Text

Amend 96 to License DPR-54,revising Administrative Controls Section of Tech Specs to Reflect Changes in Plant Mgt & Organization
	ML20149M854
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Site:	Rancho Seco
Issue date:	02/19/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
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1 l # 'o,, UNITED STATES

! o NUCLEAR REGULATORY COMMISSION

{ g $ WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LILENSE Amendment No. 96 License No. DPR-54

1. The huclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated September 16, 1987, as supplemented November 2 and 25,1987 and February 1 and 12,1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter It B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C. Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendnent will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This amendment to the Technical Specification shall become effective within 30 days of the issuance date. The implementation delay is provided to allow time for modification of affected procedures and promulgation of the changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION

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George, . Knight . Ofrector Project Directorate Y Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 19, 1988 l

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February 19, 1988 s .

ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-54 D0CKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Arnendment number and contain vertical lines indicating the area of change.

Remove Insert VIII VIII X X XII XII 6-1 6-1 6-la 6-la 6-2 6-2

- 6-2a

- 6-2b 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-10a 6-11 6-11 6-12 6-12 6-12b 6-12b 6-12c 6-12c 6-12h 6-19 6-19 6-20 6-20

, , RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Pa'ge 6 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.3 FACILITY STAFF QUALIFICATIONS 6-3 6.4 TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 Plant Review Committee 6-3 6.5.2 Management Safety Review Committee 6-6 6.5.3 Technical Review and Control 6-8 6.5.4 Audits 6-9 6.6 REPORTABLE OCCURRENCE ACTION 6-10 6.7 SAFETY LIMIT VIOLATION 6-11 6.8 PROCEDURES 6-11 6.9 REPORTING REQUIREMENTS 6-12 6.10 RECORD RETENTION 6-13 6.11 RADIATION PROTECTION PROGRAM 6-14 6.12 RESPIRATORY PROTECTION PROGRAM - Delete'd 6.13 HIGH RADI ATION AREA 6-15 l

6.14 _E_NVIRONMENTAL QUALIFICATION 6-16 s 6.15 PROCESS CONTROL PROGRA4 (PCP) 6-17 4

6.16 0FFSITE jpff CALCULATION MANUAL (0D04) ,

6-18 6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 6-19 (LIQUID, GA5EQU5, AND SDLID) 6.18 POSTACCIDENT SA'4PLING 6-22 Amendment No. 28,53,80,96 i

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l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

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LIST OF TABLES Table Page 4.21-1 RADI0 ACTIVE LIQUID WASTE SN4PLING AND ANALYSIS PROGRAM 4-70 4.22-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUkS FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE 4-88 REQUIREMENTS 4.34-1 METER 0 LOGICAL MONITORING INSTRUNENTATION 4-94 6.2-1 MINIMUM SHIFT CREW COMPOSITION 6-2 J

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0 Amendment 8o.14,33,sy,96

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, . RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES (Continued)

Figure 3.5.2-7 Core Imbalance vs. Power Level, O to 40 EFPD 3.5.2-8 Core Imbalance vs. Power Level, after 30 EFPD 3.5.2-9 Core Imbalance vs. Power Level, af ter 300 EFPD with APSRs Withdrawn 3.5.2-10 Deleted 3.5.2-11 Deleted 3.5.2-12 Deleted 3.5.4-1 Incore Instrumentation Specification Axial Imbalance Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication 3.5.4-3 Incore Instrumentation Specification 3.18-1 General Layout of Site 4.13-1 Main Steam Inservice Inspection 4.13-2 Main Feedwater Inservice Inspection 4.13-3 Main Steam Dump Inservice Inspection '

6.2-1 SMUD Corporate Support of Nuclear Safety to Rancho Seco 6.2-2 Nuclear Organization Chart I

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Amendment No. 26,28,29,48,E3,69,96 xii

. . RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.0 ADMINISTRATIVE CONTROLS .

6.1 RESPONSIBILITY 6.1.1 The Chief Executive Officer (CEO), Nuclear shall be responsible for the pianagement of the overall facility, and the Assistant General Manager (AG4), 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.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for the facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 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 i procedures shall be on site when fuel u 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 shift crew necessary for safe shutdown of the unit and any per3cnnel required for other essential functions during a fire emergency.

