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{{#Wiki_filter:jtDominion Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA | {{#Wiki_filter:jtDominion Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com March 28, 2014 U.S. Nuclear Regulatory Commission Attention: | ||
www.dom.com March 28, | Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT. | ||
Document Control | INC.MILLSTONE POWER STATION UNIT 3 Serial No NSSL/MLC Docket No.License No.14-037 RO 50-423 NPF-49 LICENSE AMENDMENT REQUEST FOR ADMINISTRATIVE CHANGES AND CORRECTIONS TO THE TECHNICAL SPECIFICATIONS In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to revise the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs). The proposed changes delete the TS Index and make administrative corrections to the TSs.Attachment 1 to this letter provides a description and evaluation of the proposed changes. Attachment 2 contains the TS page mark-ups of the proposed changes.The proposed changes do not involve a Significant Hazards Consideration under the standards set forth in 10 CFR 50.92. The Facility Safety Review Committee has reviewed and concurred with the determinations herein.In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Connecticut. | ||
INC.MILLSTONE POWER STATION UNIT | Should you have any questions in regard to this submittal, please contact Wanda Craft at (804) 273-4687.Sincerely, Mark D. Sartain Vice President | ||
Attachment 2 contains the TS page mark-ups of the proposed changes.The proposed changes do not involve a Significant Hazards Consideration | -Nuclear Engineering L --I -----VICKI L. HULL Notary Public Commonwealth of Virginia 140542 My Commission Expires May 31. 2014 I n ...COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mark D. Sartain, who is Vice President | ||
a copy of this license amendment request | -Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief Acknowledged before me this_. day of , 2014.My Commission Expires:____ | ||
Should you have any questions in regard to this submittal, please contact | JNotary Pub4lic Mir P Serial No: 14-037 Docket No. 50-423 Page 2 of 2 Attachments: | ||
Sincerely, Mark D. | : 1. Evaluation of Proposed License Amendment 2. Marked-Up Technical Specification Pages Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 M. C. Thadani Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 B 1 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No. 14-037 Docket No. 50-423 ATTACHMENT 1 EVALUATION OF PROPOSED LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 1 of 6 EVALUATION OF PROPOSED LICENSE AMENDMENT 1.0 | ||
-Nuclear Engineering L --I -----VICKI L. | |||
-Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before | ==SUMMARY== | ||
JNotary | In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc.(DNC) is submitting a license amendment request (LAR) to revise the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs). The proposed changes delete the TS Index and make administrative corrections to the TSs.2.0 PROPOSED CHANGES DNC proposes to make the following changes to the MPS3 TSs: a) Delete TS index pages i through xix.b) Replace the first sub-letter under TS Table 4.3-2 Item 4, Steam Line Isolation | ||
: 1. Evaluation of Proposed License Amendment | -Manual Initiation," which currently appears as sub-letter "d" on Page 3/4 3-37, with sub-letter "a".c) Revise TS 6.3.2, Facility Staff Qualifications, from: "If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the operations manager shall have held a senior reactor operator license at a pressurized water reactor, and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3." to: "The operations manager or at least one operations middle manager shall hold a senior reactor operator license for Millstone Unit No. 3." d) Replace the term "SORC" in paragraph b of the "Licensee initiated changes to the REMODCM," described in TS 6.13 with the term "FSRC." Mark-ups of the affected TS pages for the proposed changes described above are provided in Attachment 2.3.0 TECHNICAL EVALUATION The technical justification for each of the changes proposed in Section 2.0 of this LAR is provided below: a) This LAR proposes to delete the index from the MPS3 TSs. Past LAR submittals to the NRC have included the TS index to support requested TS changes, and a revised index has been included in issued amendments. | ||
This change will eliminate Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 2 of 6 the need to include TS index pages as part of LAR submittals for future TS changes and to issue revised index pages with an amendment. | |||
-Manual Initiation," | Although the index would no longer be considered part of the MPS3 TSs, controlled copy holders would continue to receive updates to the TS index for future TS and TS Bases changes.The TS index identifies the contents of the TSs and where the specific TS sections can be found throughout the TSs but does not contain any technical information required by 10 CFR 50.36. Therefore, this is an administrative change and does not involve any physical changes to structures, systems, or components (SSCs) in the plant, or the way SSCs are operated or controlled. | ||
which currently appears as sub-letter "d" on Page 3/4 3-37, | Similar amendments to remove the TS index were approved for Seabrook in June 2013 (Reference 1), Waterford Unit 3 in May 2005 (Reference 2), and for Arkansas Nuclear One, Unit 2 in June 2005 (Reference 3).b) A typographical error exists on Page 3/4 3-37 for TS Table 4.3-2, Engineered Safety Features Actuation System Instrumentation Surveillance Requirements. | ||
described in TS 6.13 with the term "FSRC."Mark-ups of the affected TS pages for the proposed changes described above | Specifically, the first sub-letter in Item 4, "Steam Line Isolation Manual Initiation," appears as sub-letter "d." The correct lettering should be sub-letter "a". Therefore, sub-letter "d" needs to be replaced with sub-letter "a." This proposed change is editorial in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled. | ||
This change will eliminate Serial No. 14- | c) DNC proposes to revise TS 6.3.2, Facility Staff Qualifications, from: "If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the operations manager shall have held a senior reactor operator license at a pressurized water reactor, and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3." to: "The operations manager or at least one operations middle manager shall hold a senior reactor operator license for Millstone Unit No. 3." The format of TS 6.3.2 is being revised to more closely match the format used in NUREG-1431, Rev. 4, TS 5.2.2d, for Westinghouse standard TS plants.The proposed change also replaces the position of "assistant operations manager" with "at least one operations middle manager" and would require that either the operations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) have a senior reactor operator (SRO) license for MPS3. As discussed in the regulatory analysis section of this LAR (Section 4.1.2), the proposed change to TS 6.3.2 is administrative in nature and has no technical implications on TS requirements. | ||
Although the index would | With the proposed change, operation, maintenance and testing will continue to assure safe operation of MPS3 and to protect the health and safety of the public. | ||
Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 3 of 6 The TSs will continue to provide administrative controls relating to the organization and management of MPS3 and to ensure compliance with regulations. | |||
Similar amendments to remove the TS index were approved for Seabrook in | d) The term "SORC" which appears in paragraph b of the "Licensee initiated changes to the REMODCM," described in TS 6.13 is no longer used at MPS. This acronym, which stood for Site Operations Review Committee, has been replaced with FSRC or Facility Safety Review Committee. | ||
Specifically, the first sub-letter in Item 4, "Steam Line Isolation Manual Initiation," | Consequently, the term "SORC" needs to be replaced with "FSRC." This proposed change is administrative in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled. | ||
appears as sub-letter "d." The correct lettering should be sub-letter "a". Therefore, sub-letter "d" needs to be replaced with sub-letter "a."This proposed change is editorial in nature and does not involve any | 4.0 REGULATORY ANALYSIS 4.1 Applicable Regulatory Requirements/Criteria 4.1.1 The NRC's regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications." This regulation requires that the TSs include items in the following five specific categories: | ||
c) DNC proposes to revise TS 6.3.2, Facility Staff Qualifications, from:"If the operations manager does not hold a senior reactor operator license | (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. | ||
With the proposed change, operation, maintenance and testing will continue | However, the regulation does not specify the particular requirements to be included in a plant's TSs.The TS index, which this LAR proposes to remove from the TSs, is not a required component of the TSs in 10 CFR 50.36. Similar to the TS Bases, the index provides information about the TSs but is not part of the TSs. Because the index does not provide technical information required by 10 CFR 50.36, the proposed administrative change to remove the index from the TSs is consistent with regulatory requirements. | ||
Serial No. 14- | 4.1.2 TS 6.3.1 currently requires that each member of the facility staff shall meet or exceed the minimum qualifications of American National Standards Institute (ANSI)N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," for comparable positions (note that as of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000). ANSI N 18.1-1971 specifies that the operations manager hold an SRO license for the unit. In 1987, this guidance was revised in ANSI/ANS-3.1-1987 such that if the operations manager does not hold an SRO license, then the operations middle manager shall hold an SRO license.The existing language used in TS 6.3.2, Facility Staff Qualifications, allows the assistant operations manager (functionally equivalent to the operations middle manager referenced in ANSI/ANS-3.1-1987), if one is designated, to hold an SRO Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 4 of 6 license if the operations manager does not hold an SRO license for the unit. This allowance was approved for MPS3 under License Amendment (LA) 132 (Reference 6.4). As stated in the NRC safety evaluation report for LA 132, the staff concluded that: "The specification that either the Operations Manager or the Assistant Operations Manager hold a Millstone Unit 3 SRO license is consistent with the requirements of 10 CFR 50.54(l) and ensures that a licensed off-shift senior operator is directing the licensed activities of the licensed operators provided that the crews report directly to and receive overall day-to-day guidance on plant operations from the individual holding the current Senior Reactor Operator license. Requiring an ANSI/ANS-3 | ||
