ML14339A435

Updated Final Safety Analysis Report, Revision 21, Section 13, Conduct of Operations

ML14339A435
Person / Time
Site:	Beaver Valley
Issue date:	11/24/2014
From:	FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML14339A419	List: L-14-360, Firstenergy Nuclear Operation Company, Quality Assurance Program Manual, Revision 19 ML14339A408 ML14339A410 ML14339A411 ML14339A412 ML14339A413 ML14339A414 ML14339A415 ML14339A416 ML14339A417 ML14339A418 ML14339A420 ML14339A429 ML14339A430 ML14339A431 ML14339A433 ML14339A434 ML14339A435 ML14339A437 ML14339A438 ML14339A439 ML14339A440 ML14339A451 ML14339A452 ML14339A453 ML14339A454
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BVPS-2 UFSAR Rev. 16 13-i CHAPTER 13 TABLE OF CONTENTS Section Title Page 13 CONDUCT OF OPERATIONS...........................13.1-1 13.1 ORGANIZATIONAL STRUCTURE OF FIRSTENERGY.........13.1-1 NUCLEAR OPERATING COMPANY (FENOC) AT BEAVER VALLEY POWER STATION (BVPS)

13.1.1 Offsite Organization............................13.1-1 13.1.2 Onsite Organization.............................13.1-2

13.2 TRAINING........................................13.2-1 13.2.1 Licensed Operator Replacement and Requalification Training Program................................13.2-1 13.2.2 Training Program for Non-Licensed Plant Staff...13.2-2 13.2.3 Applicable U.S. Nuclear Regulatory Commission Documents.......................................13.2-6 13.3 EMERGENCY PLANNING..............................13.3-1

13.4 REVIEW AND AUDIT................................13.4-1

13.4.1 Onsite Review...................................13.4-1 13.4.2 Independent Review..............................13.4-1 13.4.3 Audit Program...................................13.4-1 13.4.4 Independent Safety Evaluation...................13.4-1 13.5 PLANT PROCEDURES

13.5.1 Administrative Procedures.......................13.5-1 13.5.2 Operating and Maintenance Procedures............13.5-3

13.6 SECURITY........................................13.6-1

BVPS-2 UFSAR Rev. 20 13-ii LIST OF TABLES Table Number Title 13.1-1 Deleted

13.1-2 Cross-reference to Positions Referenced in Technical Specifications

13.5-1 Scope of the BVPS-2 Station Administrative Procedures

13.5-2 Deleted

13.5-3 Scope of the BVPS-2 Operating Manual

13.5-4 Scope of the BVPS Radiation Protection Procedures

13.5-5 Scope of the BVPS Chemistry Manual

BVPS-2 UFSAR Rev. 20 13-iii LIST OF FIGURES

Figure Number Title 13.1-1 Deleted

13.1-2 Onsite Organizational Structure

BVPS-2 UFSAR Rev. 20 13.1-1 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC) AT BEAVER VALLEY POWER STATION (BVPS)

In December 1999, FENOC assumed responsibility for the operation of BVPS from the previous owner and operator. As an operator of multiple

nuclear sites, some functions previously reporting onsite were

consolidated from the sites and are now provided by FENOC organizations that formally report offsite. Individuals located onsite that represent such organizations also report to onsite

management regarding direction for the service they provide.

This section describes important onsite and offsite reporting positions. Facility staff qualification requirements and minimum shift crew compositions are described in the respective unit's

technical specifications.

13.1.1 Offsite Organization

The description of the FENOC corporate organization and the lines of authority, responsibility, and communication between the corporate organization and the site organization are defined and established in the FENOC Quality Assurance Program Manual (QAPM), which is incorporated by reference into this document.

BVPS-2 UFSAR Rev. 20 13.1-2 13.1.2 Onsite Organization

Figure 13.1-2 describes the onsite BVPS organization. Responsibilities associated with key positions depicted on the figure

are described as follows.

The Site Vice President, Beaver Valley is the corporate officer responsible for overall plant nuclear safety. The vice president is responsible for the administration of activities at BVPS and has managerial control over the engineering, construction, operation, maintenance, and modification of Beaver Valley.

The Director Site Operations is responsible for the safe and efficient operation of the plants in accordance with the guidelines and requirements of the operating licenses and station manuals. The positions described below report directly to the

Director Site Operations.

The Manager, Site Operations assures the safe, reliable, and efficient operation of the plant within the constraints of

applicable regulatory requirements and the operating

license.

The Superintendent, Unit Operations is the line person responsible for managing the operation of the respective BVPS unit. This position ensures that conditions adverse to safe, reliable operation of the

unit are identified, evaluated, and effective

corrective action is completed.

The Shift Managers are responsible for the proper

startup, operation, and shutdown of station equipment associated with the respective unit.

In the absence of direct line supervision, the shift manager is authorized to act as the

ultimate authority with regard to nuclear safety.

