ML17212A083

Final Safety Analysis Report, Rev. 30, Chapter 13, Conduct of Operations

ML17212A083
Person / Time
Site:	Millstone
Issue date:	06/29/2017
From:	Dominion Nuclear Connecticut
To:	Office of Nuclear Reactor Regulation
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References
17-208
Download: ML17212A083 (21)

Text

MPS-3 FSARMillstone Power Station Unit 3 Safety Analysis Report Chapter 13 MPS-3 FSAR 13-i Rev. 30CHAPTER 13 - CONDUCT OF OPERATIONS Table of ContentsSection Title Page13.1ORGANIZATIONAL STRUCTURE......................................................13.1-113.1.1MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION....................................................................................13.1-113.1.1.1Initial Design and Operating Responsibilities..........................................13.1-113.1.1.2Organizational Arrangement.....................................................................13.1-513.1.2OPERATING ORGANIZATION............................................................13.1-513.1.2.1Unit Organization.....................................................................................13.1-513.1.2.2Assumption of Responsibility...................................................................13.1-513.1.2.3Operating Shift Crews..............................................................................13.1-513.1.3QUALIFICATIONS OF NUCLEAR PLANT PERSONNEL.................13.1-513.1.3.1Qualification Requirements......................................................................13.1-513.1.3.1.1Education and experience re quirements are established by Section 6.3 of the Technical Specifications..............................................13.1-513.

1.4REFERENCES

.........................................................................................13.1-513.1.5QUALITY ASSURANCE PROGR AM DESCRIPTION TOPICAL REPORT...................................................................................................13.1-513.2TRAINING PROGRAMS........................................................................13.2-113.

2.1REFERENCES

.........................................................................................13.2-113.3EMERGENCY PLANNING....................................................................13.3-113.

3.1REFERENCES

.........................................................................................13.3-113.4REVIEW AND AUDIT............................................................................13.4-113.4.1ONSITE REVIEW....................................................................................13.4-113.4.2INDEPENDENT REVIEW......................................................................13.4-113.4.3AUDIT PROGRAM.................................................................................13.4-113.4.4INDEPENDENT SAFETY ENGINEERING GROUP FUNCTION (DELETED)..............................................................................................13.4-113.4.5OTHER REVIEW GROUPS....................................................................13.4-113.5PLANT PROCEDURES...........................................................................13.5-113.5.1ADMINISTRATIVE PROCEDURES.....................................................13.5-113.5.1.1Conformance with Regulatory Guide 1.33...............................................13.5-113.5.1.2Preparation of Procedures.........................................................................

13.5-1 MPS-3 FSARCHAPTER 13 -CONDUCT OF OPERATIONS Table of Contents (Continued)

Section Title Page 13-ii Rev. 3013.5.1.3Procedures.................................................................................................13.5-113.5.2OPERATING AND MAINTENANCE PROCEDURES.........................13.5-313.5.2.1Operations Department Procedures..........................................................13.5-313.5.2.1.1General Operating Procedures..................................................................13.5-313.5.2.1.2System Operating Procedures...................................................................13.5-413.5.2.1.3Annunciation Response Procedures..........................................................13.5-413.5.2.1.4Abnormal Operating Procedures..............................................................13.5-413.5.2.1.5Emergency Operating Procedures............................................................13.5-413.5.2.1.6Operations Surveillance Procedures.........................................................13.5-413.5.2.2Department Procedures.............................................................................13.5-513.5.2.2.1Radiation Protection Procedures...............................................................13.5-513.5.2.2.2Emergency Preparedness Procedures.......................................................13.5-513.5.2.2.3Instrumentation and Control Procedures..................................................13.5-513.5.2.2.4Condition Based Maintenance Procedures...............................................13.5-513.5.2.2.5Chemistry Procedures...............................................................................13.5-513.5.2.2.6Radioactive Waste System Procedures.....................................................13.5-513.5.2.2.7Plant Security Instructions........................................................................13.5-513.5.2.2.8Material Control Procedures.....................................................................13.5-613.5.2.2.9Maintenance Procedures...........................................................................13.5-613.5.2.2.10Fire Protection Procedures........................................................................13.5-613.5.2.2.11Special Procedures....................................................................................13.5-613.6PHYSICAL SECURITY PLANS.............................................................13.6-113.

