid air control and check valves on associated air accumulators in the PORV control system through one complete cycle of full travel, and 2 8M.tl.:t # ,0mrating the valve through one complete cycle of full travel Giurind '
$P-3.4 il ? Abte. < ulns 3or w t n In s , ri. 3.4 826 l sn s.s.u. T MT4;lb Each block valve s 11 be demonstrated OPERABLE at least once per B2 da,s by o,eratino the vaive throu h one cos,iete c,cie of fuii travei;uniess3 O 5mit i rthe block valve is closedtwM.h4swer4,;M )in order to meet the requirements 1 W tof ACTION b. or c. of Specification 3.4.4.]
Se 2 3/4 4-12 AMENDMENT NO. 2, 33 BRAIDWOOD - UNITS 1 & 2
O CTS INSERT (S) SECTION 3.4 LCO 3.4.11 INSERT 3.4 12A (Ao)i ) ACTIONS NOTES
- 1. Separate Condition entry is allowed for each PORV and each block valve. '
- 2. ...
I INSERT 3.4 128 (La) SURVEILLANCE FREQUENCY SR 3.4.11.2 NOTE i -]L- Only required to be performed in MODES 1 ' and 2. I i O Revision A
. . _ - -. _ .- - - .- - - - - - - _ - - -. - - _ - ~ . - - . . -
i v4CTOR ram 4MT SYSTEM sp,a ciaw,, gy 3/4 AN EENERAT.QBE i h- LIMITING CONDITI N OpMtATION
/
[- 3.4.5 Each steam generator shall DPERABLE. APPLICABILITY: MODES 1, 2, 3 and 4. , gngg. . With one or more steam- tors inoperable, restore the operable steam generator (s) to OPE status prior to increasing T ,abov 00*F. SURVE CE REOUIREMENTS _' \ su ulM: m s u.r 3,4- m ; Q 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection progran and the requirements of Specification 4.0.5. 4.4.5.1 steam Generator 5==le selection and Insnection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1. O 4.4.5.2 St-weruor rose. s.-,e selecii.n .nd In,<,eciion - The steam generator tube m!nimum sample size, inspection result classification, and the corresponding act'on required shall be as specified in Table 4.4-2. The inservice inspectian 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 Specificathn 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 i 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: - j
- a. Where experience 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' l (subsequent to the preservice inspection) of each steam generator shall include:
*When referring to a steam generator tube, the sleeve shall be considered a O part of the tube if the tube has been repaired per Specification 4.4.5.4.a.10.
was-See.I E f.- h to BRAIDWDDD - UNITS 3 & 2 3/4 4-13 AMENDMENT NO. 46
t I fQ CTS INSERT (S) SECTION 3.4
- i i e LCO 3.4.13 j INSERT 3.4 13A (A3 ) .
4 SURVEILLANCE FREQUENCY i SR 3.4.13.2 Verify steam generator tube integrity is, in In accordance
.accordance with the Steam Generator Tube with the Steam >
- Surveillance Program. Generator Tube Surveillance Program i
O l l 1 O Revision A 1 l
[ REACTOR cDotANT SYSTEM tco 3.4. t& , 3/4.4.5 STEAM GENERATORS _ _ _ - - N' N 359 \ kWud in SeeH.- JA- - ! O tra>Tias cono1 Tion roa oPERAT1on ""o*'+S-9 " l 3.4*.5 Each steam generator shall be OPERAPiE. , APPLICABILITY: MODES 1, 2, 3 and 4. EIl[M: - - l With one or more steam generators inoperable, restore the inoperable steam generator (s) to OPERABLE status prior to increasing T , above 200*F. SURVE1LLANCE REDUIREMENTS l 1 l @ l ? 5.5 A 83G;9 Each steam generator shall be demonstrated OPERABLE by performance of
- the following augmented inservice inspection progrash-- --- --------- : - i '
crert ::: ::: L3 i
.5.5.9. a 5'PGE 71 Steam Generator Samole Selection and Insoaction - Each steam generator -
shall be determined OPERABLE during shutdown by selecting and. inspecting at l 1 east the minimum number of steam generators specified in Table 4.4-1. ! S.5.9.b A=4:5=E Steam Generator Tube
- Samole Selection and Insoection - The steam
- generator tube minimum sample size, inspection result classification, and the j 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 j verified acceptable per the acceptance criteria of Specification 4.4.5.4. When i 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 conhidered an area i requiring reinspection. The tubes selected for each inservice inspection shall 4 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:
i 5.5.t b. i X. Where experience 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 criti. cal areas; 5 5.9.b. 2. .kr. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include: 4 l i ! i UU j O ~ *,W. hen rt of thereferring to tube 1.be 4f the a steam generator has been repaired tube, the sleeve per spec 4f4 cation shall 4 ebe am S.S . 9. e. considered ! } BRAIDWD0D - UNITS 3 & 2 3/4 4-13 AMENDMENT NO. 46
_m _ _ _ _ _ . _._._ I S ec % n 3.4 SURVEILLANCE REDUIREMENTS (Conti-pd) .5pe c. f,.m S S 'l
- 1) All tubes-that previously had detectable tube wall penetrations greater than 205 that have not been plugged or sleeved in the i O affected area, and all tubes that previously had detectable sleeve wall . penetrations that have not tisen plugged, i 21 , Tubes in those areas where experience haL indicated potential problems, .
1
- 3) A tube inspection (pursuant to specification 4.4.5.4a.8) shall be perfomed 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 be selected and : subjected to a tube inspection,' l
- 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 inspected by bobbin coil probe during all future refueling outages, and .
, \ l
- 5) For Upit 1, tubes which remain in service due to the application of l l
I the F criteria will be inspected, in the tubesheet region, during all future outages.
- c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube l
inspection provided:
- 1) The tubes selected for these samples include the tubes from those l O areas of the tube sheet array where tubes with imperfections were previously found, and
- 2) The inspections include those portions of the tubes where 1mperfections were previously found.
- d. For 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 cold-leg tube support plate with known outside diameter i
stress corrosion cracking lowest cold-leg tube suppor(ODSCC) indications. t plate intersections TheODSCC having determination indications of the 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 I 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 !
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 i inspection for the sleeves is required on all types of sleeves installed in the Byron and Braidwood Steam Generators to demonstrate acceptable !O structurai inte rity. Aabrassab '.s
._ ==
Sec% T.O Jet %0C. -let SecMen T. 0 BRAIDWOOD - UNITS 1 & 2 3/4 4-14 AMENDMENT NO. 75
REACTOR COOLANT SYSTEM "
.5psdOcart.w 5.0 i SURVETLLANCE REQUIREMENTS (Continued) 'S u l;.n 34 :
- 5. SAL.a.0Q All tubes that previously had detectable tube wall penetrations a
-O- sreater thaa 20x that have not be a p1ussed or sleeved in the 3 affected area, and all tubes that previously had detectable sleeve wall penetrations that have not been plugged,
- s.s.o.62. Q ) Tubes in those areas where experience has indicated ~ potential !
problems, 3, q . b.p. 44 1) A tube inspection (pursuant to Specification 4.4.5.4a.8) shall be i j performe:I on each selected tube. If any selected tube dces not 4- . permit the passage of the eddy current probe for a. tube inspection, i this shall L9 recorded and an adjacent tube shall be selected and subjected to a tube inspection, 55Ab2 n N)
, For Unit 1, indications left in service as a' result of application of ;
the tube support plate voltage-based repair criteria shall be 3
; inspected by bobbin coil probe during all future refueling outages,
- and s.s.4.6.a.v % For Unit 1, tubes which remain in service due to the application of I the F' criteria will be inspected,. in the tubesheet region, during
all future outages. ! 1 i 5'5'q'@. The tubes selected as th'e second and third samples (if required by Table ! i 4.4-2) during each inservice inspection may be. subjected to a partial tube inspection provided:
- O s.s.o.u.2x Tue tubes seiected for these samples include xhe tubes from 1 hose !
i areas of the tube sheet array where tubes with imperfections were ! previously found, and ,
- 5. s.9.6.3.u b The inspections include those portions of the tubes where imperfection previously found.
7 - i s.5.q.6.1K. For Unit 1 Cycle ,i enentation of the steam generator tube / tube support plate repair criteria requires a 100-percent bobbin coil , a inspection for hot-leg and cold-leg tube support plate intersections down " to the lowest cold-leg tube support plate with known outside diameter i stress corrosion cracking (ODSCC) indications. The determination of the 1 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 Ab.5\. A random sample of at least 20% of the total number of laser welded slEaN and at least 20% of the total number of TIG welded sleeves i installed shall be inspected for axial and circumferential indications at the end of each cycle. In the 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. 2 These inservice inspections will include the entire sleeve, the tube at
!' A the heat treated area, and the tube to sleeve joints. The inservice V inspection for the sleeves is required on all types of sleeves installed 4 in thesveen-emB Braidwood Steam Generators to demonstrate acceptable structural integrity.
l l BRAIDWOOD - UNITS'l & 2 3/4 4-14 AMENDMENT NO. 75
.- . . - . . .- . . . - - .~ . - ..- -- . - . . . . . - . . . --- - - - . - - . - . . . _ . ~
- l
- . kn 3.+ -
Sy Oc.hi 5.5 - i -% s r
- REACTOR COOLANT SYSTEM
' . /&mel 14 ScAim s.o
- O- ?
'See hoc. 4n Sph r.0 SURVEILLANCE REDUIREMENTS (Continued) i i
i The results of each sample inspection shall be classified into one of the ~ i 1 following three categories: Catacory Insnection Results 5 C-1 Less than' 5% of the total tubes inspected are .
- degraded tubes and none of the inspected tubes are defe.ctive.
l C-2 One or more tubes, but not more than 1% of the
- total tubes inspected are defective, or between i
5% and 10% of the total tubes inspected are
- degraded tubes.
! C-3 More than 10% of the total tubes inspected are 4 - degraded tubes or more than 1% of the inspected ;
... tubes are defective. '
i Note: In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than 20% of wall thickness) further wall penetrations to be included O '"'h'*'""'''"'*"'- i O sRArowooo - untTS i i 2 2/4 4 AnEnoatur a0. 7s
i SpacKi ecchen 5.5 9 Se c.Aion Li
,- REACTOR COOLANT SYSTEM
- 5. 5 9 . c. In s p e c fe o n Re,s v l+ C.la ss ..f. ce,4,,,
\
SURVEILLANCE RE0VIREMENTS (Continued)
.9 The results of each sample inspection shall be ctassified into one of the i following three categories: !
