RS-06-181, Braidwood Station, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report: Difference between revisions

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#REDIRECT [[RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report]]
| number = ML063490283
| issue date = 12/15/2006
| title = Braidwood Station, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report
| author name = Benyak D M
| author affiliation = Exelon Nuclear
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000237, 05000249, 05000254, 05000265, 05000277, 05000278, 05000373, 05000374, 05000454, 05000455, 05000456, 05000457
| license number = DPR-019, DPR-025, DPR-029, DPR-030, DPR-044, DPR-056, NPF-011, NPF-018, NPF-037, NPF-066, NPF-072, NPF-077
| contact person =
| case reference number = RS-06-181
| document type = Letter type:RS, Technical Specification, Amendment
| page count = 24
}}
 
=Text=
{{#Wiki_filter:Exelon Generation wwwexeloncorp.co m 4300 Winfield Road Warrenville, IL 60555 RS-06-181 10 CFR 50.90 December 15, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
 
==Subject:==
Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report xe~ I~m Nuclear In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Appendix A, Technical Specifications (TS), of the Facility Operating Licenses listed above. The proposed amendment would modify TS by replacing the term "plant-specific titles" with "generic titles" in TS section 5.2.1.a. This revision will ensure the TS description is consistent with the EGC Quality Assurance Topical Report (QATR). The proposed amendment will also revise the Peach Bottom TS section 5.2.1.a to replace the reference to the Updated Final Safety Analysis Report with reference to the EGC QATR. This change aligns the Peach Bottom TS wording with the rest of the EGC fleet.
December 15, 2006 U.S. Nuclear Regulatory Commission Page 2 Attachment 1 provides an evaluation of the proposed change and Attachment 2 provides the existing TS pages marked up to show the proposed change. The proposed changes have been reviewed by the Plant Operations Review Committee at each applicable site and approved by the Chairman of the Nuclear Safety Review Board. EGC requests approval of the proposed license amendment by January 19, 2008. Once approved, the amendment shall be implemented within 60 days. EGC is notifying the State of Illinois and the Commonwealth of Pennsylvania of this application for a change to the TS by sending a copy of this letter and its attachments to the designated state officials in accordance with 10 CFR 50.91, "Notice for public comment; State consultation
." Should you have any questions related to this letter, please contact Ms. Michelle Yun at (630) 657-2818. 1 declare under penalty of perjury that the foregoing is true and correct. Executed on the 15 th day of December 2006. Respectfully, Darin M. Benyak Manager - Licensing Attachments
: 1. Evaluation of Proposed Change 2. Markup of Proposed Technical Specification Page Changes Braidwood Station, Units 1 and 2 Byron Station, Units 1 and 2 Dresden Nuclear Power Station, Units 2 and 3 LaSalle County Station, Units 1 and 2 Quad Cities Nuclear Power Station, Units 1 and 2 Peach Bottom Atomic Power Station, Units 2 and 3 ATTACHMENT 1 Evaluation of Proposed Change
 