Fire Brigade composition may be less than the minimum requirements for a i 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 I absence provided immediate action is taken to fill the required positions.

Amendment No. 78,24.35,$7,96 6el l

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. RANCHO SECO UNIT 1

. . TECHNICAL SPECIFICATIONS Administrative Controls 6.2 ORGANIZATION .

FACILITY STAFF

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.

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 l operating. However, in the event that unforeseen problems ;

require substantial amounts of overtine 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 :

hours 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 sesen day period, all excluding shift turnover time.

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

work periods, including shift turnover time. ;

d. Except durin] 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 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 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 above guidelines is not authorized.

Amendment No. /3,96 6-la e f

4 RANCHO SECO UNIT 1 4

TECHNICAL SPECIFICATIONS Administrative Controis-TABLE 6.2-1 SHIFT.CREN PERSONNEL AND LICENSE REQUIREMENTS

l REACTOR MODE COLD OTHER THAN POSITION SHUTDOHN COLD SHUTDOHN Shift Supervisor SL l-SL Asst. Shift Supervisor or Control Room Operator 2-L 1-SL, 2-L Non-Licensed Operator 1 3 Shift Technical Advisor 0 1 Minimum Total Personnel 4 8 l In the event that any member of a minimum shift crew is absent or incapacitated due to illness or injury, a qualified replacement shall be designated to report on site within two hours. -

SL - NRC Senior Licensed Operator L - NRC Licensed Operator 5

i Amendment No. 31,96 6-2

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls e

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each ramber of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Manager, Radiation Protection so shall meet or exceed l the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor 40 shall have a bachelor's degree or equivalent in a scientific or engineering discipline. The STA shall receive specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the operating staff shall be maintained under the direction of the Manager, Training {

and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Training and shall meet or exceed the l requirements of Section 27 of the NFPA Code - 1975, except refresher classroom training shall be on a quarterly schedule.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the AGM, Nuclear Peer Production and the Management Safety Review Committee on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Committee shall be comoosed of a chairman, and a mini.um of six members.

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l Amendment No. 14,78,24,31,62.96 6-3 4

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS o -

Administrative Controls EMBERSHIP

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6.5.1.3 Memoership of the PRC shall be as defined below:

a. A list of members made up of personnel filling positions shown in the Nuclear Organization (Fig. 6.2-2) and others 40 meet or exceed the minimum qualifications of ANSI N18.1-1971 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 AGM, Nuclear Powr Production.

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

MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calencar month and as convened by the PRC Chairman, or as directed by the AGM, Nuclear Po wr Production.

QUORUM 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.

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 and changes thereto, and 2) any other proposed procedures or changes thereto sich are as determined by the AGM, Nuclear Power Production to affect nuclear safety.

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,

d. All safety evaluations of proposed changes or modifications to plant systems or equipment that affect nuciear 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. Investigaticns 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.

Amendment No. Rf,$7,p3,96 6-4

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls RESPONSIBILITIES (Continued)

g. All events requiring a Licensee Event Report as defined by 10CFR50.73 and NUREG 1022 to detennine adequacy of corrective action and to detect any degrading trend..

h. Special investigations and reports thereon as requested by the AGM, Nuclear Power Production.

1. The Plant Security Plan and changes thereto. '

j. The Emergency Plan and changes thereto.

k. Changes to the Process Control Program and the Offsite Dose Calculation Manual. (See Specifications 6.15 and 6.16.)

1. Major changes to the Radioactive Waste Treatment Systems (Liquid, Gaseous and Solid), and all information required by Specification 6.17.

AUTHORITY 6.5.1.7 The Plant Review Committee shall:

a. Recommend in writing to the AGM, Nuclear Power Production l approval or disapproval of items conside. red under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unrev'ewed safety question.

c. Provide immediate written notification to the Chairman of the Management Safety Review Committee cf disagreement between the PRC and the AGM, Nuclear Power Production; however, the AGM, Nuclear Power Production shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above.