M '
, Cateoory Insoection Results C-1 Less than.5% of the total tubes inspected are l 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 Mote than 10% of the total tubes inspected are l degraded tubes or more than 1% of the ins?ected ) tubes are defective. Note: -Ir.elli.gecti=:,[eviouslydegrade'dtubesorsleeves must exhibit significant (greater than 10% of wall thickness) further wall penetrations to be included in the abase percentage calculations. i L / l l i O BRAIDWOOD - UNITS 1 & 2 3/4 4-14C AMENDMENT NO. 75
Secb 3.4 sec,Gr hba.55 A$c & 'm Gae.W s do O ses- POC &r Seam 5:0 REACTOR COOLANT SYSTEM l SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frecuencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
- a. The first inservice inspection shall be perfomed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be perfomed at intervals of not less than 12 nor more than 24 calendar months after the previoqs
, inspection. If two consecutive inspections, not including the pre .
l service inspection, result in all inspection results falling into the l C-1 category or if two consecutive inspections demonstrate that pre-viously observed degradation has not continued and no additional l degradation has occurred, the inspection interval r,ay be extended l to a maximum of once per 40 months; l - l 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 l 1 east 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 t. hen 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 shut % 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 Specificatiori 3.4.6.2c. , or
- 2) A seismic occurrence greater than the operating Basis Earthquake, or j
- 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.
e O l BRAIDWOOD - UNITS'I & 2 3/4 4-15
__ __ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ . _ _ _ . _ - - . i : ! l l S neRn.M.,5.0 -l S e4;o s.4 O REACTOR COOLANT SYSTEM j x' g SURVEILLANCE REQUIREMENTS (Continued) 55.i.J 4:x= c
- Inspection Frequencies - The above required inservice inspections of l steam generator tubes shall be performed at the following frequencies:
l x The first inservice inspection shall be performed after 6 Effective full Power Months but within 24 calendar months of initial criticality. 5 T,9 L I Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous 5 T.9.d.2. ', inspection. SIf two consecutive inspections, not including the pre-service inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that pre-viously observ,ed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; 55.9.J.3 Jr. If the results of the inservice inspection of a steam generator j conducted in accordance with Table 4.4-2 at 40-month intervals fall i in Category C-3, the inspection frequency shall be increased to at l 1 east once per 20 months. The' increase in inspection frequency ) 0 a ii aair atii ta
- a at 4a a cti a=
Specification 4.4.5.3a.; the interval may then be extended to a ti <> ta crit r4 at ' maximum of once per 40 months; and 5.1.JA p. 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: S E.9.J A. L. EJ 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
.55.9. J A.ti & A seismic occurrence greater than the Operating Basis Earthquake, or 5' . 5.9 . J . 4 . u. ' R A Condition IV loss-of-coolant accident requiring actuation of the Engineered Safety Features, or l E.f.i .d . 4. ir W A Condition IV main steam line or feedwater line break.
O l BRAIDWOOD - UNITS 1 & 2 3/4 4-15 j
4 !O cts 1NsERTcs> sECTION 5.0 f i ' Braidwood Specification 5.5.9 il INSERT 3.4 15A (A3 ) 4 The provisions of SR 3.0.2 are not applicable to SG Tube Surveillance Program
- inspection frequencies. ,
i. +, t O O Revision A
REACTOR COOLANT SYST.3 Albened ESeth s.o 4 See hoc h Sechr.o { 55 SURVEILLANCE RE0UIREMENTS (Continued) n O **54 ^cc "*""c" c"'
- a. As used in this specification:
- 1) Innerfection means an exception tT"The dimensions, finish or i
i contour of a tube or sleeve from that required by fabrication drawings or specifications. 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 corrosion occurring on either inside or outside of a i
4 tube or sleeve;
- 3) Deoraded Tube means a tube or sleeve containing unrepaired imperfections greater than or equal to 20% of the nominal tube or sleeve wall thickness caused by degradation;
- 4) % Deoradatl2D means the percentage of the tube or sleeve wall thickness affected or removed by degradation;
- 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;
- 6) Pluacino or Reosir limit means the imperfection depth at or (3
i 1 v 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 ; i sleeves is equal to 40% of the nominal wall thickness. The i plugging limit imperfection depth for TIG welded sleeves is equal to 32% of the nominal hall thickness. Fer Unit 1, this definition does not apply to defects in the tubesheet that meet the criteria for an F tube. For Unit 1 Cycle 6, this i l
- definition does not apply to the tube support plate
, intersections for which the voltage-based repair . criteria are 2 being applied. ' Refer to 4.4.5.4.a.11 for the repair limit applicable to these intersections; 4 7) i Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integ-l rity in the event of an Operating Basis Earthquake, a loss-of-i coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c., above;
- 8) Tube inspection means an inspection of the steam generator tube
- 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 i
O O BRAIDWOOD - UNITS 1 & 2 3/4 4-16 2 AMENDMENT NO. 75
REACTOR' COOLANT SYSTEM A Spec 4.<d.,.s.o-
**" M SURVEILLANCE RE0VIREMENTS (Continued) l O ssse4 . .:.4 Acceota#ce criteria 1 i
- 2. a w ,,,ais w rk.ticr.s i
.5. s , q , ,,, , ' y imperfection means an exception-+e-the dimensions, finish or contour of a tube or sleeve 'from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections; 5.6.q. g % Deoradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a j
tube or sleeve; " 5 5.9.e.3 pf Deoraded Tube means a tube or sleeve containing unrepaired imperfections greater than or equal to 20% of the nominal tube , or sleeve wall thickness caused by degradation; i 5.s.q.e A ff % Deoradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation; 5 5.9.e.5 / Defect means an imperfection of such severity that it exceeds i the plugging or repair limit. A tube or sleeve containing an i unrepaired defect is defective; 5 5 Sc.6 /d Pluacino or Repair limit means the imperfection depth at or O beyond wnich 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 plugging limit imperfection depth for TIG welded sleeves is
- equal to 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.9/ For Unit 1 Cycle % thW definition does not apply to the tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.5.4.a. for he rep' air limit applicable to these intersections; 13 ( 5 5 4.e.7 J4' Unserviceable describes the condition of a tube if it leaks or ,
. contains a defect large enough to affect its structural integ- j rity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam iine or feedwater line break as specified in 4.4.5.3c., above; 5 5 c)'e. g g Tube Inspection means an inspection of the steam generator tube 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 BRAIDWOOD - UNITS 1 & 2 3/4 4-16 AMEllDMENT NO. 75
f REACTOR COOLANT SYSTEM 'M Ssa bOC kr See4.om T.O ' pbMa f SURVEILLANCE REOUIREMENTS (Continued) U ! X g) Preservice Innne;,tj,an means an inspr,ction of the full length of 4 () each tube in each steam generator perfomed by addy current techniques prior ',o serv <ce to establish a baseline condition j' of the tubinn. This inspection shall be perfomed prior to initial j - - POWER OPERATLON using the equipment 9and techni { used during sut, sequent inservice inspections. ques expected to be l 10) Tube Renair refers to a process that reestablishes tube i serviceability. Acceptable tube repairs will be perfomed by.the, j following processes: , i a) Laser weldei slesving as described in a Westinghouse Technical 4 Report curre.:tly approved by the NRC, subject to the i limitations and restrictions as noted by the NRC staff, or b) TIG welded sleeving as described in A88 Combustion Engineering j Inc. Technical Reports: Licensing Report CEN-621-P, Revision 00, " Commonwealth Edison Byron and Braidwood Unit I
- and 2 Steam Generators Tube Repair Using Leak Tight Sleeves, i
FINAL REPORT," April 1995, and Licensing Report CEN-627-P, i Revision 00-P, ' Verification of the Installation Process and . Operating Perfomance of the ABB 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 O insta11ed as a corrective or Preventative meas re. A t 6e 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 Sunnart Plate Plunaine Limit is used i
for the disposition of an alloy 600 steam generator tube for l continued service that is experiencing predominantly axially l
- oriented outside diameter stress corrosion cracking confined within i the thi~ckness of the tube support plates. At tube support plate t intersections, the plugging (repair) limit is based on maintain'mg 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 i
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-lag tube support plate j
with bobbin voltages less than or equal to 3.0 volts will be allowed to remain in service. 3 b. ~ Steam generator tubes with degradation attributed to outside i diameter stress corrosion cracking within the bounds of the cold-leg tube support plate with a bobbin voltage greater than
.O plugged,'except as noted in rNote
'"' "' 1). viii be repaired or 4.4.5.4.a.11.d below, ' " " t a
BRAIDWOOD - UNITS 1 & 2 3/4 4-17 AMENDMENT NO. 75 4
REACTOR COOLANT SYSTEM Sp o c.4 c.4,en 5. o 5 " 3'# SURVETLLANCE REOUTREMENTS (Continued) f') v 5. 5.9. 4 .q '!Q Preservice Insoection means an inspection of the full length of 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' POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections. 5.59.c. lok) Tube Reoair refers to a prccess that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following processes:
- 5. 5 re.e DQ Laser welded sleeving as described in a Westinghouse Technical Report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff, or 5.5 c . e dtQ TIG welded sleeving as described in ABB Combustion Engineering Inc. Technical Reports: Licensing Report CEN-621-P, Revision 00, " Commonwealth Edison Byron and Braidwood Unit I 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 ABB 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.
n ('j 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 required prior to returning i nrav, plugg s to service. 1 O( ( C_Iase r4 h.4- SD j N h) ' 1 Cycle , Tube Succort Plate Pluacino limit is used r, i for the disposition of an alloy 600 steam generator tube for
~ 4 8 J3 continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within l
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 . o.4 A Steam generator tubes, with degradation attributed to outside diameter stress corrosion cracking within the bounds of the
( p,,, sg., td,p ( L % , r ,,4. v-eld 7e- te =ccrt phtT)with bobbin voltages less than or equal to the lower voltage repair limit [ Note 1] will be
, allowed to remain in service. Steam generator degradation attributed to outsid ss corrosion cracking within the bounds of t M leg t P < a t m ; mp with bobbin voltages less than or eaual to 3.0 voitt will be ,
allowed.to remain in service. l VL ec k ., v-L b 4 H oh ll
\n,s,see-4..,e j 4 5 5.9.c.n.4 h. Steam generator tubes with degra a ibuted to out e
/ f q diameter stress corrosion cracking within the b s the
()- gr e r-Spa r g Wd
'e voltage repair limit [ Note 1], will be repaired than
.he lower
+"be =ppert plate with a bobbin voltage greater or h "5*< lugged, except as noted in 4.4.5.4.a. .d below.
BRAIDWOOD - UNITS 1 2 2 3/4 4-17 AMENDMENT NO. 75
l CTS INSERT (S) O- SECTION 5.0 ' i I Specification 5.5.9 INSERT 3.4-17A (Au and A ) 3 <- y N 5.5.9.e.J1 M Tb NModel 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
/
inches during accident conditions. excluding the following: 1.4) All tube-to-tube support plate intersections where IPC
? cannot be applied per Generic Letter 95-05:
f .R h) All Flow Distribution Baffle intersections:
\
All steam generator tube intersections adjacent to an [MM
' intersection that contains a corrosion induced dent greater -
than 0.065 inches; and h All tube-to-tube support plate intersections that will be displaced more than 0.1 inches during accident conditions i due to failure of the steam generator internal structures. Q 5.5.9.e.1 Free-Scan 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: All tube-to-tube support plate intersections where IPC
.i 'e}
cannot be applied per Generic Letter 95-05: and
/
[k All Flow Distribution Baffle intersections.