BVPS-2 UFSAR Rev. 18 13.1-3 The Unit Supervisors are responsible for the proper startup, operation, and shutdown of equipment, supervise the preparation of various

logs and reports, direct all physical operations work, and provide on-the job training of

operating personnel.

The Manager, Site Outage Management is responsible for the coordination, schedule development and execution of all

maintenance, planned and forced outages at Beaver Valley.

The Manager, Site Work Management is responsible for the scheduling and coordination of station on-line work

activities.

The Manager, Site Chemistry is responsible for administration, implementation and maintenance of the plant environmental program ensuring compliance with state and

federal environmental protection requirements, and the

radiological environmental monitoring program. This includes the non-radioactive environmental monitoring program as well as control and disposal of non-radioactive hazardous waste. Also is responsible for all Station chemistry programs and procedures, and maintaining a

qualified radiochemical program.

The Manager, Site Radiation Protection is responsible for providing radiological control coverage, implementation of ALARA analysis, providing direction and support for all

radioactive waste shipping, radioactive waste management, and maintaining the dosimetry and respiratory protection

program, maintenance of respiratory protection equipment and radiation protection technical support. This manager also serves as Radiation Protection Manager specified in NRC

Regulatory Guide 8.8.

The Plant Operations Review Committee (PORC) provides recommendations to the Director Site Operations on matters

relating to nuclear safety. Section 13.4.1 describes onsite

review functions.

The Manager, FirstEnergy Supply Chain , Beaver Valley is responsible for the procurement of goods and services, inventory management, and warehouse operations, including the receipt, storage and issuance of materials, parts, and

components to support plant operations and maintenance.

The Director, Nuclear Maintenance has overall responsibility for the functions described below. Additionally, the Director, Nuclear Maintenance provides management and oversight of the

principle contractor providing services to the station.

The Manager, Site Maintenance manages the activities of the line maintenance organization including maintenance and

calibration of plant mechanical and electrical equipment, instrumentation, controls, and computer equipment.

BVPS-2 UFSAR Rev. 16 13.1-4 The Superintendent, Maintenance Services is responsible for janitorial services, outbuilding maintenance, painting (structures/equip), scaffolding, and yards and grounds

maintenance.

The Superintendent, Nuclear Work Planning is responsible for maintenance department support functions including detailed task planning for station activities, whether accomplished

with the plant on-line or off-line, development and revision of maintenance procedures and programs, including the

predictive monitoring of station equipment.

The Director, Site Performance Improvement has overall responsibility for the following functions.

The Manager, Site Training is responsible for providing direction, control, and overall supervision of all

accredited training of personnel required by regulations.

The Manager, Emergency Response is responsible for maintaining the BVPS Emergency Plan in accordance with all

applicable state and federal regulations. This shall include maintaining an effective onsite emergency response

organization and maintaining effective relationships with

offsite organizations that support the BVPS emergency plan.

The Manager, Site Regulatory Compliance is responsible for performance improvement and regulatory compliance activities at BVPS. The manager coordinates NRC license issues, coordinates NRC correspondence, assists in compliance with

license conditions, coordinates the reportability evaluation process, and manages the corrective action program and

operating experience program.

The Manager, Site Projects is responsible for the direction, control, and overall supervision of projects implemented at

the station.

The Director, Site Engineering is responsible for the following engineering functions.

The Manager, Design Engineering is responsible for the design basis of the station. This includes plant modifications, plant design support, design basis analysis

and design basis assurance.

The Manager, Plant Engineering maintains accountability and ownership of the short and long-term health of plant systems and components. Plant engineers specialize in particular systems and serve as the focal point for knowledge

concerning system and component performance. Plant engineering monitors system and component health through

trending and industry experience, recommends and sponsors

improvements for long-term equipment reliability, and provides technical support for operations and maintenance.

Additionally, the Manager, Plant Engineering provides reactor engineering support for the operation and monitoring of the Beaver Valley reactor cores.

BVPS-2 UFSAR Rev. 16 13.1-5 The Manager, Technical Services Engineering provides technical support for emergent plant issues and supports the

operations and maintenance organizations with engineering

changes, equivalent changes, vendor technical information

updates, temporary modifications, minor modifications, and

assistance for technical issues and condition reports. This manager is also responsible for monitoring, testing, and

technical evaluations, as required by station engineering

programs such as inservice inspection, inservice testing and

motor-operated valve testing. Technical Services Engineering provides oversight and serves as the interface

with contracted engineering/consulting service companies in

association with major plant modifications.

The Engineering Assessment Board reviews selected engineering products for attributes such as quality, achievement of purpose, compliance with design basis and

commitments, scope, constructability, inspection & testing requirements, and client satisfaction. These reviews are a supplement to normal management reviews and approvals of

engineering products.

The Manager, Site Protection is responsible for the implementation of the Physical Security Plan and has overall responsibility for directing and maintaining an effective Site

Protection organization.