d) The term "SORC" which appears in paragraph b of the "Licensee initiated | .1-1987 qualification and licensed Assistant Operations Manager when the Operations Manager does not hold a valid Millstone Unit 3 SRO license is consistent with the requirements of ANSI N18.1-1971 and ensures there is site-specific detailed relevant technical and systems knowledge in a senior operations management position." The proposed administrative change to TS 6.3.2 is consistent with the requirements of ANSI N18.1-1971. | ||
described in TS 6.13 is no longer used at MPS. This acronym,which stood for Site Operations Review Committee, has been replaced with | DNC proposes to revise TS 6.3.2 such that the operations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) shall hold an SRO license for MPS3. Modifying the title in TS 6.3.2 to allow at least one operations middle manager (i.e., any position between the operations manager and the shift managers) to hold the SRO license on the unit meets the intent of ANSI N18.1-1971. | ||
Consequently, the term "SORC" needs to | This change will allow the operations manager and other operations middle managers to perform higher level duties such as management, planning, and coordinating of operations activities with more general senior operator knowledge. | ||
4.0 REGULATORY | This proposed change continues to be consistent with the requirements of 10 CFR 50.54(l) to ensure that a licensed off-shift senior operator is directing the licensed activities of the licensed operators and with the standards set forth in ANSI N18.1-1971 to ensure there is relevant operational experience and knowledge in senior operations management position(s). | ||
This regulation requires that the TSs include items in the following five specific categories: | Additionally, the format of TS 6.3.2 is being revised to more closely match the format used in NUREG-1431, Rev. 4, TS 5.2.2d, for Westinghouse standard TS plants.4.2 No Significant Hazards Consideration The NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c). | ||
(1) safety limits, limiting safety system settings, and | A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety. | ||
However,the regulation does not specify the particular requirements to be included in | Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 5 of 6 DNC has evaluated whether or not a significant hazards consideration is involved with the proposed changes. A discussion of these standards as they relate to this change request is provided below.1) Do the proposed .changes involve a significant increase in the probability or consequences of an accident previously evaluated? | ||
4.1.2 TS 6.3.1 currently requires that each member of the facility staff shall meet | |||
if one is designated, to hold an SRO Serial No. 14- | |||
Requiring an ANSI/ANS-3 | |||
.1-1987 qualification and licensed Assistant Operations Manager when the Operations Manager does not hold a valid Millstone Unit 3 SRO license is consistent with | |||
The proposed administrative change to TS 6.3.2 is consistent with the requirements of ANSI N18.1-1971. | |||
DNC proposes to revise TS 6.3.2 such that the operations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) shall hold | |||
This change will allow the operations manager and other operations middle managers to perform higher level duties such as management, | |||
This proposed change continues to be consistent with the requirements of 10 | |||
Additionally, the format of TS 6.3.2 is being revised to more closely match | |||
A proposed amendment to | |||
Serial No. 14- | |||
A discussion of these standards as they relate to this change | |||
.changes involve a significant increase in the probability | |||
Response: | Response: | ||
No. The proposed changes are administrative in nature. The | No. The proposed changes are administrative in nature. The proposed changes remove the TS Index and make other editorial and administrative corrections to the TSs. These administrative changes are not initiators of any accident previously evaluated, and, consequently, the probability and consequences of an accident previously evaluated is not significantly increased. | ||
Therefore, the proposed changes do not involve a significant increase in | Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. | ||
: 2) Do the proposed changes create the possibility of a new or different kind | : 2) Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated? | ||
Response: | Response: | ||
No. The proposed changes are administrative in nature so no new | No. The proposed changes are administrative in nature so no new or different accidents result from the proposed changes. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a change in the method of plant operation, or new operator actions. The changes do not alter assumptions made in the safety analysis. | ||
The changes do not | Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. | ||
a change in the method of plant operation, or new operator actions. | : 3) Do the proposed changes involve a significant reduction in the margin of safety?Response: | ||
No. The proposed administrative changes do not involve a change in the method of plant operation, do not affect any accident analyses, and do not relax any safety system settings. | |||
Therefore, | Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, DNC concludes that the proposed changes do not present a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified. | ||
: 3) Do the proposed changes involve a significant reduction in the margin | |||
No. The proposed administrative changes do not involve a change | |||
Therefore, the proposed changes do not involve | |||
===4.3 Conclusion=== | ===4.3 Conclusion=== | ||
Based on the considerations discussed above, (1) there is reasonable assurance that | Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. | ||
Serial No. 14- | Serial No. 14-037 Docket No. 50-423 Attachment 1, Page 6 of 6 5.0 ENVIRONMENTAL CONSIDERATION DNC has determined that the proposed amendment would not change a requirement with respect to installation or use of a facility component located within the restricted area, as defined by 10 CFR 20, or an inspection or surveillance requirement. | ||
The | The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. | ||
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). | Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). | ||
Therefore, pursuant to 10 | Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment. | ||
no environmental impact statement or environmental assessment need to | |||
==6.0 REFERENCES== | ==6.0 REFERENCES== | ||
6.1 NRC Letter "Seabrook | 6.1 NRC Letter "Seabrook Station, Unit No. 1 -Issuance of Amendment Regarding the Administrative Changes and Corrections to the Technical Specifications (TAC No.MF1033)," June 17, 2013 (ADAMS Accession No. ML13074A760). | ||
6.2 NRC Letter "Waterford Steam Electric Station, Unit 3 -Issuance of Amendment Re: Modification of Technical Specification (TS) 5.3.1, Fuel Assemblies, T.S. 5.6.1, Criticality, T.S. 6.9.1.11.1, Core Operating Limits Reports, and Deletion of TS Index (TAC No. MC3584)," May 9, 2005 (ADAMS Accession No. ML051290368). | |||
June 17, 2013 (ADAMS Accession No. ML13074A760). | 6.3 NRC Letter "Arkansas Nuclear One, Unit 2 -Issuance of Amendments Re: Deletion of Index Pages from the Technical Specifications (TAC No. MC3246)," June 22, 2005 (ADAMS Accession No. ML051740191). | ||
6.2 NRC Letter "Waterford Steam Electric | 6.4 NRC Letter "Issuance of Amendment (TAC No. M93730)," January 7, 1997. | ||
.Serial No. 14-037 Docket No. 50-423 ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 1 of 2227, 200?,;NRE 1.PEFINiTION& | |||
May 9, 2005 (ADAMS Accession No. ML051290368). | |||
6.3 NRC Letter "Arkansas Nuclear One, Unit 2 -Issuance of Amendments Re: | |||
June 22,2005 (ADAMS Accession No. ML051740191). | |||
6.4 NRC Letter "Issuance of Amendment (TAC No. M93730)," | |||
January 7, 1997. | |||
.Serial No. 14- | |||
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3A 1 | 3A 1 26 G .R. e d ............................................. | ||
....................................... | ....................................... | ||
34 1 1 27+'%A YwW,3,14.2. | 34 1 1 27+'%A YwW, 3,14.2.3 3A1.2.4 ANIA,"L FLM6 DIFFERENC E ...................................................................... | ||
3/M 2 | 3/M 2 1 RCS FLOW RATE OiND NUCLEAR ENT-HALPY RISE; HOT CHi ANNELM FACTO9R.............................................................. | ||
314 2 | 314 2 19 QUADRANT POWER TILT RPTIO ............................................................ | ||
3,1 2 | 3,1 2 21 D N B P.... .A .ETERS................................................ | ||
................................... | ................................... | ||
3 A 2 24*1-L ..I L L L I ...................................................................................................... | 3 A 2 24*1-L ..I L L L I ...................................................................................................... | ||
| Line 192: | Line 157: | ||
: 3. ..4.. ...RE C.TOR T P, SYST.M...N | : 3. ..4.. ...RE C.TOR T P, SYST.M...N | ||
..................................... | ..................................... | ||
3A 3 | 3A 3 1 T1'4141 3.3 1 RENA CTOP. TRIP SIYSTEM. 1NS 42TRUMENTATON | ||
1NS 42TRUMENTATON | |||
.................................... | .................................... | ||
3/ 3 | 3/ 3 2 TABLE 3.3 2 DEL6ETBED T;BABL 1.3 1 REACTFOR TRIP SYSTEM pUsTRUMNTsN4AION SURVEILL6ANC RE.Q u IRE MN.TS ....................................................................................... | ||
3/43 | 3/43 10 E.43E2 P'SA.E1TY | ||
....R.. .ACTUR..ATION... | ....R.. .ACTUR..ATION... | ||
SYSTM | SYSTM N INSTRUMENTATION | ||
........................................... | ........................................... | ||
3A1 3 | 3A1 3 15 TABLE 3.3 3 RiNC~EER9D SAFETY FEATURES A.CTUA-TION 83YSTEM INSTRUMENTATION | ||
........................................... | ........................................... | ||
3M1 3 1: | 3M1 3 1:7 TAL4. ENCiEREDRB SAFE;TY FEATURERS AGTUA44ON SYSTEM;N-I -.................................................... | ||
INz.50.e0,Sf,91l207 Serial No. 14- | INz.50.e0,Sf,91l207 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 6 of 22 LIMIT-ING CONDITIONS FOR OPERATIO0N ANDlj SUCRVEILLANCýjE RE;QUIREM4ENT-S TABLEr 3.3 5 DELTEITD TABLE 41.3 a ENC;ILR;EDCG Sk.TETY FEATURE,4s AC6AIN 8TEM....T.UM .NTA..ON ... .. .... .. .......REQUI. ........3, 43 36~44~ MOIOIN.N4METTO R a im e N!:,: .m.,.. i g for_ R-__ 0, ......... | ||
... .. .... .. .......REQUI. ........3, 43 36~44~ MOIOIN.N4METTO R a im e N!:,: .m.,.. i g for_ R-__ 0, ......... | |||
._. ............................................... ;- 4.,;'TARL.E- P. 6'DIATI ON MOQNITORiNG INgThUMPENTATION FOR PL ..ANT OPERATIONS. | ._. ............................................... ;- 4.,;'TARL.E- P. 6'DIATI ON MOQNITORiNG INgThUMPENTATION FOR PL ..ANT OPERATIONS. | ||