\
V d Q .I o Revision A e
.- . - . - . - . . . . - - - . - - - - - - - - - - - - = - - - -
1 1 q AMwnaL in Se.een go RrACTOR C001 ANT..SYSTE *-l*'- O'- M *s40 ! l O suavr> trance araurararars <c ntin d> Sec b 3.4 s a-S 5s i'
- c. Steam generator tubes with degradation attributed to 4
outside diameter stress corrosion cracking within the l ' bounds of the hot-leg tube support plate with a bobbin greater than 3.0 volts will be repaired or i i
- d. Steam generator' tubes, with indications of potential J l degradation attributed to outside diameter stress
]
- corrosion cracking within the bounds of the cold-leg tube support plate with a bobbin voltage greater than the l lower voltage repair limit [ Note 1] but less than or i
j equal to the upper voltage repair limit [ Note 2 , au remain in service if a rotating pancake coil ins]pection { doea not detect degradation. Steam generator tubes with i 1 Nication of outside diameter stress corrosion crac, king degradation within the bounds of the cold-leg tube ! support plate with a bobbin voltage greater than the j upper voltage repair limit [ Note 2] will be plugged or i I repaired. l e. Certain intersections as identified in WCAp-14046,
- j. Section 4.7, will be excluded from application of the voltage-based repair criteria as it is determined that 3
these intersections may collapse or deform following a O =***" '"c^ + 555 a' f. If an unscheduled mid-cycle inspection is performed, the ! i 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 l i 4.4.5.4.a.11.d for outside diameter stress corrosion cracking indications occurring in the steam generator ! cold-legs. For outside diameter stress corrosion cracking indications occurring in the steam generator , i 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 i the following equations: pair limits are determined from 1 - y" l Va=
- 1. 0 + AIDE +Gr ( )
Va= V - ( Y - Vm)( *) a i 1 1 v i O
- BRAIDWOOD - UNITS 1 & 2 3/4 4-17a AMENDMENT N0. 69
t 5 pee.C,a. 3D ' REACTOR COOLANT SYSTEM
] g -SURVEILLANCE RE0UIREMENTS (Continued) 55.9. e .13 A E
~ Steam generator tubes with degradation attributed to I
Loc.x,s.%74, outside diameter stress corrosion cracking within the
/D*/
bd. I gounas et the/J.Ch tri: l ! ;~M .l e.l u.,.uw,dvoltage M 1ugged. greater than;3.0 volts will be repaired ortr;;:M pht with , i SS.i c)3 iv g. 1 . Steam generator tubes, with indications of potential ! degradation attributed to outside diameter stress l corrosion cracking within the bounds of the ecld ;+d: m er;;;f. pht:- with a bobbin voltage greater than the l ' 1 Fr.. -sp.n M a,i (lower voltage repair limit [ Note 11 but less than or 4 qual to the upper voltage repair limit [ Note 2), may i 2"Y#'c+'*"8 in in service if a rotating pancake coil inspection oes not detect degradation. Steam generator tubes with
>1ndication of outside diameter stress corrosion crac, king degradation within the bounds of the ::!d h; 'd:
cr;;:-t ;hte with a bobbin voltage greater than the upper voltage repair limit [ Note 2] will be plugged or repaired. 5 5.9.c.13. v g. 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 deform following a , O postulated LOCA + SSE event.' - Aa4 i 55.9.e.f 3 vi I. If an unscheduled mid-c 13 pe is performed, the following mid-cyc1 pair lim 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
( fre e-Sp n M od<l cracking
- 1d hgs indications occurring in the 21: = gn = ter i i
1 zn w e << 4. m For outside diameter stress corrosion A f t l r L oci ,d To b * ( %+ 1 the limits in occurring
, cracking indications in the e --- ----- +--
4.4.5.4.a. .a and 4.4.5.4.a. i apply. The mid-cycle re c ! M od e i In4ersec % m , the following equations: pair limits a terni rom ! I3 Va Va= 1.0+RDE+Gr( g) pg w () a 4,, u,,,, 3a <f la IekesnLm { or e t. Iso e m c linie J [ro n afpI.'c.4*a* o$ l Va= Vm (VmVm) ( yg g) y, nuy .p , s re po r c.r.4 *ri a . I O A M i BRAIDWOOD - UNITS 1 & 2 3/4 4-17a AMENDMENT NO. 69
1
~
~
' A W e e k k See w s t o kEALTOR COOLANT SYSTEM N 9"** Sen e 3.+ O suavrittANCr at0urarNrNTs < continued, 5 a-u u Where: V. V upper voltage repair limit lower voltage repair limit V . tat - mid-cycle upper voltage repair limit based on time into cycle V,t,t - mid-cycle lower voltage repair limit t.and time into cycle At - based on length of V, time since last scheduled inspection during which V and Vt ,t were implemented. CL - cycle length (the time between two scheduled steam generator l inspections) V t
- structural limit voltage G,r -
average growth rate per cycle length NDE - g5-percent cumulative probability allowance for nondestructive j examination uncertainty (i.e., a ' 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, O " 4.4.s.4.a.22.c and 4.4.5.4;a.ii.d. Note 1: The lower voltage . repair limit is 1.0 volt for indications of outside diameter stress corrosion cracking occurring at cold-leg l tube support plate intersections. ; Note 2: The upper voltage repair limit for indications of outside diameter stress corrosion cracking occurring at cold-leg tube support plate i intersections is calculated according to the methodology in Generic Letter g5-05 as supplemented.
- 12) F* Distance is the distance into the tubesheet from the !
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 9eometry. .
- b. The steam generator 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 AMENDNENT NO. 69
See, rC h f.o '! RrACTOR COOLANT SYSTet! #*d*** i O e suRvrittANet Rr0u1RrNr 15 < cont 4nued, Where: Vu - upper voltage repair limit Vtt ,at - lower voltage repair limit V ot mid-cycle upper voltage repair limit based on time into cycle V,t,t - mid-cycle lower voltage repair limit based on V t and time into cycle , at - length of U ne since last scheduled inspection during which Vuat and Vt,g were implemented. i CL = cycle length (the time between two
)
scheduled steam generator l inspections) l V G,r t structural limit voltage average growth rate per cycle length
- NDE =
95-percent cumulative probability j allowance for nondestructive examination uncertainty (i.e., a i l value of 20 percent has been l' i > approved by NRC) Implementation of these mid-cycl repair limits should follow the ! j same approach as in TS 4.4.5.4.a. .a. 4 .5.4.a. .b, O S.s A.e. l3 4454- cn 44s4 - <> i Q 1 ! Note 1: The lower volta repair limit .0 volt for indic l outside diameter rtress corrosion cracking occurr' .=+~'d '7 4
-t& 5r;;e-t pht: ntersections. i n +h e fre e Spo n '
l s.s.9. . o M od' I } Not? 2: The upper voltage repair limit for indications o unit 'di:-- l stress corrosion cracking occurring e re'd h; t& =;;:-t ;he 1 l fntersectionsiscaiculatedaccordingtothemethodologyin
- Generic Letter 95-05 as supplemented.
era e.14 F* Distance is the distance into the tubesheet from the ( secondary face of the tubesheet or the top of the last hardroll, whichever is further into the tubesheet, that has i been determined to be 1.7 inches. l S.5 9.e.15 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. O4 Defects contained in an F tube are not dependant on flaw . geometry. 5.53.e..I (. Ar. The steam generator 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 i
Table 4.4-2. l j l l BRAIDWOOD - UNITS 1 & 2 3/4 4-17b AMENDMENT NO. 69 l
- 1
. -.- . .. - - - - - . - _ - . . - - . - - - - - - - . . - ~ --
1 I W oukisSomsCo REAC10R COOLANT SYSTit' *
- u w-becken b A
- O svR m otA CE = 0u1= = #15 <Co tinued) u-4.4.5.5 Reoorts
- a. Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2;
- b. The complete results of' the steam' generator tube inservice -
inspection shall be submitted to the Comunission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
- 1) Number and extent of tubes inspected,
- 2) Location and percent of wall-thickness penetration for each j indication of an imperfection, and
- 3) Identification of tubes plugged or repaired.
- c. Results of steam generator tube inspections which fall into -l 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 , Q } a description of investigations conducted to detemine cause of the tube degradation and corrective measures taken to prevent ! recurrence. l I 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 the following conditions arise:
- 1. If estimated leakage based on the projected end-of-cycle (or i
if not practical, using the actual measured end-of-cycle) ' l 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. l
- 2. If circumferential crack-like indications are detected at the tube support plate intersections.
- 3. If indications are identified that extend beyond the confines of the tube support plate.
- 4. If indications are identified at the tube support pitte elevations that are attributable to primary water stress corrosion cracking.
O BRAIDWOOD - UNITS 1 & 2 3/4 4-17c AMENDMENT NO. 69
. . _ ___ _ _ _ . _ . ._ ~ _. _. . . .
l SHE.% 5 0 H REACTOR C00LANT SYSTEM s u % s.4 q O i !
@ suavett'aace atoutarara's <ce#14 #ed) f4-44r+----NeeeM44 4
I 54, 9 . a. Mithin 15 days /Mlowing the completion of each inservice f.
- ' inspection \of steam generator tubes, the number of tubes plugged or repaired,in each steam generator shall be reported to the Commission P
- :::::: S::;r: : r::::: :: :::: ::::::: 1. 2 z a
! Eb.7 b f. The complete results of the steam' generator tube inservice inspection shall be submitted to the Commission (m+4cee+e4-1 ' Sport pur;u:.nt in Ep:r
- r:W '^")within12monthsfollowing the completion of the inspection. This Special Report shall include:
S49bI Jr Number and extent of tubes inspected, , h ^ I k 9 b. 2. M Location and percent of wall-thickness penetration for each indication of an imperfection, and 5.b i b 1 )7 Identification of tubes plugged or repaired. i 5.4. 9 .c t. Results of steam generator tube inspections which fall into - Categcry C-3 shall be reported in a Special Report to the Commission
! within 30 days and prior to resumption of plant operation. This report shall provide ,
] a description of investigations conducted to detemine cause of the tube degradation and corrective measures taken to prevent recurrence.
t Ib9d AP. For implementation of the voltage based repai criteria to tube support plate intersections for Unit 1 Cycle notify the staff priortoreturningthesteamgeneratorstose%,iceshouldanyof rv the following conditions arise:
- 5. t,. 9. d.1 /. If estimated leakage based on the projected end-of-cycle (or 4
- if not practical, using the actual measured end-of-cycle)
] voltage distribution exceeds the leak limit (determined from ! t the licensing basis dose calculation for the postulated main 1 steam line break) for the next operating cycle.
- 5. b. 4 . d . '2.
I, _
- f. If circumferential crack-like indications are detected at the tube support plate intersections.
5.b.9.s.A y. If indications are identified that extend beyond the confines of the tube support plate.
, Et,. 9 .J 4 f'. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.
(~L nse r t '3.4 ~ l7 c A} BRAIDWOOD - UNITS 1 & 2 3/4 4-17c AMENDMENT N0. 69
em O, CTS INSERT (S)- SECTION 5.0 Specification 5.6.9 INSERT 3.4-17cA ( ) . .q 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 y coil eddy current probe currently fails to pass a 0.610 inch diameter bobbin coil eddy current probe.
