ML20006B783
| ML20006B783 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/24/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20006B713 | List: |
| References | |
| NUDOCS 9002050351 | |
| Download: ML20006B783 (5) | |
Text
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JAFNPP TABLE OF CONTENTS (Cont'd)
I D.
Emergency Service Water System P.agg 240 E.
Inteke Deicing Heaters 242 3.12 Fire Protection Systems 4.12 244a A.
High Pressure Water Fire Protection System A.
244a B.
Water Spray and Sprinkler Systems B.
244e C.
Carbon Dioxide Systems C.
244e D.
Manual Fire Hose Stations D.
244f E.
Fire Protection Systems Smoke and Heat Detectors E.
244g F.
Fire Barrier Penetration Seals F.
244g s
5.0 Design Features 245 5.1 Site 245 5.2 Reactor 245 5.3 Reactor Pressure Vessel 245 5.4 Containment 245 5.5 Fuel Storage
- 245 5.6 Seismic Design 246 6.0 Administrative Controls 247 6.1 Responsibility 247 1
6.2
. Organization 247 6.2.1 Facility Management and Technical Support 247 1
6.2.2 Plant Staff 247a 6.3 Plant Staff Qualifications 248 6.4 Retraining and Replacement Training 248
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6.5 Review and Audit 248 6.5.1 Plant Operating Review Committee (PORC) 248a 6.5.2 Safety Review Committee (SRC) 250 6.6 Reportable Event Action 253 t
6.7 '
Safety Umit Violation 253 6.8 Procedures 1 253 1
6.9 Reporting Requirements 254a 6.10 Record Retention 6.11 Radiation Protection Program 254g 255 6.12 IndustrialSecurity Program 258 D
6.13 Emergency Plan 258 6.14 i~iro Protection Program 6.15 EnvironmentalQualification
- 258 258a
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Amendment No. 7,X X X,7ffes, J td, JAT,137 ill r
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JAFNPP LIST OF FIGURES Figure Title Py 3.1 1 Manual Flow Control 47a 3.12 Operating Umit MCPR versus T 47b 4.1 1 Graphic Aid in the Selection of an Adequate Interval Between Tests 48 4.2 1 Test interval vs. Probability of System Unavailability 87 3.4 1 Sodium Pentaborate Solution 34.7 B 10 Atom % Enriched Volume-110 Concentration Requirement::
1 3.4 2 Saturation Temperature of Enriched Sodium Pentaborate Solution 111 3.5-1 Thermal Power and Core Flow Umits of Specifications 3.5.J.1,3.5.J.2 and 134 3.5.J.3 3.5-6 (Deleted) 135d 3.5 7 (Deleted) 135e 3.5-8 (Deleted) 135f 3.5 9 (Deleted) 135g 3.5-10 (Deleted) 135h 3.5 11 MAPLHGR Versus Planar Average Exposure Reloads 6 &7, BP8DRB299, 1351 QUAD +
3.5-12 MAPLHGR Versus Planar Average Exposurc Reload 7, BD319A 135]
3.5 13 MAPLHGR Versus Planar Average Exposure Reload 8, BD336A
.135k 3.5-14 MAPLHGR Versus Planar Average Exposure Reload 8, BD339A 135!
j 3.6-1 Reactor Vessel Pressure Temperature Umits 163 4.6-1 Chloride Strees Corrosion Test Results at 500 F 164 6.1 1 (Deleted) 259 6.2 1 (Deleted) 200 Amendment No.14, af,42f,64, Z 74,96,56, WJ, ths,96, 97,.184,137 vil
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JAFNPP 6.0
, ADMINISTRATIVE CONTROLS Administrative Controls are the means by which plant operations are subject to management control. Measures specified in this section provide for the assignment of responsibilities, plant organizstion, staffing qualifications and related requirements, review and audit mechanisms, procedural controls and reporting requirements. Each of these measures are necessary to ensure safe and efficient facility operation.
L 6.1 RESPONSIBlUTY -
l The Resident Manager is responsible for safe operation of the plant. During periods when the Resident Manager is unavailable, the Superintendent of Power will assume his responsibilities. In the event both are unavailable, the Resident Manager may delegate this responsibility to other qualtfied supervisory personnel. The Resident Manager reports directly to the Executive Vice Presidant Nuclear Generation.