................................................................... | ................................................................... | ||
AA 3 | AA 3 43 TA4BLE 1.3 3 RAPIA-TION MONIRTORING INSTRUMENTj4ATION FOR PLAN~T-OPERATIONS S EILLANCE QUIREMENTS.................... | ||
14 3 | 14 3 45 T-ABLE ;.3 ; DELEETED)TABLEB 1.3 1 DELETED'TAkBLE 3.; 8 9ELETED TABL-E '1.3 5 DELETED Rem.. te sh itiv. ...I o9f3/ n3 5 .3........................................................... | ||
TABLEB 1.3 1 DELETED'TAkBLE 3.; 8 | |||
314 ; 53.ABI. E 3.3 9 REMOTE ..U..OWN P491. .N .T .... ....................................... | 314 ; 53.ABI. E 3.3 9 REMOTE ..U..OWN P491. .N .T .... ....................................... | ||
3/4 3 | 3/4 3 54 TABLE 1.3 6 REMOTE SHUTD:OWN MONITOR~iG IN9T-RUME9NTATON | ||
..RV... ...a i. .REQUI,, BME. NTS........................................................ | ..RV... ...a i. .REQUI,, BME. NTS........................................................ | ||
314 3 | 314 3 55 T.^.P Mfn ............... | ||
..T.....................3. | ..T.....................3. | ||
3 TABLE 3.3 AG.. IDENT .T-,- ....M.ONITO..NG..............O 3"64 3 ,o TABLE 1.3 7 ACCID)ENT MOIO9JISTUETTO URVEILLANCE;GI | |||
..................................................................... | ..................................................................... | ||
3.1 | 3.1 62 TABLME 3.3 PLELETED;4;rTn&L 3.3 12961L644;1 TIABLE; 1.3 8 DELETED NMILLSTONE U4NFT3 N4 medmntNe. | ||
8 1. 9 1, 1 88. 193 Serial No. 14- | 8 1. 9 1, 1 88. 193 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 7 of 22 Ma~y ;1 , 2 99;LIMITING CONDITIONS FORl OPERhATIONAND TURVLRLAC TABLE 3.3 13 DELET 3114.3 .4 "149 9T" l 3.1-.-....---4 8EL6T-EPA 4AW-M ARGIN QlNO I' R ................................................................ | ||
3A 3 8-2.4.1 REACTOR COOLANT LOOPS AND COOANT CRCULTION sH t r M d p , .................................................................................. | 3A 3 8-2.4.1 REACTOR COOLANT LOOPS AND COOANT CRCULTION sH t r M d p , .................................................................................. | ||
3 / 4 | 3 / 4 i HO T T -N R .......... | ||
I....................................................................................3....... | I....................................................................................3....... | ||
--...... -..v S : F V J ' , .. ............................................................................................... | --...... -..v S : F V J ' , .. ............................................................................................... | ||
3 /4 4, | 3 /4 4, 3 COLD SHUTFDO\'N 606p Filkie.................................................. | ||
3,1 I | 3,1 I 5 COLD;I SH44RTOWN fno~zj. Nzt Filld ............................................ | ||
3/44 1 6;.O ps o ; .,~ ............................... | 3/44 1 6;.O ps o ; .,~ ............................... | ||
I......................................34.'14 iseJftledIL.op (ttq ..................................................................... | I......................................34.'14 iseJftledIL.op (ttq ..................................................................... | ||
3)/ | 3)/48 41 .'. SA FET V V AL -ES 3/..1:........................................................................................... | ||
3A , | 3A , 9 D E L E T E D .......................................................................................................... | ||
3/14 4 | 3/14 4 10 3,449 Stf, .. .. P on w;,er O ...r: i ................................................................................ | ||
... | ... 1 44IURRF4-54 PRESSURIZER LEVEL CONT-ROL ...................................... | ||
...................................... | ;4/41 !a HL aa. .itma ', , ............ | ||
;4/41 ! | |||
.. ................................... | .. ................................... | ||
..................................... | ..................................... ,P I 4 11 b A A.4 4 REP EF AL ... .......................................... | ||
,P I 4 11 | |||
........................................ | ........................................ | ||
: 3. /14 4 | : 3. /14 4 12 A314.4.5 STEAM GENERATORTUBE INTEGRITY...................................... | ||
3,14 | 3,14 141 T;A4BL 4.4 1 DEBLETED TIABLE 4.4 2 DELETED 34.4.6 REAC-TOR COOLANT SYSITEM LEAKAGE 4ýtkkePiei"9-in....... | ||
................................................... | ................................................... | ||
3/ | 3/143N Oper~zafi iF.!14AKAGE............................................................... | ||
3A 1 | 3A 1 22 TABLE 3.4 1. REACTOR COOLANT SYSTEM PRESSUPE IOLATION VALVES ... 3/ 4 24 3 4 4 D E L E T E D ......................................................................................................... | ||
3 / 4 | 3 / 4 25 t TABLE 3.4 2 DELETED ................................................................................................... | ||
;/TABLE -DELTED..344. SPECIFIC ACTIVJITY | ;/TABLE -DELTED..344. SPECIFIC ACTIVJITY.3./IA A nO...................................................................................... | ||
.3./IA A nO...................................................................................... | --.--LASTONE 6IT 3 N4i 19;, 2(01, 217w, 329, 2358 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 8 of 22 Opfab.ez 27, 2005r LIMTIN CNDIIOS FR PERTIN ADSREL.~ERQIEET FIG U649 3.114 44AA;4.4 4 L J ,L, A "b & ............................................................................................... | ||
--.--LASTONE 6IT | -" J 1 E L E T E I~ p 1 ................................................................ | ||
-" | |||
.............................. | .............................. | ||
2 ! | 2 ! 2 E ......................... | ||
.............................. | .............................. | ||
R.ACTOR G0062604 sSYT E U ........ | R.ACTOR G0062604 sSYT E U ........ P .IMITATION. | ||
P .IMITATION. | |||
APPLICABLE U4P TO9 10 ;FPYi............................................. | APPLICABLE U4P TO9 10 ;FPYi............................................. | ||
3,1 4 | 3,1 4 34 RAC-GTOR COLN YTE OLON IIAIN APPLICABLE9 UP TO 10 EF~PW............................................. | ||
X/4 4 - | X/4 4 -34 DRIB9EL ....................................................................... | ||
344 4 ; | 344 4 ;6 DELETED ..................................................................... | ||
31 1 | 31 1 37P CAzr'8F ur-e~~~ fAAip 9z,04t ~ q S~z............................................4.14 4 3549+P. .S ............... | ||
................................................... | ................................................... | ||
3/ | 3/ 1 98JI L 111 LIV "Tj~tf PUL. z fliS kCZU WVOFPZ'....... .-..................................................................................... | ||
"/4 ,4 41. | "/4 ,4 41.9EL 3/..' EL;lR7 r.......... | ||
.................................. | .................................. | ||
I ................................................. | I ................................................. | ||
| Line 267: | Line 225: | ||
6 ,,,itt .. ...... ............. | 6 ,,,itt .. ...... ............. | ||
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i6'1 | i6'1 i ECCE SJUBYSTEMS XM GREATER TIIAN OR EQUAL TO 350 ........... | ||
................. | ................. | ||
.............................................. | .............................................. | ||
3/14 5 | 3/14 5 3 E-.CCS~ SUSSTM LESS THAN 350-F......................... | ||
3,1 5 7;REFUELING WAATER STO9RAGEPTANK | 3,1 5 7;REFUELING WAATER STO9RAGEPTANK | ||
.................................. | .................................. | ||
3.'q 5 | 3.'q 5 9 PHI TRISOD~iU! | ||
IPiOspiikFE STOR4AGE 13ASK6:Ts............ | IPiOspiikFE STOR4AGE 13ASK6:Ts............ | ||
3/1 ý | 3/1 ý 10 6'. ,.o , ,.i,,bp i., 3,4.6.PRIMARY CONTAINMENT CO an' em .oag ,,: .............................................................................. | ||
3'4 6 1............. | 3'4 6 1............. | ||
...... 68 ........................................... | ...... 68 ........................................... | ||
11.................................. | 11.................................. | ||
3/14 69 | 3/14 69 2 C -ntainmen t Air Lelff ............................................................................ | ||
3' 6 5............ | 3' 6 5............ | ||
3rt!1:;r7 | 3rt!1:;r7 | ||
............................................................................ | ............................................................................ | ||
3,14 6 | 3,14 6 7 MILLSTONE TiTi IT 3 14i byýi 2, !w4, Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 9 of 22 LIMITINC CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRWOEMETS A ir Tcem por-ture ...................... | ||
...................... | |||
I.............. | I.............. | ||
........ | ........PA46 41469 Cznainfcf .Srutua .................................................... | ||
.Srutua .................................................... | 3(1 6 10 GRznthtRMF:nt | ||
3(1 6 | |||
\'zRtIatXnR 94S; m..t............................................... | \'zRtIatXnR 94S; m..t............................................... | ||
.314 6 | .314 6 11 3.'46.2 Dr.PRr.SSIJRI7ATTON AND Cool INC SYSTEMS Cz.-tainrnzWt Quz:;,h Spray ...............r......... | ||
r......... | |||
................................................. | ................................................. | ||
................................................. | ................................................. | ||
.344644-P4.. | .344644-P4..64 S L I-... ." .. .... .................................................. | ||
6 94.;a A ,R M 484 b EO jeetor ................................... | |||
....................... | ....................... | ||
I....................... | I....................... | ||
/. !SECONDAkRY | /. !SECONDAkRY OTJMN y e C Lttad Re s Sy ......................... | ||
3 | 3 6 S a e. C. .t- .A......................................31622 Struzturd hncrfitN ........................................................... | ||
........................................................... | 3/14623 31,47 "P 1 JP.6WRINE CYCLE Safct I^....TABLE 3.7 2 DELETED"... | ||
3/ | .. ... ......".............................................................3 3Y 7 2,+-I MILLSTT ONE ' I T 3 A...zaLtznt No. 59, 63, 8;7, 89, 19G, 115, 126, 217, 221, 212 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 10 of 22 Ally IMAITING CONDITIONS FOR OPER269ION AND SURVEILLANCE9 REQUIRAEMET-& | ||
.. ... ......".............................................................3 3Y 7 2,+- | |||
&BT44994.7 | &BT44994.7 | ||
.---, ý 1. 1 1 --I -4;dd3I=F 44 | .---, ý 1. 1 1 --I -4;dd3I=F 44 1 34 4.7.25 3.'4.7.6 T4ABLE14.7 2 34.-.-7. 11 3 47. 13 34147.13 MILLSTONE TC;, , ...... E ... ..... ...... .... ... ..... ................................ | ||
.I/ 7 7 Sp;ifk A F99...... | |||
.I/ 7 | |||
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3/17 | 3/17 7 Stzam Ct..cratk r M tkzie RaIgzf BT y--& .... ............................. | ||
