ML031600799

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Technical Specification, Administrative Changes to Technical Specification Section 6
ML031600799
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/06/2003
From:
NRC/NRR/DLPM
To:
References
TAC MB7160
Download: ML031600799 (18)
v • d • e


Text

INDEX 5.0 DESIGN FEATURES SECTION PAGE 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES ......................................................... 5-9 5.3.2 CONTROL ROD ASSEMBLIES ......................................................... 5-9 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE ............................... 5-9 5.4.2 VOLUME ..... 5-9 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) .................................................... 5-9 5.6 FUEL STORAGE 5.6.1 CRITICALITY ............................................................ 5-10 5.6.2 DRAINAGE ............................................................ 5-10 5.6.3 CAPACITY ............................................................ 5-10 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT ........................................................ 5-10 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS ........................................ 5-11 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY ................................. 6-1 6.2 ORGANIZATION ................................. 6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS .......... ....................... 6-1 6.2.2 STATION STAFF ................................. 6-2 FIGURE 6.2-1 (THIS FIGURE NUMBER IS NOT USED) ....................... 6-3 FIGURE 6.2-2 (THIS FIGURE NUMBER IS NOT USED) ....................... 6-3 FABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION ....................... 6-4

.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) ........ ............... 6-5 2.4 SHIFT TECHNICAL ADVISOR ....................... 6-5
.3 (THIS SPECIFICATION NUMBER IS NOT USED) ......................... . ... 6-5 EABROOK - UNIT xiii Amendment No. XO, 88

INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6.4 (THIS SPECIFICATION NUMBER IS NOT USED) ..................................... 6-6 6.5 REPORTABLE EVENT ACTION .............................. ................. 6-11 6.6 SAFETY LIMIT VIOLATION  ;.. .6-11 6.7 PROCEDURES AND PROGRAMS .  ;.;.'.6-12 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS ............................................... ' '...... ' 6-1.4D' Startup Report ...........  ;.. 6-14D Annual Reports . 6-15 Annual Radiological Environmental Operating Report.6-16 Annual Radioactive Effluent Release Report .. . 6-17 Monthly Operating Reports ........................................ - . ... 6-18 CORE OPERATING LIMITS REPORT ................................... 6-18 6.8.2 SPECIAL REPORTS .6-19 SEABROOK - UNIT 1 xiv Amendment No. 34 ,67 ,73 ,z88

INDEX 6.0 ADMINSTRATIVE CONTROLS -  :

SECTION PAGE 6.9 (THIS SPECIFICATION NUMBER IS NOT USED);;........... .............................. 6-19 6.10 RADIATION PROTECTION PROGRAM ........................ .................... 6-20 6.11 HIGH RADIATION AREA ............................................ 6-20 6.12 PROCESS CONTROL PROGRAM (PCP) ............................................ 6-21 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................................ 6-22 6.14 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS ............................ 6-23 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM............................. 6-24

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SEABROOK - UNIT 1 xv SEABR,O , UNIT,Amendment No. 34,70 88

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Director shall be responsible for overall station -operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Manager (or during his absence from the control room, a designated individual) shall be responsible for the control room command function. A management directive to this effect, signed by the Site Vice President shall be reissued to all station personnel on an annual basis. -

6.2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit 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 to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions for departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR and updated in accordance with the requirements of 10 CFR 50.71.
b. The Station Director 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.
c. The Site Vice President 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.
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 organizatiorial freedom to ensure their independence from operating pressures.

SEABROOK -UNIT 1 6-1 Amendment No.. 88

ADMINISTRATIVE CONTROLS 6.2.3 (THIS SPECIFICATION NUMBER IS NOT USED) I 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the -

Control Room Commander in the areas of thermal hydraulics, reactor engiheering, and plant analysis with regard to the safe operation of the station.