==1.0 DESCRIPTION==
 
===2.0 PROPOSED===
CHANGE 3.0 BACKGROUND
 
===4.0 TECHNICAL===
 
ANALYSIS 5.0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration
 
===5.2 Applicable===
 
Regulatory Requirements/Criteria
 
===6.0 ENVIRONMENTAL===
 
CONSIDERATION
 
==7.0 REFERENCES==
 
==1.0 DESCRIPTION==
 
In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Appendix A, Technical Specifications (TS), of the following Facility Operating Licenses. The proposed amendment revises TS requirements for TS 5.2.1, "Onsite and Offsite Organizations," section a, by replacing the term "plant-specific titles" with "generic titles" at Braidwood Station, Units 1 and 2; Byron Station, Units 1 and 2; Dresden Nuclear Power Station (DNPS), Units 2 and 3; LaSalle County Station (LSCS), Units 1 and 2; Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3; and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The current revision, Revision 77, of the EGC Quality Assurance Topical Report (QATR) uses generic titles in accordance with 10 CFR 50.54, "Conditions of licenses," paragraph (a)(3)(iii). There will be no changes to the prerequisite qualifications, the assigned responsibilities, or the organizational reporting relationships. The proposed change will align the TS with the current revision of the combined EGC QATR. In addition to the above, the proposed change will align PBAPS, Units 2 and 3 with the rest of the EGC fleet by replacing "UFSAR" with "QATR" in TS section 5.2.1.a. 2.0 PROPOSED CHANGE ATTACHMENT 1 Evaluation of Proposed Change TS section 5.2.1.a for each of the stations listed above currently reads as follows. °... These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, ..." The proposed change would revise TS section 5.2.1.a for each station above to read as follows. "... These requirements, including the generic titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, ..." Page 2 of 7 Station (*Renewed)
Facility Operating License Nos. Braidwood Station, Units 1 and 2 NPF-72 and NPF-77 Byron Station, Units 1 and 2 NPF-37 and NPF-66 Dresden Nuclear Power Station, Units 2 and 3 *DPR-19 and *DPR-25 LaSalle County Station, Units 1 and 2 NPF-11 and NPF-18 Peach Bottom Atomic Power Station, Units 2 and 3 *DPR-44 and *DPR-56 Quad Cities Nuclear Power Station, Units 1 and 2 *DPR-29 and *DPR-30 ATTACHMENT 1 Evaluation of Proposed Change In addition, PBAPS TS section 5.2.1.a currently reads as follows. "...shall be documented in the UFSAR;" The proposed change would revise PBAPS TS section 5.2.1.a to read as follows. "...shall be documented in the QATR;" Attachment 2 provides the marked-up TS pages indicating the proposed changes. 3.0 BACKGROUND The licensees adopted the Improved Technical Specifications (ITS) in amendment Nos. 98 and 98 at Braidwood Station, Units 1 and 2, dated December 22, 1998 (Reference 1); Nos. 106 and 106 at Byron Station, Units 1 and 2, dated December 22, 1998 (Reference 1); Nos. 185 and 180 at DNPS, Units 2 and 3, dated March 30, 2001 (Reference 2); Nos. 147 and 133 at LSCS, Units 1 and 2, dated March 30, 2001 (Reference 3); and Nos. 199 and 195 at QCNPS, Units 1 and 2, dated March 30, 2001 (Reference 4), respectively. These amendments added the phrase, "including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications," to the respective units' TS section 5.2.1.a. The NRC approved Technical Specification Task Force (TSTF) Traveler Number 65, Revision 1, "Use of Generic Titles for Utility Positions," in a letter, dated November 10, 1994. PBAPS, Units 2 and 3 adopted TSTF-65, Revision 1, in amendment Nos. 259 and 262, dated May 10, 2006 (Reference 5). These amendments added the phrase, "including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications," to the PBAPS, Units 2 and 3 TS section 5.2.1.a. The intent of the ITS adoption and TSTF-65, Revision 1, changes was to (1) allow licensees the flexibility to rotate management personnel and revise position titles and (2) eliminate the need for future license amendments involving plant-specific position titles. The ITS adoption and TSTF-65, Revision 1, changes were approved because none of the qualifications, duties, or responsibilities of the positions were modified. In addition, the plant-specific titles were to be in documents in which changes to the titles would be controlled by 10 CFR 50.59, "Changes, tests, and experiments" or 10 CFR 50.54, "Conditions of licenses," paragraph (a). On February 23, 1999, the NRC published the Final Rule pertaining to 10 CFR 50.54(a) (Reference 6). One of the six provisions permits licensees to make the following type of change to their Quality Assurance (QA) Programs: "The use of generic organizational titles that clearly denote the position function, supplemented as necessary by descriptive text, rather than specific titles." The proposed change will align the specified TS with the QATR by replacing the term "plant-specific titles" with "generic titles" in TS section 5.2.1.a. The proposed change will Page 3 of 7 also align PBAPS, Units 2 and 3 with the rest of the EGC fleet by replacing "UFSAR" with "QATR" in TS section 5.2.1.a. 4.0 TECHNICAL ANALYSIS The proposed change will revise TS section 5.2.1.a by replacing the term "plant specific titles" with "generic titles." This proposed change does not involve changes to the prerequisite qualifications, the assigned responsibilities, or the organizational reporting relationships. In addition to specifying generic titles rather than plant specific titles, the PBAPS TS section 5.2.1.a will be revised to replace "UFSAR" with "QATR." PBAPS shares the EGC QATR with the EGC fleet, including the current revision of the combined EGC QATR. As a result, the proposed change to refer to the QATR rather than the UFSAR aligns PBAPS with the other EGC stations. This change will not result in changes to the assigned responsibilities, the organizational reporting relationships, or the need to document the requirements of TS section 5.2.1.a in a licensee-controlled document. This change simply revises the identified location for this information from the UFSAR to the QATR. The requirements of TS section 5.2.1.a are still maintained in the UFSAR, as the QATR is part of the UFSAR by reference. 5.0 REGULATORY ANALYSIS ATTACHMENT 1 Evaluation of Proposed Change 5.1 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests an amendment to Appendix A, Technical Specifications (TS), of the Braidwood Station, Units 1 and 2 Facility Operating License; Byron Station, Units 1 and 2 Facility Operating License; Dresden Nuclear Power Station (DNPS), Units 2 and 3 Renewed Facility Operating License; LaSalle County Station (LSCS), Units 1 and 2 Facility Operating License; Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Renewed Facility Operating License; and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2 Renewed Facility Operating License. The proposed amendment would modify TS requirements for TS 5.2.1, "Onsite and Offsite Organizations," section a, by replacing the term "plant-specific titles" with "generic titles." The current revision, Revision 77, of the EGC Quality Assurance Topical Report (QATR) uses generic titles in accordance with 10 CFR 50.54, "Conditions of licenses," paragraph (a)(3)(iii). There will be no changes to the prerequisite qualifications, the assigned responsibilities, or the organizational reporting relationships as a result of this change. The proposed change will align the TS with the current version of the combined EGC QATR. In addition, the proposed change will align PBAPS, Units 2 and 3 with the rest of the EGC fleet by replacing "UFSAR" with "QATR" in TS section 5.2.1.a.
Response: No Response: No ATTACHMENT 1 Evaluation of Proposed Change According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: 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 Involve a significant reduction in a margin of safety. EGC has evaluated the proposed change to the TS for Braidwood Units 1 and 2; Byron Units 1 and 2; DNPS Units 2 and 3; LSCS Units 1 and 2; PBAPS Units 2 and 3; and QCNPS, Units 1 and 2, using the criteria set forth in 10 CFR 50.92(c), and has determined that the proposed change does not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration. 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change is a word replacement in TS 5.2.1, "Onsite and Offsite Organizations
." The proposed change involves no changes to plant systems or accident analyses. The proposed change is administrative in nature and, as such, does not affect initiators of analyzed events or assumed mitigation of accidents or transients. Therefore, the proposed change does not involve any increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Creation of the possibility of a new or different kind of accident would require creating one or more new accident precursors. New accident precursors may be created by modifications of plant configuration, including changes in allowable modes of operation. The proposed change does not involve a physical alteration of the plant, add any new equipment, or allow any existing equipment to be operated in a manner different from the present method of operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Response: No ATTACHMENT 1 Evaluation of Proposed Change 3. Does the proposed change involve a significant reduction in a margin of safety? The proposed change is administrative in nature and has no impact on equipment design or method of operation. There are no changes being made to safety limits or safety system allowable values that would adversely affect plant safety as a result of the proposed change. Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based upon the above, EGC concludes that the proposed change presents no 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. 5.2 Applicable Regulatory Requirements/Criteria As required by 10 CFR 50.36(c)(5), "Administrative Controls," the administrative controls section of the TS provides the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. The TS list requirements regarding the organization for the safe operation of the facility, including listing of positions within the organization structure. The administrative change from "plant-specific titles" to "generic titles" does not reduce the ability of the facilities to operate in a safe manner. Regulatory Guide (RG) 1.8, "Qualification and Training of Personnel for Nuclear Power Plants," provides an acceptable method for implementing 10 CFR 50.34 paragraph (b)(6)(i), "Final safety analysis report." The proposed change does not affect EGC's current implementation of 10 CFR 50.34(b)(6)(i). The proposed change aligns the TS with the EGC QATR and does not modify the EGC QATR. Therefore, EGC continues to meet the requirements of 10 CFR 50.34(f), "Additional TMI-related requirements," paragraph (3)(iii) and 10 CFR 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 6.0 ENVIRONMENTAL EVALUATION EGC has determined that 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 change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," section (c)(9). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the proposed amendments. Page 6 of 7 
 