6.1REFERENCES

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13.6-1 MPS-3 FSARNOTE: REFER TO THE CONTROLLED PLANT DRAWING FOR THE LATEST REVISION.iiiRev. 30CHAPTER 13 - CONDUCT OF OPERATIONS List of Figures Number Title13.1-1Deleted by PKG FSC 01-MP3-01313.5-1Control Room Area MPS3 UFSAR13.1-1Rev. 30CHAPTER 13 - CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTUREInformation regarding the organizational structur e is presented in Section 1.0 of the Quality Assurance Program Description (QAPD) Topical Report (Reference 13.1-1).

Dominion Nuclear Connecticut, Inc. (DNC) is an indirect wholly owned subsidiary of Dominion Energy, which is in turn wholly owned by Dominion Resources, Inc.The majority owner, holding 93.4707 percent of the Millstone 3 nuclear plant, is DNC. The remaining 6.5293 percent is owned collectively by ot her electric utility enti ties. Their individual ownership shares are:The Principal Participants in the Millstone 3 lic ense have designated DNC to act as agent and representative for all of the owners of Mi llstone 3. DNC is responsible for the design, construction, operation, and fuel ma nagement of the unit and is authorized to act as Lead Applicant in all matters relating to the license.NNECO, formerly named the Millstone Point Company, was responsible for the design and construction of the Millstone Units 1, 2, and 3 nuc lear plants. Millstone Units 1 and 2 are owned, operated and/or maintained by DNC.

13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATIONThe management and technical support organi zations consist of DNC personnel. DNC is responsible for all support and op erational activities. DNC is co mmitted to ensuring that it maintains an acceptable organization and adequate resources to provide both on site and off site technical support for the operation of Mill stone Units 1, 2 and 3 under both normal and emergency conditions.

13.1.1.1 Initial Design and Operating Responsibilities Design and operating responsibilities are discussed in the following paragraphs in three general phases: Percent DNC93.4707Green Mountain Power Corporation1.7303 Massachusetts Municipal W holesale Electric company (Massachusetts Electric) 4.7990 100.00 MPS3 UFSAR13.1-2Rev. 301.Design and construction act ivities (project phase)2.Preoperational activities3.Technical support for operations13.1.0.0(1)Design and Construction Activities (Project Phase)Stone & Webster Engineering Corporation (SWE C), by contract with NUSCO, provided overall design and construction for the Millstone 3. Westin ghouse Electric Corporat ion, also by contract with NUSCO, designed and furnished the nucl ear steam supply system (NSSS). Administration of the contract with Westi nghouse was assigned to SWEC. NUSCO, responsible to NNECO for design and construction of all aspects of the pl ant, provided varying de grees of direct design involvement in establis hing the overall design.13.1.0.0(1)(a)Site Related Engineering WorkWith Millstone 3, the third unit built on the site, the various kinds of site rela ted engineering work required had been completed.

The meteorological tower met the requirements of NUREG-0654 prior to the Emergency Plan Start-Up Appraisal. Hydrologic studies performed with updated hurricane and storm surge models were used as the design basis for shoreline an d intake structure protection from storm wave action. The demography of the surrounding area has been updated to reflect both present population and the most recent proj ections of future growth. Dose estimates for both routine and accidental releases have been made using the most recent five-year data base available from the meteorological tower and the updated demography. The thermal effects of the condenser cooling water plume on the ecological balance of offshore waters have been extensively studied and the studies documented in annual reports. Using these st udies as a baseline, and with the most recent hydrodynamic and biological models, the combined environmental ef fects of all three Millstone units have been projected.

The details of this completed work are described in Chapter 2. Many of the studies, however, are ongoing and continuing past the st artup of Millstone 3. For exam ple, post-startup verification work was done to compare the hydrodynamic model pr ojections of the thre e units cooling water plume to the plume as it actually occurs in the offshore waters.

