Text

Proposed Tech Specs Re Onsite & Offsite Organization
	ML20207L787
Person / Time
Site:	Catawba
Issue date:	10/07/1988
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20207L762	List: ML20207L757; ML20207L787;
References
	NUDOCS 8810170438
	Download: ML20207L787 (9)
	v • d • e

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Attachment 1 Proposed Technical Specification Changes l

8810170438 881007 f PDR ADOCK 05000413 PDC P

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ADMINISTRATIVE CONTROLS 1

1 SECTION PAGE 6.1 RESPONSIBILITY.............................................. 6-1 6.2 O RG AN I M 0 N . . . . . . . . . . . . . . . . . . . . . s.................. 6-1 6.2.1 0 FSITE4 . . .D cdstTE cMAnlitM/0N 3M ................................,. ............. 6-1 6.2.2 1 NIT STAFF................................... ............ 6-1

"# 6-3 F I GU R E ' . 2- 1 ^"um'".."n".'^".3.................

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^ ^ ^ ~ g.4 FIGURE 6.2-2 u"tin vnunn'u .n 4'v"n".x. M... E.. W............. .. ..........

TABLE 6.2- INIMUM SHIFT CREW COMPOSITION...... ............... 6-5 6.2.3 CATAWBA S ETY-REVlEW GROUP. ......................... 6-6 Function.................................................. 6-6 Composition............................................... 6-6 Responsibilities.......................................... 6-6 Records................................................... 6-6 6.2.4 SHIFT TECHNICAL ADVIS0R................................... 6-6 6.3 UNIT STAFF 0VALIFICATIONS................................... 6-6 6.4 TRAINING.................................................... 6-6 6.5 REVIEW AND AU0IT............................................ 6-7 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES................... 6-7 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)........................ 6-8 Function.................................................. 6-8 Organization.............................................. 6-9 Review.................................................... 6-10 Audits.................................................... 6-10 Records................................................... 6-11 6.6 REPORTABLE EVENT ACTI0N..................................... 6-12 6.7 SAFETY LIMIY VIOLATION...................................... 6-12 6.8 PROCEDURES AND PR0 GRAMS..................................... 6-13 6.9 REPORTING RE0VIREMENTS....... ........................... .. 6-15 6.9.1 ROUTINE REP 0RTS........................................... 6-15 Startup Report............. .............................. 6-15 CATAWBA - UNITS 1 & 2 XVIII

ACMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall unit coera-tion 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 function. A management directive to this effect, signed by the Vice President of Nuclear Production, shall be reissued to all Nuclear Production Department station personnel on an annual basis.

6.2 ORGANIZATION gg w

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. :.1 Th; cff site organi ation for unit mcnag;;;nt ;nd tecnrical ;;; port

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UNIT STAFF 6.2.2 yThe unit ;rgani;;ti;r : hall be a; :h;wn in igure :.2- anc. i

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

c. At least one licensed Ocerator for each unit shall be in the control room wnen fuel is in the reactor. In addition, wnile either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator snail be in the control room;

c. A Health Physics Technician

shall be on site when fuel is in eitne'r reactor;

d. All CORE ALI~ RATIONS shall be observed and directly sucervised oy eitner a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling wne has no otner concurrent responsibilities during tnis coeration; 1

e. A site Fire Brigade of at least five members

shall be maintained on site at all times. The Fire Brigade snail not include the three l memoers of the minimum shift crew necessary for safe snutcown of tne unit and any personnel required for otner essential functions during l a fire emergency; and l

'ine nealth Pnysics Technician ~and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

CATAWBA - UNITS 1 & 2 6-1

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INSERT FOR PAGE 6-1 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.

1 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 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 Station Manager 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 Vice President of Nuclear Production 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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't ADMINISTRATIVE CONTROL UNIT STAFF (Continued) L

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed 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 nominal 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modification, on a tempo-rary basis the following guidelines shall be followed: -

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1) An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excludirg shift turnover time.

2) An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shif t turnover time. ,

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3) A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

4) Except during extended shutdown periods, the use of overtime i should be considered on an individual basis and not for the entire staff on a shift. ,

Any deviation from the above guidelines 4 hall be authorized by the Station Manager or his designee, or higher levels of management, in accordance with established procedures and with documentation of i

the basis for granting the deviation. Controls shall be included l in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that l excessive hours have not been assigned. Routine deviation from I the above guidelines is not authorized.

Rh supeesnknclent erf Opedons sha{j ho(f oc haw _. he d a sene hb Opah (SRO) Uc.cose. %. Ope.m:{g 6qncer, SWh Superdsor acd Asstsht GN(4 $upervisor ghd\ ho\1 on SRO \ tc.ense. %e. MencMor- Operado t-SWA\ bd a hc.b- (O >eccdor li c.em s e ,

CATAWBA - UNITS 1 & 2 6-2

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Attachment 2 Discussion and No Significant llazards Analysis

DISCUSSION AND NO SIGNIFICANT llAZARDS ANALYSIS This proposed amendment would incorporate the guidance contained in the NRC's Generic Letter 88-06, dated March 22, 1988. The Generic Letter provided for daletion of the organization charts contained within Section 6 of the Technical Specifications provided certain statements be added to cover particular administrative control requirements.

This proposed amendment has been developed based on the Generic Letter guidance.

The NRC Staff concluded and Duke Power concurs that the removal of organization charts from the Technical Specifications will provide greator flexibility to implement changes in organizational structure but will not reduce plant safety.

10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would nots (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a cignificant reduction in a margin of safety.

The proposed amendment ooes not involve an increase in the probability or consequences of any prvelously evaluated accident. This amendment is administrative is natt e and does not change the design or operation of the facility. The accident ar.alyses are therefore unaffected by this proposal.

The proposed amendment does not create the possibility of a new or different kind of accident from any accidcat previously evaluated. The design and operation of the facility will not be changed by this amendment and no new modes of cperation will be introduced.

The proposed anendment does not involve a significant reduction in a margin of safety. This change is administrative in nature and therefore has no effect on any margin of safety.

The NRC's discussion in their Generic 1.etter 88-06 concluded that any facility incorporating the changes outlined in the Generic Letter will have greater ficxibility to implement changes to their organizational structures and will not reduce plant safety.

For the above reasons, Duke Power concludes that this proposed amendment does not involve any Significant llazards Considerations.

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ML20207L787

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