BVPS-2 UFSAR Tables for Section 13.1

BVPS-2 UFSAR Rev. 17 1 of 1 TABLE 13.1-2 CROSS-REFERENCE TO POSITIONS REFERENCED IN TECHNICAL SPECIFICATIONS (Refer to Technical Specification 5.2.1.a)

Generic Position Title (Technical Specification)

Plant-Specific Title Corporate Officer Site Vice President, Beaver Valley Plant Manager Director Site Operations Operations Manager Manager, Site Operations Assistant Operations Manager Superintendent, Unit Operations Radiation Protection Manager Manager, Radiation Protection

Note: The correlation between the positions described in Section 5.2.1 of the Technical Specifications and the plant-specific titles are documented in Table 13.1-2 above.

I I I I Director Site Operations Superintendent Unit 1 Operations Shift Manager Unit Supervisor Manager Site Outage Management Manager Site Work Management Manager Site Chemistry Manager Site Radiation Protection Plant Operations Review Committee L----Manager FE Supply Chain -BV Site Vice President Beaver Valley Rev. 16 Director Nuclear Maintenance Manager Site Maintenance Superintendent Maintenance Services Superintendent Nuclear Work Planning Director Site Performance Improvement Manager Site Training Manager Emergency Response Manager Site Regulatory Compliance Manager Site Projects I I I I I t" Director Site Engineering Manager Design Engineering Manager Plant Engineering Manager Technical Services Eng. j Manager u._ ________ M_a_n_ag __ er ________ _, 1 Fleet Oversight Functional Reporting Line Communication Line Figure 13.1-2 Onsite Organizational Structure BEAVER VALLEY POWER STATION-UNIT 2 UPDATED FINAL SAFETY ANALYSIS REPORT BVPS-2 UFSAR Rev. 14 13.2-1 13.2 TRAINING The Beaver Valley Power Station training program has been developed for use during the operational phase of Unit 1/2 (BVPS-1/2). This program identifies requirements and provides training for employees in the operations, radiological control, chemistry, testing, maintenance, quality control, and administrative organizations. The program also identifies administrative requirements to ensure the proper and uniform documentation of training.

Training at BVPS satisfies NRC regulations including 10 CFR 55, "Operators' Licenses" and 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The program also conforms to Regulatory Guide 1.8, Revision l-R, May 1977, Personnel Selection and Training (this is a reissuance of Revision 1, September 1975 without

changes to its content).

Training is conducted by a qualified staff of instructors who meet or exceed training program minimum requirements.

Evaluation of the effectiveness of the training program is measured utilizing one or more of the following methods:

1. Written and/or oral examinations.

2. Demonstration of proficiency during actual or simulated operations.

13.2.1 Licensed Operator Replacement and Requalification Training Program The Operator Replacement and Requalification Training Program of Record was submitted to the NRC by letter dated October 30, 1985 with

supplemental information provided to the NRC in letters dated June 30 and September 30, 1986. The training program detailed in training administrative procedures was found acceptable to the NRC with clarifications noted in an NRC letter dated December 2, 1986.

A response to NRC Generic Letter 87-07 was submitted by a letter dated September 11, 1989, which certified that the BVPS-1 and BVPS-2 licensed operator initial and requalification training programs were accredited and based on a systems approach to training. Changes to the approved operator training programs, as clarified by the NRC in a letter dated November 12, 1997, are processed under the provisions of GL 87-07. Therefore, prior approval from the NRC is no longer

required to change these programs.

BVPS-2 UFSAR Rev. 14 13.2-2 13.2.1.1 Licensed Operator Training Program The Licensed Operator Training Program is designed to provide operating personnel with the knowledge and skills required to operate BVPS in a safe and efficient manner. Personnel whose duties require them to possess a Reactor Operator or Senior Reactor Operator license (as specified in 10 CFR 55) will complete the Licensed Operator

Training Program.

13.2.1.2 Licensed Operator Retraining

The Licensed Operator Retraining Program ensures that licensed personnel remain competent to operate either BVPS-1 or BVPS-2 in a

safe, reliable, and efficient manner. This program is administered to all personnel whose duties require them to maintain a Reactor Operator or Senior Reactor Operator license (as specified in 10 CFR 55).

13.2.2 Training Programs for Non-Licensed Plant Staff

This section contains a description of the training and retraining programs for selected non-licensed members of the BVPS-1/2 staff. The training is derived from a systems approach to training as required by 10 CFR 50.120 and includes:

1. General Employee Training

2. Engineering Support Personnel Training 3. Maintenance Training (mechanical, electrical, and instrument and control) 4. Fire Protection Training

5. Shift Technical Advisor Training 6. Mitigating Core Damage Training

7. Radiological Protection Technician Training 8. Chemistry Technician Training

13.2.2.1 General Employee Training General Employee training is provided to all employees in Plant Access Training and Radiation Worker Training to meet the intent of 10 CFR 19 Section 19.12. Plant Access Training provides individuals with an indoctrination in the general requirements necessary to gain access to

the plant. This program enhances employee effectiveness and safety by covering plant organization, security, safety regulations, radiation fundamentals, quality assurance, fire protection, and the emergency

plan. All individuals who require unescorted access to the protected area of Beaver Valley Power Station must complete Plant Access Training.

