ML060440019

Technical Specification Pages Administrative Controls

ML060440019
Person / Time
Site:	Davis Besse
Issue date:	02/07/2006
From:	Office of Nuclear Reactor Regulation
To:
Sands, S, NRR/DPLM/LPD III-2, 415-315
Shared Package
ML052640528	List: ML052640393 ML060440019
References
TAC MC6805
Download: ML060440019 (13)

Text

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS ..................................................... 1-1 THERMAL POWER . .................................................. 1-1 RATED THERMAL POWER ............ ................................ 1-1 OPERATIONAL MODE ................................................ 1-1 ACTION .................................................. 1-1 OPERABLE - OPERABILITY ........... ................................ 1-1 DELETED ..........................................................

CONTAINMENT INTEGRITY ........................................... 1-2 CHANNEL CALIBRATION: ............................................ 1-2 CHANNEL CHECK .................... ....... 1-2 CHANNEL FUNCTIONAL TEST ......................................... 1-3 CORE ALTERATION . .................................................. 1-3 SHUTDOWN MARGIN ................................................. 1-3 IDENTIFIED LEAKAGE ................................................ 1-3 UNIDENTIFIED LEAKAGE ............................................. 1-4 PRESSURE BOUNDARY LEAKAGE ..................................... 1-4 CONTROLLED LEAKAGE ............. ................................ 1-4 QUADRANT POWER TILT ............ ................................. 1-4 DOSE EQUIVALENT I- 131 ............ ................................. 1-4 E-AVERAGE DISINTEGRATION ENERGY ............................... 1-4 STAGGERED TEST BASIS ............. ................................. 1-5 FREQUENCY NOTATION ............................................... 1-5 AXIAL POWER IMBALANCE ........... ............................... 1-5 DELETED ...........................................................

REACTOR PROTECTION SYSTEM RESPONSE TIME ...................... 1-5 SAFETY FEATURE RESPONSE TIME ................................... 1-6 PHYSICS TESTS ...................................................... 1-6 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME ...................................................... 1-6 DELETED .

DAVIS-BESSE, UNIT 1 I Amendment No. 48, go" 1,7 AMA 272

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIILITY.. ............................... I .......... 6-1 6.2 ORGANIZATION Offsite and Onsite Organizations ................................ 6-1 Facility Staff .......... 6-la Facility Staff Overtime ......................................... 6-4a 6.3 FACILITY STAFF QUALIFICATIONS ................................ 6-5 6.4 DELETED 6-5 6.5 REVIEW AND AUDIT 6.5.1 Deleted 6.5.2 Deleted 6.5.3 Technical Review and Control .......................................................................... 6-12 6.6 DELETED......................................................................................................... 6-12a 6.7 DELETED......................................................................................................... 6-13 I 6.8 PROCEDURES AND PROGRAMS................................................................. 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 Routine Reports ................................................................................................. 6-14e 6.9.2 Special Reports.................................................................................................. 6-18 6.10 RECORD RETENTION .................................................................................... 6-18 6.11 DELETED 6.12 HIGH RADIATION AREA .............................................................................. 6-20 6.13 ENVIRONMENTAL QUALIFICATION......................................................... 6-21 6.14 DELETED ......................................................................................................... 6-22 I 6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................................. 6-22 6.16 CONTAINMENT LEAKAGE TESTING PROGRAM ................................... 6-23 6.17 TECHNICAL SPECIFICATIONS (TS' BASES CONTROL PROGRAM. 6-24 DAVIS-BESSE, UNIT 1 XV AmendnientNo. }U ,//Ot , t1M fijoJXO,8g44 272

DEFINITIONS 1.29 Deleted 1.30 Deleted 1.31 Deleted OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.32 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (I) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Specifications 6.9.1.10 and 6.9.1 .11.

1.33 Deleted 1.34 Deleted 1.35 Deleted 1.36 Deleted MEMBER(S) OF THE PUBLIC 1.37 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recrea-tional, occupational or other purposes not associated with the plant.

SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

DAVIS-BESSE, UNIT I 1-6a Amendment No. X10ri ,4, 2 72

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of the reactor coolant core outlet pressure and outlet temperature shall not exceed the safety limit shown in Figure 2.1-1.

APPLICABILITY: MODES I and 2.

ACTION:

Whenever the point defined by the combination of reactor coolant core outlet pressure and outlet temperature has exceeded the safety limit, be in HOT STANDBY within one hour.

REACTOR CORE 2.1.2 The combination of reactor THERMAL POWER and AXIAL POWER IMBALANCE shall not exceed the protective limit shown in the CORE OPERATING LIMITS REPORT for the various combinations of three and four reactor coolant pump operation.

