Text

Amend 158 to License DPR-13,revising Section 2.D of Plant, Unit 1 Operating License to Remove Reporting Requirement Redundant to Reporting Requirements in 10CFR50.72 & 50.73
	ML20128L714
Person / Time
Site:	San Onofre
Issue date:	10/03/1996
From:	Weiss S; NRC (Affiliation Not Assigned)
To:	;
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ML20128L692	List: ML20128L689; ML20128L714; ML20128L723;
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	NUDOCS 9610150173
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sMt REC

, O". k. UNITED STATES g g NUCLEAR REGULATORY COMMISSION o C WASHINGTON, D.C. 20555 4001 s,...../

SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ON0FRE NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. DPR-13

1. The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for amendment by Southern California Edison Company-(the licensee) and the San Diego Gas and Electric Company dated March 13, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by 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 regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied.

9610150173 961003 PDR ADOCK 05000206 P PDR 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.C.(2) and 2.0 of Facility Operating License No. DPR-13 are hereby amended to read as follows:

C.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.158, are hereby incorporated in the license. Southern California Edison Company shall maintain the facility in accordance with the Technical Specifications.

D. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in license conditions 2.C(l) and 2.C(3) in the following manner: initial notification shall be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).

3. This license amendment is effective as of the date of its issuance and shall be implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director l Non-Power Reactors and Decommissioning Project Directorate !

Division of Reactor Program Management Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance: october 3, 1996

i ENCLOSURE TO LICENSE AMENDMENT NO. 158 FACILITY OPERATING LICENSE NO. DPR-13 DOCKET N0. 50-206 1

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert D6.1-1 D6.1-1 D6.2-1 D6.2-1 1 D6.2-2 D6.2-2 '

D6.2-3 D6.2-3 D6.5-1 D6.5-1 D6.5-2 D6.5-2 D6.5-3 D6.5-3 l D6.5-4 D6.5-4 D6.5-6 D6.5-6 D6.5-7 D6.5-7 1 D6.6-1 D6.6-1 l D6.7-1 D6.7-1 D6.8-1 D6.8-1 D6.9-2 D6.9-2 D6.13-1 D6.13-1 D6.14-1 D6.14-1 1

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4 D6 ADMINISTRATIVE CONTROLS D6.1 RESPONSIBILITY D6.1.1 The Vice President - Nuclear Generation shall be responsible for l overall management of the plant and ensuring the safe storage and handling of irradiated fuel, and all site support functions.

He shall delegate in writing the succession to this responsibility in his absence. ;

D6.1.2 The Shift Supervisor (or during his absence from the Control Room Area,* a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice President - Nuclear Generation shall be reissued to all site / station personnel on an annual basis.

D6.1.3 Any emergency action which departs from a License Condition or Technical Specification, as permitted by 10 CFR 50.54(x), shall be approved, as a minimum, by a Certified Fuel Handler prior to taking the action.

" Control Room Area" is defined as the area interior to the control room entry doors.

SAN ON0FRE - UNIT 1 D6.1-1 AMENDMENT N0: 158

, D6.2 ORGANIZATION OFFSITE AND ONSITE ORGANIZATION D6.2.1 Onsite and offsite organizations shall be established for plant I management and corporate management, respectively. The onsite i and offsite organizations shall include the positions for !

activities affecting the safe storage and handling of irradiated fuel.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels i through intermediate levels to and including all organization positions involved with the safe storage and handling of irradiated fuel. 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 SONGS Topical Report Quality Assurance Program.

b. The Vice President - Nuclear Generation shall be responsible for overall unit safety and shall have control over those onsite activities necessary for the safe storage and handling of irradiated fuel.

c. The Vice President - Engineering & Technical Services and i the Vice President - Nuclear Generation shall have corporate '

responsibility for overall plant nuclear safety. The Vice President - Nuclear Generation shall take any measures needed to ensure acceptable performance of the staff in the safe storage and handling of irradiated fuel. The Vice President - Engineering & Technical Services shall take any measures needed to ensure acceptable performance of the staff in providing technical support to the plant to ensure the safe storage and handling of irradiated fuel.

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.

UNIT STAFF D6.2.2 a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table D6.2-1.

