ML20154D482

Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes

ML20154D482
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/08/1988
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20154D479	List: ML20154D476 ML20154D482
References
NUDOCS 8809150291
Download: ML20154D482 (8)

Text

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ATTACHMEh7 Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICAT.ON PAGE CHANGES September 8, 1988 1

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l 8809150291 880908 PDR ADOCK 05000155 i

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l TsB0468-0105-NL04 l

4 CONTENTS (Contd)

Page No 91 8.0 Research and Development Program (Deleted) 79 9.0 Inservice Inspection and Testing 92 - 102 9.1 Applicability 92 92 9.2 Objective..

92 9.3 Specifications 9.4 Basis.

92 10.0 (Section 6.0) Administrative Controls.

103 - 126 6.1 Responsibility 103 103 - 106 6.2 Organization 6.3 Plant Staff Qualifications 106 - 107 l

6.4 Training 107 6.5 Review and Audit 107 - 111 6.6 Deleted..........

113 6.7 Safety Limit Violation 113 6.8 Procedures 113 - 114 6.9 Reporting Requirements 114 - 120 6.10 Record Retention 120 - 122 6.11 Radiation Protection Program 122 123 - 123a 6.12 High Radiation Area 6.13 Environmental Qualification.

124 6.14 Process Control Program.

125 6.15 Offsite Dose Calculation Manual (ODCM) 125 11.0 (Section 3.1.4/4.1.4) Emergency Core Cooling System.

130 - 134 (Section 3.1.5/4.1.5) Reactor Depressurization System..

135 - 142 (Section 3.3.4/4.3.4) Containment Spray System 143 - 145 (Section 3.5.3/4.5.3) Emergency Power Sources..

146 - 149 12.0 Fire Protection Program 150 - 157 (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation 150 - 151 (Section 3.7.11.1/4.7.11.1) Fire Suppression Water System.

152 - 153 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems 154 (Section 3.7.11.5/4.7.11.5) Fire Hose Stations 155 (Section 3.7.12/4.7.12) Penetration Fire Barriers.

156 - 157 13.0 Radiological Effluent Technical Specifications 158 - 186 13.1 Radiological Effluent Releases 158 - 173 13.2 Radiological Environmental Monitoring.

174 - 186 11 l Proposed llProposed by CR of 7/5/88 TSB0488-0103-NLO4

s, BfG' ROCK POINT ADMINISTRATIVE CONTROLS t

6.1 RESPONSIBILITY 6.1.1 The Plent Manager shall be responsible for overall plant operation ll and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shif t Supervisor shall be responsible for the shif t command function. A Management directive to this effect shall bt issued annually by the Vice President - Nuclear Operations.

6.2 ORGANIZATION 6.2.1 OTFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for plant operation and corpoaste management, respectively. The onsite and offsite organizations shall include the positions for activities affectia.g the safety of Big Rock Point Plant.

Lines of authority, responsibility and communication shall be a.

established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented, updated and reported to the NRC, as appropriate, in the farm of organization charts functional descriptions of departmental responsibilities and relationships, and job descriptions for key positions, or in equivalent forms of documentation. These requirements shall be documented in the FHSR. Quality Assutance Program Description for Operational Nuclear Power Plants (CPC-2A). Nuclear Operations Department Standards (NODS) or Plant Administrative Procedures.

b.

The Plant Manager shall be responsible for overall plant safe operation and shall have co-trol over those onsite activities necessary for safe operation and maintenance of the plant.

c.

The Vice President - Nuclear 0,*erations 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 organizational freedom to ensure their independence from operating pressures.

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103 IProposed ll Proposed by CR of 7/23/87 TSB0488-0105-NLO4

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'g ADMINISTRATZVE CONTROLS 6.2.2 PLANT STAFF a.

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

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor, c.

At least two licensed Operators shall be present in the control coom during reactor start-up (to a power level

>$ percent), scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.*

e.

All core alterations, after the initial fuel loading, shall either be performed by a licensad Reactor Operator under the general supervision of a Senior Reactor Operator or a nonlicensed Operator directly supervised by a licensed Senior Reactor Operator (or Senior Operator Limited to Fuel Handling) who has no other concurrent responsibilities during this operation.

f.

A Fire Brigade of at least 5 members shall be maintained on site at all times.* The Fire Brigade shall not include 2 members of the minimum shift crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

g.

Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related operation functions; ie, senior reactor operators, reactor operators, auxiliary operators, health physicists and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, 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 shif t turnover time.

(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-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 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 shif t turnover time.

• Radiation Protection coverage and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence provided immediate action is taken to restore the minimum requirements.

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PLANT STAFF 6.2.2 (continued)-

(3) A break, including shift turnover time, of at least eight hours should be allowed after continuous work periods of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> duration.

l (4) Except during extended shutdown periods, the use of j

overtise should be considered on an individual basis and i

not for the entire staff on a shift.

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Any deviation from the above guidelines shall be authorised by the Plant Manager or his alternate (Production and Performance l

l or Maintenance Superintendent), 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 i

individual overtime will be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have y

not been assigned. Routine deviations from the above

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suidelines is not authorized.

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1 105 IProposed llProposed by CR of 7/23/88 TSB0488-0105-NLO4 1

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(SUPPLIED FOR INFORMATION ONLY)

Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Power Refueling Shutdown or Operation Operation Cold Shutdown SS 1

1 1

RO 2

1 1

A0 2

2 1

SS - Shif t Supervisor with a Senior Reactor Operators License RO - Individual with a Reactor Operators License AO - Auxiliary Operator The Shift Crer Composition may be one less than the minimum requirements of Table 6.7-1 fer 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 uneyne,ted absence of on-duty shift crew members provided immediate action is take..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 uten shift change due to an oncoming shift crewman being late or absent.

Ar. on-call Technical Advisor is required and must be able to arrive on-site within one hour. During any absence of the Shift Supervisor from the control room during power operation an individual with a Reactor Operators Licerse chall be designated to assume the control room command function.

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105a Amendment No 63. 86 July 11. 1986 l

TSE0488-0105-NLO4

LIED TOR INTORMATION ONLY)

ADV.INISTRATIVE coy 7potg 6.2.3 INDEPENDENT SATETY ENGINEERING CRotP j

6.2.3.1 The ISEG may function to examine plant operating characteristics.

NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety.

The organisation shall report to the Director - Nuclear Safety.

With the concurrence of the Director ISEG may function as staff to the onsite and offsite review organizations and provide technical support for problem resolution and General Office interface.

COMPOSITION 6.2.3.2 The ISEG shall be composed of members located at other Consumers Power Company Nuclear Power facilities. Any ISEC member may be drawn upon to perforn ISEG duties on a temporary basis at Big Rock Point.

REPORTS 6.2.3.3 Reports of ISEG activities shall be submitted regularly to the NSB with copies to PRC.

6.3 PLANT STATT QUALITICATIONS 6.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.

6.3.2 Either the Chemistry and Health Physics Superintendent or the Chemistry and Radiation Protection Supervisor shall meet or exceed the gus11fications of Regulatory Guide 1.8, September 1975.g 6.3.3 The On-call Technical Advisor (OTA) shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

I Tor the purpose of this section, "Equivalent " as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following (a) Pornal schooling in science engineering, or (b) operational or technical experience / training in nuclear power.

106 Amendment No. f), 76 July 1, 1985 (SUPPLIED TOR INFORMATION ONLY)

TSB04f8-0105-NLO4

fi ADMINISTRATIVE CONTROLS PLANT STAFF QUALIFICATIONS (continued) 6.3.4 An individual holding a Senior Reactor Operator license shall be responsible for directing the activities of licensed operators.

He shall meet the other requirements of Section 6.3.1 (as applicable to Operations Manager in ANSI N18.1).

6.4 TRAINING 6.4.1 A retraining and Teplacement training program for the plant staff shall be maintained and implemented and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55.

ll 6.4.2 A fire brigade training program shall be maintained and implemented and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire Brigade training drills shall be held at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION 6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant Manager on all matters related to nuclear safety.

ll COMPOSITION 6.5.1.2 The PRC shall be composed of t Chairman: Plant Manager or Designated Alternate Appointed by the the Plant Manager.

Member:

Production & Performance Superintendent Member Maintenance Superintendent 1

Member:

Engineering Superintendent Member Operations Supervisor Member:

Instrument and Control Supervisor l

l Moebert Reactor Engineer 1

Member:

chemistry and Health Physics Superintendent Member Shif t Supervisor l

Member:

Technical Engineer 1

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107 l Proposed llProposed by CR of 7/23/87 l

TSB0488-0105-NLO4