Site-related engineering work in geology a nd seismology was performed by SWEC and their subcontractors. Information and reports gene rated by SWEC were reviewed by NUSCO for general information and content, as well as for comparison with work previously performed at the site.13.1.0.0(1)(b)Design of Plant and Ancillary Systems MPS3 UFSAR13.1-3Rev. 30Westinghouse designed the NSSS. SWEC incorporated this design into the overall plant design and has provided detailed design of the balance of plant systems and all ancillary systems required for their operation.13.1.0.0(1)(c)Review and Appr oval of Plant Features SWEC provided review and approval of plant design features of Millstone 3 in accordance with its engineering procedures. This review was subject to NUSCO's subsequent selective review and approval based upon NUSCO's experience in the design and support of operations for Millstone 1 and 2 and support of operations for the CY plant. NUSCO's review and approval included coordinated review and concurren ce by appropriate personnel of NNECO.13.1.0.0(1)(d)Site Layout for Environmental Effects and Security ProvisionsVarious figures in Chapter 2 show the locati on of the meteorological tower, environmental dosimetry stations, and the pattern of the condenser cooling water plume.The detail description of management responsibi lities and control philosophies are included in the security plan. The implementation schedule for major milestone events for establishing Millstone 3 security was as follows:October 18, 1985-Rev. 0 of Security Plan for Millstone 3 became effective November 9, 1985-Security Plan imp lemented (prior to fuel load)13.1.0.0(1)(e)Development of Safety Analysis Report Preparation of the Millstone 3 FSAR was coordinated by NUSCO's Nuclear Licensing Group with support from NUSCO, NNECO, SWEC, and Westinghouse, and was s ubmitted to the NRC in support of the November 1985 fuel load date.13.1.0.0(1)(f)Review and Approval of Ma terial and Compone nt Specifications SWEC provided review and approva l of material and component sp ecifications in accordance with its engineering procedures. This review was subject to NUSCO's subsequent review and approval selectively base d upon NUSCO's experience in the design and support of operations for Millstone 1 and 2 and support of operations for the CY plant. NUSCO's review and approval included coordinated review and concur rence by appropriate personnel of NNECO.13.1.0.0(1)(g)Procurement of Materials and Equipment NUSCO procured the NSSS and the turbine genera tor for the Millstone 3 plant. SWEC procured the balance-of-plant materials, components, and systems. NUSCO exercised its right of approval of bid lists and contract aw ards for SWEC procured e quipment on a selective basis.13.1.0.0(1)(h)Management and Review of Construction Activities MPS3 UFSAR13.1-4Rev. 30SWEC was responsible for construction and management of construction forces for the Millstone 3 plant. NUSCO was responsible for supervis ion of the constructi on portion of the SWEC contract. To this end, NUSCO maintained from the start of site preparation an on site staff of experienced construction personnel under the direction of the on site NUSCO Superintendent--New Site Constr uction. Provisions for control of construction quality assurance aspects are in accordance with Chapter 17.13.1.0.0(2)Preoperati onal Activities13.1.0.0(2)(a)Human Engineerin g Design Objectives in Control Room Layout SWEC, under the direction of NUSCO and NNE CO, developed human engineering design objectives that would enhance operator effectiveness dur ing normal and abnormal plant operations.

The design phase review of the proposed control room layout was an iterative process involving SWEC, NUSCO, and NNECO. During the review process the original operational design objectives were continually validated to ensure an eff ective control room work space. NUSCO and NNECO remained continually involved in the design review of the control room by review of the design documents, utilizing mock-ups, and c onsiderable operating experience from CY and Millstone 1 and 2.13.1.0.0(2)(b)Staff Recruiting and Training ProgramsThe staff recruiting program is designed to maintain adequate staffing. The training program is in accordance with Section 13.2.13.1.0.0(2)(c)Initial Testing The development of plans for init ial testing were as outlined in Chapter 14, Initial Test Program.13.1.0.0(2)(d)Plant Maintenance Programs The development of the plant maintenance program incl uded the initial staf f buildup. In addition, prior to initial plant testing the generic mechanical/electrical test proce dures were completed and the specific equipment and pl anned maintenance procedures development was initiated.13.1.0.0(2)(e)Emergency PlanA full-scale emergency preparedness exercise was performed prior to initial start-up.13.1.0.0(3)Technical Support for OperationsThe organization providing techni cal support for operations is de scribed in Section 1.0 of the QAPD Topical Report.

