ML20059M102

Proposed Tech Specs Section 5.0 Re Administrative Controls

ML20059M102
Person / Time
Site:	05200001
Issue date:	11/09/1993
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20059M095	List: ML20059M093 ML20059M102
References
NUDOCS 9311180152
Download: ML20059M102 (23)

Text

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"w. . 1 Organization: l

-5.2 i

. i 5.2 Organization j 5.2.2 Unit Staff  !

The unit staff organization shall include the following:  :

a. An auxiliary operator shall be assigned to each reactor  ;

containing. fuel and an additional auxiliary operator shall be assigned for each control room from which a reactor is operating.' ,

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b. At least one licensed Reactor Operator (RO) shall be present i in the control room when fuel is in the reactor. In 1 addition, while the unit is in NODEff!?S31Ef4, 'at least .!

one licensed Senior Reactor OpefatoF(SRO)~lhill be present

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in the control room. l

c. A [ Health Physics Technician) shall be on site when fuel is ,

in the reactor. The position may be vacant for not more f than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected. absence, l provided immediate action is taken to fill the required  !

position. j

d. Administrative procedures shall be developed and implemented  !

to limit the working hours of unit. staff who perform  !

safety related functions (e.g., licensed SR0s, licensed R0s, j health physicists, auxiliary operators, and key maintenance  !

personnel).

Adequate shift coverage shall be maintained without' routine  !

heavy use of overtime. The objective shall be to have .  !

operating personnel work an [8 or 12] hour day, nominal  :

40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week, while the unit is operating. However, in the  !

event that unforeseen problems require substantial amounts j of overtime to be used, or during extended periods of  ;

shutdown for refueling, major maintenance, or major plant  ;

modification, on a temporary basis the following guidelines .j shall be followed:  ::

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1. An individual should not' be permitted to work more than  !

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time; _

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' Two unit sites with both units shutdown or defuele'd require a total of l three auxiliary operators for the two units >

(continued) fi i

ABWR TS 5.0-3 11/01/93 9311100152 E .!

PDR ADOCK931109 05200001 g  :;

A PDR tt j

i Responsibility I 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The [ Plant Superintendent) shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The [ Plant Superintendent], or his designee, in accordance with i approved administrative procedures, shall approve, prior to '

implementation, each proposed test or experiment and proposed changes and modifications to unit systems or equipment that affect ,

nuclear safety.

5.1.2 The [ Shift Supervisor (SS)] shall be responsible for the control room command function. A management directive to this effect, ,

signed by the [ highest level of corporate or site management]

shall be issued annually to all station personnel. During any absence of the [SS] from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor '

Operator (SR0) license shall be designated to assume the control room command function. During any absence of the [SS] from the control room while the unit is in MODE 5, an individual with an active SR0 license or Reactor Operator license shall be designated to assume the control room command function.

l ABWR TS 5.0 1 11/01/93

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Oraanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The ensite and '

offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. ,

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel ,

positions, or in equivalent forms of documentation. These requirements shall be documented in the [SSAR];

b. The [ Plant Superintendent] shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c. The [a specified corporate executive position] shall have corporate responsibility for overall )lant 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; and  :

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

(continued) )

ABWR TS 5.0-2 11/01/93 1

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Organization .

5.2 '

5.2 Organization 5.2.2 Unit Staff l The unit staff organization shall include the following:

a. An auxiliary operator shall be assigned to each reactor containing fuel and an additional auxiliary operator shall beassignepforeachcontrolroomfromwhichareactoris operating '

b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2, 3 or 4, at least l one licensed Senior Reactor Operator (SR0) shall be present in the control room.

c. A [ Health Physics Technician) shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position. ,

d. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g., licensed SR0s, licensed R0s,  ;

health physicists, auxiliary operators, and key maintenance ,

personnel).  !

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work an [8 or 12] hour day, nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week, while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines  ;

shall be followed: '

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time; i

r t

u Two unit sites with both units shutdown or defueled require a total of  ;

three auxiliary operators for the two units (continued)

ABWR TS 5.0-3 11/01/93 L

Organization 5.2 5.2 Organization ,

5.2.2 Unit Staff (continued) ,

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in ,

any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time; _

3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time; >

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the [ Plant Superintendent] or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting l the deviation.

Controls shall be included in the procedures such that '

individual overtime shall be reviewed monthly by the [ Plant -

Superintendent] or his designee to ensure that excessive hours have not been assigned. Routine deviation from the  !

above guidelines is not authorized.

