ML061500264

Tech Spec Pages for Amendments 250 & 251 Adoption of Technical Specification Task Force Travelers

ML061500264
Person / Time
Site:	Turkey Point
Issue date:	05/26/2006
From:	Plant Licensing Branch III-2
To:
Moroney B, NRR/DLPM, 415-3974
References
TAC MC5840, TAC MC5841, TAC MC6027, TAC MC6028, TAC MC6029, TAC MC6030, TAC MC6031, TAC MC6032, TAC MC6033, TAC MC6034, TAC MC6035, TAC MC6036, TAC MC6037, TAC MC6038, TAC MC6039, TAC MC6040
Download: ML061500264 (12)

Text

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPO NSIBILITY............................................................................................................

6-1 6.2 O RGANIZATIO N..............................................................................................................

6-1 6.2.1 O NSITE AND O FFSITE O RGANIZA TIO N...................................................................

6-1 6.2.2 PLANT STAFF............................................................................................................

6-2 TABLE.6.2-1 MINIMUM SHIFT CREW COMPOSITION.....................................................

6-4 6.2.3 SHIFT TECHNICAL ADVISO R FUNCTIO N.................................................................

6-5 6.3 FACILITY STAFF Q UALIFICATIO NS..............................................................................

6-5 6.4 DELETED.........................................................................................................................

6-5 6.5 DELETED.........................................................................................................................

6-5 TURKEY POINT - UNITS 3 & 4 xv AMENDMENT NOS. 2 2 9,2 2 5

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 DELETED.........................................................................................................................

6-12 6.7 DELETED.........................................................................................................................

6-12 6.8 PROCEDURES AND PROG RAMS..................................................................................

6-13 6.9 REPO RTING REQ UIREM ENTS......................................................................................

6-18 6.9.1 RO UTINE REPO RTS..................................................................................................

6-18 Startup Report.......................................................................................................

6-18 Annual Reports......................................................................................................

6-19 Annual Radiological Environm ental Operating Report............................................

6-20 Annual Radioactive Effluent Release Report..........................................................

6-20 Peaking Factor Lim it Report...................................................................................

6-21 Core Operating Lim its Report.................................................................................

6-21 6.9.2 SPECIAL REPO RTS...................................................................................................

6-22 6.10 DELETED.......................................................................................................................

6-23 TURKEY POINT - UNITS 3 & 4 xvi AMENDMENT NOS. 22 9, 2 2 5

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tgv) shall not exceed the limits shown in Figure 2.1-1, for 3 loop operation.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

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

ACTION:

MODES 1 and 2:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

MODES 3, 4 and 5:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

I I

TURKEY POINT - UNITS 3 & 4 2-1 AMENDMENT NOS. 2 2 9,2 2 5

REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or equal to 92% of indicated level, and at least two groups of pressurizer heaters each having a capacity of at least 125 kW and capable of being supplied by emergency power.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a.

With only one group of pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s** or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the Reactor Trip System breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.3.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified to be at least 125 kw at least once per 18 months.

• • 14 days If the Inoperability is associated with an Inoperable diesel generator.

I TURKEY POINT - UNITS 3 & 4 3/4 4-9 AMENDMENT NOS. 22 9, 225

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation*.

APPLICABILITY:

MODE 6, when the water level above the top of the reactor vessel flange is less than 23 feet.

ACTION:

a.

With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible.

b.

With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.8.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other RHR loop i OPERABLE and in operation.

I TURKEY POINT - UNITS 3 & 4 3/4 9-9 AMENDMENT NOS. 2 2 9, 2 2 5

ADMINISTRATIVE CONTROLS PLANT STAFF 6.2.2 The plant organization shall be subject to the following:

a.

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

b.

DELETED

c.

At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips. In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;

d.

A Health Physics Technician* shall be on site when fuel is in the reactor;

e.

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

f.

DELETED

h.

The Operations Supervisor shall hold a Senior Reactor Operator License.

i.

The Operations Manager shall either:

1.

hold or have held a Senior Reactor Operator License on the Turkey Point Plant; or,

2.

have held a Senior.Reactor Operator License on a similar plant (i.e., another pressurized water reactor); or

3.

have completed the Turkey Point Plant Senior Management Operations Training Course.

(i.e., certified at an appropriate simulator for equivalent senior operator knowledge level.)

• The Health Physics Technician composition 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 positions.

TURKEY POINT - UNITS 3 & 4 6-2 AMENDMENT NOS. 2 2 9, 22 5

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR FUNCTION 6.2.3.1 An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit and the opposite unit, This individual shall meet the,.qualifications specified by the 1985 NRC Policy Statement on Engineering Expertise on Shift.

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 6.3.1.1 The Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.3.1.2 The Operations Manager whose requirement for a Senior Reactor Operator License is as stated in Specification 6.2.2.i.

6.3.1.3 The licensed Operators and Senior Operators who shall also meet or exceed the minimum qualifications of the supplemental requirements specified in 10 CFR Part 55, and ANSI 3.1, 1981.

6.3.1.4 The Multi-Discipline Supervisors who shall meet or exceed the following requirements:

a.

