ML17228B144

Proposed Tech Specs Re Administrative & Conforming Update

ML17228B144
Person / Time
Site:	Saint Lucie
Issue date:	05/17/1995
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228B143	List: ML17228B142 ML17228B144
References
NUDOCS 9505240105
Download: ML17228B144 (16)

Text

St. Lucie Unit 1 d Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative and Conformin U date L-95-140 ATTACHMENT 3 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES PAGE 1-2 6-1 6-2 F'DR 9505240105 950517 PDR ADOCK 05000335

St. Lucie Unit 1 d Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative and Conformin U date L-95-140 INSERTS NEW SECTION 1.9 INSERT ON PAGE 1-2 CORE ALTERATION shall be the movement or manipulation of any fuel, sources, reactivity control components, lifting or lowering the upper guide structure (UGS), or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel. Shared (4 fingered) control element assemblies (CEAs) withdrawn into the UGS or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/unlatching are exceptions to the above and do not constitute a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

NEW SECTION 6.2.2.d INSERT ON PAGE 6-2 Either a licensed SRO or licensed SRO limited to fuel handling who has no concurrent responsibilities during this operation shall be present during fuel handling and shall directly supervise all CORE ALTERATIONS.

DEFINITIONS CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to. verify OPERABILITY including alarm and/or trip functions.

CONTAINMENT VESSEL INTEGRITY 1.7 CONTAINMENT VESSEL INTEGRITY shall exist when:

a. All containment vessel penetrations required to be closed during accident'onditions are either:

1. Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed position except as provided in Table 3.6-2 of Specification 3.6.3.1,

b. All containment vessel equipment hatches are closed and sealed,

c. Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3,

d. containment leakage rates are within the limits of Specification 3.6.1.2, e.'he and The sealing mechanism associated with each penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE

~ P 1.8 CONTROLLED LEAKAGE shall be the seal water flow supplied from the reactor coolant pump seals.

CORE ALTERATION gS

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1.9 CORE ALTERATION shall. be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

ST. LUCIE - UNIT 1 1-2 Amendment No. 69

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6. 0 ADMINISTRATIVE CONTROLS 6.1 'RESPONSIBILITY 6.1.1 The Plant General Manager 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 Supervisor, or during his absence from the control room a designated d tt t .t individual, shall be responsible for the control room command t

shall dt be tt t ttt reissued to dt t, all station td d personnel tt tt on n annual basis.

6.2 ORGANIZATION SnevlcK PRES>QHÃ ONSITE AND OFFSITE ORGAN IZ TION 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management. This onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

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. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented in the Topical guality Assurance Report and updated in accordance with 10 CFR 50.54(a)(3).

b. The President Nuclear Division shall be responsible for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

C. The Plant General Manager shall be responsible for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d. Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

e. Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the Health Physics Supervisor shall have direct access to that onsite individual having responsibility for overall unit management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

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6. ORGANI T N (Continued)

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

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

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in NODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

C ~ A health physics technicianf shall be on site when fuel is in the reactor.

d. All CORE A TERATIONS shall be observed by a licensed operator and 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.

The SRO in charge of fuel handling normally supervises from the control room and has the flexibility to directly supervise at either the refueling deck or the spent fuel pool.

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II fThe health physics technician may be less than the minimum requirement 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 unex-pected absence, provided immediate action is taken to fill the required positions.

ST. LUCIE - UNIT 1 6-2

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St. Lucie Unit 1 a d Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative and Conformin U date L-95-140 ATTACHMENT 4 ST ~ LUCIE UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES PAGE 1-2 6-1 6-2

St. Lucie Unit 1 and Unit 2 Docket Nos. 50-335 and 50-389 Proposed License Amendments Administrative and Conformin U date L-95-140 INSERTS NEW SECTION 1.9 INSERT ON PAGE 1-2 CORE ALTERATION shall be the movement or manipulation of any fuel, sources, reactivity control components, lifting or lowering the upper guide structure (UGS), or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel. Shared (4 fingered) control element assemblies (CEAs) withdrawn into the UGS or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/unlatching are exceptions to the above and do not constitute a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

NEW SECTION 6.2.2.d INSERT ON PAGE 6-2 Either a licensed SRO or licensed SRO limited to fuel handling who has no concurrent responsibilities during this operation shall be present during fuel handling and shall directly supervise all CORE ALTERATIONS.

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6. RGANI AT ON (Continued)

~UN T STAFF 6.2.2 The unit organization shall be subject to the following:

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

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the reactor is in MODE I, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the control room.

c. A health physics technician¹ shall be on site when fuel is in the reactor.

d. All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concur rent responsibilities during this operation. The SRO in charge of fuel handling normally supervises from the control room and has the flexi-bility to directly supervise at either the refueling deck or the spent fuel pool.

e. DELETED

~@FpcAM ~xi~ /~<&~i Administrative procedures shall and implemented to limit the working hours o'nit bestaffdeveloped who oerform safety-rela:ed reactor operators, functions;. e.g., senior reactor operators, 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 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, or during extended periods of shutdown for refueling, major maintenance or major plant modification, on a temporary basis the following guidelines shall be followed:

¹The health physics technician may be less than the minimum requirement 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, provided immediate action is taken to fill the required positions.

ST. LUG IE - UNIT 2 6-2 Amendment No. 89 55

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OEF INITIONS-CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close .to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CONTAINMENT VESSEL INTEGRITY 1.7 CONTAINMENT VESSEL INTEGRITY shall exist when:

a. All containment vessel penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.

b. All containment vessel equipment hatches are closed and sealed,

c. Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3,

d. The containment leakage rates are within the limits of Specification 3.6.1.2, and

e. The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be the seal water flow supplied from the'eactor coolant pump seals.

CORE ALTERATION

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1.9 CORE ALTERATMN shall be the movement or manipulation of any component within the reactor=pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

ST. LUCIE - UNIT 2 1-2,

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AOMINISTRATIVE CONTROLS 6 RESPONS T 6.l.l The Plant General Manager 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 Supervisor, or during his absence from the control room, a designated individual, shall be responsible for the control room command tt . A g tdt tt t tgt ff t, tg dtytt

, shall be reissued to all station personnel on an annual basis.

ttttÃBA TIATIOO Rl7R, Ylc.E 'PLaSlOEl4T 0 SITE ANO FFS TE 0 GA 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management. This onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

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. Those relationships shall be documented and updated, as appropriate, in the form of organizational cha} ts. These organizational charts will be documented in the Topical guality Assurance Report and updated in accordance with 10 CFR 50.54{a)(3).

b. The President - Nuclear Division shall be responsible for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

Ci The Plant General Manager shall be responsible for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d. Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organiza-tional freedom to be independent from operating pressures.

e. Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the Health Physics Supervisor shall have direct access to that onsite individual having responsibility for overall unit management. Health physics personnel'hall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

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