ML20128Q215
| ML20128Q215 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 10/16/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20128Q213 | List: |
| References | |
| NUDOCS 9610180278 | |
| Download: ML20128Q215 (24) | |
Text
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e NPF-38-186 ATTACHMENT A 9610180278 961016 PDR ADOCK 05000302 P
'ADMhNISTRATIVECONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Menager Plant Operations shall be responsible for overall l
unit operation and shall delegate in writing the succession to this responsibil-ity during his absence.
6.1.2 The Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command f0nc-tion.
A management directive to this effect, signed by the Vice President Operations, shall be reissued to all station personnel on an annual basis.
l 6.2 ORGANIZATION 6.2.1 0FFSITE 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 from 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 descrip-tions 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 FSAR.
b.
The Vice President Operations shall have corporate responsibility l
for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintain-ing, and providing technical support to the plant to ensure nuclear
- safety, The General Manager Plant Operations shall be responsible for overall l
c.
unit safe operation and shall have control over those onsite activ-ities 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.
6.2.2 UNIT STAFF Each on-duty shift shall be composed of at least the minimum shift a.
crew composition shown in Table 6.2-1; WATERFORD - UNIT 3 6-1 Amendment No. 28,41,63
ADNINISTRATIVECONTROLS i
UNIT STAFF (Continued) b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
In addition, while the reactor is i-N DE i
1, 2, 3, or 4, at least one licensed Senior Operator shall b. in the l
control room.
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c.
A Health Physics Technician" shall be on site when fuel is in the reactor; d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or 56nior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities 1
i during this operation.
l e.
Administrative procedures shall be developed r.nd implemented to l
i limit the working hours of individuals of the nuclear power plant i
operating staff who are responsible for manipulating plant controls
)
or for adjusting on-line systems and equipment affecting plant safety i
which would have an immediate impact on public health and safety, h
j Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be l
followed:
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1.
An individual shall 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 2.
An individual shall 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 /> i
in any 24-hour 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-hour i
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 exclud-ing shift turnover time.
l 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 /> shall be allowed between work l
periods, including shift turnover time.
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l "This requirement tolerates Health Physics Technician unexpected absences 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 />, provided management takes immediate action to fill the required Health Physics Technician position.
i WATERFORD - UNIT 3 6-2 Amendment No,18, AZ, 56, 61
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. ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) 4.
Except during extended shutdown periods, the use of overtime shall be considered on an individual basis and not for the entire staff on a shift.
I Any deviation from the above guidelines shall be authorized by the General Manager Plant Operations, the Manager Technical Services, the Manager Operations and Maintenance, the Operations Superintendent or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Con-trols shall be included in the procedures such that individual over-1 time will be reviewed monthly by the General Manager Plant Operations l
or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not methorized.
f.
The Operations Superintendent shall hold a senior reactor operator license.
F WATERFORD - UNIT 3 6-2a Amendment No. 18,4Z,50,63
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TABLE 6.2-1 i
MINIMUM SHIFT CREW COMPOSITION 1
POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION i
j MODE 1, 2, 3, OR 4 M00E 5 OR 6 SS 1"
1 SRO la None j
M 2
1 1
M 2
1 STA la Mone l
SS Shift Supervisor with a Senior Operator License SRO Individual with a Senior Operator License R0 Individual with an Operator License i
A0 Auxiliary Operator STA Shift Technical Advisor Except for the Shift Supervisor, the shift crew composition may be one less than the minimum requirements of Table 6.2-1 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 of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due 4
f to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room corisand function.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the control room command function.
1 "An individual with SR0/STA qualifications can satisfy the SS/STA or SR0/STA position requirements simultaneously.
WATERFORD - UNIT 3 6-5 AMEN 0 MENT NO. 7
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ADMINISTRATIVE CONTROLS l
'6.2.3 INDEPENDENT TECHNICAL REVIEWS FUNCTION 6.2.3.1 Independent technical reviews shall be conducted to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 A minimum of five, full-time engineers shall be dedicated to perform the independent technical review functions described herein.
Each shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in his/her field.