In addition to Plant Access Training, Radiation Worker Training is provided for employees who will be exposed to radioactive material(s).

This course covers basic radiation theory, exposure controls, safe work practices, workers' rights and responsibilities.

General Employee Refresher Training is provided on both Plant Access and Radiation Worker Training.

BVPS-2 UFSAR Rev. 14 13.2-3 13.2.2.2 Engineering Support Personnel Training Engineering Support Personnel are provided training as required to meet the intent of ANSI N18.1-1971 Section 5.3, "Training of Personnel Not Requiring AEC Licenses," as endorsed by Regulatory Guide 1.8. The engineering support personnel population is established by a management review of the functional responsibilities assigned to various job positions in comparison to the activities listed in the National Academy for Nuclear Training Guideline for Training and Qualification of Engineering Personnel.

BVPS-2 UFSAR Rev. 14 13.2-4 13.2.2.3 Maintenance Training Maintenance Training is provided for permanently assigned BVPS maintenance personnel and consists of five individual programs: Mechanical, Electrical, Instrument & Control, Relay Technician, and

Maintenance Supervisory Training. In addition, trained welders are

qualified by the Site Maintenance Department.

Initial training includes minimum job training requirements (MJTR)

training, plant specific training, and systems training.

The Continuing Training Program is designed to maintain proficiency in learned tasks and ensures that personnel are kept informed of plant and industry changes. Continuing training includes refresher and

current topics training.

Each program contains material specific to the job discipline. The programs are designed to provide entry-level or supervisory personnel

with the knowledge and skills necessary to perform their job duties.

13.2.2.4 Fire Brigade Training Program

Fire Brigade Training is conducted to train individuals with assigned

site fire brigade duties to respond safely and effectively to fire

emergencies.

This program provides information on fire fighting procedures, equipment operation, and safety requirements through initial classroom and practical training. Continuing training is required annually as

is participation in fire response drills.

More detail on Fire Protection Training is presented in Section 9.5.1.4.

BVPS-2 UFSAR Rev. 15 13.2-5 13.2.2.5 Shift Technical Advisor (STA) Training The STA program is designed to provide training that will enable personnel to provide effective analytical and technical assistance to operating personnel during normal and abnormal operating conditions.

13.2.2.5.1 STA Initial Training Personnel who are not licensed for the Beaver Valley Power Station

will complete the STA Training Program prior to assuming responsibility for the duties of the Shift Technical Advisor positions. The education of enrolled personnel will be reviewed and supplemental education or training will be performed on an as-needed basis in the following academic areas:

Reactor Theory Reactor Chemistry Nuclear Materials

Thermal Sciences Electrical Sciences Nuclear Instrumentation and Control

Nuclear Radiation Protection

The STA Training Program consists of instruction in the following

areas: Fundamentals Training Plant Systems Instruction Transient and Accident Assessment Management/Supervisory Training

Simulator Training On-Shift Training 13.2.2.5.2 STA Retraining The STA Retraining Program is designed to ensure that personnel remain competent to carry out the duties of the STA position. Retraining is completed on a two-year basis.

The STA Retraining Program consists of classroom and simulator training. The STA participates in selected modules of the Licensed Operator Retraining Program, as well as lectures to cover any differences between the units. Annual requalification examinations and completion of individual study guides are not required.

Individuals not actively performing the STA functions for a period of 30 days or longer are required to review appropriate facility and procedural changes that have occurred since their last assignments to

STA duties.

Simulator training is divided between Unit 1 and Unit 2 and scenarios

are designed to evaluate the STA's analytical and advisory skills.

BVPS-2 UFSAR Rev. 14 13.2-6 13.2.2.6 Mitigating Core Damage (MCD) Training The Mitigating Core Damage Training Program provides training on recognizing and responding to accidents in which the reactor core is

severely damaged.

Shift Technical Advisors and operations personnel will be provided training to meet the intent of NUREG-0737,Section II.B.4. Radiological Control Managers and Technicians, Chemistry personnel and I&C personnel will receive training commensurate with their responsibilities.

Continuing training on selected MCD topics is conducted periodically as a part of continuing training programs.

13.2.2.7 Radiation Technician Training Radiation Protection Technician personnel are provided training as required to meet the intent of ANSI-18.1-1971, Sections 4.5.2, "Technicians" and Section 5.3.4, "Training for Technicians and Repairmen" as endorsed by Regulatory Guide 1.8.