3./1 7; | 3./1 7;91 D ELETED ... ... ............................................................................ | ||
7 | 7 10 sET'JI W'ART R SYSTEM "3I1 7i 1: i ULATIMAT HEAT SIQT-_ r 'A4 ............... | ||
.................. | .................. | ||
34 7 | 34 7 13 MaiELETED..............." .......................................... | ||
.......................................... | .314 7 9 P R IU 9 :ýVh ..................................... | ||
.314 7 | |||
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9A4 7 | 9A4 7 19 sDELETED ...s.. ...... ........ ................................. | ||
...s.. ...... ........ | 3/4 7 17 D E E ............................................... | ||
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3/4 7 | |||
D........................................... | D........................................... | ||
3/14 7 | 3/14 7 30 99159T-ED I)Fsbl;qzB DFITSTE DETMETED DrSI'V54:99 pril5i;q;99 4T- 3 t nent Ne.62, 84, 0,2211, 232,250 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 11 of 22 bIMITING~ | ||
cuO.DITIO FO1zlR UPIMIr.A4DSU m'E!16LArNLE ICEQ UI;;tEN.1LN:1 4A. | cuO.DITIO FO1zlR UPIMIr.A4DSU m'E!16LArNLE ICEQ UI;;tEN.1LN:1 4A.8 44-94 g .................................................................................................. | ||
-.-.'ELE D................................................ | -.-.'ELE D................................................ | ||
,.1/ 8 | ,.1/ 8 9 8 aJ ................................................. | ||
3M' 8 | 3M' 8 10 3149. .G. SQURGES TpAfing 1.8 Re BATT;ERY 9EUR'/EiLANCE | ||
.............................. | .............................. | ||
3M' 8 1;TABLA 1.9 2b BATTERY [ HARCER CAP ..T .. | 3M' 8 1;TABLA 1.9 2b BATTERY [ HARCER CAP ..T .. | ||
3M | 3M 14 S....................................... | ||
3,1 | 3,1 15 3/1.8.3 QNSITE POSAER DShBTO Oprii .................................................................. | ||
3. | 3.148i g h'td &,',' ................................................................................................. | ||
3,1 8 | 3,1 8 18 ELECTPICAL EQUIPMENT PROTECpI.VE DEVICES DELE;TED ...................................................................... | ||
...................................................................... | 3.'81 DF;ELET ..................... | ||
3.' | |||
D..................................................... | D..................................................... | ||
2.. .... ..B 9. ................................................................................................ | 2.. .... ..B 9. ................................................................................................ | ||
;1,4 g 2 | ;1,4 g 2 2 X4.9. ; 3ORON CONCE?19NSTR-RUMENTAT | ||
~4A CONTAINMkENT:] | ~4A CONTAINMkENT:] | ||
3A 4DELETED | 3A 4DELETED ............ | ||
............ | MILLSTONE T U'iT 3 i t ib "i i i" N .................................................................... | ||
MILLSTONE T U'iT | |||
iurk ............................................................ | iurk ............................................................ | ||
3149 | 3149 2 TTITTlD I _ I' T........T............... | ||
....... .. ..3... ... ... ... .. .. ... ... ... ... .. ... ... ... ...'1 9-I" Serial No. 14- | ....... .. ..3... ... ... ... .. .. ... ... ... ... .. ... ... ... ...'1 9-I" Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 12 of 22 Maefe4 26, 201 LIMI9TING CONDITIONS FRo OPEILATION AND SURVEIILLANCE REQUIREENT DE.T................................................. | ||
OA~ | OA~V 914.94i;314942 F4~WW ;94..L .....L. ........................................................................................... | ||
....... , , I RIESyIDUAL HEAT RT AGMO'L& ANrD COOLTANT CICULT ION- | ....... , , I RIESyIDUAL HEAT RT AGMO'L& ANrD COOLTANT CICULT ION- T L-e. Wehetz 1 ........................................... | ||
: 1. 9 9...A .TER L ................................................................................................. | : 1. 9 9...A .TER L ................................................................................................. | ||
;/ 9 | ;/ 9 10 DELTn In/1A Q 11 SPENT FUEL6 POOL REACTIVITY | ||
............................ | ............................ | ||
31'49 | 31'49 16i SPENT FUEL POOL TRAGE PATTER ..................... | ||
3/14 9 1?MINIMU164 FUL-; ASSEMBLY BURNU4P V'ERSUS | 3/14 9 1?MINIMU164 FUL-; ASSEMBLY BURNU4P V'ERSUS NOMINAL INIIALENR~hMNT OR RECION 11 OUT;: OF 4..TO......C...........TION............................ | ||
3/19 15-REGION 1 3 OUT OF 4 9TORACEFEGA9ML LOGAD ~iC SGHEMATIC | 3/19 15-REGION 1 3 OUT OF 4 9TORACEFEGA9ML LOGAD ~iC SGHEMATIC | ||
.................................. | .................................. | ||
3M' 9 | 3M' 9 19 NOI.. NITIAL ENRICHMENT FOR REGION; 2 STO-RAGE, CONFIGURATION............................................ | ||
3/1,9 | 3/1,9 20 MINIMUM FUEL ASSEMNBLY* | ||
BUR44UP ANiD DECAY TIME | BUR44UP ANiD DECAY TIME VERSUS NOMPINAL INITIL ENRIGHMIENT FOR REGION 3 STOR AGEl CONIGRTONFLO R ASEBLE FROM PME UPiRAF (3111 ........... | ||
CORE .................................... | CORE .................................... | ||
3;M19 | 3;M19 21 MAINIMUM FE SSML URU N DCYTMEVRU NOM 44A I ITIA BNRiCHIMEN'r FOR REGION 3 ST9RAG G3 5 M T ORES ........................................ | ||
1M 9 2. | 1M 9 2.2 w4iTTA49 4.--3;4. 10 SPECIALTEST EXCEPTIONS O4110 3,4.10.~4410.4 3/4.10.SHUTDOV10WIA.N MARGIN......................................................... | ||
3M11 GROUP HPEGIIT, INSERTION, AND POWER DISTWhBU4TIGN L-IM ITS9. ................................................... | |||
3M1 10 | 3M1 10 2 PC,,.T T TESTS 3/A 10 1 REACOR COLAN LOOF........................./1 0~41l4 1 14Fqs DELETED~MILSO ELE'.3r9 8, 95 99'27 neni Ne.;I7,21ig, 225, 21g Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 13 of 22 WOND'A11- 1". : ,"4.tl °",. L , ..................................................................................................... 3 " ; ;31.1 REACTIITR CNTRL YSEM 3-4. 1. 1 BORATION CON4ROLM............................................................ | ||
B 3A 1 | B 3A 1 11 3D EL1 O 1 E T E D ........................................................................................................ | ||
B 3/14 1 | B 3/14 1 2 314.3 D E TEDT.B... | ||
.........T................................[ | .........T................................[ | ||
B 3 ;.;.14.2 POWEIIR DITR U I N OLM T-8 ...................................... | B 3 ;.;.14.2 POWEIIR DITR U I N OLM T-8 ...................................... | ||
B ;A 2 | B ;A 2 I 9.-42.1......................................................................... | ||
--1 .-RAE N FNUCLEAR EN IIAPY RISE HOT CHANNEL....B F ACTOR A / 2 | --1 .-RAE N FNUCLEAR EN IIAPY RISE HOT CHANNEL....B F ACTOR A / 2 3 94. 2.4 QU4ADRANT POWER'B 41TIL RATIO .............. | ||
................................ | ................................ | ||
B 314 2.1 | B 314 2.1 9 3,42 DNB PARAMETFERS | ||
................................................................ | ................................................................ | ||
B 3/1 2 | B 3/1 2 9 3,3.'1. anzd 3,14.3.2 REACTRA 44P SY-STEMI INSTUMENPRFION AND ENCD;EERED SAFETY51 FEARWRES AC4;hATION SYSTEM..N...T.........N.....T............................................... | ||
B 3M' 3 | B 3M' 3 1 343.3 MONITORING | ||
..STPRUMENTAT!ON | ..STPRUMENTAT!ON | ||
.......................................................... | .......................................................... | ||
B 3/ 3 | B 3/ 3 3 114,3 4 TURB-pINE OVER-SPEED1 PROTECTION | ||
......................................... | ......................................... | ||
BA 3/14 - | BA 3/14 -3 3A.4 3.5 1UTDOWAN MARGIN MONITRG.............................................. | ||
B 3.1A3 | B 3.1A3 7 X41.1 REACTOýR COOLAdNTF 8YSTEMN 34 4 REACTOR COOLANT LnOOPSAND COOLANT CIRCLATION | ||
.B 14 , | .B 14 , i 3,4 4.2 U P.I Z E R .............................................................................................. | ||
B -I'A, 4 | B -I'A, 4 2 3A.4.3 PRE;SSUR+AER.......................................................................[3, 1 22 3 44 .4 R ELIEF V A LV ES ............................................................................................. | ||
B 3 14 4 | B 3 14 4 2b A l"4 A GENERTORS | ||
................................................... | ................................................... | ||
B 3,14 | B 3,14 3 3,4464 REACTOR COOL;ANT 8SY-STM LEAKACE................................... | ||
B 3,'1 | B 3,'1 414 3 DELE;TED -9 q W............................................................................... | ||
-9 q W............................................................................... | p P4 45 3,44.4.8 SPECIFIC 7ACG 4TIVITY .......................................... | ||
p P4 | B ;114 15 3,4.4.9 PRE;SSU4RE/TEM;PERATURýPE LIMITS ................................. | ||
B ;114 | B P4"7-I-N41669TONS 644T-3 4H ft MILLSTOnE N3 60, 89, 160, 161. 4,W-7., | ||
B P4"7-I-N41669TONS 644T- | Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 14 of 22 Seritl~ber | ||
Serial No. 14- | !§, 2006 BASES TALEB /11 RACOR'.ESELFAkC-TU6RE TOU6GINEsS PROPERTIES | ||
!§, | .... B 3A 1 9 RQ;;REB3CT 41FA9TN1T Q O)A9ARWINQ F F*ý 1 POWIER SE -ic 1 6 11/ .......................................................... | ||
.... B 3A 1 | 13 3 1 4 4 3+4.44_ DELETE- ........... | ||
13 3 1 4 | |||
...... .................... | ...... .................... | ||
3,4 4. H ,ECETE E.............. | 3,4 4. H ,ECETE E.............. | ||
| Line 400: | Line 347: | ||
314.4. slid 3144.93 EGGS ..U...Y..... | 314.4. slid 3144.93 EGGS ..U...Y..... | ||
s..... ............ | s..... ............ | ||
g.J4.9.4 "UEUELIG 3AT4DR STOQRAGE dT.;E4S44 ....R.....U.P.OSPHATE 9T..3,4.6t~l~'r GOT-MMEN~T' | g.J4.9.4 "UEUELIG 3AT4DR STOQRAGE dT.;E4S44 ....R.....U.P.OSPHATE 9T..3,4.6t~l~'r GOT-MMEN~T' SYSTEMS1 314.6.1 PRIMIACR CONTAPIMENT. | ||
......DEPRES.SURIZATION AND | ......DEPRES.SURIZATION AND OOL 344.4 CONFTAIMN IOAIO p 3,4.64 6i4BATN4OSPIERIC PRESSURE G(9,146.6 ECOGNDARY CONTA.MENT 3/147 PLANT-SYSTEMS 3A.74 TURBINE CYCI;....................... | ||
DELET-;IED | DELET-;IED | ||
................................ | ................................ | ||
REAC-TOR PL6ANT COMPONENT | REAC-TOR PL6ANT COMPONENT C ggpl4pp LTIM TEA REA FsINE........... | ||
.DELETE])........904............... | .DELETE])........904............... | ||
CONTROLn ROOM EMERCENCY V~44-L& DRwELETED | CONTROLn ROOM EMERCENCY V~44-L& DRwELETED | ||
| Line 413: | Line 360: | ||
B !3/1 1 2......................................................... | B !3/1 1 2......................................................... | ||
; 113 4 9 ]i........................................................ | ; 113 4 9 ]i........................................................ | ||
B 3 '4 "5 | B 3 '4 "5 3 Ad i .. .A ... ....................... | ||
.1".NG SYSTEMS ....................... | .1".NG SYSTEMS ....................... | ||
B 34 6 | B 34 6 2 19 ...E.................................. | ||