Education: Minimum of a high school diploma or equivalent

b.

Experience: Minimum of four years of related technical experience, which shall include three years power plant experience of which one year is at a nuclear power plant

c.

Training: Complete the Multi-Discipline Supervisor training program 6.3.2 When the Health Physics Supervisor does not meet the above requirements, compensatory action shall be taken which the Plant Nuclear Safety Committee determines and the NRC office of Nuclear Reactor Regulation concurs that the action meets the intent of Specification 6.3.1.

6.3.3 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator and a licensed reactor operator are those individuals who, in addition to meeting the requirements of 6.3.1.3, perform the functions described in 10 CFR 50.54(m).

6.4 DELETED 6.5 DELETED TURKEY POINT - UNITS 3 & 4 6-5 AMENDMENT NOS. 22 9, 225

ADMINISTRATIVE CONTROLS 6.6 DELETED 6.7 DELETED TURKEY POINT - UNITS 3 & 4 6-12 AMENDMENT NOS2229, 225

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 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 the Safety Injection System, Chemical and Volume Control System, and the Containment Spray System. The program shall include the following:

(1)

Preventive maintenance and periodic visual inspection requirements, and (2)

Integrated leak test requirements for each system at least every 18 months.

The provisions of Specification 4.0.2 are applicable.

b.

DELETED

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall Include:

(1)

Identification of a sampling schedule for the critical variables and control points for these variables, (2)

Identification of the procedures used to measure the values of the critical variables, TURKEY POINT - UNITS 3 & 4 6-14 AMENDMENT NOS. 229, 225

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

f.

Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained In the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1.

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

2.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2402;

3.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

4.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I;

5.

Determination of cumulative dose from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

6.

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

7.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with I

the following:

a.

For noble gases: a dose rate less than or equal to 500 mrems/yr to the whole body and a dose rate less than or equal to 3000 mrems/yr to the skin, and

b.

For iodine-1 31, iodine-1 33, tritium, and all radionuclide in particulate form with half-lives greater than 8 days: a dose rate less than or equal to 1500 mrems/yr to any organ.

8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR §50, Appendix I; TURKEY POINT - UNITS 3 & 4 6-16 AMENDMENT NOS. 2 2 9, 2 2 !

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

9.

Limitations on the annual and quarterly doses to a member of the public from iodine-1 31, iodine-1 33, tritium, and all radionclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

10.

Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

g.

Deleted

h.

Containment Leakaae Rate Testing Proaram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, and as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following deviations or exemptions:

1)

Type A tests will be performed either in accordance with Bechtel Topical Report BN-TOP-1, Revision 1, dated November 1, 1972, or the guidelines of Regulatory Guide 1.163.

2)

Type A testing frequency in accordance with NEI 94-01, Revision 0, Section 9.2.3, except:

a)

For Unit 3, the first Type A test performed after the November 1992 Type A test shall be performed no later than November 2007.

b)

For Unit 4, the first Type A test performed after October 1991 shall be performed no later than October 2006.

3)

A vacuum test will be performed in lieu of a pressure test for airlock door seals at the required intervals (Amendment Nos. 73 and 77, issued by NRC November 11, 1981).

The peak calculated containment interval pressure for the design basis loss of coolant accident, Pa, is 49.9 psig.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.25% of containment air weight per day.

Leakage Rate acceptance criteria are:

1)

The As-found containment leakage rate acceptance criterion is < 1.0 La. Prior to increasing primary coolant temperature above 200OF following testing in accordance with this program or restoration from exceeding 1.0 La, the As-left leakage rate acceptance criterion is <0.75 La, for Type A test.

2)

The combined leakage rate for all penetrations subject to Type B or Type C testing is as follows:

TURKEY POINT - UNITS 3 & 4 6-17 AMENDMENT NOS.229, 225

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

The combined As-left leakage rates determined on a maximum pathway leakage rate basis for all penetrations shall be verified to be less than 0.60 La, prior to increasing primary coolant temperature abovd 200OF following an outage or shutdown that included Type B and Type C testing only.

The As-found leakage rates, determined on a minimum pathway leakage rate basis, for all newly tested penetrations when summed with the As-left minimum pathway leakage rate leakage rates for all other penetrations shall be less than 0.6 La, at all times when containment integrity is required.

3)

Overall air lock leakage acceptance criteria is _ 0.05 La, when pressurized to Pa.

The provisions of Specification 4.0.2 do not apply to the test frequencies contained within the Containment Leakage Rate Testing Program.

i.

Technical Specifications (TS) Bases Control Proqram This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1.

Change in the TS incorporated in the license or

2.

A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d.

Proposed changes that meet the criteria of Specification 6.8.4 i.b. above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be. provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).

6.8.5 Administrative procedures shall be developed and Implemented to limit the working hours of personnel who perform safety-related functions, e.g. licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance personnel. The procedures 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 by the applicable department manager or higher levels of management, In accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned. Routine deviation from the working hour I

guidelines shall not be authorized.

TURKEY POINT - UNITS 3 & 4 6-18 AMENDMENT NOS.229, 225