The Radiation Protection Technicians training program meets the National Academy of Nuclear Training "Guidelines for Training and Qualification of Radiological Protection Technicians." 13.2.2.8 Chemistry Training Chemistry personnel are provided training as required to meet the intent of ANSI-18.1-1971, Sections 4.5.2, "Technicians" and Section 5.3.4, "Training for Technicians and Repairmen" as endorsed by Regulatory Guide 1.8.

The Chemistry training program meets the National Academy of Nuclear Training "Guidelines for Training and Qualification of Chemistry Technicians."

13.2.3 Applicable U.S. Nuclear Regulatory Commission Documents

The BVPS training program will be conducted in accordance with applicable portions of 10 CFR 50; 10 CFR 55; and 10 CFR 19.

Additionally, the program will be conducted in accordance with the intent of the following guidance documents, including any alternative methods that may be specified in Section 1.8.

1. Regulatory Guide 1.8, "Personnel Selection and Training." 2. Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants."

3. Regulatory Guide 8.2, "Guide for Administrative Practices in Radiation Monitoring."

BVPS-2 UFSAR Rev. 14 13.3-1 13.3 EMERGENCY PLANNING The Beaver Valley Power Station Emergency Preparedness Program is an in-depth concept designed to protect both employees and property and

the health and safety of the general public surrounding Beaver Valley Power Station.

The BVPS Emergency Preparedness Plan provides guidance for coping with both onsite and offsite emergency situations. The Plan ranges in scope from relatively minor occurrences involving small releases of

radioactive material, up to and including a major nuclear incident having significant offsite radiological consequences.

The Emergency Preparedness Plan provides for a graded scale of response for distinct classifications of emergency conditions, actions within those classifications, and criteria for escalation to a more severe classification. The Plan interrelates with BVPS Operating Procedures, Security Procedures, the BVPS radiation protection procedures and the associated EPP Implementing Procedures. The overall preparedness concept is emphasized onsite in training as well as preparedness drills and exercises. The Plan is in compliance with the standards of 10 CFR 50 Appendix E and is responsive to the

individual acceptance criteria of NUREG-0654 to meet the intent of Item III.A.2 of NUREG-0737 and Item III.A.1.1 of NUREG-0660.

The Emergency Preparedness Program includes emergency measures out to a radius of at least 10 miles from BVPS. The 10-mile Emergency Planning Zone (EPZ) encompasses three states (Pennsylvania, Ohio and

West Virginia) and three counties (Beaver County, PA; Columbiana County, Ohio; and Hancock County, WVa). Each emergency response agency has an Emergency Operations Plan. These plans are coordinated closely with the BVPS Plan to ensure compatibility. Arrangements and procedures exist and training has been conducted for the treatment of contaminated injuries and significant over-exposures to radiation.

The Medical Center, Beaver, PA; and Presbyterian-University Hospital, Pittsburgh, PA; are included in these arrangements. Letters of Agreement with agencies providing support to BVPS during an emergency

are on file and reviewed annually to ensure currency.

BVPS has designated an Emergency Response Organization (ERO) which

encompasses both the operating and support elements of the nuclear organization. Provisions are in place for a timely, staged response consistent with the emergency classification. Personnel are trained

to provide in-depth response capability for required actions in an emergency situation. Upon activation, the ERO remains in effect until such time as conditions have been stabilized or normal operations are resumed. In support of handling any emergency operations at BVPS, an onsite Technical Support Center has been provided which meets the intent of Item III.A.1.2 of NUREG-0660. The Technical Support Center is separate from, but in close proximity to the Control Room, having the capability to display plant status of reactor operations in the event of an accident.

BVPS-2 UFSAR Rev. 18 13.4-1 13.4 REVIEW AND AUDIT

A review and audit program has been established to assure that

operations of BVPS-2 are performed in a safe manner consistent with license provisions, approved procedures, and company policy. The review program is the responsibility of the Plant Operations Review

Committee (PORC) and the Company Nuclear Review Board (CNRB). The audit program is the responsibility of the Manager, Nuclear Quality

Assessment. The functions of the review and audit program are

detailed as follows:

1. Review proposed plant changes, tests, experiments, and implementing procedures pursuant to the criteria established

in 10 CFR 50.59.

2. Verify that unusual events are promptly investigated and corrected.

3. Detect trends of conditions that may not be apparent to a day-to-day observer.

13.4.1 Onsite Review

The review functions of the on-site review organization, which is known as the Plant Operations Review Committee (PORC), are described in ANSI N18.7-1976, which is committed to as delineated in the FENOC Quality Assurance Program Manual (QAPM). The specific details related

to the activities of PORC are set forth in administrative procedures.

13.4.2 Independent Review

Company Nuclear Review Board (CNRB)

The description, responsibilities, and functions of the independent review organization, which is known as the Company Nuclear Review

Board (CNRB), are described in ANSI N18.7-1976, which is committed to as delineated in the FENOC Quality Assurance Program Manual (QAPM).

The specific details related to the activities of CNRB are set forth

in administrative procedures.

