ML18024A311
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BFN-27 13.6-1 13.6 Normal Operations 13.6.1 General Day-to-day operations are carried out by the various plant organizations. Each organization, within its assigned area of responsibility, operates with some degree of independence and freedom from close supervision, yet their actions are closely coordinated to best achieve the common purpose.
The Site Vice President, BFN, issues procedures governing employee actions and establishing standards for plant activities. Additionally, standar d NPG administrative procedures are issued by the Vice President Nuclear Support which are applicable to all TVA Nuclear plants. Managers of principal organizations issue instructions governing activities under thei r cognizance. The plant manager issues instructions which contain administrative restrictions and station requirements established to ensure safe operation of the plant within the limits set by the facility licenses and technical specifications. They provide that plant activities will be conducted in a manner to protect the general public, plant personnel, and equipment.
A formalized system of written procedures is employed conforming to the requirements of the Nuclear Quality Assurance Plan (TVA-NQA-PLN-89-A). Procedures covering plant activities which mi ght adversely affect safety are put into effect only after being reviewed and approved by appropriate members of the plant staff as specified in the NQAP. These activities include operation, maintenance, testing and modifications.
The Plant Operations Review Committee (PORC), is responsible for reviewing proposed changes as outlined in the NQAP. The plant manager has the responsibility to ensure that safety re lated procedures prepared by his staff or submitted to him by other organizations receive required reviews and approvals before authorizations are issued.
There is, in addition to planned changes in t he plant and procedures, the area of accidental or gradual changes in plant equipment characteristics or conditions. Each supervisor and employee has the responsibility to be continually alert for such changes and for reporting them upon detection. The periodic inspection of plant equipment and the continuing review and analysi s of operating data from plant logs, instruments, and tests provide regular sources of information on plant conditions.
13.6.2 Normal Operating Instructions Normal Operating Instructions include those procedures for individual system operation, including precautions, preoper ational requirement s, startup, and BFN-27 13.6-2 shutdown; integrated operations for majo r plant activities, including startup, shutdown, and refueling; general equipment operation, such as valves and electrical breakers; responses to annunciators
- anticipated equipment or system abnormalities; layup of systems; and inst ructions for operation during special circumstances to compensate for changed plant conditions (usually used only once
for those special conditions).
13.6.3 Emergency Operating Instructions
As a result of the accident at the Three Mile Island Nuclear Plant, the NRC required the upgrade of Emergency Operating Inst ructions (EOIs) from event based procedures to symptom-based procedures. Symptom-based procedures are procedures which do not require the operator to diagnose the event in order to be able to correctly respond to the event. In stead, the operator responds to symptoms that result from the initiating event(s) and attempts to control these symptoms within established limits. Browns Ferry E OIs are symptom-based procedures and are based on the Boiling Water Reactor Owners Group (BWROG) Emergency Procedure Guidelines (EPGs). The EOIs specify actions necessary to address any event including less than design basis events, design basis events, and beyond design basis events (e.g., multiple equipment failures) and specifies limits to assure continued safe operation of the plant.
The operator monitors the general state of th e plant. If any of the entry conditions for the EOIs are met, the operator takes ac tions to control reactor power, reactor pressure, reactor water level, primar y containment pressure and hydrogen concentration, drywell temperature, pr essure suppression pool temperature, pressure suppression pool water level, and secondary containment temperatures, water levels, and radiation levels. The EOIs are used until either directed out by the EOIs or when the operator concludes that an emergency condition no longer exists.
All operating personnel thr ough training and experience l earn to recognize and evaluate impending failures or malfunctions and to initiate proper corrective actions.
The EOIs are used to train the operating personnel and make them aware of the accidents or situations that could o ccur, and the proper co urse of action.
Specialized Fire Safe Shutdown (FSS) procedur es directing activities to bring a unit to a safe and stable condition following a fire (if required) detail which equipment can be relied upon for performing the required steps, dependent on the location of the fire.
BFN-27 13.6-3 13.6.4 Maintenance Instructions
The plant maintenance program is desi gned to safely and efficiently provide maintenance and repair to keep the plant in good operating order. Maintenance is initiated through the maintenance/work request and a preventive maintenance program. Safe working conditions are assured by the use of TVA's Hold Order, Clearance, and Radiation Work Permit procedures. Complex maintenance operations require step-by-s tep performance and therefor e are detailed in written instructions. These instructions, covering mechanical, electrical, and instrumentation maintenance w ill provide information to a ssure proper coordination of operating and maintenance personnel as well as step-by-step procedures for items such as removal and installation of control rod drives.