MPS3 UFSAR13.1-5Rev. 30 13.1.1.2 Organizational ArrangementThe organizational arrangement is as describe d in Section 1.0 of the QAPD Topical Report (Reference 13.1-1).

13.1.2 OPERATING ORGANIZATION 13.1.2.1 Unit OrganizationThe unit organizations are as shown in Reference 13.1-1.

13.1.2.2 Assumption of ResponsibilityIn the event of unexpected contingencies of a temporary nature, the line of succession of authority and responsibility for overall station operation will be delegated in writing in accordance with Section 6.1, Responsibility, of the Technical Specifications.

13.1.2.3 Operating Shift CrewsThe minimum shift crew composit ion and license requirements during all modes of operation are contained in Section 6.2 of the Technical Specifications.

13.1.3 QUALIFICATIONS OF NUCLEAR PLANT PERSONNEL 13.1.3.1 Qualification Requirements 13.1.3.1.1 Education and experience re quirements are established by Section 6.3 of the Technical Specifications.

13.

1.4 REFERENCES

13.1.5 Quality Assurance Program Description Topical Report.

MPS3 UFSAR13.2-1Rev. 30 13.2 TRAINING PROGRAMS Formal training programs have b een established to train and qualify the personnel who operate and maintain the Millstone nuclear units. These programs are structured to fulfill the requirements of 10 CFR 55 and 10 CFR 50.120 using training crit eria set forth in ACAD 02-001 (Reference 13.2-1). Descriptions of the training program pro cesses exist in a set of training department documents. The programs are based on a systems appr oach to training and are accredited by the National Academy for Nuclear Training. Initial accreditation of these programs was awarded on August 21, 1986, for operator tr aining and on December 15, 1987, fo r maintenance and technical training. These programs are implemented for the following categories of nuclear power plant personnel:*Non-licensed Operator*Reactor Operator*Senior Reactor Operator*Shift Manager*Continuing (Requalification) Tr aining for Licensed Personnel*Shift Technical Advisor*Instrument and Control Technician *Electrical Maintenance Personnel *Mechanical Maintenance Personnel *Chemistry Technician*Radiological Protection Technician*Engineering Support Personnel 13.

2.1 REFERENCES

13.2-1ACAD 02-001, National Academy for Nuclear Training, "The Objectives and Criteria for Accreditation of Training in the Nuclear Power Industry."

MPS3 UFSAR13.3-1Rev. 30 13.3 EMERGENCY PLANNINGThe staff-approved Millstone Nuclear Power Station Emerge ncy Plan (Reference 13.3-1) addresses the criteria set forth in NUREG-0654, FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emer gency Response Plans and Prepar edness in Support of Nuclear Power Plants, Revision 1, November 1980 and NUREG-0737, Supplement 1. As such, the Emergency Plan provides for an acceptable state of emergency preparedness and meets the requirements of 10 CFR Part 50 and Appendix E thereto.

13.

3.1 REFERENCES

13.3-1J. F. Opeka letter to U.S. Nuclear Re gulatory Commission Document Control Desk, transmitting Revision 6 to the Millstone Nuclear Power Station, Unit Nos. 1, 2, and 3, Emergency Plan dated November 9, 1991, and subsequent revisions thereto submitted on an annual basis.

MPS3 UFSAR13.4-1Rev. 30 13.4 REVIEW AND AUDIT A program describing the review a nd audit of activities important to and affecting station safety during the operational phase has been established and complies with Regulatory Guide 1.33, Rev.

2 "Quality Assurance Program Requirements (Ope ration)." The program provides a system to ensure that these activities are performed in accordance with company policy, rules, and approved procedures.