13.4.3 Audit Program

A description of the audit program for the operational phase of BVPS-2

is contained in the FENOC QAPM, referenced in Section 17.2.

13.4.4 Independent Safety Evaluation

The intended function of the Independent Safety Evaluation Group (ISEG) will be maintained by current FENOC programs and processes that provide oversight of plant operating characteristics, NRC issuances, Licensing Information Services, and other sources of plant design and operating experience information that may indicate areas for improvement to insure overall safe operation of the station. Included

BVPS-2 UFSAR Rev. 18 13.4-2 within the oversight process are reviews of plant activities including Maintenance, Modifications, and Operational problems. The ISEG functions are directly incorporated into engineering, operations, performance improvement, and oversight functions through administrative processes such as the Corrective Action and Operating Experience programs. Organizational entities responsible for engineering assessment, corrective action review, oversight and assessment are structured to provide the necessary experience and independence.

BVPS-2 UFSAR Rev. 15 13.5-1 13.5 PLANT PROCEDURES Various administrative and operating procedures have been established for the Beaver Valley Power Station (BVPS) operating organization to ensure that routine operating, off-normal, and emergency activities are conducted in a safe manner.

Detailed guidelines for the preparation of procedures have been developed for each type of required written procedure. These guidelines include the information required to be included in the procedures, the appropriate references for precautions and limitations, the review and approval sequence for the various types and safety categories of equipment and systems, and the method to

implement temporary and permanent changes to the procedures.

13.5.1 Administrative Procedures

The administrative procedures establish methods and controls which aid in the safe and efficient operation of BVPS. These procedures are

intended to direct the plant personnel in the performance of safety-related functions in accordance with regulatory requirements and the BVPS-2 Technical Specifications. Table 13.5-1 lists the subjects included in the corporate and station administrative procedures. Administrative procedures were prepared in accordance with the intent of Regulatory Guide 1.33, Revision 2, "Quality Assurance Program

Requirements (Operations)" for BVPS-1.

The administrative procedures conform to the BVPS-2 Final Safety Analysis Report and Technical Specifications, the FENOC Quality Assurance Program Manual , and the intent of the following ANSI Standards and USNRC documents.

1. NUREG-0694 Item I.C.2 for procedures for shift relief and turnover for shift operating personnel

2. NUREG-0694 Item I.C.4 for control room access

3. NUREG-0737 Item I.C.5 for procedures for feedback of operating information

4. NUREG-0737 Item I.C.6 for procedures for verifying the correct performance of operating activities

BVPS-2 UFSAR Rev. 15 13.5-2 6. ANSI B30.2-1976, Chapters 2 and 3 for qualification and conduct of crane operators who operate cranes over fuel pools

7. NUREG-0694 Item I.A.1.2 for procedures covering shift supervisor administrative duties

8. NUREG-0694 Item I.C.3 for procedures covering shift supervisor responsibilities The administrative procedures provide a clear understanding of the operating philosophy and administrative policies. The procedures establish the rules and instructions pertaining to personnel conduct and control; on-call availability of professional and supervisor

personnel; the method of conducting operations; and the preparation, issue, revision, and retention of BVPS-2 documents.

The administrative procedures delineate the responsibilities and authorities of the BVPS staff. As a minimum, the procedures shall include requirements set forth in 10 CFR 50.54, paragraphs (i), (j),

(k), (l), (m), and the following:

1. Procedures include the reactor operator's authority and responsibility for shutting the reactor down after determining that the safety of the reactor is in jeopardy, or when operating parameters exceed any of the reactor protection circuit set points and automatic shutdown does not occur. Additionally, procedures include the reactor operator's responsibility to believe and respond conservatively to instrument indications unless they are proven incorrect.

2. Procedures include the senior reactor operator's authority and responsibility to determine the circumstances, analyze the cause, and determine that operations can proceed safely before the reactor is returned to power after a trip or an unscheduled or unexplained reduction in power. Additionally, procedures include the senior reactor operator's responsibility to be present at BVPS-2 and to provide direction for returning the reactor to power following a trip or an unscheduled or unexpected power reduction.

The administrative procedures require that all documents such as those described previously, including any revisions or changes thereto, are reviewed for adequacy by authorized personnel, approved for release by authorized personnel, distributed to personnel performing the

activity, and used by the personnel performing the activity.

BVPS-2 UFSAR Rev. 15 13.5-3 13.5.1.1 Preparation of Procedures BVPS has developed administrative procedures governing policy and

conduct of operations for BVPS.

13.5.1.2 Initial Test Program

The organizational system for control of the initial test program is

described in Section 14.2. Section 14.2.3 describes the method used to develop, review and approve individual test procedures. Section 14.2.4 describes the administrative control mechanisms governing

conduct of the test program. Section 14.2.5 describes the controls that govern the review, evaluation, and approval of test results.