RECORDS 6.5.1.8 Records of the PRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each PRC meeting, including appropriate documentation of reviews encompassed by Specification 6.5.1.6e and g, shall be ,

prepared, approved, and forwarded to the AGM, Nuclear Power

?roduction and to the Chainnan, Management Safety Review Comittee within fourteen (14) days following each meeting.

Amendment No. 7p,E2,63,96 6-5

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. . TECHNICAL SPECIFICATIONS Administrative Controls 6.5.2 Management Safety Review Committee (MSRC) ,

1 FUNCTION 6.5.2.1 The Management Safety RevicM Committee shall function to provide independent review and audic of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety i

9 mechanical and electrical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 The MSRC shall be composed of a chaiman and a minimum of eight members. The MSRC membership shall be made up of manager levels or above as shown on the Nuclear Organization (Fig. 6.2-2) or of other personnel meeting or exceeding the minimum qualifications of ANSI /ANS 3.1-1981, Section 4.7.2. ,

MEMBERSHIP 6.5.2.3 The Chairman of the MSRC 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 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 members described in Specification 6.5.2.2.

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Amendment No. 96 6-6

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RANCHO SECO UNIT 1 l TECHNICAL SPECIFICATIONS Administrative Controls 1 6.5.2.4 HEETING FRE00ENCY-The HSRC shall meet at least once per calendar quarter and as convened by the MSRC Chairman or as directed by the CEO, Nuclear.

OUORUM 6.5.2.5 A quorum of MSRC shall consist of a majority of the men 6ers listed in Specification 6.5.2.2, including the chairman or alternate chairman. No more than two alternates shall participate in MSRC activities at any one time for the purpose of establishing a quorum.

No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEH ,

6.5.2.6 The HSRC shall be responsible for review of:

a. The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.

c. Proposed tests or experimr;nts which involve an unreviewed safety question as defined in 10 CFR 50.59.

d. Proposed changes in Technical Specifications or the Operating License.

e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance,

f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g. Licensee Event Reports as defined by 10 CFR 50.73 and NUREG 1022.

h. Any indication of an identified significant deficiency in the design or operation of safety-relt.ted structures, systems, or components.

1. Reports and meeting minutes of the Plant Review Committee.

j. Any facility activity brought to the attention of the HSRC by ,

the District's executive management which may be indicative of l conditions adverse to nuclear safety.

Amendment No. 24.67,53,96 6-7 t

RANCHO SECO UNIT 1 3

TECHNICAL SPECIFICATIONS Administrative Controls

k. The HSRC.shall provide oversight review of: '

e The District Quality Program, including the Audit Program content and implementation, and audit reports.

The Radioactive Haste Control Program.

Effectiveness of the Licensee Event Report Program per Specification 6.6.1.

. AUTHORITY 6.5.2.7 The HSRC shall:

a. Report to and advise the CEO, Nuclear, of those areas of responsibility specified in Specification 6.5.2.6.

b. Recommend to the CEO, Nuclear, other areas of facility operation for which the HSRC has determined the need for additional auditing per Specification 6.5.4g.

c. Advise the CEO, Nuclear, of the need for independent auditing of facility operations.

RECORDS ,

6.5.2.8 Records of MSRC activities shall be prepared, approved, and distributed as indicated below:

a. Minutes of each MSRC meeting and separate documentation of reviews encompassed by Specifications 6.5.2.6d,e,f,g and h shall be prepared, approved, and forwarded to the CEO, Nuclear, within fourteen (14) days following each meeting.

6.5.3 TECHNICAL REVIEW AND CONTROL Activities which affect nuclear safety shall be conducted as follows:

a. n rocedures required by Technical Specification 6.8 and other proc 6dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an I individual (s) other than the preparer, but who may be from the same organization as the individual (s) that prepared the procedure or procedure change. Proadures other than plant i administrative procedures will be approved as delineated in writing by the AGH, Nuclear Power Production, but not lower than the department manager level. Such procedures shall be reviewed periodically in accordance with administrative procedures.

