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Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff
	ML20154D759
Person / Time
Site:	Rancho Seco
Issue date:	09/08/1988
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
Shared Package
ML20154D756	List: ML20154D753; ML20154D759;
References
	NUDOCS 8809160094
	Download: ML20154D759 (9)
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ATTACHMENT.II Technical Specification Pages Affected by Proposed Amendment No. 168, Revision 1 Etanya Insert

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.0 ADU NISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Chief Executive Officer (CEO), Nuclear shall be responsible for the management of the overall facility, and the Assistant General Manager (AGM), Nuclear Power Production shall be responsible to him for the operation and maintenance of the plant. They shall delegate in writing the succession to their responsibility during their absences.

6.1.2 The Shift Supervisor (or a qualified, designated individual) shall be responsible for the control room command function. A management directive to this effect signed by the CEO, Nuclear shall be issued to all plant personnel on an annual basis.

6.2 QEGANIZATION OFFSITE AND ONSITE ORGANIZATIONS 6.2.1 Offsite and onsite organizations shall be established for corporate management and facility operation, respectively. The offsite and onsite organizations shad include the positions responsible for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be i established and defined for the nighest management levels i through intermediate levels, including all operating l organization positions. These relationships shail be documented l 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. The organization and responsibilities shall be documented in the USAR.

b. The CEO, Nuclear shall have corporate responsibility for and shall take any measures needed to ensure acceptable performance I

of the staff in operating, mLintaining, and providing technical support to the plant to ensure nuclear safety,

c. The individuals who train the operating staff and those who carry out health physics functions may report to the appropriate onsite manager; however, they shall have sufficient l organizational freedom to ensure their independence from l

operating prossures.

d. Individuals who carry out quality assurance functions shall report to the CEO, Nuclear to ensure their independence from operating pressures.

Proposed Amendment No. 18, 24, 35, 87, 96, 168, Rev. I 6-1 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls FACILITY STAFF 6.2.2 The Facility organization shall be as shown in the USAR and:

a. Each on duty shift shall be composed of at least the minimum shif t 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, one of whom shall be senior licensed, shall be present in the control room when the UM t is in other than cold shutdown or refueling.

d. An individual qualified it radiation protection practices and ,

procedures shall be on site when fuel is in the reactor.

e. ALL CORE ALTERATIONS after the initial fuel loading shall be 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.

f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times.* The Fire Brigade shall not inc1ude 3 members of the minimum shift crew necessary for safe shutdown of the unit 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 facility staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, radiation protection personnel, auxiliary operators, and key maintenance personnel.

' 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.

Proposed Amendment No. 49, 96, 169, Rev. I 6-la

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i

Administrative Controls 6.2.2 FACILITY STAFF (Continued)

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal shift schedule 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 modifications, on a temporary basis, the following guidelines shall be followed:

a. 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, excluding shift turnover time.

b. 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 seven day period, all excluding shift turnover time,

c. A break of at least eight hours thould be allowed between work periods, including shift turnover 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 AGH, Nuclear Power Production or designee, 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 AGM, Nuclear Power Production or designee to assure that excessive hours have not been assigned. Routine deviation from the abos'e guidelines is not authorized.

h. The Shift Operations Superintendent shall hold a Senior Reactor Operator license in accordance with 10 CFR 55.

i l Proposed Amendment No. 168, Rev. 1

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Administrative Controls FIGURE 6.2-1 -

SMUD CORPORATE SUPPORT OF NUCLEAR SAFETY HAS BEEN DELETED l

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Proposed i Amendment No. 4, 18. 43, 62, 96, 168. Rev. I j 6-2a I

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

q Administrative Controls FIGURE 6.2-2 NUCLEAR ORGANIZATION CHART- ,

HAS BEEN DELETED Proposed Amendment No. 18, 24, 31, 62, 96, 168, Rev. I 6-2b

. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls HEMBERSHIP 6.5.1.3 Membership of the PRC shall be as defined below:

a. A list of members made up of personnel filling positions in the Nuclear Organization and others who meet or exceed the minimum qualifications of ANSI N18.1-1971, Section 4.2 or 4.4, shall be developed and approved by the AGM, Nuclear Power Production.