13.4.1 ONSITE REVIEW Onsite review is conducted by committee(s) as described in the Quality Assurance Program Description (QAPD) Topical Report.

13.4.2 INDEPENDENT REVIEW Independent review of activities affecting the unit's safety is performed by the Management Safety Review Committee, as described in the QAPD Topical Report.

13.4.3 AUDIT PROGRAM The audit program for activities af fecting safety-related systems, structures, or components is as described in the QAPD Topical Report.

13.4.4 INDEPENDENT SAFETY ENGINEERING GROUP FUNCTION (DELETED) 13.4.5 OTHER REVIEW GROUPSOther review groups evaluate, on a periodic basis, the effectiveness of the units. These groups are:

independent consultants, task forces, nuclear industry management a ssessments, insurance inspections, INPO Evaluation and Assistance Division, etc.

MPS3 UFSAR13.5-1Rev. 30 13.5 PLANT PROCEDURESAdministrative procedures are written on a department (or common department), unit, and station (or common station) level. Technical Procedures are written on a unit and department (or common department) level. These procedures are requi red for controlling the specifics of station operations, including specifications; maintenance and modification; peri odic test, inspection, calibration, and special processes; and plant and equipment operation.

13.5.1 ADMINISTRATIVE PROCEDURES 13.5.1.1 Conformance with Regulatory Guide 1.33Regulatory Guide 1.33, Rev. 2, issued February 1978, Quality Assurance Program Requirements, is used as guidance for the preparation of administrative and station procedures.

13.5.1.2 Preparation of ProceduresPreparation, review and approval of procedures is as described in the Quality Assurance Program Description Topical Report.

13.5.1.3 Procedures Administrative Procedures include Department, Unit, and Station Procedures that cover a wide range of topics. Major areas are described as follows.Standing Orders to Operating Personnel Administrative procedures define the authorities and responsibili ties of operating personnel. The procedures specify the number of personnel with reactor operator and senior reactor operator licenses required to be on site or at the contro ls in all plant conditions. (Figure 13.5-1 shows the area of the control room which has been designate d "at the controls.") Th ese procedures contain the necessary directives to implement Sec tions i, j, k, l, and m of 10 CFR 50.54. The administrative procedures direct the proper maintenance, review, and disposition of operating records, establish requirements for shift turnover, and establish the authority and responsibilities of the person in charge of the control room to limit access. Procedures also direct the assignment of shift personnel to duty stations , establish limits fo r scheduled working hour s, provide methods of timely and concise feedback of operating experience to applicable plant staff, and describe methods used to verify operational activities are performed correctly. Procedures also provide for shift turnover such that all necessary information is properly transmitted to the oncoming shifts.

Crane Operations Personnel involved with crane ope rations over the fuel pool are qualified and conduct crane operations in accordance with ANSI B30.2-1976 (C hapter 2-3), Overhead and Gantry Cranes.

MPS3 UFSAR13.5-2Rev. 30Special Orders of a Transien t or Self-Cancelling Character Night orders can be issued when appropriate to provide guidance to operating shifts. When used, night orders are of a temporary nature. When appropriate, night orders are incorporated into either a special procedure or an administrative procedure if the need becomes permanent.

Equipment Control Procedures Instructions are written to sp ecify proper methods of obtaining clearances on plant equipment for maintenance or construction and to specify procedures for control of jumper, lifted lead, and bypass control. The clearance proced ure assigns responsibility for clearance issue to the shift manager. A licensed operator, after ensuring he or she is aware of the effect of the activity on the system, is required to authori ze all maintenance, tests, and surveillances performed on plant systems. Upon completion of the it em, the document is returned to the operator for acceptance or for the purpose of returning the system to servic

e. The administrative procedures which control these evolutions provide the re quired explicit notification of operational personnel whenever a safety related system is removed from and retu rned to service. The clearance procedure also contains certain restrictions on the issuance of a clearance. The work control procedures for control of jumper, lifted lead, a nd bypass control allow temporary alterations to critical structures, systems, or components to facilitate tests, maintenance, or ope rations. They specify administrative procedures to be foll owed in performing such alterations.

