ML20155D305

Amend 100 to License DPR-54,deleting Organizational Charts from Tech Spec Administrative Section

ML20155D305
Person / Time
Site:	Rancho Seco
Issue date:	09/28/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20155D302	List: ML20155D300 ML20155D305 ML20155D313
References
NUDOCS 8810110214
Download: ML20155D305 (11)

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((. .Wr%q%, 7, NUCLEAR REGULATORY COMMISSION UNITED STATES

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SACRANENTO MUNICIPAL UTILITY DISTRICT

DOCKET No. 50-312 RANCHO SECO NUCLEAR GENERATING STATION ANENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. OPR-54

1. The Nuclear Regulatory Comission (the '; omission) has found that:

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated July 1, 1988, as supplemented September 8,1988, complies with the standards and requirements of thethe Atemic Energy Comission's regulations Act set of 1954,forth in 10 CFR Chapter !;asamended(t B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by I this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in ccmpliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i

! E. The issuance of this amendment is in accordance with 10 CFR Part 51 1 j of the Comission's regulations and all applicable requirements have '

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,. 2. Accordingly, the license is amended by changes to the Technical Specificetions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised t1 rough Amendhient No. 100, are hereby incorporated in the ifcense. The licensee shall operate the facility in accordance with the Technical Specifications.

I i 3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ry P ,M p George W. ighton, Director Project Directorate Y I

Division of Reactor Projects - 111 IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications l

Date of Issuance: September 28, 1988 l

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September 28,198@

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, ATTACHMENT TO LICENSE AMENDHENT NO. 100 FACILITY OPERATING LICENSE NO. DPR-54 l 1 DOCKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications l with the attached pages. The revised pages are identified by Amendment nuirher  ;

and contain vertical lines indicating the area of change.

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Ryg Insert I

. 6-1 6-1 6-la 6-la 1 6-lb i

6-26 6-2a 6-2b 6-2b 6-4 64 6-6 6-6 6-11 6-11 l I

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RANCFO SECO UNIT I

. TECHNICAL SPECIFICATIONS Administrative Controls 6.0 ADM?.NISTRAT!YE CONTROLS -

6.1 RESEONSIBILITY , .

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 writth absences.s the succession to their responsibility during their I

6.1 's 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, Nuclelt shall be issued to all plant personnel on an annual basis.

6.2 ORGANIZATION 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 shall include the positions responsible for i activities affecting the safety of the nuclear power plant.

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a. Lines of authority, responsibility, and comunication shall be established and defined for the highest management levels through intermediate levels, including all operating organization positions. These relationships shall be documented '

and updated, as appropriate, in the form of organization charts, y

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. '

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

t of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

c. The individuals who train the operating staff and those who i

carry out health physics functions may report to the appropriate 4

onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures, i d. Individuals who carry out quality assurance functions shall report to the CEO, Nuclear to ensure their independence from i operating pressures. l Amendment No. 18, 24, 35, 87, 96, 100 6-1 ,

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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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 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, one of whom shall be senior licensed, shall be present in the control room when the unit is in other than cold shutdown or refueling,

d. An individual qualified in 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 include 3 members of the minimum shif t 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.

I reactor operators, radiation protection personnel, auxiliary operators, and key maintenance personnel.

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• Fire Brigade composition may be less than the minimum requirements for a period of time not to excaed 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.

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! Amendment No. 49, 96, 100 6-la

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, TECHNICAL SPECIFICATIONS -

Administrative Controls 6.2.2 FACILITY STAFF (Continued)

Adequate shift coverage shall be maintained without r'outine 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- I l

a. An individual should not be permitted to work more tian 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover 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-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 seven day -

l period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between ,

work periods, including shift turnover time. '

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d. Except during extended shutdown periods, the use of overting st.ould be considered on an individual basis and ,

not for the entire staff on a shift. I i

Any deviation from the above guidelines shall be authorized by 4

the AGM, 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 j procedures such that individual overtime shall be reviewed l monthly by the AGH, Nuclear Power Production or designee to  :

l assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

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

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TECHNICAL SPECIFICATIONS Administrative Controls l

FIGURE 6.2-1 l SMJD CORPORATE SUPPORT OF NUCLEAR SAFETY HAS BEEN DELETED t

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l Amendaent No. 4, 78, 43, 62, 96, .

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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Administrative Controls FIGURE 6.2-2 .