==7.0 REFERENCES==
 
ATTACHMENT 1 Evaluation of Proposed Change 1. Letter from Mr. Ramin R. Assa (U.S. NRC) to Mr. Oliver D. Kingsley (Commonwealth Edison Company), "Issuance of Amendments," dated December 22, 1998 2. Letter from Mr. Stewart N. Bailey (U.S. NRC) to Mr. Oliver D. Kingsley (Exelon Generation Company, LLC), "Issuance of Amendments," dated March 30, 2001 for Dresden Nuclear Power Station 3. Letter from Mr. Stewart N. Bailey (U.S. NRC) to Mr. Oliver D. Kingsley (Exelon Generation Company, LLC), "Issuance of Amendments," dated March 30, 2001 for LaSalle County Station 4. Letter from Mr. Stewart N. Bailey (U.S. NRC) to Mr. Oliver D. Kingsley (Exelon Generation Company, LLC), "Issuance of Amendments," dated March 30, 2001 for Quad Cities Nuclear Power Station 5. Letter from Mr. Richard V. Guzman (U.S. NRC) to Mr. Christopher M. Crane (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendments RE: Incorporation of Previously NRC Approved Generic Technical Specification Changes," dated May 10, 2006 6. Federal Register, Volume 64, Number 35, "10 CFR Part 50 Changes to Quality Assurance Programs; Final and Proposed Rules," dated February 23, 1999 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2a) Braidwood Station Units 1 and 2 2b) Byron Station Units 1 and 2 2c) Dresden Nuclear Power Station Units 2 and 3 2d) LaSalle County Station Units 1 and 2 2e) Quad Cities Nuclear Power Station Units 1 and 2 2f) Peach Bottom Atomic Power Station Unit 2 2g) Peach Bottom Atomic Power Station Unit 3 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2a) Braidwood Station Units 1 and 2 Revised TS P ayes 5.2-1 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization
 