Control of Maintenance and ModificationsAdministrative procedures implement the review and approval requirements for maintenance and modifications. These procedures include the cont rol of plant modifications and maintenance on safety-related equipment. These procedures establish a framework of special process and maintenance procedures.Master Surveillance Testing Schedule An administrative work control procedure establis hes a master test control list, implements the surveillance test program, and assigns responsibi lity for review and approval of surveillance procedures in accordance with Technical Specifications. Writ ten surveillance procedures are controlled as Department or Common Department procedures.

Procedures for Logbook Usage and Control An administrative department procedure es tablishes the requireme nts for logbook usage and control.Maintenance and Testing of Safety-Related SystemsThe Work Control Process is used for administra tively controlling maintenance and testing of safety-related systems so that prior to the removal of a safety-related system from service, the credited redundant system is verified operable. Fo r equipment that requires specific surveillance MPS3 UFSAR13.5-3Rev. 30in accordance with Technical Specifications, surveillance testing is verified to be up to date or the successful surveillance testing of the credited redundant system is completed prior to removing the system from service.These procedures are reviewed and approved, if necessary, to ensure operability of safety systems prior to taking credit for the system(s) to satisfy Technical Spec ification requirements.

Independent position verification of safety-related components/sy stems (valves, breakers, and control switches) with no indication in the cont rol room are performed prior to the return-to-service of the component/system.

Special Procedures Special procedures are prepared as necessary to support infrequent ly performed activities which are not to be included in the pe rmanent list of procedures. A speci al procedure can be written for any type of procedure (i.e., maintenance, operating, testing). Th e format of a special procedure is the same as the applicable type of administrati ve or technical procedure. All requirements for review, approval, revisions, and changes are the same as for permanent procedures.

13.5.2 OPERATING AND MAINTENANCE PROCEDURES Operating and maintenance procedur es are divided into several ca tegories which are described in the following subsections. The list of these pro cedures is contained in the Master Document Index.Operating and maintenance procedures preparat ion is the responsibility of the appropriate department head. When a procedure is written, the applicable department Head/Manager is responsible to forward the procedure for review and approval in accordance with Technical Specifications.

Plant operations are performed in accordance with written and approved Station and Department procedures.

13.5.2.1 Operations Department Procedures 13.5.2.1.1 General Operating ProceduresThese procedures cover major plant evolutions. The list of these procedures is controlled by NDM 4, "Controlled Document Distribution," and is c ontained in the Electron ic Master Document Index. Step-by-step instructions are provided for the function or task with the appropriate cross reference to system operating procedures for de tails of specific system operation. Appropriate precautions and limitations are included.

MPS3 UFSAR13.5-4Rev. 30 13.5.2.1.2 System Operating Procedures These procedures provide step-by-step deta ils for system operations with appropriate prerequisites, precautions, and limitations. Each procedure covers the expected modes of operation of the system as well as startup, s hutdown, filling and venti ng, and standby operation as applicable. The list of thes e procedures is controlled by NDM 4, "Controlled Document Distribution," and is contained in th e Electronic Master Document Index.

13.5.2.1.3 Annunciation Response Procedures These procedures provide step-by-step details for appropriate system operation in response to annunciators. Annunc iator alert plant personnel of a changing conditions which could lead to off normal system performance. The list of these procedures is controlled by NDM 4, "Controlled Document Distribution," and is contained in the Electr onic Master Document Index.

13.5.2.1.4 Abnormal Operating Procedures Abnormal Operating Procedures are prepared for abnormal operation of the unit. Abnormal operation is a condition that could degrade into an emergency or could violate Technical Specifications if proper action we re not taken. These procedures identify the symptoms of the abnormal condition, automatic actions that may occur, and the appropriate immediate and subsequent operator actions. The list of these procedures is controlled by NDM 4, "Controlled Document Distribution," and is contained in the Electr onic Master Document Index.