\-Q ~
./
~ W- J
%)
o O l Revision A l l j
,, ,.,v..
. /tAdreewi u sea,w go ' -
Ges. Tec C*e Secum 5;o \ REACTOR CQQLANT SYSTEM A Secma.3.4
- O suavoittanto Rrouratar#1s < Con 14nceo, e, e +ss
- 5. If the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actu x 10'gl, measured notify the NRC end-of-cycle) voltage and provide distribution of an assessment exceeds the .1 safety significance of the occurrence.
l
- 6. Following a steam generator internals inspection, if. l indications detrimental to the integrity of the load path '
j necessary to support the 3.0 volt IPC are found, notify the NRC and provide an assessment of the safety significance of l 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 i
shall include: i
- 1) Identification of F* Tubes, and
- 2) Location and size of the degradation. !
1 l l
.i '
1 I 4 4 O BRAIDWOOD - UNITS 1 & 2 3/4 4-17d AMENDMENT NO. 69
l 3 pes. S s % 5 0 REACTOR COOLANT SYSTEM S ' '4 ' *
- 3 'i
- O @ suavrtttauer ar0urarMeurs <Co t4eued)
S co.9 .d .7 X. If the calculated conditional burst probability based on the i projected end-of-cycle (or if not practical, using the i actual measured end-of-cycle) voltage distribution exceeds 1 x 10 2, notify the NRC and provide an assessment of the 4 safety significance of the occurrence. 4 Sto.4.d.E . Following a steam generator internals inspection, if. indications detrimental to the integrity of the load path h necessary to support the 3.0 volt IPC are found, notify the NRC and provide an assessment of the safety significance of the occurrence. ! 5.L. 9 .c #~ The results of inspections of F* Tubes shall be reported to the I Commission prior to the resumption of plant operation. The report l
- shall include
5 6 4 e.l 4 Identification of F* Tubes, and
- 5. 6. 4 . e. 2. Location and size of the degradation.
d O i 3 i I i i 1 a
- O 4
~
BRAIDWOOD - UNITS 1 & 2 3/4 4-17d AMENDMENT NO. 69
l 5et e a 3 4 ~
.5per.Ar*M455 i
1 TABLE 4.4-1 1 - MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION ' 1 Preservice Inspection Yes No. of Steam Generators per Unit Four ~ First Inservice Inspection Two { Second & Subsequent Inservice Inspections One l 4 TABLE NOTATION
- 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 performing in a like manner. Note that under some circumstances, the i operating conditions in one or more steam generators may be found to ' be more severe than those in other steam generators. Under such - t circumstances the sample sequence shall be modified to inspect the most severe conditions. Each of the other two steam geaerators no? 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.
See )cc Gr Sec.Mou So O BRAIDWOOD - UNITS 1 & 2 3/4 4-18
1
\
.1 l Se ec ih.+..a s. o l i Su+ on i.4 \
T. s. 4 ~ l i O ' TABLE +-4-t i MINIMUM NUMBER OF STEAM GENERATORS TO BE i INSPECTED OURING INSERVICE InAFECTION l t i Preservice Inspection Yes No. of Steam Generators per Unit Four
- First Inservice Inspection
, Two Second & Subsequent Inservice Inspections l l One 3 i ' i {
- TABLE NOTATION i 1.
4 The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the i number of steam generators in the plant) if the results of the first
- or previous inspections indicate that all steam generators are performing in a like manner.
i Note that under some circumstances, the
- operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such
( circumstances the sample sequence shall be modified to inspect the j most severe conditions. Each of the other two steam generators not inspected during the first inservice ins , during the second and third inspections.pections The fourth shall besubsequent and inspected 1 i inspections shall follow the instructions described above. ) i
. I i
i O BRAIDWOOD - UNITS 1 & 2 3/4 4-18 -
() O (3 V V V T Aistu 4.4-2 txs g STEAM GENERATOR TUDE INSPECTION o 5 - g 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required 5 A mininum of C-1 None N.A. N.A. N.A. N.A. d S Tubes per C-2 Plug or repair
- S.-G. C-1 None N.A. N.A.
defective tubes and inspect additional C-2 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 R8 C-3 Perform action for N.A. N.A. C-3 result of first I" sample C3 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 S. G. are C-3 second sample akg Notificatior: to NRC pgl p 3-pursuant to Additional Inspect all tubes N.A N.A. 5 50.72 (bil2l of 10 S. G. is C-3 art 50 in each S. G. and f b) ,f o plug or repair defective tubes. ' 4h '[' Notification to E NRC pursuant to M S $ 50.72(bil2l of I 6' ' ',, 10 CFR Part 50 y cn 5 'I#% Wh&c N is 1.im numlin of steam genwalss in um unit, and n is um number of simam n uenerators inspected elurinn an insnettion -
O o
@ m< S m .
h STEAM _ GENERATOR TUBE INSPECTION U 5 g 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION - Sample Sire Result Action Required Restdt Action Regtdred Result Action Required 5 A mininum of C-1 None N.A. N.A. N.A. N.A. G S Tubes per 1
- S. G' C-2 Plug or repair C-1 None N.A. N.A. l " defective tubes and inspect additional C-2 Plug or repair C-1 None l 2S tubes in this defective tubes S. G* and inspect, C-2 Mug w repdr l additional 4S defective tubes tubes in this S. G.
C-3 Perform action for C-3 result of first sample
~
R C3 Perform action for N.A. N.A. C-3 result of first sample
; Llole-
%g C-3 Inspect all tubes in All other None N.A. N.A.
this S. G.. plug or S. G.s are repair detective C-1 tubes and inspect 2S tubes in each Some S. G.s Perform action for N.A. N.A. i other S. G. C-2 but no C-2 result of additional second sample
- N ication to C S. G. are C-3 4
7"$"* Additionai ins,eci sii tubes N.A N.A. f? g
,4,o , , , ,
,,,, , ,o S. G. is C-3 in each S. G. and plug or repair c1
;13 g defective tubes. ,
3 g g Il tification to , yg NRC s to A *
$ 083 #
550. of
', JWCFR Part 5 ine s die numl>& o s cam geyators in W unit, and n is die nudin of stram 4 S=3% 0 n generatorsinspecteddur}inganinspection -
4 U-O 3. 4. lf i - 1 ' i 3.81 REACTOR COOLANT SYSTEM (r.c.5) g { m.;.;5 == L L5.""" cc;L=: =:= L:=@ (M.s 2+ (*f* Pew % W~~e9 0 !5:T"= EY TE".h - _ 4
! LIMITING CONDI. TION FOR OPERATION i
l ! .t.o Mel5'GMFE The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE: [ Ln l .{a'.b.~TheContainmentAtmosphereParticulateRadioactivityMonitor"n: sv:t:4 l The Containment f! er " 2: :: ::nnr cem.. Rv6 Monito@ l @ 6 and - ( g-i t or The Containment Gaseous Radioactivity Monitortne-5vsteel i t t N.6 m APPLICABILITY: MODES 1, 2, 3, and 4. i (or nc W
- m. w, M W! c)
! , ACTION: g .u.,,.sr 7,.3,4 3 Nde 'k. With a. or c. of the above required Leakage Detection Systems inoperable, coup g operation may continue for up to 30 days providec grab samples of the
, containment atmosphere are obtained and analyzed = 7 :n ::= ;nd ;;rtical t;,
, ir=:::tivitpat least once per 24 hours when the required Gaseous or '
' Particulate Radioactivity Monitorina System is inoperable:J otherwise, be in )
gp c fat least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN withinj i j i the followina 30 hoursJ g y _y . j cosp te F. With b. of the above requi ed Leakage Detection Systems inoperable,+ restore l to OPERABLE status within days;Jotherwise be in at least HOT STANDBY t j C*MP C +-(within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.) j j .c. With a. and c. of the above required Leakage Detection Systems inoperable: ) l coup 5 a4 s.21)' Restore (-ither T t:rin: syst= ::. er .J to OPERABLE status within l GiMetreshand % g - l co"P 5 M.I.i 2J Obtain and analyze a grab sample of the containment atmosphere for W { gaseous and particulate radioactivity at least once per 24 hours,(.and-) or i Perform a Reactor olant System water inventory balance at least once ! coup e n s. 2 -37 Per$ hours. . 29 % % 3 om J.4-2ocA . l I coH P c- Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD ! ! g, p SHUTDOWN within the following 30 hours. T " "'##d'"** * ! SURVEILLANCE REQUIREMENTS f
- (4TED The Leakage Detection Systems shall be demonstrated OPERABLE by
i pg,$','y,( .af Containment Atmospherelmee . end er^.;; 1;tdMonitoring System-l gg y.y,g,4 performance of CHANNEL CHECK, CHANNEL CALIBRA" ION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, sump L6 sg 3,4,y;3 k!" Containment Flur Drei ere 5::r rr Er::t. 928MonitorE; i:.[- i i performance of CHANNEL CALIBRATION at least once per 18 months ~ -nd I C'
; .!!.[. $.. .}..$5.
!..S;f.f!N.... N. .[.f.b..
5 '$',55Sk.N.. f..E.'.!
. .33. s.bb. ...>
1 ( eenteinment ficer drein-tmidentified-4eekage p;r 10 nr.th:, folle;ia; . nilectida -eir M nn)' refwling, ;;d pri;r t: iri444Mtar4upr l ("The :pecified-le month-interval--may- b -extended-to-sa-months-fer cy:1: 1 erly.) Q BRAIDWOOD - UNITS 1 & 2 3/4 4-20 AMENDMENT NO. 21
, - - - - - , r
~1
. CTS INSERT (S)
- SECTION 3.4 l
LCO 3.4.15 INSERT 3.4 20A (L3 ) { NOTE LC0 3.0.4 is not applicable. INSERT 3.4-20B (A3 ) CONDITION REQUIRED ACTION COMPLETION TIME ; D. All required monitors D.1 Enter LCO 3.0.3. Immediately I inoperable. ; O-O Revision A
4 CTS INSERT (S)
~O SECTION 3.4 I
LC0 3.4.15 INSERT 3.4 20C (Ln Ln and Lu)- 2 CONDITION REQUIRED ACTION COMPLETION TIME - A. ... A.1 NOTE Not required until 12 hours after establishment of steady state operation near operating pressure. Perform SR 3.4.13.1. Once per 24 hours 6.NQ
'O ^.2 .. ...