SAN ON0FRE - UNIT 1 D6.2-1 AMENDMENT N0: 158

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b. At least one individual qualified to stand watch in the Control Room (a Shutdown Control Room Operator or a 1 Certified Fuel Handler) shall be in the Control Room Area

I when fuel is in the spent fuel pool, unless Unit 2 or 3 l post-accident conditions allow only intermittent manning of i the Control Room. The requirements for transfer of the Control Room Command Function contained in Specification D6.1.2 and Table D6.2-1 are not applicable if the Control Room is manned intermittently.

c. A health physics technician shall be on-site when fuel is in the spent fuel pool. A health physics technician normally assigned to Units 2 and 3 may fulfill this function.

d. All FUEL HANDLING OPERATIONS shall be observed and directly supervised by a Certified fuel Handler who has no other concurrent duties during this operation.

e. Administrative procedures shall be developed and implemented l to limit the working hours of unit staff who perform safety functions (e.g., operators responsible for the safe storage l and handling of irradiated fuel, health physicists, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:

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, excluding 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 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24** hours in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 1 day period, all excluding shift turnover time; '

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.

Any deviation from the above guidelines shall be authorized '

by the Vice President - Nuclear Generation, or designee, in l accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

" Control Room Area" is defined as the area interior to the control room entry doors.

- Personnel regularly assigned to 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts may work up to 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period.

SAN ON0FRE - UNIT 1 D6.2-2 AMENDMENT NO: 158

i Controls shall be included in the procedures such that

. individual overtime shall be reviewed monthly by the Vice President - Nuclear Generation, or designee, to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

f. The Plant Superintendent (at time of appointment) shall be a Certified Fuel Handler or shall have previously held an SR0 license for the unit.

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SAN ONOFRE - UNIT 1 D6.2-3 AMENDMEN1 N0: 158

D6.5 REVIEW AND AUDIT D6.5.1 ONSITE REVIEW COMMITTEE (0SRC)

FUNCTION D6.5.1.1 The Onsite Review Committee (OSRC) shall function to advise the Vice President - Nuclear Generation on all matters related to l nuclear safety.

! COMPOSITION

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1 D6.5.1.2 The Onsite Review Committee shall be composed of the:

i i Chairman: Vice President - Nuclear Generation I i Member: Manager, Operations

! Member: Manager, Technical

] Member: Plant Superintendent Unit 1

Member: Manager, Health Physics Member: Manager, Chemistry Member: Manager, Maintenance i Member: San Diego Gas & Electric Representative, Senior Engineer

j ALTERNATES

, 06.5.1.3 All alternate members shall be appointed in writing by the OSRC 1

Chairman to serve on a temporary basis; however, no more than i two alternates shall participate as voting members in OSRC

! activities at any one time. I i

MEETING FRE0VENCY 1

. D6.5.1.4 The OSRC shall meet at least once per calendar month and as 1

convened by the OSRC Chairman or his designated alternate. The Chairman may decrease the frequency of the OSRC meetings to a minimum of once per six months if warranted by a decrease in activity in the unit.

OV0 RUM D6.5.1.5 The minimum quorum of the OSRC necessary for the performance of the OSRC responsibility and authority provisions of these

', Technical Specifications shall consist of the Chairman or his

designated alternate and four members including alternates.

BS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four years experience shall be nuclear power plant experience.

SAN ON0FRE - UNIT 1 D6.5-1 AMENDMENT NO: 158

RESPONSIBILITIES D6.5.1.6 The Onsite Review Committee shall be responsible for:

a. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Nuclear Safety Group (NSG).

b. Review of all REPORTABLE EVENTS.

c. Review of irradiate,. fuel storage and handling, and radioactive waste operations to detect potential nuclear safety hazards.

d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Vice President -

Nuclear Generation or the NSG Supervisor.

AUTHORITY D6.5.1.7 The Onsite Review Committee (OSRC) shall:

a. Render determinations in writing with regard to whether or not items considered under D6.5.1.6.a above constitute unreviewed safety questions.

b. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President - Engineering & Technical Services, and the NSG Supervisor of disagreement between the OSRC and the Vice President - Nuclear Generation; the Vice President -

Engineering & Technical Services shall have responsibility for resolution of such disagreements.

RECORDS D6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Nuclear Safety Group Supervisor.

j SAN ON0FRE - UNIT 1 D6.5-2 AMENDMENT NO: 158

' e D6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES D6.5.2.1 The Vice President - Nuclear Generation shall assure that each procedure and program required by Specification D6.8 and other procedures which affect nuclear safety, and changes thereto, is prepared by a qualified individual / organization. Each such procedure, and changes thereto, shall be reviewed by an ,

individual / group other than the individual /grou) which prepared the procedure, or changes thereto, but who may 3e from the same organization as the individual / group which prepared the procedure, or changes thereto. Documentation of these activities shall be provided to the NSG Supervisor.