13.5.2 Operating and Maintenance Procedures

Operating and maintenance procedures are established for the BVPS operating organization to ensure that routine operating, off-normal, and emergency activities are conducted in a safe manner. The administrative procedures define the mechanisms to be employed by the various groups in the preparation of that group's procedures.

Operating and maintenance procedures were prepared in accordance with

the intent of Regulatory Guide 1.33 Revision 2 and ANSI/ANS 3.2-1976.

BVPS-2 UFSAR Rev. 15 13.5-4 13.5.2.1 Control Room Operating Procedures

No change in station parameters that may affect the reactivity and power level of the core, and no change in valving or switchinq that may compromise the availability of engineered safeguards will be made without written procedures. Table 13.5-3 lists the subjects included

in the BVPS-2 Operating Manual which relate to normal, abnormal, and emergency operation of safety-related and nonsafety-related systems and equipment. The Operating Manual is composed of individual chapters

which contain detailed operating procedures. These procedures present clear and concise directions to BVPS management and operating personnel, thus ensuring system operations are conducted in accordance with manufacturers' instructions, applicable rules and regulations, and in a manner conducive to overall plant safety. The operating

procedures meet the intent of applicable Regulatory Guides including:

1. NUREG-0737 Item I.C.1

2. NUREG-0799

3. NUREG-0737 Item III.D.1.1

4. NUREG-0737 Item II.K.1.5

5. NUREG-0737 Item II.K.1.10

6. NUREG-0737 Item II.K.3.17 13.5.2.2 Radiation Protection Procedures

The BVPS radiation protection procedures establish the policy and

procedures to ensure that radiation exposure received by persons working in, or making visits to, BVPS is maintained as low as reasonably achievable. Table 13.5-4 lists the subjects included in

the radiation protection procedures.

13.5.2.3 Chemistry Procedures

The Chemistry organization establishes the policy and procedures to ensure that routine and special chemical and radiochemical tests and

analyses produce meaningful, reproducible results. Table 13.5-5 lists

the subjects included in the chemistry procedures.

13.5.2.4 Maintenance Procedures

Maintenance administrative procedures are established to minimize outages and assure the safe, efficient production of electrical power. The procedures outline standardized methods of implementation for maintenance work performed on safety-related systems and equipment

consistent with the quality assurance program.

BVPS-2 UFSAR Rev. 15 13.5-5 13.5.2.5 Engineering Procedures

Engineering Procedures were developed in accordance with the FENOC Quality Assurance Program. These procedures govern the design, review and approval, installation, and completion of modifications accomplished at BVPS-2. Administrative procedures describe the involvement of the onsite and independent review committees with respect to engineering changes, to assure that plant safety is not compromised.

13.5.2.6 Equipment Control Procedures

Procedures are provided for control of equipment in order to maintain reactor and personnel safety and to avoid unauthorized operation of equipment. These procedures require control measures such as locking or tagging to secure and identify equipment in a controlled status.

The procedures require independent verification, where appropriate, to

ensure that necessary measures have been implemented correctly.

13.5.2.7 Station Security Procedures

Procedures have been developed to control access to sensitive areas and equipment of the station. Security procedures provide for visitor control, fences and lighting, lock controls, traffic provisions, badge identification for personnel and visitors, screening of potential employees, and inspection and observation of areas and individuals. A security program and procedures have been provided in accordance with

ANSI N18.17, "Industrial Security For Nuclear Power Plants."

BVPS-2 UFSAR Tables for Section 13.5

BVPS-2 UFSAR Rev. 15 1 of 1 TABLE 13.5-1 SCOPE OF ADMINISTRATIVE PROCEDURES Administrative procedures address the following topics:

Administrative Controls/General instructions

Personnel Protection/General Safety Training/Qualifications

Reports/Reporting

Correspondence/Documents/Records Control Design/Modification Control

Assurance of Quality/Performance Programs

Procurement/Material Management

BVPS-2 UFSAR Rev. 0 1 of 4 TABLE 13.5-3 SCOPE OF THE BVPS-2 OPERATING MANUAL The Operating Manual includes but is not limited to, the following chapters which relate to normal, abnormal, and emergency operation of safety-related and nonsafety-related systems and equipment:

Chapter 1 Reactor Control and Protection 2 Reactor Excore Instrumentation 3 Incore Instrumentation System 4 Plant Process Control System 5A Plant Computer System 5B Annunciator System 5C ERFS/SPDS 5D Plant Safety Monitoring System 6

Reactor Coolant System 7 Chemical and Volume Control System 8 Boron Recovery and Primary Grade Water System 9

Reactor Plant Vents and Drains 10 Residual Heat Removal System 11 Safety Injection System 12 Containment Vacuum and Leakage Monitoring 13 Containment Depressurization System 14A Reactor Plant Sampling System 14B Turbine Plant Sample System 14C Post Accident Sampling System 15 Primary Component and Neutron Shield Tank Cooling Water Systems 16 Supplementary Leak Collection and Release System

BVPS-2 UFSAR Rev. 0 2 of 4 TABLE 13.5-3 (Cont)