B3.'4 6 3)N4406 SYSTEM .................. | B3.'4 6 3)N4406 SYSTEM .................. | ||
B A41 6 | B A41 6 3d 00LiNG k'.WTER SYSTEM......B 3,'4 7 7 ENTILATION SYSTEM............ | ||
B 344:7 | B 344:7 10 r E. ................................. | ||
3.. 172.................... | 3.. 172.................... | ||
.8... 1.....5... | .8... 1.....5... | ||
14 1 4 :13 2.,t"MILLSTONE Serial No. 14- | 14 1 4 :13 2.,t" MILLSTONE Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 15 of 22 IWDE BASES D ELE ............................... | ||
3A7.4 DELETED-'1-13 DELET I.......B............................ | 3A7.4 DELETED-'1-13 DELET I.......B............................ | ||
.-4 14 W 2 | .-4 14 W 2 s 4-I 5.,i ?5 i :jq K ii (ffld:jjq | ||
?5:j Iýj b ?i9bit(6166 Q el QQT Tnf'PV | ?5:j Iýj b ?i9bit(6166 Q el QQT Tnf'PV 2AIIIQ ONSITE POWER.DICTIUBUTION | ||
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3,14.9.10 and 3419.11 './TRLVL REACTOR ;,EggEL AND... .. .... ... ...... -I -..... ......... | 3,14.9.10 and 3419.11 './TRLVL REACTOR ;,EggEL AND... .. .... ... ...... -I -..... .........B 3) 9192 ft 4LATION.......B 3/1' 9 2a................ | ||
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B 3/1 10 | B 3/1 10 1 D)ELERTEDR14...........................................................................B1 3A1 1.0 1 ,f-nende.. 0.4, 89, 100, 1 0' 11 i4, 136 189. 192,,,0;, 91,2 9,225,924 2-50 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 16 of 22 N8VOR~bOF 28, 2000 BASES 3/1.. 11 DELETED {i.2 L666T61 D14 .3 ,4"T5TONE T "3 Adne"dffieflf Ne. | ||
91,2 9,225,924 2-50 Serial No. 14- | Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 17 of 22 sapteffi 17,200 RESIGN FEATURES 5. S rTTITE LOC1ATIO 5 , J.CR IT IC A L IT .............................................. | ||
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Serial No. 14- | Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 18 of 22.o&p ..4.. 1999 ADMINISTRATEVE CONTROLS 6.A .........rT.T-..................................................64 6.2 ORGANIZATION9............................................................................... | ||
rT.T-..................................................64 6.2 ORGANIZATION9............................................................................... | 6 1 6-24 OFF-SITE AND ONSITE; ORCANIZATIONS.................................. | ||
6 | 6 1 6-2 FACILITY STAFF.................................................................. | ||
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65 6._.7. DELETED?#411minSTONI; UNIT 3 MLO... nt .. .26, 36, 69 89,104, Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 19 of 22 ADMINISTRATIVE CONTROLS&&G444@@4 Ak449 A 9 ONLU I I ."J'EO s .r..........Ar .T .14 6.9 REPORTING REOUIREMENTS............................................................6... | |||
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6 | 6 .27 a'fl 211 n11 n'21 23 383 1 4w Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 20 of 22 ENGINEEI 0 CC z e, CHA FUNCTIONAL UNIT CHE'3. Containment Isolation a. Phase "A" Isolation 1. Manual Initiation N.A.2. Automatic Actuation N.A.Logic and Actuation It, Relays 3. Safety Injection See]b. Phase "B" Isolation 1. Manual Initiation N.A.TABLE 4.3-2 (Continued) tED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH NNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED N.A.N.A.N.A.N.A.R N.A.N.A.M(1)N.A. N.A. 1,2,3,4 M(I) Q (4) 1, 2, 3, 4 tem 1. above for all Safety Injection Surveillance Requirements. | ||
PCI.CTIN.....AS..ONhO POGA 6 | N.A.0.B o 2. Automatic Actuation Logic and Actuation Relays 3. Containment Pressure-High-3 | ||
6 . | : c. DELETED 4. Steam Line Isolation 4. Manual Initiation | ||
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: 1. Individual | : 1. Individual | ||
: 2. | : 2. System N.A. N.A.S R N.A. N.A.N.A. N.A.N.A.N.A.Q N.A.N.A.R N.A.N.A.R R N.A.M(1)N.A.N.A.N.A.N.A. NA. 1,2,3,4 M(l) Q(4) 1,2,3,4 N.A. N.A. 1,2,3,4-t N.A. N.A. 1, 2, 3.4 N.A. N.A. 1,2,3,4 | ||
*Serial No. 14- | *Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 21 of 22 September 1COT.20L ADMINISTRATIVE CONTROLS 63 FACILITTY RTAFF 0IIA1.T1FICATIONR 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 | ||
* for comparable positions. | * for comparable positions. | ||
Exceptions to this requirement are specified in | Exceptions to this requirement are specified in the Quality Assurance Program.63.2 #bl th,, OpcrAtia,- | ||
mana,"ger does, not held- ase,'ier rvaeteF operator lie,,en ,% \,ilto-,6. shall -- e-ld a senior r ettz. e :a p erat e z.Ji em ofr i. | mana,"ger does, not held- ase,'ier rvaeteF operator lie,,en ,% \,ilto-, 6. shall -- e-ld a senior r ettz. e :a p erat e z.Ji em ofr i.t The operations manager or at least one operations middle manager shall hold a senior reactor operatorlicense for Millstone Unit No. 3.6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff that meets or exceeds the requirements as specified in the Quality Assurance Program and 10 CFR Part 55.59 shall be maintained. | ||
6.4.2 Deleted.6.5 DELETED.+/--1"As of November 1, 2001, applicants for reactor operator and senior reactor | 6.4.2 Deleted.6.5 DELETED.+/--1" As of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.MILLSTONE | ||
-LUNIT | -LUNIT 3 6-5 Amendment No. 46,-69, 84, 99, 94, 44G, 2, +3-54 4-4,4-7, 499, 2-2, IZ6 Serial No. 14-037 Docket No. 50-423 Attachment 2, Page 22 of 22 Novembe. 28, 2000 ADMINISTRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)a. The REMODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental program; and b. The REMODCM shall also contain the radioactive effluent.controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 6.9.1.3 and Specification 6.9.1.4.Licensee initiated changes to the REMODCM: a. Shall be documented and records of reviews performed shall be retained. | ||
28, | This documentation shall contain: I) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and 2) a determination that the change(s) will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; | ||
: b. Shall become effective after review and acceptance by SORG and the approval of the designated officer; and c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMODCM as a part of or concurrent with the Rad~ioactive Effluent Release Report for the period of the report in which any change in the REMODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicated the date (i.e., month and year) the change was implemented. | |||
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. | |||
These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.The Solid Radioactive Waste Treatment System shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements. | |||
: b. Shall become effective after review and acceptance by SORG and the approval | |||
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, | |||
These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.The Solid Radioactive Waste Treatment System shall be operated in accordance with the | |||
MILLSTONE | MILLSTONE | ||
-UNIT 3 6-24 Amendment No. 40, 69, 86, 90, 444,4-q4-, +4-73, 4-g8}} | -UNIT 3 6-24 Amendment No. 40, 69, 86, 90, 444, 4-q4-, +4-73, 4-g8}} | ||
Revision as of 19:39, 9 July 2018
| ML14093A026 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/28/2014 |
| From: | Sartain M D Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 14-037 | |
| Download: ML14093A026 (32) | |
Text
jtDominion Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com March 28, 2014 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT.
INC.MILLSTONE POWER STATION UNIT 3 Serial No NSSL/MLC Docket No.License No.14-037 RO 50-423 NPF-49 LICENSE AMENDMENT REQUEST FOR ADMINISTRATIVE CHANGES AND CORRECTIONS TO THE TECHNICAL SPECIFICATIONS In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to revise the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs). The proposed changes delete the TS Index and make administrative corrections to the TSs.Attachment 1 to this letter provides a description and evaluation of the proposed changes. Attachment 2 contains the TS page mark-ups of the proposed changes.The proposed changes do not involve a Significant Hazards Consideration under the standards set forth in 10 CFR 50.92. The Facility Safety Review Committee has reviewed and concurred with the determinations herein.In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Connecticut.
Should you have any questions in regard to this submittal, please contact Wanda Craft at (804) 273-4687.Sincerely, Mark D. Sartain Vice President
-Nuclear Engineering L --I -----VICKI L. HULL Notary Public Commonwealth of Virginia 140542 My Commission Expires May 31. 2014 I n ...COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mark D. Sartain, who is Vice President
-Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief Acknowledged before me this_. day of , 2014.My Commission Expires:____
JNotary Pub4lic Mir P Serial No: 14-037 Docket No. 50-423 Page 2 of 2 Attachments:
- 1. Evaluation of Proposed License Amendment 2. Marked-Up Technical Specification Pages Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 M. C. Thadani Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 B 1 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.14-037 Docket No. 50-423 ATTACHMENT 1 EVALUATION OF PROPOSED LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 Serial No.14-037 Docket No. 50-423 Attachment 1, Page 1 of 6 EVALUATION OF PROPOSED LICENSE AMENDMENT 1.0
SUMMARY
In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc.(DNC) is submitting a license amendment request (LAR) to revise the Millstone Power Station Unit 3 (MPS3) Technical Specifications (TSs). The proposed changes delete the TS Index and make administrative corrections to the TSs.2.0 PROPOSED CHANGES DNC proposes to make the following changes to the MPS3 TSs: a) Delete TS index pages i through xix.b) Replace the first sub-letter under TS Table 4.3-2 Item 4, Steam Line Isolation
-Manual Initiation," which currently appears as sub-letter "d" on Page 3/4 3-37, with sub-letter "a".c) Revise TS 6.3.2, Facility Staff Qualifications, from: "If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the operations manager shall have held a senior reactor operator license at a pressurized water reactor, and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3." to: "The operations manager or at least one operations middle manager shall hold a senior reactor operator license for Millstone Unit No. 3." d) Replace the term "SORC" in paragraph b of the "Licensee initiated changes to the REMODCM," described in TS 6.13 with the term "FSRC." Mark-ups of the affected TS pages for the proposed changes described above are provided in Attachment 2.3.0 TECHNICAL EVALUATION The technical justification for each of the changes proposed in Section 2.0 of this LAR is provided below: a) This LAR proposes to delete the index from the MPS3 TSs. Past LAR submittals to the NRC have included the TS index to support requested TS changes, and a revised index has been included in issued amendments.