Amendment No. U ,53,J7,$),96 6-3 1

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a. (Continued) .

The AGil, Nuclear Power Production will approve plant administrative procedures, Security Plan Implementing Procedures and Emergency Plan Implementing Procedures.

Approval of temporary procedure changes which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. The change shall be documented, reviewed and approved by the procedures approval '

authority within fourteen (14) des of implementation.

b. Proposed changes or modifications to plant systems or equipment that affect nuclear safety shall be reviewed by an individual (s) other than the individual (s) who designed the modification, but who may be from the same organization as the individual (s) who designed the modifiedtfons. Such modifications shall be approved by the AGM, Nuclear Power Production or designee, but shall be no lower than a division director level,

c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Updated Safety Analysis Report shall be reviewed by an individual (s) other than the individual (s) who prepared the proposed test or experiment.

Such tests or experiments shall be approved by the AGM, Nuclear Power Production or designee, but shall be no lower than a division director level.

d. Events reportable pursuant to the Technical Specification 6.9

. and violations of Technical Specifications shall be investigated and a report prepared which evaluates the event and which provides recorxaendations to prevent recurrence. Such report shall be reviewed by the PRC and foNdrded to the AGM, Nuclear Power Production, and to the Chairman, MSRC.

e. Individuals responsible for reviews perfbrmed in accordance with 6.5.3.a. 6.5.3.b and 6.5.3.c shall meet or exceed the qualification requirements of Section 4.4 of ANSI 18.1, 1971.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deamed necessary, such review shall be perfonned by the review

' m annet c' the appropriate discipline. A list of qualiftee ,

e , ewers otr the independent reviews described in 6.5.3a., b.,

. above .... . % establisheo by the AGM, liuclear lawer cc Son Amendment No. 56 6-9

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

. . Administrative Controls AUDITS 6.5.4 Audits of facility activities shall be performed under the cognizance of the Of rector, Quality Assurance, Nuclear. The se-l audits shall encompass:

a. The confomance of facility operation to all provisions contained within the Technical Specifications and applicable ifcense conditions at least once per year.

b. The performance, training and qualifications of the District's l entire facility technical staff at least once per year.

c. The result of all actions taken to cr.Prect deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months for those changes not previously audited. l

d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two (2) years. I

e. The Facility Emergency Plan and implementing procedures at least once per two (2) years. I

f. The Facility Security Plan and implemen'cing procedures at least g once per two (2) years.

g. Any other area of facility operation considered appropriate by the Chief Executive Officer, Nuclear,

, h. Compliance with fire protection requirements and implementing procedures at least once per two (2) years.

1. An independent fire protection end loss prevention inspection and audit shall be perfomed annually utilizing either qualified offsite licei<see personnel or an outside fire protection fim.

j. An inspection and audit of the fire protection and loss prevention program shall be perfomed by an outside qualified fire consultant at intervals no greater than three (3) years. l

k. The radiological environmental monitoring program and the results thereof at least once per 12 months.

1. The OFFSITE 00SE CALCULATION 14ANUAL and implementing procedures at least once per 24 months,

m. The PROCESS CONTROL PROGRR4 for the SOLIDIFICATION of radioactive wastes from liquid systems at least once per 24 months.

Amndment No. 18,53,96 6-10 l

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O 8 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative C.ontrols Audit reports of reviews encompassed by Section 6.5.4 shall be forwaraed to the Chief Executive Officer, Nuclear, etSRC Chairman, and to the management positions reroons1L'e for the areas reviewed within 30 days af ter completion.