7 NUCLEAR ORGANIZATION CHART HAS BEEN DELE 1ED I

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AsgndmentNo.18,24,IT.62,96, 00 6-2b

. . RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls NEMBERSHIP - .-

6.5.1.3 Membership of the PRC shall be~as defined below: '

a. A list of members made up of personnel filliiig positions in the Nuclear Organization and others who meet or exesad the minimum ,

qualifications of ANSI N18.1-1971 Section 4.2.or 4.4, shall be developed and approved by the AGH, Nuclear Pcwer 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 AGH, Nuclear Power Production. When a meeting is scheduled or an emergency meeting is neressary, and the P8C Chairman will be absent, an alternate Chairman may be designated by the PRC Chairman or the AGH, Nuclear Power Production from among the PRC members described in Specification 6.5.1.L HEETING FRE00ENCY 6.5.1.A The PRC shall meet at least once per calendar month and as convened by the PRC Chairman, or as directed bf the AGH, Nuclear Power Production.

. OOORUM 6.5.1.5 A Quorum of the PRC shall consi:t of a majority of the members list, ,

in Specification 6.5.3.2 including the Chairman or alternate Chairman. No more than two alternates shall participate in PRC activities at a,ny one time for the purpose of establishing a quorum.

RESPONSIBILITIES 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 ano~ char.ges thereto, and 2) any other proposed procedures or cha9ges thereto which are as determined by the AGH, Nuclear Power Production to affect nuclear safety.

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

c. All proposed changes to the Technical Specifications or the "

Operating License, j

d. All safety evaluations of proposed changes or modifications to plant systers or equipment that afftet nuclear safety. Items I 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 j by the PRC.

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e. Investigations of all violations of the Technical Specifications ,

to determine adequacy of corective action and to detect any I degrading trend. j

f. Facility operations to detect potential safety hazards.

Amendment No. 24, 62, 62, 96, 100 6-4

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- TECHNICAL SPECIFICATIONS j Administrative' Controls 6.5.2 MANAGEMENT SAFETY REVIEW CCMMITTEE (MSRC)

FUNCTION 6.5.2.1 The Management Safety Review Comittee shall function to provide i independent review and audit of designated activities in the areas of:

a. nuclear power plant operations -

b. nuclear engineering

c. chemistry and ndiochemir.try

d. metallurgy

e. instrumentation and cont *ol

f. radiological safety

g. mechanical and electrical engineering ,

h. quality assurance practices COMPOSITION g 6.5.2.2 The MSRC shall be composed of a chairman and a minimum of eight ,

) members. The MSRC 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.

HEMBERSHIE .

6.5.2.3 T.5e Chairman of the MSRC shall be appointed by the CEO, Nuclear. A current list of members and alternates as described in Specification 6.5.P.2 shall be developed and approved by the CEO, Nuclear and mair.tained by the MSRC Secretary. In the absence of the Chairman, an  :

Alternate Chairman may be designated by the MSRC Chairman or the CEO, Nuclear. The Alternate Chairman shall be selected from among the MSRC nembers described in Specification 6.5.2.2. I l

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1 i Amendment No. 2, 96, 100 i 6-6 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS .

j Administrative Controls 6.7 SAFETY LIMIT VIOLATION 6.7.1 The follo~ w ing actions shall be taken in the event a Safety Limit is vio%ted;

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

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b. The NRC Operations Center shall be notified by telephone as soon as l possible and in all cases within one hour. The AGM, Nuclear Power l Production and the Chairman of the MSRC shall be notified within 24 i hours.

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c. A Safety Limit Violation Report shall be prepared. The report shall l be reviewed by the PRC. This report shall describe (1) applicable  !

circumstances preceding the violation, (2) effects of the violation I upon facility components, systems or structures, and (3) corrective .

action taken to prevent recurrence.

i d. The Safety Limit Violation Report shall be submitted to the {

1 Comission, the MSRC, and the AGM, Nuclear Power Production, within i 14 days of the violation.-

6.8 150CQURES g 6.8.1 Nritten procedures shall be estabitshed, implemented and maintained j covering the activities referenced below:

a. The appitcable procedures recomended 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.

i f. Fire Protection Procedures implementation, j g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

! 1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL implementation.

l 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.

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! Amtndment No. 18, 24, 53, 87, 96, 93, .

100 6-11 1

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