B. ... B.1.1 ... ... 83Q B.1.2 NOTE l Not required urtil
- 12 hours after i establishment of .
steady state l operation at near operating pressure. i i O Revision A
L. : o 3.
l L' # M '85 C {150 gallons per day tTrough any one steam generator,)
Lee 5M ts.4 d: 10 ppm IDENTIFIED LEAKAGE from the Reactor Coolant System, l
- f e. 40 gpa CONTROLLED LEAKAGE at a Reactor Coolant System pressure ~^ oO
~ * ~
2235 1 20 psi
- and]
V=dM 1 = i d.* #[ 6A 3 4.Ne l f. m )1eakage at a Reactor Coolant System pressure of 2235 i 20 osi.g " l .from any Raactor, Coolant System Pressure Isolation Valve (iiipe61f46dj d
;inqabre va-Aq (M*ere per n . nut 'se.L 4 mhoe. << ee sq k <. u~~~ A fsem)
APPLICABILITY: MODES I, 2, 3, and 4. l 3 Lxr O co L s^.a'.'s' ":With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY t coup 3 .a . within 6 hours and in COLD SHOTDOWN within the following 30 hours. coup 4 Jr. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakase rate to within limits within 4 hoursfor be in at least H0T STANDBY) coHP S within the next 6 hours and in COLD SHUTD0601 within the following ) 30 hours.f 4 2,setRT 3 4-;ts A ) go 7j,[q 71 L7 E With any Reactor Coolant System Pressure Isolation Valve leakage Coe A greater than thg/above limit./ reduce the leakage rate to within ~ pitswithinWhours.)orbeinatTeastHDTSTANDBYwitEin_thenext) c o n D C. : t6 hours a_ad_,in _ COLD _ SHUTDOWN,within the following 30 hours.J acrees aerre.+ ( zmur .r.v-x e ]
*P8i q onseu .r.4. 2 c. 3 8
T p/ L [ Test-pre ssures-less- than-2235-psig-but-greater--than Observed-leakage-shell k djusted--for-the-actual-test-ptess-350 re ;;;;-pto-2235~ sig-are-aMowed.
;i;; e;; sir.;; tM 1:Wp te h di ::tly-proporational t: ;,7;;;;;.7 diffe,er,ti;1 )
( ;,e t t k x: b1f ; r:r.f 3/4 4-21 AMENDMENT NO. 57 BRAID"000 - UNITS I & 2
.{
1 O. v CTS INSERT (S) !
.SECTION 3.4 1 LCO 3.4.14 INSERT 3.4 21A (L7 ) }
CONDITION REQUIRED ACTION COMPLETION TIME l V . A. One or more flow paths NOTE- 4 with leakage from one Each valve used to satisfy l or more RCS PIVs not Required Action A.1 and ; within limit. Required Action A.2 must have : been verified to meet l SR 3.4.14.1 and be in the ! reactor coolant 3ressure ' boundary _ or the ligh pressure l portion of the system. ; A.1 Isolate the high 4 hours 4 pressure portion of _O the affected system t from the low pressure l l portion by use of one closed manual. I de-energized power i operated. ! de-activated i automatic. or check valve. ) AND A.2 ... .. l l I l l lO
- Revision A
~
y +-4g.,
P CTS INSERT (S) . SECTION 3.4 LCO 3.4.14 j INSERT 3.4 21B -(A3 ) 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.
l I INSERT 3.4-21C (M,) , CONDITION RE0lriD ACTION COMPLETION TIME O B. Residual Heat Removal B.1 Isolate the affected 4 hours-(RHR) System suction flow path by use of isolation valve one deactivated interlock function automatic valve. inoperable. 4 l O Revision A
- L. c,0 E E. 5' i i
g 3.5 EeAmensuex Coue Cootsws Swrem (ECCQ LC O 3 .4. 13 E,t. r og FS.pw L. C O 3 M \h !O l LIMITING CONDITION FOR OPERATION l s.s S Cso\ % d o^ %
- L C.O LO.4.0.D Reactor Coolant l5ystem-hehage)shall be (F958558:5594, w w t.n;y '
- a. No PRESSURE BOUNDARY LEAKAGE ' [hSee,r bOC dYer*seeMCM hn 3.4
- b. I gpa UNIDENTIFIED LEAKAGE,
! c. 500 gallons per day total reactor-to-secondary leakage through all ' I steam ponerators not isolated from the Reactor Coolant System and !- 150 ga lens per day through any one steam generator, 1
- d. 10 ppm IDENTIFIED LEAKAGE from the Reactor Coolant System, ,
[:. 20 !""LL" :.E""'f5 :t e-Ree ta C; ele;;t het;; ne; . . ;f L4 i (
'?'!. t 20 =' . r-i /
i l f. I gpu leakage at a Reactor Coolant Systes pressure of 2235 1 20 psig i from any Reactor Coolant System Pressure Isolation Valve specified I j < in Table 3.4-1. s l APPLICABil m : MODES 1, 2, 3,(-end-4Q Q Mdd5A$Y 4 S% bCC. -Qcx .5ei.%n +3. -4 * >r l EI,lg: 1 4 1 a. With any PRESSURE B0UNDARY LEAKAGE, be in at least NOT STANDBY l 4 within 6 hours and in COLD SHUTDOWN within the following 30 hours. 4 Csul A S With any Reactor Coolant System le*- ornater thauany one og } above limits / excluding PREtt"E B0UMARY LEAKAGE and leakage from , j (Reactor Coolant System Pressure Isolation Valves. Cn; tr.: ::taeas i c ,J B P :t: 1: ritt.t- it tt ' within 4 hours or be in at leas 1'HDT STANDBY thin the next 6 hours and in ---r 22.-- within tte following hours. Modt. 4 g [nsec+ 3.4.yyQ
#c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the aLove limit, reduce the leakage rate to within limits within 4 hours, or be in at least HOT 5"ANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. ,
y ,,-y Addrer se.A ws S e n k ervs. E 4 See. bCt 9er Secem M
.M
- Test pressures less than 2235 psig but greater than 350 psig are allowed.
O obs.rved isaka.e shaii be ad3usted for the actuai test pressure u, to 2235 psig assuming the leakage to be directly properational to pressure differential to the one-half power. , 3/4 4-21 AMENDMENT NO. 57 BRAIDWOOD - UNITS 1 & 2
._ _ . _ . _ _ . _ _ _ . . _ . . _ .l 4
CTS INSERT (S) C) SECTION 3.5 LCO 3.5.5 INSERT 3_d J,18 IAu ) CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow A.1 Adjust manual seal 4 hours not within limit. injection throttle 4 valves to give a flow l within the limits of I Figure 3.5.5-1. l i O l l O Revision A
i l LCO 2.4,G - ! ~ Lco "Lu.ltl
'~ ~ ~~
l.co 3.S'.S' REACTOR COOLANT SYSTEM j O SURVEILLANCE..REDEIP7MENTS
- .SR 3.4.LS, I
! Q . 5. : . :) Reactor Coelant System leakages shall be demonstrated to be within
- each of the above limits by
i j . T ..;im io, ih. w ^..;. a; ei.- ro... v.;ees; ;; ;:rre:Mt: g, ! , di:::ticity ::-it-er :t 1:: t :::: ::r 22 5::r::J a ( ___ ___ {t. i P.:: " : rte; th: = :ter ;.;;;;,: 7 c::Nir;;, x: -:: ::: = -.; t
- : di::h;r;; ;;d 'n::ter; :t ?:::t :::: ::r !? S: :;
14 ! t::r dr:t _ i l ., AM d c. Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump 3 h so: 3. , seals when the Reactor Coolant System pressure is 2235 i 20 psig at l s,, w .4,, least once per 31 days with the modulating valve fully open. The
- 5. e i. s.sJ( provisions of Specification 4.0.4 are not aonlicable for entry into L NODE 3 or 4;J g,g73,,3g i d. Performance of a Reactor Coolant System water inventory balanchat least once per 72 hours; and i [: . F.eaitering the Re::ter "::d ch::: L::h;ff ";iste et h;,;t ea;. p;r) l
{ i t.c o .14. Ial r!' S: r:d A*t
- g.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve {r;
- 4Fi-d ir I,
,I;tl 2.4 H shall be demonstrated OPERABLElby vertrying leakage to De within
{ '{its limit: 1
# 3#'#a At least once per 18 months, 3
- 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 j the. previous 9 months, i Pri r t r:t;rning th: V:h: :: :;rvi;; f:l h W ; triatea - e, re; i-_)
( ;r r;; h ;;;; t'a:rk ;; th; ;; h:, ::d y
- d. Within 24 hours following valve actuation due to automatic or manual action or flow through the valve lexcept for valves RH 8701 A and B)
SR Afe 3 *iand RH 8702 A and B. f IThe presi;ien.; ;f 5;;;ific;ti;; 0.0.4 ;r; ne; ;;,,,1;;;L'. fe. ;a;., ;..t. F.^,::: i l
- Dr-+-J t b SR ys e i A,3 [LJste.T 3.4 225)
Lil a+e 1 limtR.T 3.0 - 22 C. L,s-O BRAIDWND - UN HS 1 & 2 3/4 4-22 M NDMENT NO. 74
1 P) V CTS INSERT (S) , SECTION 3.4 LCO 3.4.13 l INSERT 3.4-22A (L3 ) SURVEILLANCE FREQUENCY i i SR 3.4.13.1 NOTE
- Not required to be performed until 12 hours after establishment of steady state i operation near operating pressure, i
. Verify RCS operational leakage is within 72 hours l liraits by Jerformance of RCS water j inventory aalance. l i O i d a 1 1 i O Revision A 4
l i l - .]t . CTS INSERT (S) SECTION 3.4 l l LC0 3.4.14 l INSERT 3.4.??R (A,). 3 j i 1 SURVEILLANCE FREQUENCY
*)
SR 3.4.14.1 NOTES . i
- 1. Only required to be performed in !
l MODES 1 and 2.
- 2. ... ;
l O ; INSERT 3.4 22C (Ls) i - l l SURVEILLANCE. FREQUENCY SR 3.4.14.1 -NOTES
- 1. ..
- 2. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than :
)
- once if a repetitive testing loop j cannot be avoided. ;
- 3. ...