RESPONSIBILITIES 6.2.3.3 Independent technical review responsibilities shall encompass surveillance to independently verify
- that these activities are performed safely and correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 Individuals assigned the authorit.y to perform the functions and responsibilities delineated above shall make detailed recon:endations for revised procedures, equipment modifications, maintenance activ! ties, operations activities, or other meanc of improving unit safety.
EECD8DI Written records of the activities described above shall be maintained.
6.2.3.5 Reconmiendations for improving unit safety shall 'c4 forwarded each calendar month to the Director of Nuclear Safety.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engir.eer-The ing, and plant analysis with regard to the safe operation of the unit.
STA shall meet the requirements of either Option I or 2 as shown below:
Option 1 - Combined SR0/STA Position. This option is satisfied by a.
assigning an individual with the following qualifications to each operating shift crew as one of the SR0's required by 10 CFR 50.54(m) (2) (1):
- Not respcnsible for sign-off function.
WATERFORD - UNIT 3 6-6 AMENDMENT NO. 10,53,33
ADMINISTRATIVE CONTROLS i
t PROCEDURES AND PROGRAMS (Continued) j L
OFFSITE D0SE CALCULATION MANUAL implementation.
t k.
Quality Assurance Program for effluent and environmental monitoring, i
using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 i
and Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Each procedure of Specification 6.8'.1, and changes thereto, shall be j
reviewed and approved prior to implementation and reviewed periodically as set l,
forth in administrative procedures, s
}
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made j
provided:
f The intent of the original procedure is not altered; a.
b.
The change is approved by two membes of the plant management staff, j
at least one of whom holds a Senior Operator license on the unit affected; The change is documented, reviewed and approved as required by c.
administrative procedures within 14 days of implementation.
l 6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources outside Contai n ;t 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 containment spray, safety injection, hydrogen analyzer, and the post-accident sampling system.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak teit requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitorina 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:
)
WATERFORD - UNIT 3 6-15 AMENDMENT NO. 6bMG,109
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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS '.EPORT COLR (Continued) t 6.9.1.11.2 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal limits, core thermal-hydraulic limits, 1
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ECCS limits, nuclear limits such as shutdown margin, and transient and accident 1
analysis limits) of the safety analysis are met.
\\
6.9.1.11.3 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and i
Resident Inspector.
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SPECIAL REPORTS l
6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
5.10 pECORD RETENTION i
6.10.1 In addition to the applicable record retention requirements of l
Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
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,I WATERFORD - UNIT 3 6-20a AMENDMENT NO.102 I
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' ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each j
power level.
1 b.
Records and logs of principal maintenance activities, inspections, i
repair, and replacement of principal items of equipment related to nuclear safety.
f c.
All REPORTABLE EVENTS.
I d.
Records of surveillance activities; inspections, and calibrations i
required by these Technical Specifications.
e.
Records of changes made to the procedures required by Specification 6.8.1.
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Records of radioactive shipments.
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g.
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
6.10.3 The folla.,g records shall be retained for the duration of the unit j
Operating Lice de.
i a.
Records and drawing changes reflecting unit design modifications i
made to systems and equipmed described in the Final Safety Analysis
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Report.
b.
Records of new and irradiated fuel inventory, fuel transfers, and j
assembly burnup histories.
c.
Records of radiation exposure as required by 10 CFR 20.
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d.
Records of gaseous and liquid radioactive material released to environs.
e.
Records of transient or operational cycles for those unit components indentified in Table 5.7-1.
f.
Records of reactor tests and experiments.
q.
Re m de nf training and quclification for current members of the unit staff.
h.
Records of inservice inspections performed pursuant to these Technical Specificas; ions.
WATERFORD - UNIT 3 6-2]
Amendment No. 116
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ADMINISTRATIVE CONTROLS
' RECORD RETENTION (Continued)
I 1.
Records of quality assurance activities required by the Quality l
Assurance Program Manual.
j.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
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k.
Records of meetings of the PORC and the SRC.
1.
Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records.
m.
Records of secondary water sampling and water quality.
n.
DELETED.
c.