13.6.5 Radiologica l Emergency Plan 13.6.5.1 General
The Radiological Emergency Plan contains t he precautionary planning, delegation of authority and responsibility, and implementing procedures to protect the public, plant employees, and equipment in case of unusual incidents. The plan contains information for control of emergency conditi ons modeled after those contained in NUREG-0654, Rev. 1 and R egulatory Guide 1.101, Rev. 3 as appropriate.
13.6.5.2 Radiological Emergency Plan The Radiological Emergency Plan provi des that the Shift Manager on duty is responsible for placing the plan in e ffect based on conditions listed in the implementing procedures.
Upon declaration of an emer gency, the Shift Manager provides for notification of the designat ed people, and assumes the duties of site emergency director until relieved by the plant manager or an alternate.
The emergency organization is as described in the Radiological Emergency Plan, and staffed by pre-selected, experienced personnel. The entire plant facilities and personnel, as well as other TVA organizations, are at the site emergency director's disposal. Adequate qualif ied personnel are availabl e to staff the emergency organization around the clock until the em ergency is over. Advance plans and arrangements have been made in conjunction wit h state and local aut horities, where applicable, for warning the local populace of an emergency and possible evacuation, evacuating the area around the pl ant site, preventing entry of the public to affected areas, medical care of injured or exposed personnel, surveying affected areas for radioactivity, and restricting use of water supplies and foods.
The plant emergency organization will be c ontrolled from the Technical Support Center. This center is adequately shielded to ensure it is occupiable throughout an BFN-27 13.6-4 incident. Communications consist of a dedicated emergency telephone system and the TVA radio system. The Technical Support Center contains area maps, plant drawings, copies of the emergency pl an and necessary emergency supplies and equipment. The overall TVA emergency organization is controlled from the Central Emergency Control Center in Chattanooga.
Additional emergency supplies and equipment are stored in various plant locations.
One vehicle is fully equipped for area radiological surveillance duty.
When an emergency notification is received, all personnel with emergency duty assignments report to the di rector and assume preassi gned duties. All other personnel will normally remain at their wo rk stations, unless accountability is required. They then assemble in a designat ed area and wait for further instructions.
Radiation surveillance team s and other emergency personnel will survey affected areas and report to the director who will evaluate the sit uation and take appropriate actions as outlined in the emergency plan. Complete details are available in the Radiological Emergency Plan and Emergency Plan Implementing Procedures.
13.6.6 Radiation Control Instructions These procedures provide gui dance for the protection of employees and the public from nuclear radiation and contamination. Applicable requirements of the NRC, as published in Title 10, Code of Federal R egulations, Part 20 and 30, and regulations of the Department of Transportation have been incorporated.
13.6.7 Surveillance Instructions These instructions cover periodic tests and inspections required by the technical specifications to assure proper operations, and to prove the adequacy and availability of critical systems and equipment. Formalized schedules and check sheets are used to ascertain that all critical equipm ent and safeguards systems will satisfy their design intent.
Test schedules and records will be maintained so as to provide an orderly test and surveillance program.
13.6.8 Technical Instructions Instructions concerning analytical techniques, calculations, and test procedures will be prepared as required. Examples are chemical control procedures (chemical BFN-27 13.6-5 instructions) which provide plant per sonnel with instruction on the types and frequency of chemical and radiochemical anal ysis, steps to be taken to maintain conditions within established limits, reactor calculatio ns procedures, and test procedures on CSSC equipment beyond that r equired by technical specifications.
The plant computer normally will perform the calculations and assessments on the reactor core and primary system to assure that the reactor is operated safely and efficiently within limits specified by the technical specifications. The reactor calculation procedures outline the backup calculations necessary to assure overall compliance when the computer is unavailable.
Fuel Accountability Procedures delineating the requirements, responsibilities, and methods of nuclear material control from the time new fuel is received until such time as it is shipped from the plant as s pent fuel are contained within the technical procedures. They provide detailed steps for physical safeguards, inventory, accounting, and for preparing reports to the Nuclear Regulatory Commission.
13.6.9 Security Plan Procedures
Procedures for implementing the plant Physical Security Plan are prepared as required. Included are pr ocedures regarding badging, access control, search requirements, posting of personnel, ke ys and locks, lighting, and reporting requirements.
13.6.10 Special Test Instructions
Instructions for special activities which are normally performed one time are not
covered by existing plant instructi ons. These are prepared as required.
13.6.11 Modification/A ddition Instructions Routine continuing requirem ents for fabrication, instal lation, and checkout of materials and components concerning plant modifications are placed in modification/addition instructions. Typica lly included are instructions regarding supports, bolting, coatings, cabling, and electrical terminations.