b. A list of alternate members of the PRC shall be developed and approved by the AGH, Nuclear Power Production.

c. The Chairman of the PRC shall be appointed by the AGM, Nuclear Power Production. When a meeting is scheduled or an emergency meeting is necessary, and the PRC Chairman will be absent, an alternate Chairman may te designated by the PRC Chairman or the AGH, Nuclear Power Production from among the PRC members described in Specification 6.5.1.2.

HEETINGJREOUENCY 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman, or as directed by the AGM, Nuclear Power Production.

OUORUM 6.5.1.5 A Quorum of the PRC shall consist of a majority of the members listed in Specification 6.5.1.2 including the Chairman or alternate Chairman. No more than two alternates shall participate in PRC activities at any one time for the purpose of establishing a quorum.

BESPONSIBILITIES 6.5.1.6 The Plant Review Committee shall be responsible for review of:

a. The required safety evaluation of 1) all procedures required by Specification 6.8 and changes thereto, and 2) any oth r proposed procedures or changes thereto which are as determined by the AGM, Nuclear Power Production to affect nuclear safety,

b. The safety evaluations of all proposed tests snd experiments that affect nuclear safety.

c. All proposed changes to the Technical Specifications or the Operating License.

i d. All safety evaluations of proposed changes or modifications to plant systems or equipment that affect nuclear safety. Items which are determined by a qualified reviewer as not involving an unreviewed safety question, a change of technical specifications, or a change in a licensing basis document, need not be reviewed by the PRC.

e. Investigations of all violations of the Technical Specifications to determine adequacy of corrective action and to detect any degrading trend.

f. Facility operations to detect potential safety hazards.

Proposed 1 Amendment No. 24, 62, 63, 96, 168, Rev. 1 6-4

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.5.2 MANAGEMENT SAFETY REVIEH C0HNITTEE (Hsis')

FUNCTION 6.5.2.1 The Management Safety Review Committee shall function t', provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. ine,trumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices CQHPOSITION 6.5.2.2 The HSRC shall be composed of a' chairman and a minimum of eight members. The HSRC membership shall be made up of manager levels or above as shown on the Nuclear Organization or of other personnel meeting or exceeding the minimum qualifications of ANSI /ANS 3.1-1981, Section 4.7.2.

HEMBERSHIP 6.5.2.3 The Chairman of the HSRC shall be appointed by the CEO, Nuclear. A current list of members and alternates as described in Specification 6.5.2.2 shall be developed and approved by the CEO, Nuclear and maintained by the HSRC Secretary. In the absence of the Chairman, an Alternate Chairman may be designated by the HSRC Chairman or the CEO, Nuclear. The Alternate Chairman shall be selected from among the HSRC members described in Specification 6.5.2.2.

Proposed Amendment No. 2, 96, 168. Rev. I 6-6

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36(c)(1)(1) and 10 CFR 50.72 shall be complied with.

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all ctses within one hour. The AGM, Nuclear Power Production and the Chairman of the MSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the HSRC, and the AGM, Nuclear Power Production, within 14 days of the violaticin.

6.8 PROCEDURES 6.8.1 Hritten procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Safety Guide 33, November 1972,

b. Refueling operations,

c. Surveillance and test activities of safety related equipment,

d. Security Plan implementation,

e. Emergency Plan implementation.

f. Fire Protection Procedures implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

1. RADIOLOGICAL ENVIRONHENTAL MONITORING PROGRAM MANUAL implementation.

j. Quality Assurance Program for Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide 4.15, Revision 1 February 1979.

6.8.2 Each procedure of 6.8.1 above and changes thereto shall be reviewed and approved as set forth in Specification 6.5.

Proposed Amendment No. 18, 24, 53, 87, 96, 98, 168, Rev. I 6-11

ML20154D759

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