Records of analyses
- required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed.
p.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
4.21 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prept
'osis-tent with the requirements of 10 CFR Part 20 and shall be aeroved, e
and adhered to for all operations involving personnel radi n expo 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by 10 CFR Part 20.1601, each high radiation area in which the inten-ity of radiation is greater than 100 mres/h but less than 1000 arem/h 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)*. 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 which continuously indicates the radiation dose rate in the area.
- Health physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
WATERFORD - UNIT 3 6-22 Amendment No. 50,100,116
l-l ADMINISTRATIVE CONTROLS j..
HIGH RADIATION AREA (Continued) i b.
A radiation monitoring device which continuously integrates the I
radiation dose rate in the area and alarms when a preset integrated l
dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitorino device.
who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
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6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of i
the body could receive in one hour a dose greater than 1000 mrems* but less than 500 rads ** shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the l
Shift Supervisor on duty and/or health physics supervision / designee.
Doors l
shall remain locked except during periods of access by personnel under an i
approved RWP which shall specify the dose rate levels in the immediate work 1
area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation level., such that a j
major portion of the body could receive in I hour a dose in excess of 1000 i
arems* but less than 500 rads ** that are located within large areas, such as
}
PWR containment, where no enclosure exists for purposes of locking, and no i
enclosure can be reasonably constructed around the individual areas, then that
}
area shall be roped off, conspicuously posted and a flashing light shall be i
activated as a warning device.
In lieu of the stay time specification of the l
RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in fadiation protection 1
procedures to provide positive exposure control over the activities within the i
area.
J.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Licensee-initiated changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10i3p.
This documentation shall contain:
l.
Sufficient information to support the charge together with the appropriate analyses or evaluation justifying the change (s) and
- Measurement msde at 30 centimeters from the radiation source or from any I
surface that the radiation penetrates.
- Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
WATERFORD - UNIT 3 6-23 Amendment No. 68,116
' ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 2.
A detemination that the change will maintain the overall confomance 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 PORC and the approval of the Plant Manager.
6.14 0FFSITE D0SE CALCULATION MANUAL (00CM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
J a.
Shall be documented and records of reviews perfomed shall be retained as required by Specification 6.10.3p. This document 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 pursuant to 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 and acceptance by the PORC and the approval of the Plant Manager, c.
Shall be suba'tted to the Commission in the form of a complete, legible copy of the entire ODCM as a 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 shall indicate the date (e.g., month / year) the change was implemented.
l WATERFDRD - UNIT 3 6-24 Amendment No. 61h44,116
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i NPF-38-186 ATTACHMENT B I
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SECTION 6.0 ADMINISTRATIVE CONTROLS
.m.
4 ADMINISTRATIVE CONTROLS
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6.1 RESPONSIBILITY 6.1.1 The General Manager Plant Operations shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Superintendent, or during his absence from the control room, a designated individual l
shall be responsible for the control room command function. A management directive to this effect, j
signed by the Vice President Operations, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION r
6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, 4
respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
l
- a. Lines of authority, responsibility, and communication shall be established and defined from i
the highest management levels through intermediate levels to and including all operating i
organization positions. These relationships shall be documentad and updated, as i
appropriate, in the form of organization charts, functional descriptions of departmental i
responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR.
- b. The General Manager Plant Operations 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.
1
- c. The Vice President Operations shall have corporate responsibility for overall plant nuclear l
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.
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- d. The individuals who train the operating staff and those who carry out health physics and j
quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF l
- a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in 4
Table 6.21; i
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i WATERFORD - UNIT 3 6-1 AMENDMENT NO. 63
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, e ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in MODE 1,2,3, or 4, at least one licensed Senior Operator shall 4
be in the control room.
}
- 0. A Health Physics Technician
- shall be on-site when fuelis in the reactor; i
- d. ALL CORE ALTERATIONS shall be observed and 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.
- e. Administrative proceduces shall be developed and implemented to limit the working hours of 1
individuals of the nuclear power plant operating staff who are responsible for manipulating i
plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public health and safety, Adequate shift coverage shall be maintained without routine heavy use of overtime. The 4
l objective shall be to have operating personnel work an 8 or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> l
l week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:
- 1. An individual shall 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.
- 2. An individual shall 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-hour period, nor i
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-hour 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 /> shall be allowed between work periods, including shift turnover time.