6.6 LICENSEE EVENT REPORT ACTION 6.6.1 The following actions a, hall be taken for events which are reportable ,

as LICENSEE EVENT REPORTS:

a. The Commission shall be notified and a report submitted per Specification 6.9.4, pursuant to the requirements of Section 50.73 to 100FR50, and

b. Each LICENSEE EVENT REPORT shall be reviewed by the PRC and the results of this review submitted to the r1SRC. Each LICENSEE EVENT REPORT shell be reviewed and approved by the Chief Executive Officer, Nuclear, or designee, t

Amendment No. 96 6-10a

' l RANCHO SECO UNIT.1 l TECHNICAL SPECIFICATIONS l Administrative Controls l

6. 7 ' SgETY LIMIT VIOLATION l 6.7.1 The follcwing actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36 (c) (1) (i) 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 cases within one hour. The Director, Nuclear Operations and Maintenance, the AG4, 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 prec: ding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrencJ., ,

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

> Commtssion, the MSRC, and the AG4, Nuclear Power Production, within 14 days of the violation. l l 6.8 PROCEDURES 6.8.1 Written procedures shall be established, finplemented and maintained covering the activities referenced below:

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a. The applicable procedures recommended in Appendix "A" of t Regulatory Guide 1.33, November 1972.

b. Refueling operations,

c. Surveillance and test activities of safety related equipment. i

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection P ocedures implementation.

g. Process control program implementation.

h. Offsite Dose Calculation Manual implementation.

. 1. Effluent arid environmental quality control program.

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

1 Amendment No. JB,H ,53,$7,96 6-11 T.

RANCHO SECO UNIT 1 TECHNICAL SPECIF! CATIONS Administrative Controls 6.9 REPORTING REQUIREMENTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

Startup Report 6.9.1.1 A besumary submittedreport of plant(1) following startup and Receipt ofpower escalation an operating testing)shall license; (2 amendment to the license involving a planned increase in power level; (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic perfonnance of the plant. The report shall address each of the tests identified in the USAR and shall include a description of the measured values of the operating conditions or characteristics obtained during l the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in ifcense conditions based on other commitments shall be included in this report.

6.9.1.2 Startup reports shall be submitted within (1) Ninety (90) days folloring completion of the startup test program; (2) Ninety (90) days '

following resumption or commencement of commercial power operation; or (3) Nine (9) months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program and resumption or commencement of comercial power operation),

supplementary reports shall be submitted at least every three (3) months until all three events have been completed.

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l Amendment No. 77,87,96 6-12

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.2.2 (Continued) .

The annual radiological environmental operating reports shall include sumarized and tabulated results of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a sumary description of the radiological environmental monitoring program; including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the result of land use censuses, and the results of licensee participation in the Interlab Comparison Program. The annual report shall also include information related to Specification 4.29.

6.9.2.3 SemtAnnual Radioactive Effluent Release Report Routine radioactive effluent release reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

i 6.9.2.3.1 The radioactive effluent release reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data sumarized on a quarterly basis, following the fonnat of Appendix B thereof.

The radioactive effluent release reports shall include the release of gaseous effluents during each quarter, as outlined in Regulatory Guide 1.21, with the data sumarized on a quarterly basis, following the fonnat of Appendix B thereof. A summary of l meteorological conditions during the release of gaseous effluents l will be retained on-site for two years. In addition, any changes i to the Offsite Dose Calculation Manual will be submitted with the Semiannual Radioactive Effluent Release Report.

l Amendment No. g3,g/,96 6-12b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 Continued) l The radioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the site boundary during the report period. All assumptfons used in making these assessments (e.g.,

specific activity, exposure time, and location) shall be included in these reports.

The radioactive effluent release reports shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved,

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence,

d. Consequences of the unplanned release.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gascous effluents released from the unit during each calendar quarter, as outline in Regulatory Guide 1.21. The releases of effluents shall be used for determining the ga,eous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (0D04).

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRNi (Pf,P) or (ODQi) made during the reporting period, as provided in Specifications 6.14 and 6.15.

MONTHLY REPORT 6.9.3 Routine reports of operating statistics, including narrative summary of operating and shutdown experiuce, of lif ts of the Primary System Safety Yalves or EMOVs, of major safety related maintenance, and tabulations of facility changes, tests or experiments required pursuant to 10 CFR 50.59(b). shall be submitted on a monthly basis to the Document Control Branch,- U. S. Nuclear Regulatory l Commission, Washir.gton, D. C. 20555, with a copy to the Regional '

, Office, postmarked no later than the 15th day of each month following the calendar month covered by the report.