This change will eliminate Serial No.14-037 Docket No. 50-423 Attachment 1, Page 2 of 6 the need to include TS index pages as part of LAR submittals for future TS changes and to issue revised index pages with an amendment.
Although the index would no longer be considered part of the MPS3 TSs, controlled copy holders would continue to receive updates to the TS index for future TS and TS Bases changes.The TS index identifies the contents of the TSs and where the specific TS sections can be found throughout the TSs but does not contain any technical information required by 10 CFR 50.36. Therefore, this is an administrative change and does not involve any physical changes to structures, systems, or components (SSCs) in the plant, or the way SSCs are operated or controlled.
Similar amendments to remove the TS index were approved for Seabrook in June 2013 (Reference 1), Waterford Unit 3 in May 2005 (Reference 2), and for Arkansas Nuclear One, Unit 2 in June 2005 (Reference 3).b) A typographical error exists on Page 3/4 3-37 for TS Table 4.3-2, Engineered Safety Features Actuation System Instrumentation Surveillance Requirements.
Specifically, the first sub-letter in Item 4, "Steam Line Isolation Manual Initiation," appears as sub-letter "d." The correct lettering should be sub-letter "a". Therefore, sub-letter "d" needs to be replaced with sub-letter "a." This proposed change is editorial in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.
c) DNC proposes to revise TS 6.3.2, Facility Staff Qualifications, from: "If the operations manager does not hold a senior reactor operator license for Millstone Unit No. 3, then the operations manager shall have held a senior reactor operator license at a pressurized water reactor, and the assistant operations manager shall hold a senior reactor operator license for Millstone Unit No. 3." to: "The operations manager or at least one operations middle manager shall hold a senior reactor operator license for Millstone Unit No. 3." The format of TS 6.3.2 is being revised to more closely match the format used in NUREG-1431, Rev. 4, TS 5.2.2d, for Westinghouse standard TS plants.The proposed change also replaces the position of "assistant operations manager" with "at least one operations middle manager" and would require that either the operations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) have a senior reactor operator (SRO) license for MPS3. As discussed in the regulatory analysis section of this LAR (Section 4.1.2), the proposed change to TS 6.3.2 is administrative in nature and has no technical implications on TS requirements.
With the proposed change, operation, maintenance and testing will continue to assure safe operation of MPS3 and to protect the health and safety of the public.
Serial No.14-037 Docket No. 50-423 Attachment 1, Page 3 of 6 The TSs will continue to provide administrative controls relating to the organization and management of MPS3 and to ensure compliance with regulations.
d) The term "SORC" which appears in paragraph b of the "Licensee initiated changes to the REMODCM," described in TS 6.13 is no longer used at MPS. This acronym, which stood for Site Operations Review Committee, has been replaced with FSRC or Facility Safety Review Committee.
Consequently, the term "SORC" needs to be replaced with "FSRC." This proposed change is administrative in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.
4.0 REGULATORY ANALYSIS 4.1 Applicable Regulatory Requirements/Criteria 4.1.1 The NRC's regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications." This regulation requires that the TSs include items in the following five specific categories:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
However, the regulation does not specify the particular requirements to be included in a plant's TSs.The TS index, which this LAR proposes to remove from the TSs, is not a required component of the TSs in 10 CFR 50.36. Similar to the TS Bases, the index provides information about the TSs but is not part of the TSs. Because the index does not provide technical information required by 10 CFR 50.36, the proposed administrative change to remove the index from the TSs is consistent with regulatory requirements.
4.1.2 TS 6.3.1 currently requires that each member of the facility staff shall meet or exceed the minimum qualifications of American National Standards Institute (ANSI)N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," for comparable positions (note that as of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000). ANSI N 18.1-1971 specifies that the operations manager hold an SRO license for the unit. In 1987, this guidance was revised in ANSI/ANS-3.1-1987 such that if the operations manager does not hold an SRO license, then the operations middle manager shall hold an SRO license.The existing language used in TS 6.3.2, Facility Staff Qualifications, allows the assistant operations manager (functionally equivalent to the operations middle manager referenced in ANSI/ANS-3.1-1987), if one is designated, to hold an SRO Serial No.14-037 Docket No. 50-423 Attachment 1, Page 4 of 6 license if the operations manager does not hold an SRO license for the unit. This allowance was approved for MPS3 under License Amendment (LA) 132 (Reference 6.4). As stated in the NRC safety evaluation report for LA 132, the staff concluded that: "The specification that either the Operations Manager or the Assistant Operations Manager hold a Millstone Unit 3 SRO license is consistent with the requirements of 10 CFR 50.54(l) and ensures that a licensed off-shift senior operator is directing the licensed activities of the licensed operators provided that the crews report directly to and receive overall day-to-day guidance on plant operations from the individual holding the current Senior Reactor Operator license. Requiring an ANSI/ANS-3
.1-1987 qualification and licensed Assistant Operations Manager when the Operations Manager does not hold a valid Millstone Unit 3 SRO license is consistent with the requirements of ANSI N18.1-1971 and ensures there is site-specific detailed relevant technical and systems knowledge in a senior operations management position." The proposed administrative change to TS 6.3.2 is consistent with the requirements of ANSI N18.1-1971.
DNC proposes to revise TS 6.3.2 such that the operations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) shall hold an SRO license for MPS3. Modifying the title in TS 6.3.2 to allow at least one operations middle manager (i.e., any position between the operations manager and the shift managers) to hold the SRO license on the unit meets the intent of ANSI N18.1-1971.
This change will allow the operations manager and other operations middle managers to perform higher level duties such as management, planning, and coordinating of operations activities with more general senior operator knowledge.
This proposed change continues to be consistent with the requirements of 10 CFR 50.54(l) to ensure that a licensed off-shift senior operator is directing the licensed activities of the licensed operators and with the standards set forth in ANSI N18.1-1971 to ensure there is relevant operational experience and knowledge in senior operations management position(s).
Additionally, the format of TS 6.3.2 is being revised to more closely match the format used in NUREG-1431, Rev. 4, TS 5.2.2d, for Westinghouse standard TS plants.4.2 No Significant Hazards Consideration The NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c).
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety.
Serial No.14-037 Docket No. 50-423 Attachment 1, Page 5 of 6 DNC has evaluated whether or not a significant hazards consideration is involved with the proposed changes. A discussion of these standards as they relate to this change request is provided below.1) Do the proposed .changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No. The proposed changes are administrative in nature. The proposed changes remove the TS Index and make other editorial and administrative corrections to the TSs. These administrative changes are not initiators of any accident previously evaluated, and, consequently, the probability and consequences of an accident previously evaluated is not significantly increased.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No. The proposed changes are administrative in nature so no new or different accidents result from the proposed changes. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed), a change in the method of plant operation, or new operator actions. The changes do not alter assumptions made in the safety analysis.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3) Do the proposed changes involve a significant reduction in the margin of safety?Response:
No. The proposed administrative changes do not involve a change in the method of plant operation, do not affect any accident analyses, and do not relax any safety system settings.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, DNC concludes that the proposed changes do not present a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
4.3 Conclusion
Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Serial No.14-037 Docket No. 50-423 Attachment 1, Page 6 of 6 5.0 ENVIRONMENTAL CONSIDERATION DNC has determined that the proposed amendment would not change a requirement with respect to installation or use of a facility component located within the restricted area, as defined by 10 CFR 20, or an inspection or surveillance requirement.
The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment.
6.0 REFERENCES
6.1 NRC Letter "Seabrook Station, Unit No. 1 -Issuance of Amendment Regarding the Administrative Changes and Corrections to the Technical Specifications (TAC No.MF1033)," June 17, 2013 (ADAMS Accession No. ML13074A760).
6.2 NRC Letter "Waterford Steam Electric Station, Unit 3 -Issuance of Amendment Re: Modification of Technical Specification (TS) 5.3.1, Fuel Assemblies, T.S. 5.6.1, Criticality, T.S. 6.9.1.11.1, Core Operating Limits Reports, and Deletion of TS Index (TAC No. MC3584)," May 9, 2005 (ADAMS Accession No. ML051290368).
6.3 NRC Letter "Arkansas Nuclear One, Unit 2 -Issuance of Amendments Re: Deletion of Index Pages from the Technical Specifications (TAC No. MC3246)," June 22, 2005 (ADAMS Accession No. ML051740191).
6.4 NRC Letter "Issuance of Amendment (TAC No. M93730)," January 7, 1997.
.Serial No.14-037 Docket No. 50-423 ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 3 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 1 of 2227, 200?,;NRE 1.PEFINiTION&
44 A CTIO N ................................
44 ACTUAT1dION LOGICG TEST.4-.4 ANALO6G CRI'NNEL OPEII 41-4 2604,41 FL6" DIFFERENCI-
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4- CONTAINMENT "iTEG'IE '44 DOSE EQUIrVALENT
! 131.4~4 DOSE EQUIVALENT XE L2 D4. ENGNEE.ID SF~ E 4-9. DELETED-9 LEKACE .........
.........4-4 MASTER PRELAY 1 ,ST .4t44 N OF THE rUT 444 OPERALE OPERABILT 44 M.ODE M, 4-4 PHYSCS TESTS.............
4PURGE PURGING*9
.............
-444 QUADRANT POWER TILT 4-- DELETED 44 ATED THEPiM.AI POWER 444 REPODTADLE E2VENI12T.
44 SHUTDOWN M APC-It....
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1 q RATIO.................................................