APPLICABILITY: MODE 1.

ACTION:

Whenever the point defined by the combination of Reactor Coolant System flow, AXIAL POWER IMBALANCE and THERMAL POWER has exceeded the appropriate protective limit, be in HOT STANDBY within one hour. I REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The Reactor Coolant System pressure shall not exceed 2750 psig.

APPLICABILITY: MODES 1,2, 3, 4 and 5.

ACTION:

MODES I and 2 - Whenever the Reactor Coolant System pressure has exceeded 2750 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within one hour.

MODES 3, 4 and 5 - Whenever the Reactor Coolant System pressure has exceeded 2750 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

DAVIS-BESSIE, UNIT I 2-1 Amendment No. fX, 272

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his/her absence.

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS 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 the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels up to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of 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-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Updated Safety Analysis Report.

b. A 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.

c. The plant manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

DAVIS-BESSE, UNIT I 6-1 Amendment No.Aj,$0, ,yj'/$,# 272

ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control panel area when fuel is in the reactor.

c. At least two licensed Operators, one of which has a Senior Reactor Operator license, shall be present in the control room while in MODES 1, 2, 3, or 4.

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f. Deleted

g. The operations manager shall either hold or have held a senior reactor operator's license on a pressurized water reactor. The assistant operations manager shall hold a senior reactor operator license for the Davis-Besse Nuclear Power Station.

I

1. The individual qualified in radiation protection procedures may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence, provided immediate action is taken to fill the required position.

DAVIS-BESSE, UNIT 1 6-la Amendment No.1, IA, pX, jyy ,f2,ill, 272 (next page is 6-2) l4I, , 79

ADMINISTRATIVE CONTROLS FACILITY STAFF OVERTIME 6.2.3 Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.

Any deviation from the working hour guidelines shall be authorized in advance by the plant manager or his/her designees, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the above guidelines shall not be authorized.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the plant manager or his/her designee(s) to ensure that excessive hours have not been assigned.

DAVIS -BES SE, UNIT I 64a Amendment No. 498,1/g, 272

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the operations manager whose requirement for a senior reactor I operator license is as stated in Specification 6.2.2.g.

6.4 Deleted 6.5 REVIEW AND AUDIT 6.5.1 Deleted 6.5.2 Deleted Pages 6-6 through 6-11 have been deleted. The next page is 6-12.

DAVIS-BESSE, UNIT I 6-5 Amendment No. *,i,7,73,,,~,/

It ,, 1V 2t i>,A gt2 lDY#/,SA~tt,,#7#p,272

ADMINISTRATIVE CONTROLS 6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Plant procedures required by Section 6.8.1 and changes thereto shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual/group other than the individual/group which prepared the procedure or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Plant procedures, (including plant administrative procedures), Physical Security Plan Implementing Procedures and Davis-Besse Emergency Plan Implementing Procedures will be approved by procedurally authorized individuals.

b. Temporary approval of changes to plant procedures cited in Section 6.8.1 which clearly do not change the intent of the approved procedures, can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. For changes to plant procedures, which may involve a change in intent of the approved DAVIS-BESSE, UNIT I 6-12 Amendment No. ,tJmoh ,d V, Yt#,f 2272

ADMINISTRATIVE CONTROLS 6.7 Deleted 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, February, 1978.

b. Refueling operations.

DAVIS-BESSE, UNIT 1 6-13 Amendment No. "'60 1Xa,1Aej,, 272

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES AND PROGRAMS (Continued)

c. Surveillance and test activities of safety related equipment.

d. Physical Security Plan implementation.

e. Davis-Besse Emergency Plan implementation.

f. Fire Protection Program implementation.

g. The radiological environmental monitoring program.

h. Deleted.

i. Offsite Dose Calculation Manual implementation.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in 6.5.3 above.

6.8.3 (deleted) 6.8.4 The following programs shall be established, implemented and maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling and reactor coolant drain systems. The program shall include the following:

(i) Preventive maintenance and/or periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

DAVIS-BESSE, UNIT I 6-14 Amendment No. A XO~ft,J 01 272

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1 .10 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1 . I The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and the Process Control Program, and (2) in conformance with 10 CFR 50.36a and Section IV.B. I of Appendix I to 10 CFR Part 50.

DAVIS-BESSE, UNIT I 6-17a AmendmentNo.40,4,470A,2'$4 272

ADMINISTRATIVE CONTROLS 6.14 Deleted 6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by the USAR Chapter 17 Quality Assurance Program. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b. Shall become effective after the approval of the plant manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

DAVIS-BESSE, UNIT I 6-22 Amendment No. Ad 10, #p', Ty4, 1,f !#q, 272