6.3 TRAINING 6.3.1 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK - UNIT 1 6-5 Amendment No. 4 ,3 5-,7 0 , 88

ADMINISTRATIVE CONTROLS 6.4 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK - UNIT 6-6 Amendment No. 34,55, 88

ADMINISTRATIVE CONTROLS THIS PAGE INTENTIONALLY BLANK SEABROOK - UNIT 1 6-7 Amendment.No. 34,39,55, 88

ADMINISTRATIVE CONTROLS THIS PAGE INTENTIONALLY BLANK SEABROOK - UNIT 6-8 Amendment No. 34,5:57079 88

ADMINISTRATIVE CONTROLS THIS PAGE INTENTIONALLY BLANK 6-8A S ONAmendment No. 3 4r ,5 5 , 7 0 ,7 9 , 88 SEABROOK - UNIT 1

ADMINISTRATIVE CONTROLS I I

THIS PAGE INTENTIONALLY BLANK I SEABROOK - UNIT 1 6-8BB NAmendment No. 84,65,67, 88

ADMINISTRATIVE CONTROLS 6.5 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the.

requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the SORC and the results of this review shall be submitted to the NSARC and the Site Vice President.

6.6 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Site Vice President and the* l NSARC shall be notified within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />;
b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SORC. This report shall describe: (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence;
c. The Safety Limit Violation Report shall be submitted to the Commission, the NSARC, and the Site Vice President within 14 days of the violation; and
d. Operation of the station shall not be resumed until authorized by the Commission.

SEABROOK- UNIT 1 6-11 Amendment No. 3,55,67, 88

ADMINISTRATIVE CONTROLS 6.7 PROCEDURES AND PROGRAMS 6.7.1 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, Revision 2, February 1978;
b. The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter No. 82-33;
c. Not used;
d. Not used;
e. PROCESS CONTROL PROGRAM implementation;
f. OFESITE DOSE CALCULATION MANUAL implementation;
9. Quality Assurance Program for effluent and environmental monitoring;
h. Fire Protection Program implementation; and
i. Technical Specification Improvement Program implementation.

SEABROOK - UNIT 6-12 Amendment No. , .88

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS 6.7.6 (Continued)

9. Radioactive Effluent Controls Proqram A program shall be provided conforming with 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 ODCM, (2) shall be implemented by operating procedures, and (3) 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, Colu-mn 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 the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,
5) Determination of cumulative and projected dose contributions 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,
6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, SEABROOK - UNiT 1 6-14A - Amendment No. 66,88

ADMINISTRATIVE CONTROLS The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*

6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions**

(e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [describe maintenance], waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80%

of the total whole-body dose received from external sources should be assigned to specific major work functions;

b. The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1)

Reactor power history starting 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (Ci/gm) and one other radio-iodine isotope concentration (Ci/gm) as a function of time for the

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

SEABROOK - UNIT 1 6-15 Amendment No. 88

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.8.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attn: Document Control Desk, with a copy to the NRC Regional Administrator within the time period specified for each report.

6.9 (THIS SPECIFICATION NUMBER IS NOT USED)

SEABROOK- UNIT 1 6-19 Amendment No. 88

ADMINISTRATIVE CONTROLS 6.10 RADIATION PROTECTION PROGRAM 6.10.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

6.11 HIGH RADIATIONAREA 6.11.1 Pursuant to paragraph 20.1601 (c) of 10 CFR Part 20, in lieu of the "control device' or "alarm signal" required by paragraph 20.1601(a) and (b), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less-than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface that the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high SEABROOK - UNIT -- ~~~- 6-20 STArnendment No. 66- 88

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA 6.11.1 (Continued) radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area; or
b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or
c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within'the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation Work Permit.

6.11.2 In addition to the requirements of Specification 6.11.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface that the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance nay be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mRlh that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around'the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.12 PROCESS CONTROL PROGRAM (PCP) -

Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by the-Operational Quality Assurance Program (OQAP). This documentation shall contain: -
1) Sufficient information to support the change togethe'with the appropriate analyses or evaluations ju'stifying the chafige(s) and- - '

SEABROOK - UNIT 6-21 Amendment No. 2, 88

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (PCP) 6.12 (Continued)

2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.) Shall become effective after review and acceptance by the SORC and approval of the Station Director.

6.13 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 Operational Quality Assurance Program (OQAP). 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 review aid acceptance by the SORC and the approval of the Station.Director.
c. Shall be submitted to th'e Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Annual 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 each affected page shall indicate the revision number the' change was implemented.

SEABROOK - UNIT I 6-22 Amendment No. 2-, 88

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