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15.i.15.. .......... .......... .... .............1 ........... .............. ............imsg 25ib C Serial No.14-037 Docket No. 50-423 Attachment 2, Page 2 of 22&94449 4-4;444+451 448 4-P 4-44 PhiA-Wg RELA T4:EP:...........T......................................................
1 6 SO U R C E C H EC K ...............................................................................................
1 6 8S;6rGI;RED TEST: BASIS ..........................................................
1 6 THERMAL4 POWER ...................................................................
1 6 TIPIACT N DEVICE OPr TiONA TEST...........................1 6 U1NP4ETRiCTED ArE4A..............................................................I i V E N T-T I C .......................................................................................................
..1 7 SPENT RPHL POOL STO9RAGE PA:IFIERNS......................................1 7;PE. ..E POO ..T.R..........................................
CORS OPERATING LIMITS REPOR-T (GOER)...................................1 7 ALLOWEID POWER LESVEL ................................................
1 7 LEVELT' APLHWN"TrI"'T 17" FREQU.E.NCy NOTATI.......................................
- OpE TONAL MODES .........................................
1 9-I" MLT, O-Ns.E UNIT 3 4 2-ýdendfiefi
?I. 6 , a, (31, -,-. by, Serial No.14-037 Docket No. 50-423 Attachment 2, Page 3 of 22 Mrh14, 200:7 SAFETY LIMAITS AND LiMiTINC SAFETY SYSTEM SETTINCS 2.1 SAFETYX LNI~TS 2-4.4 REA CTO R C O RE .........................................................................................
2 1......... .REAC4h.R COOLiT 94...M PREE8R ............................
........ 2 1 FIG U PR E 2. 1 2 E L E T ED ...........................................................................................................
2 S2 .2 E .........................................................................................................
2 2.24REACTýOR TRIP 8*944M N4 TRUMENTAR1ON...T...............
2 1 TABLE 2.2 1 REACTOR TRIP 8*844;N FN4ST4HUMNTA-RON TMP sE4hOpTs ......2 5 2.1 SA4FEFh' IMITS4: 24A REACTOR CORE .........................................
B 2 1.2. i. -RERACTOR COOL6ANT 8YSTEMR PRESSURE.
............
B 2 2+.2 i EAC'1TOJ TRI4P S*STEM vINTUET IO SETPOINTS...........B 24 ;-MILLTONE~IT Affienzmet Ne. 2P.. 236 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 4 of 22 MIeh4 16, LIMITINC CONDITIO:RNS FO-R O-PERAti-TIO N AND SUR-VEILL:ANCE REQUIREMENTS:F
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4 G 3.1 RACFVIY CNTOL SYTEM SHUDOVN MRCI MOESI AD 2........
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3A1 11 Fi~Pi4RI 4 D. ELETED6 ........................................................................
3.1 115 F G U PI.E 3 .i -D ELETED ............................................................................................
31A 1 64 " 14 DELETED..............................................3A 1 7 8,R1T:D .N M1AcRGIN COLD... SIRUTDOWN Lzcrps Nei F~illd....................................................................A-14 1 9---I.;. Z ;. .L ........................................................
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3A' 1 12 1DORATION SYSTEMS1 DELETED ...............................................
3/14 1 1R D E L E T E D ..................................................................................................
1M 15 D E L E T E D ..................................................................................................
1,A i 16 D EL .ETE PD ...........................................................................................
.. 3/41 1 1 D E L D. ...................................................................
- 31. 1 MOVABLE CON44OL ASSEMBLIEs G .u p H .................................................................................................
3 ,14 1 20.ACCIDENT AM E NG REEVYT4tUATON TiNTILE EVNTOFAN GNpE;R.ABL FULL LE GTH4 ROD ..................
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1.4 1 23 .:A4: P;P 44.1 1 MRILLSTOBNEýA TT 3..... .N. .0.. 60. , 197, 21i7, 218.29 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 5 of 22 Mafeh 9 29..:2.,i. :" ,-.U :"*.,; :.. .L? ; :'.~ L:.°1 :..". .L; %2L : ;U; aIS :.M,'115 1 E D E L E T E D ..............................................................................................................
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3A 1 26 G .R. e d .............................................
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34 1 1 27+'%A YwW, 3,14.2.3 3A1.2.4 ANIA,"L FLM6 DIFFERENC E ......................................................................
3/M 2 1 RCS FLOW RATE OiND NUCLEAR ENT-HALPY RISE; HOT CHi ANNELM FACTO9R..............................................................
314 2 19 QUADRANT POWER TILT RPTIO ............................................................
3,1 2 21 D N B P.... .A .ETERS................................................
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3 A 2 24*1-L ..I L L L I ......................................................................................................
4 14.3 INS- T.U.MENTA.PO.
- 3. ..4.. ...RE C.TOR T P, SYST.M...N
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3A 3 1 T1'4141 3.3 1 RENA CTOP. TRIP SIYSTEM. 1NS 42TRUMENTATON
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3/ 3 2 TABLE 3.3 2 DEL6ETBED T;BABL 1.3 1 REACTFOR TRIP SYSTEM pUsTRUMNTsN4AION SURVEILL6ANC RE.Q u IRE MN.TS .......................................................................................
3/43 10 E.43E2 P'SA.E1TY
....R.. .ACTUR..ATION...
SYSTM N INSTRUMENTATION
...........................................
3A1 3 15 TABLE 3.3 3 RiNC~EER9D SAFETY FEATURES A.CTUA-TION 83YSTEM INSTRUMENTATION
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3M1 3 1:7 TAL4. ENCiEREDRB SAFE;TY FEATURERS AGTUA44ON SYSTEM;N-I -....................................................
INz.50.e0,Sf,91l207 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 6 of 22 LIMIT-ING CONDITIONS FOR OPERATIO0N ANDlj SUCRVEILLANCýjE RE;QUIREM4ENT-S TABLEr 3.3 5 DELTEITD TABLE 41.3 a ENC;ILR;EDCG Sk.TETY FEATURE,4s AC6AIN 8TEM....T.UM .NTA..ON ... .. .... .. .......REQUI. ........3, 43 36~44~ MOIOIN.N4METTO R a im e N!:,: .m.,.. i g for_ R-__ 0, .........
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...................................................................
AA 3 43 TA4BLE 1.3 3 RAPIA-TION MONIRTORING INSTRUMENTj4ATION FOR PLAN~T-OPERATIONS S EILLANCE QUIREMENTS....................
14 3 45 T-ABLE ;.3 ; DELEETED)TABLEB 1.3 1 DELETED'TAkBLE 3.; 8 9ELETED TABL-E '1.3 5 DELETED Rem.. te sh itiv. ...I o9f3/ n3 5 .3...........................................................
314 ; 53.ABI. E 3.3 9 REMOTE ..U..OWN P491. .N .T .... .......................................
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3 TABLE 3.3 AG.. IDENT .T-,- ....M.ONITO..NG..............O 3"64 3 ,o TABLE 1.3 7 ACCID)ENT MOIO9JISTUETTO URVEILLANCE;GI
.....................................................................
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8 1. 9 1, 1 88. 193 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 7 of 22 Ma~y ;1 , 2 99;LIMITING CONDITIONS FORl OPERhATIONAND TURVLRLAC TABLE 3.3 13 DELET 3114.3 .4 "149 9T" l 3.1-.-....---4 8EL6T-EPA 4AW-M ARGIN QlNO I' R ................................................................
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3)/48 41 .'. SA FET V V AL -ES 3/..1:...........................................................................................
3A , 9 D E L E T E D ..........................................................................................................
3/14 4 10 3,449 Stf, .. .. P on w;,er O ...r: i ................................................................................
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...................................................
3/143N Oper~zafi iF.!14AKAGE...............................................................
3A 1 22 TABLE 3.4 1. REACTOR COOLANT SYSTEM PRESSUPE IOLATION VALVES ... 3/ 4 24 3 4 4 D E L E T E D .........................................................................................................
3 / 4 25 t TABLE 3.4 2 DELETED ...................................................................................................
- /TABLE -DELTED..344. SPECIFIC ACTIVJITY.3./IA A nO......................................................................................
--.--LASTONE 6IT 3 N4i 19;, 2(01, 217w, 329, 2358 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 8 of 22 Opfab.ez 27, 2005r LIMTIN CNDIIOS FR PERTIN ADSREL.~ERQIEET FIG U649 3.114 44AA;4.4 4 L J ,L, A "b & ...............................................................................................
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3/14 5 3 E-.CCS~ SUSSTM LESS THAN 350-F.........................
3,1 5 7;REFUELING WAATER STO9RAGEPTANK
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3,14 6 7 MILLSTONE TiTi IT 3 14i byýi 2, !w4, Serial No.14-037 Docket No. 50-423 Attachment 2, Page 9 of 22 LIMITINC CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRWOEMETS A ir Tcem por-ture ......................
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.. ... ......".............................................................3 3Y 7 2,+-I MILLSTT ONE ' I T 3 A...zaLtznt No. 59, 63, 8;7, 89, 19G, 115, 126, 217, 221, 212 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 10 of 22 Ally IMAITING CONDITIONS FOR OPER269ION AND SURVEILLANCE9 REQUIRAEMET-&
&BT44994.7
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3M 14 S.......................................
3,1 15 3/1.8.3 QNSITE POSAER DShBTO Oprii ..................................................................
3.148i g h'td &,',' .................................................................................................
3,1 8 18 ELECTPICAL EQUIPMENT PROTECpI.VE DEVICES DELE;TED ......................................................................
3.'81 DF;ELET .....................
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....... .. ..3... ... ... ... .. .. ... ... ... ... .. ... ... ... ...'1 9-I" Serial No.14-037 Docket No. 50-423 Attachment 2, Page 12 of 22 Maefe4 26, 201 LIMI9TING CONDITIONS FRo OPEILATION AND SURVEIILLANCE REQUIREENT DE.T.................................................
OA~V 914.94i;314942 F4~WW ;94..L .....L. ...........................................................................................
....... , , I RIESyIDUAL HEAT RT AGMO'L& ANrD COOLTANT CICULT ION- T L-e. Wehetz 1 ...........................................
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- / 9 10 DELTn In/1A Q 11 SPENT FUEL6 POOL REACTIVITY
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31'49 16i SPENT FUEL POOL TRAGE PATTER .....................
3/14 9 1?MINIMU164 FUL-; ASSEMBLY BURNU4P V'ERSUS NOMINAL INIIALENR~hMNT OR RECION 11 OUT;: OF 4..TO......C...........TION............................