0.B The amount of overtime worked by unit staff members performing safety related functions shall be limited and  !

controlled in accordance with the faC Policy Statement on working hours (Generic Letter 82-12'

e. The [ Operations Manager or Assistant Operations Manager]  !

shall hold an active SR0 license.

f. The Shift Technical Advisor (STA) shall provide advisory ,

technical support to the Shift Supervisor (SS) in the areas  !

of thermal hydraulics, reacter engineering, and plant .

analysis with regard to the safe operation of the unit. In l addition, the STA shall meet the qualifications specified by  ;

the Commission Policy Statement on Engineering Expertise on Shift. l ABWR TS 5.0-4 11/01/93 l 1

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Unit Staff Qualifications 5.3 -

5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position ,

qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum

, qualifications of [ Regulatory Guide 1.8, Revision 2,1987, or more ,

recent revisions, or ANSI Standard acceptable to the NRC staff].

The staff not covered by [ Regulatory Guide 1.8] shall meet or exceed the minimum qualifications of [ Regulations, Regulatory  ;

Guides, or ANSI Standards acceptable to NRC staff].

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ABWR TS 5.0-5 11/01/93

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TS Basos Control 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Technical Specifications (TS) Bases Control 5.4.1 Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

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5.4.2 Licensees may make changes to Bases witnout prior NRC approval ,

provided the changes do not involve either of the following:  ;

a. A change in the TS incorporated in the license; or  :

b. A change to the updated SSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

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

5.4.4 Proposed changes that meet the criteria of (a) or (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.

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1 ABWR TS 5.0-6 11/01/93 l

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Procedures, Programs, and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures, Progrrms, and Manuals 5.5.1 Procedures 5.5.1.1 Scope  ;

Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement l', '

as stated in [ Generic Letter 82-33];

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.2.

5.5.2 Proarams and Manuals The following programs shall be established, implemented, and maintained: l 5.5.2.1 Offsite Dose Calculation Manual (0DCM) i

a. The 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 and trip  ;

setpoints, and in the conduct of the Radiological Environmental Monitoring Program; and

b. Thc ODCM shall also contain the Radioactive Effluent  !

Controls program required by Specification 5.5.2.4, and descriptians of the information that should be included in the Annual Radiological Environmental Operating, and l Radioactive Effluent Release, reports required by i Specification 5.7.1.2 and Specification 5.7.1.3.

(continued)

ABWR TS 5.0-7 11/01/93 l

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Procedures, Programs, and Manuals .

5.5 5.5 Procedures, Programs, and Manuals 5.5.2.1 Offsite Dose Calculation Manual (0DCM) (continued) i Licensee initiated changes to the ODCM: i

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

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

2. a determination that the change (s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after review and acceptance by plant reviews and the approval of the [ Plant Superintendent]; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in 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 (i.e., month and year) the change was implemented.

5.5.2.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems .utside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Low '

Pressure Core Flooder, High Pressure Core Flooder, Residual Heat Removal, Reactor Core Isolation Cooling, Hydrogen Recombiner, Post Accident Sampling, Standby Gas Treatment, Suppression Pool Cleanup, Reactor Water Cleanup, Fuel Pool Cooling and Cleanup, Process Sampling, Containment Atmospheric Monitoring, and Fission Product Monitor. The program shall include the following- .

(continued)

ABWR TS 5.0-8 11/01/93 P

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.2 Primary Coolant Sources Outside Containment (continued)

a. Preventive maintenance and periodic visual inspection requirements; and ,

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.2.3 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall' include the following:

a. Training of personnel;

b. Procedures for sampling and analysis; and

c. Provisions for maintenance of sampling and analysis .

equipment.

5.5.2.4 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 (1) shall be contained in the ODCH, (2) shall be implemented by procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: 1

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation inc.luding surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in i Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401; (continued)

ABWR TS 5.0-9 11/01/93

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. ' Procedures, Programs, and Manuals

. . 5.5 .!

It 5.5 Procedures, Programs, and Manuals 1

5.5.2.4 Radioactive Effluent Controls Program (continued)

c. Monitoring, sampling, and analysis of radioactive liquid and .

gaseous effluents pursuant to 10 CFR 20.1302 and with the -

methodology and parameters in the ODCM-

d. 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;

e. Determination of cumulative and projected dose contributions l from radioactive effluents for the current calendar quarter i and current calendar year in accordance with the. methodology 1 and parameters in the ODCM at least every 31 days;  !

f. Limitations on the functional capability and use of the '

liquid and gaseous effluent treatment systems to ensure that l 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 commitroent, conforming to i 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the j site boundary conforming to the dose associated with  :

10 CFR 20, Appendix B, Table II, Column 1; (

h. 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 '

l 10 CFR 50, Appendix I; '

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all.

radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

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

(continued) l 1

ABWR TS 5.0-10 11/01/93  !

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Procedures, Programs, and Manuals 5.5 1 i

5.5 Procedures, Programs, and Manuals 5.5.2.5 Component Cyclic or Transient Limit This program provides controls to track the SSAR, Section 3.9.1.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.2.6 inservice Testing Program This program shall include the following:

a.

Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testino activities Weekly Monthly At least once per 7 days Quarterly or every At least once per 31 days 3 months Semiannually or At least once per 92 days every 6 months Every 9 months At least once per 184 days Yearly or annually At least once per 276 days Biennially or every At least once per 366 days 2 years At least once per 731 days b.

The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activit!es;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and d.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

(continued) l ABWR TS 5.0-11 11/01/93

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals i

5.5.2.7 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation '

systems at the frequencies specified in [ Regulatory Guide ],

and in accordance with Regulatory Guide 1.52, Revision 2; ASME N510-1989; and AG-1-1991.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < [0.05]% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below [110%):

ESF Ventilation System Flowrate Control Room Habitability System Standby Gas Treatment System

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < [0.5]% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below [i 10%]:

ESF Ventilation System Flowrate Control Room Habitability System Standby Gas Treatment System

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as '

described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified i below when tested in accordance with [ ASTM 03803-1989) at a temperature of 5 [30*C] and greater than or equal to the relative humidity specified below:

ESF Ventilation System Penetration RH Control Room Habitability System Standby Gas Treatment System (continued) l ABWR TS 5.0-12 11/01/93 i

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Procedures, Programs, and Manuals .

5.5 5.5 Procedures, Progra.ns, and Manuals 5.5.2.7 Ventilation Filter Testing Program (VFTP) (continued)

Reviewer's Note: Allowable penetration = [100% - methyl d.odide efficiency for charcoal credited in staff safety evaluation]/

(safety factor).

Safety factor = [5] for systems with heaters.

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below [! 10%]:

ESF Ventilation System Delta P Flowrate Control Room Habitability System Standby Gas Treatment System

e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [i 10%] when tested in j accordance with ASME N510-1989: i ESF Ventilation System Wattage Control Room Habitability System Standby Gas Treatment System The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.2.8 Explosive Gas and Storage Tank-Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Offgas System. The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5,

" Postulated Radioactive Release due to Waste Gas System Leak or Failure".

(continued)

ABWR TS 5.0-13 11/01/93

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals '

5 5.2.8 Explosive Gas and-Geerage Tank Radioactivity Monitoring Program ,

(continued)

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Offgas System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to .

the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

b. A surveillance program to ensure that the quantity of radioactivity in the Offgas System is less than'the amount that would result in a whole body exposure of 2 0.5 rem to I any individual in an unrestricted area, in the event of inadvertent bypass of the Offgas Systems charcoal beds as analyzed in SSAR Section 15.7.1.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Stcrage T:nk Radioactivity Monitoring nogram surveillance frequencies.

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(continued)  !

ABWR TS 5.0-14 11/01/93 l

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.8 Explosive Gas and Ster:ge T:nk-Radioactivity Monitoring Program (continued)

The program shall include: f f

a. The limits for concentrations of hydrogen and oxygen in the -

Offgas System and a surveillance program to ensure the ,

limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

b. A surveillance program to ensure that the quantity of radioactivity in the Offgas System is less than 'the amount that would result in a whole body exposure of 2 0.5 rem to any individual in an unrestricted area, in the event of inadvertent bypass of the Offgas Systems charcoal beds as analyzed in SSAR Section 15.7.1.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and St0r:ge T:nk Radioactivity Monitoring Program surveillance frequencies.

(continued)

ABWR TS 5.0-14 11/01/93

i Procedures, Programs, and Manuals i 5.5 .

5.5 Procedures, Programs, and Manuals l 5.5.2.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel ail shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM ,

Standards. The purpose of the program is to establish the following: l

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has: i i

1. an API gravity or an absolute specific gravity within limits, ,

2. a flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. a clear and bright appearance with proper color;

b. Other properties for ASTM 20 fuel oil are within limits within 30 days following sampling and addition to storage tanks; and

c. Total particulate concentration of the fuel oil is s 10 mg/l when tested every 31 days in accordance with ASTM 0-2276, Method A-2 or A-3.

5.5.2.10 Software Error Evaluation Program This program provides controls to ensure that appropriate software error evaluation procedures, to protect the plant from common mode software errors, are established to ensure that redundant system '

capability is not adversely affected. This program shall evaluate the cause of the inoperability, the affected components, and the plans and schedule for completing proposed remedial actions. If a determination is made that a common mode software error exists,

, then a Special Report shall be submitted in accordance with  :

Specification 5.7.2.b. ,

ABWR TS 5.0-15 11/01/93

SFDP

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5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Safety function Determination Program (SFDP) 5.6.1 This program ensures loss of safety function is detected and appropriate actions taken. Upon failure to meet two or more LCOs at the same time, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LC0 3.0.6.