.O ;
Revision A ;
l t.t 0 So b,5 Lco 39'oI3 t /. D 5 . % l'l O 8MF&&# SURVEILLANCE REQUIREMENTS seat s', ec.+iaw Rao sns.5,f,( G..;.u u Reactor Coolant 5=tr 7 :i :::) shall be demonstrated to be withi p,[, ggp " ,3 the'ylimitsy g ,g , gm 3,q.u a y
- a. Monitoring the containment atmosphere gaseous and particulate radioactivity monitor at least once per 12 hours;
- b. Monitoring the reactor cavity sump discharge, and the containment floor drain sump discharge and inventory at least once per 12 hours; hg/MeasurementgtheCONT LED LE E to th eactor ant pu seals when dhe Reacto Coolant stem pr ure is 5120 g at least once per 31 days lwith e modul ng valv ully op . f-Hve-r;7xt::::: :r;;;;;;;;: ;;; :.c.: r: ::: :;;:::=:: ::7 ::try St: ,
ggg _ d. irws e.g.r z#-zts Performance of a Reactor Coolant System water inventory balance at h l 1 east once per 72 hours; and '
- e. Monitoring the Reactor Head Flange Leakoff System at least once per t
24 hours. 4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in O 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 i 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. l A0sef,M) 1n Seckick SnY 6ee )ot fee 6ce.Has34 lO 1 BRAIDWOOD - UNITS 1 & 2 3/4 4-22 AMENDMENT NO. 74 l
l l CTS INSERT (S) SECTION 3.5 LCO 3.5.5 IEERI 3.4 22A (L,) g 250 en S (60.36, 225) x 225 (56.91, 200) 150 (49.28, 150)
- o i" gggggy 100
'(40.24, 100) 5 5
W (24, 63.43) (32, 63.43) UNACCEPTABLE REGION 5 50
- c. .
x E 25 e Z
- 2 0 3 20 30 40 50 60 70 D
SEAL INJECTION FLOW (GPM) t 'l l
- Figure 3.5.5-1 (page 1 of 1)
Seal Injection Flow limits O Revision A
. _ . _ . . . . _ . . . . _ . . _ _ _ . _ _ . _ _ . . . - . _ _ _ . _ . _ . _ . _ _ _ . _ . ~ . _ _ . . . _ . _ _ _ _ . . _ _ _ . . . _ _ . . _ _ . ,
1
'i --Q CTS INSERT (S)
SECTION 3.5 l i ! LCO 3.5.5 i ! l INSERT 3.4 22B (M2 and L.) - NOTE i j Not required to be performed until 4 hours after the Reactor Coolant System ' l pressure stabilizes at = 2215 psig and 5 2255 psig. j 4 i i: F i O I R 1 1 i O ! Revision A e i
,7 4,*,. 3,4 i
(~ TABLE 3.4-1 - - REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION
)
i SI8900A,B,C,D CHG/SI Check Valve 5I8815 CHG/SI Backup Check alve SIB 948A,B,C,0 Accumulator Check Ive IB956A,B,C,D Accumulator Backu Check Valve 8818A'B,C,D
, RHR Cold Leg Ch k Valve SI 19A,B,C,0 SI Cold Leg Ch ck Valve S18 9A,B,C,D SI Hot leg C ek Valve S1890 ,B,C,0 SI Hot Leg ckup Check Valve 518841 B RHR Hot Le Check Valve
*RH8701A, RHR Suct" n MOV's a
*RH8702A,8 RHR Suc ion MOV's l
j l l O . l
- NOTE:
- 1. Leakage rate greater than 1.0 gpm but less than or en 1 to 5.0 gpm are conside ed acceptable if the latest measured rate h q 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 gpe by 50% or greater,
- 2. Lea ge rates greater than 1.0 gpm but less than or equal to 5. gpm are co ideredunacceptableifthelatestmeasuredrateexceededthehate termined by the previous test by an amount that reduces the marg'n etween measured leakage rate and the maximum permissible rate of S. gpm
. by 50% or greater, and
. Leakage rates greater than 5.0 gpm are considered unacceptable.
BRAIDWOOD - UNITS 3.& 2 3/4 4-23
4 ! sec b 3.4 ,
- 1tEACTOR COOLANT SYSTEM N
3/4\.4 7 CHEMISTRY i LIMITING ONDITION FOR OPERATION
/
/
j 3.4.7 .The Rea tor Coolant System chemistry shall be maintained withir tse l limits specifie in Table 3'.4-2. APPLICABILITY: At 11 times. ! ACTION: MODES 1, 2, 3, and 4: ,-
- a. With any one or mor chemistry parameter in 'xcess of its Steady -
3 State Limit but with its Transient Limi) restore the parameter to } within its Steady-Stat Limit within 24, hours or be in at least HOT
- STANDBY within the next hours and in/ COLD SHUTDOWN within the i following 30 hours; and
- b. With any one or more chemist parameter in excess of its Transient-1 limit, be in at laest HOT STAN Y within 6 hn'urs and in COLD.SHtf700'"1 within the following 30 hours.
At All Other Times: With the conceatration of,e'ither chloride or fluoride in the Reactor Coolant System in excess f its Steady-State L*mit for more than 24 hours
'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 System; 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.
!.SURVEILLAN REQUIREMENTS
, s 4.4. The Reactor Coolant System chemistry shall be determined to be wit 'n ;
t limits by analysis of.those parameters at the frequencies specified in able 4.4-3. 4 O BRA 1DWOOD - UNITS 1 & 2 3/4 4-24 i
R , 5,,g,,3 4 3 . TABLE 3.4-2 O REACTOR C00 taut Sv5 TEM CHEMISTRY LIMITS 1
' STEADY-STATE ItANSIENT PARAMETER
\ LIMIT LIMIT Dissolved Oxygen
- N, 5 0.10 ppm
/ $ 1.00 ppm Chloride \.
x 5 0.15 ppm 5 1.50 ppm Fluoride \0.15p
- _< 1.50 ppe s
\
i
,,/ 'N' i
/ 's\
l
/ \
x !O f
/
)
/
imit not applicable with T,yg less than or equal to 250*F. E i i 1
?
l I i [O, BRAIDWOOD - UNITS 1 & 2 3/4 4-25
l R 5ec4 3A -l l s - l TABLE 4.4-3 y ! O REACTOR COOLANT SYSTEM I CHEMISTRY SURVEILLANCE REQUIREMENTS SAMPLVdND PARAMETER ANALYSIS' FREQUENCY l Dissolved Oxygen * , At leas once per 72 hours i Chloride At east once per 72 hours
,i _ f.e y At ,e.st _ e pe, ,2 h _ s
/
l / 4 IO - required with T, less than or equal to 250', I l 4 e 4 0 . BRAIDWOOD - UNITS 1 & 2 3/4 4-26
LCo s.st+ SM REALTOR COOLANT SYSTEM (Re-6) l O c.4.W { U C /4.0 E SPECIFID AGTIVITY. ! LIMITING CONDITION FOR OPERATION W' 15:M The specific activity of the reactor coolant shall be G ; ned tM"'*", bd.M j 5 A 7.4./G. 2 X: Less than or equal to 1 microcurie per gram DOSE EQUIVALENT ' j I-131**, and l l SR SA.IG.I K Less than or equal to 100/E microcuries per gram of gross j radioactivity. APPLICABILITY, MODES 1, 2, C. 4. - J 5 4 j ACTION: bod 3 A h 5 eseT"Wm W U=)L M .) h l MODES 1, 2 and 3*: ) CMP 4 RA A. A r. With the specific activity of the reactor coolant greater than l 1 microcurie per gram DOSE EQUIVALENT I-131** for more than I
- 48 hours during one continuous time intervaljor exceecing the limit i [11ne shown on 1gure 3.4-1, be in st least HOT STANDBY with T*
j tot 0 B *---Lless than 500*F whhin 6 hours; andi Casp C. X With_the specific activity of the reactor coolant greater than 100/E microcuries per gram, be in at least HOT STANDBY with T , O . less than 500*F within 6 hours. bdd L.C6 3.illlo (r,.diJlw A A>eTc.*}
._ - - - - - N07( --
L.CO T.O. L{ s's no k AffUtsi.h It . L_. i Leo E.4tk Mhsc'6n M _ . [ *With T,, greater than or equal to 500*F.J
'**For Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35j microcuries per gram.f O n s.r.is. J BRAIDWOOD - UNITS 1 & 2 3/4 4 AMENDMENT NO. 69
- - - - . . -. - . - - - - - - - . . .-~ .. . . _ , . . - , . . . - - . . . . . - -
i i LCO 5,4, t(, , REACTOR COOLANT SYSTEM - O t1N111No CoNo1 Tron roR o, ERAT 1oN ACT10N (Continued) MODES 1, 2 G. . -..J Lynope 3 was acs &~3.hrera+*re (_h) r 6oo *r. 6 (.oNp A K4 A,# With the specific activity of the reactor coolant greater than 1 f microcurie per gram DOSE EQUl?ALENT I-131*1= greeter t.br. ;;;/t --; 3 I ;^ereCerieUr ;; =,,'perfom the sampling and analysis requirements of l , Item 4.a) of Tati e 4 4-4 until the specific activity.of the reactor - coolant-is restored to within its limits. 9 j SURVE1LLANCE REQU1REMENTS 4 (EElD The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of
- Table 4.4-4. .
. S ft. 3,4. fin , (
. E 3 , 4.1/, , 7-
" g, g 2 .4.14. 5 4
l d 5 4 M ./6, 2 Vor Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0.35) 4 , microCuries per gram.f BRAIDWOOD - UNITS 1 & 2 3/4 4-28 AMENDMENT NO. 69
O O ~ O TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT O SAMPLE AND ANALYSIS AND ANALYSIS MODES IN WHICH SAMPLE FREQUENCY AND ANALYSIS REQUIRED
- 1. Gross Radioactivity 54 s.4.tu.i 4 [At least once per C'2 t. sad Determination ** I,2,38 so.v.I&.a yg t
- 2. Isotopic Analysis for DOSE EQUIVA- Once per 14 days LENT I-131 Concentration I Sg s.4.ts. 3
- 3. Radiochemical for E Determination *** [Onceper6 months
- I s
- 4. Isotopic Analysis for Iodine .at (Once per 4 hours, including I-131, I-133, and I-135 If,2f,3f[",50]-L, 3 '
whenever the specific activity exceedsfl ' UNA N -131**** 5 N # Y' A I wr 100lE ,T.
... --mlpr 7 i '
imr ---tiview g,, tand AT [One sample between 2 1,2,3 and 6 hours following a l THERMAL POWER change , s e s.v.it M > exceeding 15% of , i ftheRATEDTHERMAL ' POWER within a 1-hour (period. ' 4 i h r
,t BRAIDWOOD - UNITS 1 & 2
-4 3/4 4-30 AMEN 0 MENT NO. 69 i
I , D .h. b.m 1.1 - -
,, , TAatr 4.4-4 tra-tt 'I l-ce 3.4.Its TABLE HDTAT10HS f
- Unttl Wits within s 5 1ts.ific activity of W Reactor Coolant System is restored 4
- Sample to be taken after a minimum of 2 EFPD and 20 days of POWER
- OPERATION have elapsed since reactor was last subcritical for 48 hours er j longer.
i . A gross radioactivity analysis shall consist of the quantitative i measurement of the total specific activity of the reactor coolant'except ! for radionuclides with half-lives less than 10 minutes and all .