3/19 15-REGION 1 3 OUT OF 4 9TORACEFEGA9ML LOGAD ~iC SGHEMATIC
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3M' 9 19 NOI.. NITIAL ENRICHMENT FOR REGION; 2 STO-RAGE, CONFIGURATION............................................
3/1,9 20 MINIMUM FUEL ASSEMNBLY*
BUR44UP ANiD DECAY TIME VERSUS NOMPINAL INITIL ENRIGHMIENT FOR REGION 3 STOR AGEl CONIGRTONFLO R ASEBLE FROM PME UPiRAF (3111 ...........
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3;M19 21 MAINIMUM FE SSML URU N DCYTMEVRU NOM 44A I ITIA BNRiCHIMEN'r FOR REGION 3 ST9RAG G3 5 M T ORES ........................................
1M 9 2.2 w4iTTA49 4.--3;4. 10 SPECIALTEST EXCEPTIONS O4110 3,4.10.~4410.4 3/4.10.SHUTDOV10WIA.N MARGIN.........................................................
3M11 GROUP HPEGIIT, INSERTION, AND POWER DISTWhBU4TIGN L-IM ITS9. ...................................................
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B 3A 1 11 3D EL1 O 1 E T E D ........................................................................................................
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B 314 2.1 9 3,42 DNB PARAMETFERS
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B 3/1 2 9 3,3.'1. anzd 3,14.3.2 REACTRA 44P SY-STEMI INSTUMENPRFION AND ENCD;EERED SAFETY51 FEARWRES AC4;hATION SYSTEM..N...T.........N.....T...............................................
B 3M' 3 1 343.3 MONITORING
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B 3/ 3 3 114,3 4 TURB-pINE OVER-SPEED1 PROTECTION
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BA 3/14 -3 3A.4 3.5 1UTDOWAN MARGIN MONITRG..............................................
B 3.1A3 7 X41.1 REACTOýR COOLAdNTF 8YSTEMN 34 4 REACTOR COOLANT LnOOPSAND COOLANT CIRCLATION
.B 14 , i 3,4 4.2 U P.I Z E R ..............................................................................................
B -I'A, 4 2 3A.4.3 PRE;SSUR+AER.......................................................................[3, 1 22 3 44 .4 R ELIEF V A LV ES .............................................................................................
B 3 14 4 2b A l"4 A GENERTORS
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B 3,14 3 3,4464 REACTOR COOL;ANT 8SY-STM LEAKACE...................................
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p P4 45 3,44.4.8 SPECIFIC 7ACG 4TIVITY ..........................................
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B P4"7-I-N41669TONS 644T-3 4H ft MILLSTOnE N3 60, 89, 160, 161. 4,W-7.,
Serial No.14-037 Docket No. 50-423 Attachment 2, Page 14 of 22 Seritl~ber
!§, 2006 BASES TALEB /11 RACOR'.ESELFAkC-TU6RE TOU6GINEsS PROPERTIES
.... B 3A 1 9 RQ;;REB3CT 41FA9TN1T Q O)A9ARWINQ F F*ý 1 POWIER SE -ic 1 6 11/ ..........................................................
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.3'1[ i 115.........................................................
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B !3/1 1 2.........................................................
- 113 4 9 ]i........................................................
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B A41 6 3d 00LiNG k'.WTER SYSTEM......B 3,'4 7 7 ENTILATION SYSTEM............
B 344:7 10 r E. .................................
3.. 172....................
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14 1 4 :13 2.,t" MILLSTONE Serial No.14-037 Docket No. 50-423 Attachment 2, Page 15 of 22 IWDE BASES D ELE ...............................
3A7.4 DELETED-'1-13 DELET I.......B............................
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4A .9 .A* ýR M E ....................................................................-Z 4.9-7 D EL.E T E D ..........................................................................
3-14.9.8 RESIPDAL HEAT. RBM0'L6 ..AND ..OOL.ANT CIRCE.1,4.9.9 DELETED.......................................................
3,14.9.10 and 3419.11 './TRLVL REACTOR ;,EggEL AND... .. .... ... ...... -I -..... .........B 3) 9192 ft 4LATION.......B 3/1' 9 2a................
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A-4944 SPENT FUEL POOL REAtC-TP.Ir:4
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'1, 3.14. i.e. i Rý4 10 ;'3410.3 3,410.4 3/4.10.5"ip6T', O W N ", ' 4'; 2 k R.=, p.;; ...............................................................................
1 S I GROUP IILC TIsERTION, AND POW'ER DSDT L IM IT g ..........................................................................................................
13 3,4 10 1 REACTOR COOL.AN T LO OPS ....................................
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B 3/1 10 1 D)ELERTEDR14...........................................................................B1 3A1 1.0 1 ,f-nende.. 0.4, 89, 100, 1 0' 11 i4, 136 189. 192,,,0;, 91,2 9,225,924 2-50 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 16 of 22 N8VOR~bOF 28, 2000 BASES 3/1.. 11 DELETED {i.2 L666T61 D14 .3 ,4"T5TONE T "3 Adne"dffieflf Ne.
Serial No.14-037 Docket No. 50-423 Attachment 2, Page 17 of 22 sapteffi 17,200 RESIGN FEATURES 5. S rTTITE LOC1ATIO 5 , J.CR IT IC A L IT ..............................................
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Serial No.14-037 Docket No. 50-423 Attachment 2, Page 18 of 22.o&p ..4.. 1999 ADMINISTRATEVE CONTROLS 6.A .........rT.T-..................................................64 6.2 ORGANIZATION9...............................................................................
6 1 6-24 OFF-SITE AND ONSITE; ORCANIZATIONS..................................
6 1 6-2 FACILITY STAFF..................................................................
6 1 T.A.L 6.-2V4A--
1 MINIMUM SHIFT CREW COMPOSITION
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6 3 6.24 SIIF-T TECIR4CALM ADVISOR.................................................
6 4 6.3 FACILITY 9TAFF GiduAl- fiCATIOem....................................
6 5 6. F 2 N i ..............................................................................
65 6._.7. DELETED?#411minSTONI; UNIT 3 MLO... nt .. .26, 36, 69 89,104, Serial No.14-037 Docket No. 50-423 Attachment 2, Page 19 of 22 ADMINISTRATIVE CONTROLS&&G444@@4 Ak449 A 9 ONLU I I ."J'EO s .r..........Ar .T .14 6.9 REPORTING REOUIREMENTS............................................................6...
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6 M 6.15g RApQdIOACTIVE EFFILUENT-CONT-ROLns PROGRAM ................................
6 25, 6.16 RADiIOLOICAL .N..OMETA.MNITRIG..OR...........
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6 26 6.19 .........PCI.CTIN.....AS..ONhO POGA 6 26 6.19 COMPONENT GCYCICI OR q:~dNSINT LIMIT......................................
6 .27 a'fl 211 n11 n'21 23 383 1 4w Serial No.14-037 Docket No. 50-423 Attachment 2, Page 20 of 22 ENGINEEI 0 CC z e, CHA FUNCTIONAL UNIT CHE'3. Containment Isolation a. Phase "A" Isolation 1. Manual Initiation N.A.2. Automatic Actuation N.A.Logic and Actuation It, Relays 3. Safety Injection See]b. Phase "B" Isolation 1. Manual Initiation N.A.TABLE 4.3-2 (Continued) tED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH NNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED N.A.N.A.N.A.N.A.R N.A.N.A.M(1)N.A. N.A. 1,2,3,4 M(I) Q (4) 1, 2, 3, 4 tem 1. above for all Safety Injection Surveillance Requirements.
N.A.0.B o 2. Automatic Actuation Logic and Actuation Relays 3. Containment Pressure-High-3
- c. DELETED 4. Steam Line Isolation 4. Manual Initiation
- 1. Individual
- 2. System N.A. N.A.S R N.A. N.A.N.A. N.A.N.A.N.A.Q N.A.N.A.R N.A.N.A.R R N.A.M(1)N.A.N.A.N.A.N.A. NA. 1,2,3,4 M(l) Q(4) 1,2,3,4 N.A. N.A. 1,2,3,4-t N.A. N.A. 1, 2, 3.4 N.A. N.A. 1,2,3,4
- Serial No.14-037 Docket No. 50-423 Attachment 2, Page 21 of 22 September 1COT.20L ADMINISTRATIVE CONTROLS 63 FACILITTY RTAFF 0IIA1.T1FICATIONR 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971
- for comparable positions.
Exceptions to this requirement are specified in the Quality Assurance Program.63.2 #bl th,, OpcrAtia,-
mana,"ger does, not held- ase,'ier rvaeteF operator lie,,en ,% \,ilto-, 6. shall -- e-ld a senior r ettz. e :a p erat e z.Ji em ofr i.t The operations manager or at least one operations middle manager shall hold a senior reactor operatorlicense for Millstone Unit No. 3.6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff that meets or exceeds the requirements as specified in the Quality Assurance Program and 10 CFR Part 55.59 shall be maintained.
6.4.2 Deleted.6.5 DELETED.+/--1" As of November 1, 2001, applicants for reactor operator and senior reactor operator qualification shall meet or exceed the education and experience guidelines of Regulatory Guide 1.8, Revision 3, May 2000.MILLSTONE
-LUNIT 3 6-5 Amendment No. 46,-69, 84, 99, 94, 44G, 2, +3-54 4-4,4-7, 499, 2-2, IZ6 Serial No.14-037 Docket No. 50-423 Attachment 2, Page 22 of 22 Novembe. 28, 2000 ADMINISTRATIVE CONTROLS 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)a. The REMODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental program; and b. The REMODCM shall also contain the radioactive effluent.controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 6.9.1.3 and Specification 6.9.1.4.Licensee initiated changes to the REMODCM: a. Shall be documented and records of reviews performed shall be retained.
This documentation shall contain: I) sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and 2) a determination that the change(s) will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;
- b. Shall become effective after review and acceptance by SORG and the approval of the designated officer; and c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMODCM as a part of or concurrent with the Rad~ioactive Effluent Release Report for the period of the report in which any change in the REMODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicated the date (i.e., month and year) the change was implemented.
6.14 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents.
These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.The Solid Radioactive Waste Treatment System shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
MILLSTONE
-UNIT 3 6-24 Amendment No. 40, 69, 86, 90, 444, 4-q4-, +4-73, 4-g8