====5.2.1 Onsite====
and Offsite Organizations Organization
 
===5.2 Onsite===
and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships,,and job descriptions for key personnel positions, or in equivalent forms of documentati on. The requirements, including the -p-1-air',-see-i 4-e i tl es of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Program; b. The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c. The Chief Nuclear Officer shall be responsible for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, or perform health physics or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. BRAIDWOOD - UNITS 1 & 2 5.2 - 1 Amendment 109 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2b) Byron Station Units 1 and 2 Revised TS Paqes 5.2-1 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization
 
====5.2.1 Onsite====
and Offsite Organizations Organization
 
===5.2 Onsite===
and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant. 5pe ' ~* itTes of-those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Program; b. The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c. The Chief Nuclear Officer shall be responsible for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, or perform health physics or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. BYRON - UNITS 1 & 2 5.2 - 1 Amendment 115 generic ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2c) Dresden Nuclear Power Station Units 2 and 3 Revised T S Pages 5.2-1 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization
 
====5.2.1 Onsite====
and Offsite Orga nizations 5.2.2 Unit Staff Organization
 
===5.2 Onsite===
and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of docu rkentation. Th ese requirements, including the -pl a-H-qppeei i-c- titles ~ f those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Manual. b. The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. c. A corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. d. The individuals who train the operating staff, or perform radiation protection or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. The unit staff organization shall include the following: (continued)
Dresden 2 and 3 5.2-1 Amendment No. 185/180 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2d) LaSalle County Station Units 1 and 2 Revised TS P aqes 5.2-1 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization Organization 5.2 5.2.1 Onsite and Offsite-Organizations 5.2.2 Unit Staff Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of docum entation. These requirements, including the - 'tit esl o whose personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Manual. b. The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. c. A corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. d. The individuals who train the operating staff, or perform radiation protection or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. The unit staff organization shall include the following: a. A total of three non-licensed operators for the two units is required in all conditions. At least one of the required (continued)
LaSalle 1 and 2 5.2-1 Amendment No. 147/133 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2e) Quad Cities Nuclear Power Station Units 1 and 2 Revised TS Pacies 5.2-1 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization
 
====5.2.1 Onsite====
and Offs ite Organizations 5.2.2 Unit Staff Organization
 
===5.2 Onsite===
and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of docu Re tation. These. requirements, including the-p la sp eeif-~ titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Manual. b. The station manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. c. A corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. d. The individuals who train the operating staff, or perform radiation protection or quality assurance functions, may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. The unit staff organization shall include the following: (continued)
Quad Cities 1 and 2 5.2-1 Amendment No. 199/195 ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2f) Peach Bottom Atomic Power Station Unit 2 Revised TS Pages 5.0-2 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization
 
====5.2.1 Onsite====
and Offsite Organizations
 
====5.2.2 LLnitStaff====
 
Organization
 
===5.2 Onsite===
and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of docum Vptation. Thes e requirements, including the sp eex++4-e-'titles of those personnel,fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented i n the - F§ -; °~-~ QATR b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c. The specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. The unit staff organization shall also include the following; _(continued)
PSAPS UNIT 2 5.0-2 Amendment No. 25 0 ,
ATTACHMENT 2 Markup of Proposed Technical Specification Page Changes 2g) Peach Bottom Atomic Power Station Unit 3 Revised TS Page s 5.0-2 
 
===5.0 ADMINISTRATIVE===
 
CONTROLS 5.2 Organization 5.2.i Onsite and Offsite OrganiZation5 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of docum~ptation. These requirements, including the -a- ~'titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specific ions, shall be documented in the ~, b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c. The specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures. 5.2.2 Unit The unit staff organization shall, also include the following: (cant?nu ed~ QATR Organization
 
===5.2 PBAPS===
UNIT 3 5.0-2 Amendment No. 262 generic}}

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