~-
i radiciodines. The total specific activity shall be the sim of the
- degassed beta-gamma activity and the total of all identified gaseous activities in the sample within 2 hours after the sample is taken and extrapolated back to when the sample was taken. Determination of the i i contributors to the gross specific activity shall be based upon those i \
{ _ (energy peaks identiflable with a 955 confidence The latest able level.avai data ma i E h.ms.o*** i i fA radiochemical analysis for E shall cons.ist of the quantitative - measurement of the specific activity for each radionuclide, except for i radienuclides with half-lives less than 10 minutes and all radiciodines, i 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.Ishall be based upon these energy peaks identifiable with a 955 confidence)
Q . f****For Unit 1, reactor coolant DOSE EQUIVALENT I-131 will be limited to 0,35 i l microcuries per gram. ywys,p.y i l i O BRAIDWOOD - UNITS 1 & 2 3/4 4-31 4 AMENDMENT NO. 69 I , 5 l
4
- L.C.o .5 S.tk -
f f f i 4 ' O- '< i L I n 't ! 2 i t 1 - n g i ' i s 1 g l i g
]
j
- i
. i i
200
' ' uncumat 3 OPERA m t
it 1 y 't h L u \ t'e 1 t 150 %, g t i 5 4 u
> I
$ t, 'l 3 ,
a x O ig 100 ', g \ t s ACCEMARE OP9tATION POR UWF 2 s
- UNAccEnAaLE OPERATION FOR UWF1 '
L 3 i E k \ w 3' h
# s %
$ 1 0 1 uwt 7 tem --
W
\
W 50 ' 3 8 s
~ s
- Acct m eLt T OPtamon T wm i tam---
0 20 30 so 50 so 70 ao to 100 PERCENT Or RATED MRWAL POWER o.4 4 0 FIGURE N DOSE EQUIVALENT I-13I REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWERJtt: T;;
.. ---- --. . .... .!::: ": ,".;.T."i
( _.-. __ _ _. _ .,. .-.... A, O 1 rw . .. w a s a v rwsavaii raswar =:m yuan u.wwa wns.6na a aea. I (*F:- "-it b ".::otor> h-t S;;;ific ".:thity M.35 ;:01/Gr:= "0SE O','!"^at."! ::1) BRAIDWOOD - UNITS 1 & 2 3/4 4-29 AMENDMENT No. 69
L eo 3.44 . l I IABLE 4.4-4 (Ct,ntinued) _. Tas't "oTattoas O I ups sa Al f Until the specific activity of the Reactor Coolant System is restored within its limits. i , nam a
- 5AMe3 * 'Sampletobetaken*yo6l after a minimum of 2 EFPD and 20 days of POWER
- M8 ~ OPERATION have elapsed since reactor was last suberitical for 48 hours or j longer. NA gross radioactivity analysis shall consist of the quantitative i j menurement of the total specific activity of the reactor cool ept i for radion11ti- with half-lives less than 10 minutes - 4 h radiciodines. The taLppecific activity shal.1 degassed beta-gamma activitTwultheAtar of all identified gaseous e sum of the activities in the sample withWTTdurs-4fter the sample is taken and extrapolated backMeff the sample was ta . termination of the
- contributor.s.-ttr'the gross specific activity shall be on those {
, e y peaks identifiable with a 95% confidence level. The j QavailaMe data may be used for pure beta-emitting radionuclides. ! [*** A. radiochemical analysis for E shall consist of the quantitative 3 l ! measurement of the specific activity for each radionuclide, except for i
- radionuclides with half-lives less than 10 minutes and all radioiodines, -
which is identified in the reactor coolant. The specific activities for i these individual radionuclides shall be used in the determination of E_ for the reactor ct olant sample. Determination of the contributors to E ] 4 l 0 . N.,
=h 11 6 6 = d urea th == a rar P ks ideatiri hi level.
ith '55 c arid ac-
****For Unit 1, reactor coolant DOSE EQUI'3 microcuries per gras / ] LENT I-131 will be limited to 0.35) j I* '
- 44drp+ed W IipNn le sa w s - wg 3
i 4 ) J O BRAIDWOOD - UNITS 1 & 2 3/4 4-31 AMENDMENT NO. 63
- .. _ .. - - . . - . - . -_ . ~ .. - - - .
l LCO 3 + $ l , ; 6pec'.4ca:HoJ4/a p :3,51 REACTOR COOLANT SYSTEM (Rc6') , s P/d S.4.3 @ PRESSURE / TEMPERATURE [ LIMITS es m e mim =rm s LIMITING CONDITION FOR OPERATION L c.o 3 A.(vnatmeA wh +u h av4 oMM h %e PrcR.) I GPJ:D.sThe Rea or Coolant System ':::::t tt: : = ::-t::rU temperature and pressure shall b i nimited in accordance with the limi< lines shown on Figures 3.4-2a and 3.4-3a for Unit 1 (Figures 4-2b and 3.4-3b for Unit 2) during . I heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
- a. A maximum heatup of 100*F in any 1-hour period,
- b. A maximum cooldown of 100*F in any 1-hour period, and
- c. A maximum t'emperature change of less than or equal to 10'F in any 1-hour period during inservice hydrostatic and leak testing operations ~
above the heatup and cooldown limit curves. l APPLICABILITY: At all time ' Ma> ACTION: tm, y g,. j With any of the abw limits exceeded, restore the temperature and/or pressure OMo t within the lirrQyithin 30 minutes perfo n enginj(ring eyafuationJ# T det ine the geects of e out- imit c dition #the sWctural Maoritvl (o he Reactpf Coolan vstem: ee ine that the Reactor Coolant System remains RR4,2 acceptable for continued operation r/be in at least HDT STANDBY within the next 6 hours and reduce the RC5 T avg and pressure to less_than 200*F Esig usp g (5D0'prfg,() respectively, within the f011owing 30 hours.f t y conp f._ cusurs* m i SURVEILLANCE REQUIREMENTS SR 5 4,3.1 (4. 4. ^ i D The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutesfauring system ) 45.hltheatup, cooldown, and inservice leak and hydrostatic testino operations. j daTE 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens 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), and 3.4-4a for Unit 1 (Figure 3.4-4b for Unit 2)., O **"*"""'"" ' 6- vy BRAIDWOOD - UNITS 1 & 2 3/4 4-32 AMENDMENT NO. 30
i d 8
, fQ CTS INSERT (S)
SECTION 3.4 e
- LCO 3.4.3 INSERT 3.4-32A (Mu )
1 i
- CONDITION REQUIRED ACTION COMPLETION TIME i
Initiate action to Immediately ! C. NOTE ~.1
- Required Action C.2 restore parameter (s) j shall be completed to within limits-.
- whenever this l Condition is entered. MQ i
, C.2 Detecmine RCS is Prior to i Requirements of LC0 acceptable for entering H0DE 4 not met any time other continued operation. i than in MODE 1, 2, 3, . or 4. 4 i O b i 4 i ( O Revision A
2 A c o 1.4.3
- REACTOR COOLANT SYSTEM 5pe.c/(ice oa 5.6 6 3/4.4.9 PRESSURE / TEMPERATURE LIMITS I
REACTOR COOLANT SYSTEM 4 LIMITING CONDITION FOR OPERATION
} 3 saa 6,.+se <.as cir.rs.-a r.+,s l l
Qoo c.s fo r 5.c v. h ! s.64.a 2.'. t 1 The Reactor Coolant System kexcent the cressur< ::eri temperature and ' pressureAshall be limited in accordance with the limita.F =: c: - v es i s O. ' 2; :-d 3. '-2: fer L'ait 1 U;; . ;;; 2.'-25 ;;d 0.4 OL fe, L ,ii. O dria; Heatup, cooldown, criticality, and inservice leak and hydrostatic testing with;
- w0 ko I.a. 4ed h a eco J.m v.m +v PTL R .
- a. imum heatup of 100*F in any 1-hour period, 1
- b. A maximum cooldo O'F in any 1-ho l-% , and b c. A maximum temperat ge of less j 1-hour
- equal to 10*F in any uring inservice hydrostatic an sting operations he heatup and cooldown limit curves.
- APPLICABILITY
- At all times.
.} s ACTION: ' Q 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 determine. the effects of the out-of-limit condit'on 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 next-6 hours and reduce the RCS T,yg and pressure to less than 200*F and 500 psig, respectively, within the followin 3 h r Addressed in Lc.o 3.4 3 SURVEILLANCE REQUIREMENTS S"' 00C3 & 54 ~ 3 4 x - _ m
- ~ ~~
4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
. . . The reactor vessel material irradiition surveillance speci shall be rem examined, to determine changes in mate erties, as required by 10 CF Appendix H, in a with the schedule in Table 4.4-5. The results of thes ns shall be used to update Figures _3.4-2a'and 3.4-3a (Figur 6; and 3.4-3b for Unit 2),
and 3.4-4a ,f,or o Un-it igure 3.4-4b for Unit 2). O % 9 3.e su BRAIDWOOD - UNITS 1 & 2 3/4 4-32 AMENDMENT NO. 30 -
I
}
CTS INSERT (S) j
-Q' SECTION 5.0 i
- Specification 5.6.6 INSERT 3.4 32A (LA22 ) I 4 5.6.6 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR).
]
- a. ...
l i b. The analytical methods used to determine the RCS pressure and ^ temperature limits shall be those previously reviewed and approved 1 1 by the NRC. specifically those described in the following i documents
- 1. WCAP 14040-A. " Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown .
, Limit Curves." Revision 1. December 1994 Approval provided l by NRC Safety Evaluation Report, dated October 16. 1995. .
4
- 2. Comed letter to NRC " Initial Pressure and Temperature 'l Limits Report." dated . Approval provided by NRC Safety Evaluation Report. dated : and O coPen tte= - see aust f cation for oi"erences eu ]
. 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 I revision of supplement thereto. I T l l l l I O Revision A
_ _ _ _ _ _ _ _ _ _ _ _ _ __ _ . _ _. _ _ . . _ . _ . - . _ . .__ _ _ _ . . . _ _ . . _ . . . _ . _ . _ _ .m m. -.._.._.m..
.1 1
- A N fes,44en [O *f
- OP*ehe* %
4 Gen. W .Qor-Mon go . ..y -- 4 . 4,. g, 1 M1Ym1YhL PRcFERTY BASIS -
~ . .
.f .__ j ~ CONTROLLING MATERIAL: CIRCUTERENTIAL WELD ~~' - . INITIAL RTurr: 4 0*F . l ART AFTER 32 EFPY: 1/4T, 159'T - l 3 /4T, 135'T I i . I i These curves are applicable for heatup rates up t6100*F/hr for j the service period up to 32 ETPY and contain margins of 10'T and , j so- psig for possible instrument errors. - i j 8 , . g , ... i
&~',- . r r. : a + .
. i 4 , .. . , . ,
j r . . . . .
. ' I m ,, gg . J ft 4 1
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.t * , , t e i J g t J ,
a . . , . .. 1 i r i r i
, . 1 i , i i j ... . . i i ,
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4
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- t f a r.
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- ... , i i -
i e 1500 , , , , , ,
. ! r .
i ; ! c 6 ; s .
- . . Inmacceptable I I
- y g
- pt
-- i .'
oe 4 Operation
* ** I f
acetPTABLE ygagsga
, +
1 m . # , ,. . i , c i .. 0 , . . , , o r i .sr n
, , a r,*3 E , , 2 .... . 6 .
L . , . , , ,, .. s .i i e i
. i . . .i r.i r ,.
3i . J i > *, , l [ s . . IIEATW R170 '
- i , e i . F F -
3 ' ' ' i ! 750i .
. i ,
,' W70 leo'Fna[ ,
2 . t , I t / . I
* . i f . .
. , ... s s , ,
+ E00
'i
, , ' ' ' i ,'
/ ,
crittsality Limit ansed en taasteten Bydreetatic feet . l j
+ Tany. GDi*F) for the Servisa persed ap To.32.strY
~50 ., , ,
. 6 4 4
, i e
i ei i i I
,..i
. 4 , . + . , ! 500 !
! O E0 100 150 200 250 300 350 400 450 i '
2 INDICATED TCwPERATURE (DEC.F) 1 l j i 4 i FIGURE 3.4-2a k l O .
===eTo= Cooo=== =r r== =====> LI Irarzo .