LICENSEE EVENT REPORT 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including corrective action: and measures to prevent recurrence, shall be reported to the NRC as Licensee Event Reports. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a Licensee Event Report shall be completed and reference shall be made to the original report date, pursuant to the requirements of 10 CFR 50.73.

Amendment No. 77,0,E3,63,96 6-12c 7.____-------- - - _ - - - - - - - _ - - -

-6 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.6 Environmental Reports .

1. When a change to the plant design or to the plant operation is planned which would have a significant adverse effect on the

, environment or which involves an environmental matter or question not previously reviewed and evaluated by the NRC, a report on the change will be made to the NRC prior to implementation. The report will include a description and evaluation of the change including a supporting benefit-cost analysis.

2. Changes or additions to permits and certificates required by Federal, State, local and regional authorities for the protection of the environment will be reported. When the required changes are submitted to the concerned agency fc ipproval, they will also be submitted to the NRC for informacsors. The submittal will include an evaluation of the environmental impact of the change.

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Amendment No. 96 6212h

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID, GASEOUS, AND 5OLID) 6.17.1 Function The radioactive waste treatment system (if quid, gaseous, and solid) are those systems described in the facility Final Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are used to maintain that control over radioactive materials in gaseous and ifquid effluents and in solid waste packaged for offsite shipment required to meet the LCOs set forth in these Specifications.

6.17.2 Major changes to the radioactive waste systems (liquid, gaseous, and solid) shall be made by the following method. For the purpose of this specification, "major changes" is defined in Specification 6.17.3. l Licensee-initiated changes:

1. The Commission shall be informed of all changes by the inclusion of a suitable discussion of each change in the annual USAR update j for the period in which the changes were made. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made (in accordance with 10 CFR 50.59);

b. Sufficient information to support the reason for the change l without benefit of additional or supplemental information;

c. A description of the equipment, components, and processes involved, and the interfaces with other plant systems;

d. An evaluation of the change with regard to the predicted releases of radioactive materials in ifquid and gaseous effluents and/or quantity of solid waste if different from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change with regard to the expected maximum exposures to individuals at or beyond the SITE BOUNDARY and to the general population if different from those previously estimated in the license application and amendments thereto; Amendment No. 53,87,96 6-19

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. . RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS

, ,, , Administrative Controls 6.17.2 (Continued)

f. A comparison of the predicted releases of radioactive .

materials in liquid and gaseous effluents and in solid waste :

to the actual releases following perfonnance of the change for the period in which the changes were made; g.

An estimate a result ofchanges; of the the exposure and to plant operating personnel as I

h. Documentation of the fact that the change was reviewed and found acceptable by the PRC. l

2. The Change shall become effective upon review and acceptance by the PRC, and approved by the AG4, Nuclear Power Production per Specification 6.5.3b.

6.17.3 Background and definition of what constitutes "major changes" to radioactive waste systems (liquid, gaseous, and solid).

A. Background

1. 10 CFR Part 50, Section 50.34a(a) requires +. hat each application to construct a nuclear power reactor provide a description of the equipment instelled to maintain control over radioactive material in gaseous and liquid effluents produced during normal reactor operations, including operational occurrences.

2. 10 CFR Part 50, Section 50.34a (b) (2) requires that each application to construct a nuclear power reactor provide an estimate of the quantity of radionuclides expected to be released annually to unrestricted areas in liquid and gaseous effluents produced during normal reactor operations.

3. 10 CFR Part 50, Section 50.34a (b) (3) requires that each application to construct a nuclear power reactor provide a description of the provisions for packaging, storage, and shipment offsite of solid waste containing radioactive materials resulting from treatment of gaseous and liquid effluents and from other sources.

4. 10 CFR Part 50, Section 50.34a (c) rewires that each application to operate a nuclear power reactor shall include (1) a description of the equipment and procedures for the control of gaseous and liquid effluents and for the maintenance and use of equipment installed in radioactive waste systems, and (2) a revised estimate of the infonnation required in (b)(2) if the expected releases and exposures differ significantly from the estimate submitted in the construction permit.

Amendment No. H , 96 6-20 l

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ML20149M854

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