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- This requirement tolerates Health Physics Tech'.cian unexpected absences 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 />, provided management takes immediate action te till the required Health Physics Technician position.
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WATERFORD - UNIT 3 6-2 AMENDMENT NO. 61 l
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ADMINISTRATIVE CONTROLS UNIT STAFF (Continuod)
- 4. Except during extended shutdown periods, the use of overtime shall be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the General Manager Plant Operations, or designee, or higher levels of management, in accordance with established l
procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the General Plant Manager Operations or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
- f. The Operations Manager shall hold a senior reactor operator license.
l WATERFORD - UNIT 3 6-2a AMENDMENT NO. 63 I
5 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE 1,2,3, OR 4 MODE 5 OR 6 SS 1*
1 SRO 1*
None RO 2
1 AO 2
1 STA 1*
None j
SS - Shift Superintendent with a Senior Operator License l
SRO - Individual with a Senior Operator License RO - Individual with an Operator License j
AO - Auxiliary Operator 4
STA - Shift Technical Advisor Except for the Shift Superintendent, the shift crew composition may be one less than the min mum l
requirements of Table 6.2-1 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 accommodote unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
i During any absence of the Shift Superintendent from the control room while the unit is in MODE 1,2,3 or l j
4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function. During any absence of the Shift Superintendent from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior l
Operator or Operator license shall be designated to assume the control room command function.
- An individual with SRO/STA qualifications can satisfy the SS/STA or SRO/STA position requirements simultaneously.
WATERFORD - UNIT 3 6-5 AMENDMENT NO. 7
ADMINISTRATIVE CONTROLS 4
6 2.3 Not Used 4
6.2.4 SHIFT TECHNICAL ADVISOR i
i 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Superintendent in l the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. The STA shall meet the requirements of either Option 1 or 2 as shown below:
- a. Option 1 - Combined SRO/STA Position. This option is satisfied by assigning an individual with the following qualifications to each operating shift crew as one of the SRO's required by 10 CFR 50.54(m)(2)(i):
- Not responsible for sign-off function.
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WATERFORD - UNIT 3 6-6 AMENDMENT NO. 83
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j ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
J. OFFSITE DOSE CALCULATION MANUAL implementation,
- k. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Not Used l
6.8.3 Not Used l
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 containment spray safety injection, hydrogen analyzer, and the post-accident sampling system. The program shallinclude the following:
- 1. Preventive maintenance and periodic visualinspection requirements, and
- 2. 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 WATERFORD - UNIT 3 6-15 AMENDMENT NO.109
l ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT COLR (Continued) 6.9.1.11.2 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal limits, core thermal-hydraul'c limits. ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
6.9.1,11.3 The CORE OPERATING LIMITS REPORT, including any mid<ycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.
SPECIAL REPORTS 6.9.2 Special reports sha.ll be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
6.10 Not Used l
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I WATERFORD - UNIT 3 6-20a AMENDMENT NO.102
Page 6-21 Not Used l
WATERFORD - UNIT 3 6-21 AMENDMENT NO.116
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ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM l
6.11.1 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.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by 10 CFR Part 20.1601, each high radiation area in which the intensity of radiation is greater than 100 mrem /h but less than 1000 mrem /h 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)*. 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 which continuously indicates the radiation dose rate in the area.
- Health physics personnel or personnel esco.ded by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
WATERFORD - UNIT 3 6-22 AMENDMENT NO.116
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)
- b. A radiation monitoring device which 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 levelin the area has been established and personnel have been made knowledgeable of them.
- c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the 1
activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP, 6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems*
but less than 500 rads" snall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health l
physics supervision / designee. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area-and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems' but less than 500 rads ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Licensee-initiated changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:
- 1. Sufficient information to support the chenge together with the appropriate analyses or evaluation justifying the change (s) and
- Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
" Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
WATERFORD - UNIT 3 6-23 AMENDMENT NO.116
ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (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 PORC and the approval of the General Manager Plant Operations.
l 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM i 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document 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 pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix ! to 10 CFR Pau 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.
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- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a 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 shall indicate the date (e.g., month / year) the change was implemented.
WATERFORD - UNIT 3 6-24 AMENDMENT NO.116