AFFLICABLE UP TO 32 EFFY (UNIT 1) i
?
e BRAIDWOOD - UNITS 1 & 2 3/4 4-33 AMENDMENT No. 53 1
- . - - . . - . . . . _ _ - . -. . _ . ~ .- -_ _ _ .... - .. - - _ - . - _ _ _ .
i i (h -' - - - s e c A. S ee.u s:c,.,3.4 s s,c.c y j l j MATELIAL PROPERTY BASIS -
. ~ . . . .
i .,s . j CONTROLLING MATERIAL: CIRCUTERENTIAL WELD ! NITIAL RT,m: 4 0*F g~~- l l 4 T AFTER 32 ETPY: 1/4T, 159'F .. i 3/4T, 135'T l curves are applicable for heatup rates up to 100* /hr for 4 j Thes ! the s vice period up to 32 EFPY and contain margins f 10*F and , l 60- psi for possible instrument errors. 1 U '" 3 3 ' F. J\ & a i 6 6 #i .. r 4 i l ,,,. . i i
- e
.s.
\* e t , .
e ! l m u ,, g . J
# 7 f.
/
; . i a g
t 8 t t ' \ e ' ' i* * " t, I fj i r i 4 i y j e* ' t a
' i i t' il e , e g
, g ' ra rj j ., j , i
- t * * \ # I e 4 ' . * ! *
/# 1 y . I
! \* 3
. t . .' t. . 1 . '
J j ,, . e e . . . 4 \ r e i r r i j
**gg
..
- 6 e !\ 6 I t
- 8 i / 1 e i a 4 i e t . t \ e4 t * / .j j i f
? s
- 4 t 1 iT a i 89 ; er I + , ;
l , 6 . e N. 4 ee r .y i i a ; e + \' t i / r . r. 6 ,
- e 6 e e e e '
) .
l
- I ++ t e i N 2 1 i j ... i \ r I i I I i i i e <
/ r F
-~
) s ..+ , , , l j
~
2 1500 e
+
e x / i i
'I
' / I '
l g ' . , i C. \' J J l g
~
t
- i 1 i I
*-o'_t u *:: ' a F
- t. g - i. J ACctPTABLE t +
j .-
- 8
- t 6 2 s I\ t I _ ggygg
, 6 i , . .. e i ( e <
e . g 4 y t e e t / 4 L I . II' I y 1 j .... a 6 ? e . / \'Ft
- 3 E t
= **** I .*I t , t ; 8
- M e 1 I i a
4 . . . 4 f . i, f\ l F t *
' 3
* ' 6 / ll(AIUP M7($ J '
\ I I t t t
' ' / F ' ' * '
i
. .
- 2 W 10 IM'F M / .r.. .
w, 1 . 53 I 8
- t . .r e / T 3 h O 1 *
- l t i / f 2F \ e i
,r j 3 i e
e si x i , i 500 f CritM.ey Limit tata ,Saeed sa
! , ' ,l ' , ,' , f i , - , us.wse n,er not i 3 '
+ for the Sonica
' / Ta perted g . (3)4'F)32.IFFT By To. '
} ' 150 . . j , { . y + s , s
, .f i ( .N I 6 /i i ! I i i I ! t
'/ L 9
- i
- 1 t 0 E0 100 150 200 250 300 350 400 - 450 500 -
lNDICATED TEWPERATURC (DCC.r) 1 l FIGURE 3.4-2a k REACTOR COOLANT SYSTEM REATUP LIMITATIONS O. APPLICABLE UP TO 32 EFPY (UNIT 1) ; I BRAIDWOOD - UNITS 1 & 2 3/4 4-33 AMP!DMENT No. 53 -
- Sec% 3 A -
s a Spec $an 5 6. fo
$ rE Mt$ Yh 6Gc.ktok. ( O %
Sed- Toc M $2.nPk 40 O v i CURVES ~ APPLICABLE FOR HEATUP RATES UP TO 100*F/HR FOR THE SERV 1 16 EFPY. CONTAINS MARGIN OF 10*F AND 60 PSIG FOR POSSIBLE INSTRUNEN i i
- 25
- 0 w.. -- i ,.
' iiii i,,i,i ieriieii ineisi j '
i lll Leak lest % ,
=
l ; ,, 1 2250 Limit + , , ,
!c
, . r r ,
' i r ,
i , ; , 2000 , , j ,,,, 3, , i
--r r -
e , ea ' ' 1 4 . '>
; ,) l-l i
- 750 r
a i
,,' i i > ,
j ,
. i
- E ;5%
i,l,::,
! Acceptable- l; ;
i r l
/ Operation 1 ';
lll:: : ' o 1 Unacceptable
, l ,9 :
- 5. 33r' ;,, +. . , operation
___-- q e ' * - ** i r i , 4 /'~N g * ' -
** . ,, r, ,
U
.. . i a ,
! 20:0 , ;;; '- . .i , , 3
* . - , ..... i l l,;, Heatup Rates e ie i r.
i t i . i t' 750 ! ' , ' ' Up To !/l 1 : ' 6 lan 'F/Hr /l' ' ' '+ ' l ! ::
'l / '
' criticality Limit I
,. .I
{ '
- gg +
l , Based on Ir. service I
=
- Hydrostatic Test --
1 , Temperature (292*F) ~ l 250 for the Service --
~
1 Period Up to 16 EFPY 2 i .. s -- - 0
- 0 60 100 -
160 200 260 300 350 400 450 500 ]; 4 seelcatt0 Truptaafunt (DEC.F) i 1 FIGURE 3.4-2b REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 16 EFPY (UNIT 2) O ' J l BRAIDUOOD - UNITS 1 & 2 3/4 4-34 AMENDMENT NO. 30
1 b
- O t.d e' on 5,Q AA S e c4i on 3,4 i
i O \ CURVES APPLICABLE FOR' HEATUP RATES UP TO 100*F/HR FOR THE SE '
- 16 EFPY. CONTAINS MARGIN OF 10*F AND 60 PSIG FOR POSSIBLE INS
$ l 4 5:D i c .. = > .. . . i { i ll 6 ' '# # # # +i# ii# # # # # i 4 2250 ', ,' ; Leak Limit Test x w 1,
; ,,- ;; )
- s , , , , , , , ,
s ,,, i I l
'i J / , , l V t 2000
- R D j ,
, , J ' , , , , 6 5 j yag 1 ; - f f/ . , i e I {;
- no I
; l
; 1 o ,,, ,
l i - 1 r - , ... i i i i ,,,,,, .
, < 4 , . ,
! - ' ,l \ '
$ Acceptable '
7 ;5;;
' i,;,l
.' \ " Operation
, s >
s ,: 44
,:' e -
o 33ri . . un ceptable ', i : . 3, ,,
, Ope tion r w- i .
i 1 i , , w '
- i. <1 . , ,,1 ,. , ,
,i ., , ,,,
t jo:o '. i+ , s
, r.
a
* \ , 2 ,r l l l ,' , ' , '
e iri , , , ,,,, i *
- Heatup Up ToRates N', ,
-l,'
i i 1 75 0 ! .' . ' :' lon *F/Hr / ' ' ' ! ! -l
/
k'l'
' Criticality Limit I l'
j '
' ' t 500 i
, , 1 ' Based on Ir. service I '
i '
=
2 i s Hydrostatic Test --
, Temperature (292*F) ~:
i 250 / for the Service --
,, eriod Up to 16 EFPY_- -_ )
i i 1 n, < , -- ]
- o 60 soo
, ~.- 1 a 160 200 260 ano aso 4co eso soo i
seesearro truptaatuut (occ.r) i i
)
FIGURE 3.4-2b 1 i i l REACTOR COOLANT SYSTEM HEATUP LIMITATIONS \
- APPLICABLE UP TO 16 EFPY (UNIT 2) \
4 s s
\
4 i O 4 a' i } BRAIDUOOD - UNITS 1 & 2 3/4 4-34
- AMENDMENT NO. 30 1
i . - . .
l ' t
~E' e % 3. 4. . Abkred% Cach+m hb j.
._.JeacR,.C 7, g - w. wC*c - - . %~ -@f4 ,
} MATERIA 1, FRDPERTY BA IS * * [ T, _. ' v CONTROLLING MATERIAL: C ItCUMFIRENTIAL WELD j INITIAL RTwm: 40*F. - ART AFTER 32 EFPY: 1/4T, r 159'T d 3/4T, 135'T i These curves are applicable for cooldown rates up to 100'F/hr for the service period up to 32 EFPY and contain margins of 10'T and 60 psig for possible instrument errors. i i 2500. am ..w i i ' .. .*
' ' ' I
' ' ' ' i I i ', 2250* , \ l i j ! 4 s
' t t
- 2000 l ., !i 1
j
, , ,i !i l
n . >, E i
- ., l r -
i 1750 1
) -
i j J l G, 1500 ._ _ f
- e > ;
l & ! I i w , . I w 1250 a 5 , / l ,. , , t w --. '
' i I E 1000 ---
Unacceptable / L, ' ', , ,
- w .,_ . Operation y .
O 7gg ii,iii . Acceptable. A ' Operaties o W .' Mr m i a NM m PGP f l f 4
- _ , aates zw/
{
$gg _, eg g ,a ne'%ef9' )
j , _. g -a-w e erunn3p*' A' le% 's'"' . f8 Mdm ,,a F j 250 - - 00
# . /
l 100 " l
*0 ' ' '
i 4 0 50 100 150 200 250 300 350 400 450 500 l lesDICATED TCisPCAATURC (DCC.r) t a 1 FIGURE 3.4-3a O ======= coat ==T T T== coat =o = LI=ITATro== 4 APPLICABLE UP TO 33 EFFI (UNIT 1) 1 1 3/4 4-35 AMENDMENT No. 53 ] BRAIDWOOD - UNITS 1 & 2 4
4 . _ .Q. __ . . . S ecf on 5, o , BtATERIAL PROPERTY BASIS ~ , , , , . ...
\ '~ S e cd. oa 34 i A CONTROLLIWG MATERIAL:
1 () INITIAL RTm: CI'RCUHFIR15NTIAL WELD 4 0'F.- - I ART A ER 32 IFPY: 1/4T,*159'T ! 0 ! 3/4T, 135F These cur es are applicable for cooldown rates up to 100'T hr for
'the servic
{ 50 psig for period up to 32 EFpY and contain margins of O'F and 4 I ossible instrument errors. i j 2500, am m
\ , i i s
l , , e
< *g u ... -
l
}
i /e f } l [t
. 3 i i
a r4 8 t x > r e 2250!, *'l # j i s 1 s , ir -7 . x # 1 4 '>' : 2000 l ., x I . e . r,i i n , ii i ' i
- u . i, a E I
- i I,
' . A i 1750 ,
/ ]~
> r k a r
. \ F 3' \ I t g 1500 ' s
)
f ) - 3 ! K 1 u
/ t E W f i w 1250 i e ( r
- t e
, i u e 2 r, N r ; 3 j
E 1000 ---}}