5.6.2 The SFDP shall contain the following:

a. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

5.6.3 A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system (s) supported by the inoperable support system is also inoperable (Case A); or

b. A required system redundant to system (s) in turn supported by the inoperable supported system is also inoperable (Case B); or (continued) i ABWR TS 5.0-16 11/01/93 l

• i SFDP l 5.6  ;

l 5.6 SFDP 5.6.3 (continued)

c. A required system redundant to support system (s) for the-  !

supported systems (a) and (b) above is also inoperable  ;

(Case C).

Generic Example:

t Division A Division B '

System i System i 4 ase C l 4 4 System ii -(Support System System 11 l Inoperable) 4 &

System iii System iii dase A  ;

1 1 System iv System iv -Case B l.

1 5.6.4 The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

ABWR TS 5.0-17 11/01/93 i

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Reporting Requirements .

5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.1 Routine Reports The following reports shall be submitted in accordance with i 10 CFR 50.4.

5.7.1.1 Annual Reports ,

______________________...__...-NOTE-------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the ,

station.  !

Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted by <

March 31 of each year. [The initial report shall be submitted by March 31 of the year following initial criticality.]

Reports required on an annual basis include:

a. Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) for whom monitoring was required, receiving an annual deep dose equivalent > 100 mrem and the associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for. In the ,

aggregate, at least 80% of the total deep dose equivalent ,

received from external sources should be assigned to '

specific major work functions; and (b. Any other unit unique reports required on an annual basis.]

(continued) t ABWR TS 5.0-18 11/01/93 l

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.2 Annual Radiological Environmental Operating Report

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NOTE------------------------------- .

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses 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 the Offsite Dose Calculation Manual

, (0DCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCH, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979]. [The report shall identify the TLD '

results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each  :

result.] In the event that some individual results are not available for inclusion with the report, the report shall be ,

_ submitted noting and explaining the reasons for the missing  !

results. The missing data shall be submitted in a supplementary  !

report as soon as possible.  !

+

1 i

i (continued) l I

ABWR TS 5.0-19 11/01/93

. , Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.3 Radioactive Effluent Release Report

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NOTE-------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year 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 consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.7.1.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience [,

including documentation of all challenges to the safety / relief valves ] shall be submitted on a monthly basis no ltter than the 15th of each month following the calendar month covered by the report.

5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following: i The individual specifications that address core operating  !

limits must be referenced here.

4

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

i (continued)

ABWR TS 5.0-20 11/01/93

1 Reporting R:quirements '

5.7

,f 5.7 Reporting Requirements ,

5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)  ;

Identify the Topical Report (s) by number, title, date, and -

NRC staff approval document, or identify the staff Safety

• Evaluation Report for a plant specific methodology by'NRC letter and date.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, '

core thermal hydraulic limits, Emergency Core Cooling i Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety .

analysis are met. ,

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the a NRC.

5.7.1.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS '

REPORT (PTLR) ,

The RCS pressure and temperature limits, including heatup and. ..

cooldown rates, criticality, and hydrostatic and leak test limits, shall be established and documented in the PTLR. [The individual Specifications that address the reactor vessel pressure and temperature limits and the heatup and cooldown rates may be ,

referenced.] The analytical methods used to determine the ,

pressure and temperature limits including the heatup and cooldown '

4 rates shall be those previously ~ reviewed and approved by the NRC in [ Topical Report (s), number, title, date, and NRC staff approval document, or staff safety evaluation report for a plant specific - -

methodology by NRC letter and date]. The reactor vessel pressure and temperature limits, including those for heatup and cooldown -

rates, shall be determined so that all applicable limits (e.g.,

heatup limits, cooldown. limits, and inservice' leak and hydrostatic .i testing limits) of the analysis are met. The PTLR,-including revisions or supplements thereto, shall be provided upon issuance ,

for each reactor vessel fluency period. l 4

f 3

5 5

(continued)

ABWR TS 5.0-21 11/01/93 )

I H

~

.- ~

Reporting Requirements 5.7 5.7 Reporting Requirements (continueQ 5.7.2 Soecial Reoorts l Special Reports may be required covering inspection, test, and maintenance activities. These special reports are determined on an individual basis for each unit, and their preparation and submittal are designated in the Technical Specifications. '

Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition C.of LCO 3.3.3.1, " Essential Multiplexer System," a report shall be submitted within the following 14 days. The report shall outline the cause of the inoperability, consideration of common mode failures, and the plans and schedule for restoring the EMS transmission segments to OPERABLE status.

b. When a Special Report is requried by Specification 5.5.2.10,

" Software Error Evaluation Program," a report shall be submitted within the following 7 days. The report shall outline the cause of the inoperability, the affected components, and the plans and schedule for completing proposed remedial actions.

ABWR TS 5.0-22 11/01/93