Chapter 17 Liquid Waste Disposal System 18 Solid Waste Disposal System 19 Gaseous Waste Disposal System 20 Fuel Pool Cooling and Purification System 21 Main Steam System 22A Condensate System 22B Condensate Polishing System 23A Extraction Steam System 23B Heater Drains 24 Steam Generator Feedwater System 25 Steam Generator Blowdown System 26 Main Turbine and Condenser 27A Auxiliary Steam and Condensate System 27B Auxiliary Boiler System 28 Turbine Plant Component Cooling Water System 29 Chilled Water System 30 Service Water System 31 Circulating Water System 32 Water Treating System 33 Fire Protection System 34 Compressed Air System 35 Main Generator and Main Transformer 36 4 kV Station Service System 37 480 V Station Service System 38 120 V ac Distribution and Lighting System BVPS-2 UFSAR Rev. 0 3 of 4 TABLE 13.5-3 (Cont)

Chapter 39 125 V dc Distribution System 40 Station Communications 41A Building Services Hot Water Heating System 41C Domestic Water System 41D Building and Yard Drains 42 Sewage Treatment 43 Radiation Monitoring System 44A Area Ventilation Systems - Control Area 44B Area Ventilation System - Cooling System 44C Area Ventilation Systems - Containment 44D Area Ventilation Systems - Auxiliary Building 44F Area Ventilation Systems - Miscellaneous 44G Area Ventilation Systems - Condensate Polishing Building 45A Loose Parts Monitoring 45B Seismic Instrumentation System 45D Electric Heat Tracing System 45E Fault Recording System 46 Post DBA Hydrogen Control System 47 Containment 48 Conduct of Operations 49 Rx Engineering Procedures 50 Station Start-up 51 Station Shutdown 52 General Operating Instructions 53A Emergency Operating Procedures

BVPS-2 UFSAR Rev. 17 4 of 4 TABLE 13.5-3 (Cont)

Chapter 53B Emergency Operating Procedures - Executive Volume 53C Abnormal Operating Procedures 54 Station Logs 55A Periodic Checks - Operating Surveillance 56A (Deleted) 56B Fire Protection and Prevention 56C Alternate Safe Shutdown from Outside Control Room 59A South Office Shop Building 59B Primary Access Facility

BVPS-2 UFSAR Rev. 15 1 of 1 TABLE 13.5-4 SCOPE OF THE BVPS RADIATION PROTECTION PROCEDURES The radiation protection procedures include the following topics:

General Program

Exposure Control

Contamination Control Airborne Radioactivity Control Monitoring and Surveys

Radioactive Material Control Records, Reports, and Notifications References and Commitments

Radiation Worker Practices Radioactive Sources

Radiological Work Surveillance Personnel Monitoring Exposure Control/Dose Assessment Radiological Work Controls Radiation/Contamination Protection Respiratory Protection Worker Instruction/Processing

Radiological Instrument Calibration and Use Emergency Use of Radiation Monitoring Systems and Equipment

Emergency Entry, Radiation Exposure Control and Monitoring

BVPS-2 UFSAR Rev. 17 1 of 1 TABLE 13.5-5 SCOPE OF BVPS CHEMISTRY PROCEDURES Chemistry procedures include the following topics:

1. Administrative Controls

a. Introduction

b. Conduct of Operations c. Chemistry Manual Description d. Laboratory Control Programs

2. Chemical Specifications

a. Reactor Plant Chemicals b. Turbine Plant Chemicals c. Water Treating Chemicals

d. Waste Disposal System Chemicals e. Laboratory Chemical and Counting Room Gases

3. Sampling and Testing

a. Reactor Plant

b. Turbine Plant c. Water Treating d. Waste Disposal

e. Sewage Conveyance System f. Environmental Sampling Requirements

g. Reactor Plant Sample System

h. Turbine Plant Sample System i. Reactor Coolant Chemistry Follow During Initial Power Testing Sequence j. Beaver Valley Power Station Chlorination Study Program

k. Gaseous Waste, Containment Air, and Continuous Releases Sampling Systems l. Liquid and Gaseous Radwaste

4. Analytical Methods

5. Radiochemistry Procedures

6. Post Accident Sampling Procedures

7. Chemical Additions

8. Logs and Forms

9. Conduct of Operations

10. Training Guidelines

BVPS-2 UFSAR Rev. 14 13.6-1 13.6 SECURITY BVPS has prepared a security plan that meets the intent of Regulatory Guide 1.17. This plan provides the protection needed to meet the general performance requirements of 10 CFR 73.55(a) and the objectives

of the specific requirements of 10 CFR 73.55, paragraphs (b) through (h).

The approved security plan for BVPS-2, withheld from public disclosure pursuant to 10 CFR 2.790(d) and 73.21, "Requirements for the Protection of Safeguards Information," is identified as the "Beaver

Valley Power Station Physical Security Plan."