13.5.2.1.5 Emergency Operating ProceduresEmergency Operating Procedures are prepared for conditions which might possibly lead to injury of plant personnel or the public if the release of radioactivity in excess of established limits occurs. These procedures include symptoms of the emergency conditions, automatic actions that may or should occur, and immedi ate and subsequent operator acti ons. All immediate actions are required to be memorized by the operator since th e primary responsibility for detection of an emergency and initiation of corrective action rests upon the operator. Emergency operating procedures are prepared based upon Revision 1B to the Westinghouse Owners Group Emergency Guidelines, and subsequent revision thereto, as implemented pending approval by the NRC. The list of these procedures is controlled by NDM 4, "C ontrolled Document Distribution," and is contained in the Electroni c Master Document Index.

13.5.2.1.6 Operations Surveillance Procedures These procedures provide step-by-step details for system or component surveillance. These procedures verify the operabil ity of the system or component in accordance with Technical Specifications. The list of these procedures is controlled by NDM 4, "Controlled Document Distribution," and is contained in th e Electronic Master Document Index.

MPS3 UFSAR13.5-5Rev. 30 13.5.2.2 Department ProceduresProcedures are written by the chemistry, radi ation protection, instrume ntation and controls, condition based maintenance, security, generation test, maintenance services, material control, nuclear document services, co mputer services, engineeri ng and any other group. These procedures control the specific activities of these department s in support of unit or station operation (may be common or unit specific). Station calibration proce dures written by the Maintenance or Instrument Action and Control de partments are also Common or Unit specific procedures.

13.5.2.2.1 Radiation Protection Procedures Radiation protection procedures suppor t Section 12.5 and 10 CFR 20 requirements.

13.5.2.2.2 Emergency Preparedness ProceduresEmergency preparedness procedures support and implement the Emergency Plan.

13.5.2.2.3 Instrumentation and Control Procedures Instrumentation and Control Procedures are prep ared for the performance of periodic calibration, testing, and channel checking of safety-related pl ant instrumentation and all instruments used to satisfy technical specifi cation requirements. These procedures ensure measurement accuracies adequate to maintain plant safety parameters within operational and safety limits. In addition, instrumentation and control procedures outline the periodic calibration and accuracy requirements of test equipment necessary to support the cal ibration of safety related instrumentation.

13.5.2.2.4 Condition Based Maintenance Procedures Condition Based Maintenance Procedures are prepar ed to monitor the condi tion of safety related and balance of plant equipment.

13.5.2.2.5 Chemistry ProceduresChemistry procedures are prepared covering the routine analysis and sampling methods to ensure compliance with plant chemistry and discharge limits.

13.5.2.2.6 Radioactive Waste System Procedures Procedures for operation of radwaste systems are included in system operating procedures.

13.5.2.2.7 Plant Security Instructions This topic is discussed in Section 13.6.

MPS3 UFSAR13.5-6Rev. 30 13.5.2.2.8 Material Control Procedures This topic is covered by administr ative procedures in Section 13.5.1.3.

13.5.2.2.9 Maintenance Procedures Maintenance procedures are prepared to cover safety-related work which requires a specific technique or sequence not normally part of an individual's routine skill.

The procedures support the requirements a nd programs of Section 13.5.1.3 which covers administrative control of maintenance.

13.5.2.2.10 Fire Protection Procedures The Fire Protection Program is described in Section 9.5.1. The li st of these procedures is controlled by NDM 4, "Controlle d Document Distribution," and is contained in the Electronic Master Document Index.13.5.2.2.11 Special Procedures This topic is covered by administrative pro cedures (refer to FSAR Section 13.5.1.3, Special Procedures).

MPS3 UFSAR13.6-1Rev. 30Withheld under 10 CFR 2.390 (d)(1) 13.6 PHYSICAL SECURITY PLANS

MPS-3 FSARFIGURE 13.1 - 1 DELETED BY PKG FSC 01-MP3-013 FIGURE 13.1-1 WAS REMOVED BY FSARCR 01-MP3-013 Rev. 20.3 MPS-3 FSARFIGURE 13.5-1 CONTROL ROOM AREARev. 20.1