6.2 ORGANIZATION 6.2.1 Facility Management and Technical Support l
Onsite and oGite organizations shall be establirhed for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities that affect the safety of the nuclear power plant.
1.
Unes of authority, responsibility, And communication shall be established and de'ined for the nighest management levels through intermediate levels to and
- including all operatino organization posnions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptioris 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 Updated FSAP.
2.
The Resident Manager shall be responsible for overall plant operation, and shall have control over those onsite activities that are necessary for safe operation and i
maintenance of the plant.
3 The Executive Vice President Nuclear Generation shall take any. measures.
needed to ensure acceptable performance of the stall in operating, maintaining, l
and providing technical support to the plant to ensure nuclear safety.
4.
The individuals who train the operating staff and those who carry out health physics ac,d quality assuranch functions rnay report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures, i
6.2.2 Plant Staff The plant staff organization shall be as follows:
1.
Each shift crew shall be composed of at least the minimum shift crew composition shown in Table 6.2-1;
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- i Amendment No. p6,pd,7g,'}#1',1,XI,137
JAFNPP t
An SRO or SRO with a license limited to fuel handling shall directly supervise all 2.
Core Alternations. This person shall directly supervise all Core Alterations. This person shall have no other duties during this time; 3.
A fire brigade of five (5) or more members shall be maintained on site at all times. 'this excludes two (2) members of the minimum shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency; 4.
In the event of illness or unexpected absence, up to two (2) hours is allowed to restore the shift crew or fire brigade to the minimum compliment; i
5.
The Operations Superintendent, Assistant Operations Superintendent, Shift Supervisor and Assistant Shift Supervisor shall hold a SRO license and the Senior Nuclear Operator and the Nuclear Control Operator shall hold a RO i
license.
6.
Administrative procedures shall be developed and implemented to limit the '
working hours of unit staff who perform safety related functions; e.g., senior reactor operators, rce.ctor operators, health physicists, auxiliary operators, and maintenance personnel who are working on safety related systems.
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.
4 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 modifications, on a temporary basis, the following guidelines shall be followed:
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 /> a.
straight, excluding shift 'urnover time, b.
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-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 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 seven day period, all excluding shift turnover time.
A break of at least eight hours should be allowed between work periods, c.
including shift tumover time.
d.
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 by the Resident Manager or the Superintendent of Power, or higher levels of management,in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Resident Manager or his designee to assure that execssive hours have not been assigned.-- Routine deviation from the above guidelines is not authorized, l
Amendment No. p 1/f,1)KT,137 1
247a
J JAFNPP 6.3 PLANT STAFF OUALIFICATIONS 6.3.1 The minimum qualifications with regard to educational background and experience for plant staff positions shown in FSAR Figure 13.2 7 shall meet or exceed the minimum qui.lifications of ANSI N18.11971 for comparable positions; except for the Radiation and Environmental Services Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of either Option 1 (Combined SRO/STA Position) or Option 2 (Continued use of STA 1
Position), as defined in the Commission Policy Statement on Engineering Expertise on y
Shift, published in the Octob6r 28,1985 Federal Register (50 FR 43621). When invoking Option 1, the STA role may be filled by the Shift Supervisor or Assistant Shift Supervisor. (t) 6.3.3 Any deviations will be justified to the NRC prior to an individual's filling of one of these positions.
NOTE:
(1)
The 13 individuals who hold SRO licenses, and 'have completed the:FitzPatrick Advanced Technical Training Program prior to the issuance of Ucense Amendment 111c shall be considered qualified as dua!. role SRO/ STAS.
6.4 RETRAINING AND REPLACEMENT TRAINING i
A training program 'shall be maintained under the direction' of the Training Superintendent to assure overall proficiency of the plant staff organization. It shall consist of both retraining and replacement training and'shall meet or exceed the minimum requirements of Section 5.5 of ANSI N18.1 1971.
The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements of 10 CFR 55, Appendix A.
In addition fire brigade training shall meet or exceed the requirements of NFPA 21 1975, except for Fire Brigade training sessions which shall be held at least quarterly. The:
effective date for implementation of fire brigade training is March 17,1978.
6.5 REVIEW AND AUDIT l
Two separate groups for plant operations have been constituted.' One of these, the; Plant Operating Review Committee (PORC), is an onsite review group. The other is an independent review and audit group, the offsite Safety Review Committee (SRC).
Amendment No. jlf,,W, jFf, WW,1X 1M' 137 248