D6.5.2.2 Proposed changes to the Technical Specifications shall be !

prepared by a qualified individual / organization. The j preparation of each proposed Technical Specifications change l shall be reviewed by an individual / group other than the i individual / group which prepared the proposed change, but who may i be from the same organization as the individual / group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the Vice President - Nuclear Generation. Documentation of these activities shall be provided to the NSG Supervisor.

1 D6.5.2.3 Proposed modifications to unit nuclear safety-related l structures, systems and components required to be operational l for the safe storage and handling of irradiated fuel shall be i designed by a qualified individual / organization. Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification. Proposed modifications to nuclear safety-related structures, systems and components required to be o)erational for the safe storage and handling of irradiated fuel s1all be approved prior to implementation by the Vice President

- Nuclear Generation or by the Manager, Technical as previously designated by the Vice President - Nuclear Generation.

Documentation of these activities shall be provided to the NSG Supervisor.

D6.5.2.4 Individuals responsible for reviews performed in accordance with D6.5.2.1, D6.5.2.21nd D6.5.2.3 shall be members of the nuclear division management staff, previously designated by the Vice President - Nuclear Generation to perform such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary and a verification that the proposed actions do not constitute an unreviewed safety question. If deemed necessary, such review shall be performed by the appropriate designated review personnel.

SAN ON0FRE - UNIT 1 06.5-3 AMENDMENT N0: 158

D6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in tha FSAR.or Technical Specifications shall be reviewed by the Vice President - Nuclear Generation or members of the nuclear division management staff, as previously designated by the Vice President - Nuclear Generation. Documentation of these activities shall be provided to the NSG Supervisor.

D6.5.2.6 The Site Security Plan and implementing procedures shall be I reviewed at least once per 12 months. Recommended changes to the Site Security Plan shall be approved by the Vice President -

Nuclear Generation and transmitted to the NSG Supervisor; implementing procedures shall be prepared and approved in accordance with Specification D6.8.

D6.5.2.7 The Site Emergency Plan and implementing procedures shall be I reviewed at least once per 12 months. Recommended changes to the Site Emergency Plan shall be approved by the Vice President

- Nuclear Generation and transmitted to the MG Supervisor; l implementing procedures shall be preparea and approved in accordance with Specification D6.8.

D6.5.2.8 The Vice President - Nuclear Generation shall assure the l parformance of a review by a qualified individual / organization of every uncontrolled or unplanned release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence to I the NSG.

D6.5.2.9 The Vice President - Nuclear Generation shall assure the l performance of a review by a qualified individual / organization and may designate the approval of changes to the PROCESS CONTROL PROGRAM, 0FFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. Documentation of these activities shall be provided to the NSG Supervisor.

D6.5.2.10 Documentation of each of the activities performed under Specifications D6.5.2.1 through D6.5.2.9 shall be maintained in accordance with Specification D6.10.

l SAN ON0FRE - UNIT 1 D6.5-4 AMENDMENT N0: 158 l

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

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes to Technical Specifications or this Operating (Possession Only) License.

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

f. All REPORTABLE EVENTS.

g. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or components that are required to be operational for the safe storage and handling of irradiated fuel,

h. Reports and meeting minutes of the Onsite Review Committee.

AUDIT '

D6.5.3.5 Audits of unit activities shall be performed under the '

cognizance of the NSG. These audits shall encompass:

a. The conformance of irradiated fuel storage and handling operations to the provisions contained within the_ Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months.

c. The results of the actions taken to correct deficiencies occurring in safety-related structures, systems, or components that are required to be operational for the safe storage and handling of irradiated fuel, or in their method of operation, at least once per 12 months.

d. The performance of the activities required by the Quality Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

e. Any other area considered appropriate by the Nuclear Safety Group Supervisor or the Vice President - Nuclear Generation. l SAN ON0FRE - UNIT 1 D6.5-6 AMENDMENT N0: 158

The Fire Protection Program and implementing procedures at f.

least once per 24 months.

g. An independent fire protection and loss prevention inspection and audit shall be performed annually, utilizing l d

either qualified offsite licensee personnel or an outside

, fire protection firm.

h. An inspection and audit of the fire protection and loss prevention program shall be performed ty a qualified outside l

} fire consultant at intervals no greater than 36 months.

AUTHORITY r

i D6.5.3.6 The NSG shall report to and advise offsite organization management on thoso areas of responsibility specified in Sections D6.5.3.4 and D6.5.3.5.

RECORDS D6.5.3.7 Records of NSG activities shall be prepared and maintained.

Reports of reviews and audits shall be distributed monthly to the Vice President - Nuclear Generation and to the management positions responsible for the areas audited.

SAN ON0FRE - UNIT 1 D6.5-7 AMENDMENT N0: 158

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l D6.6 REPORTABLE EVENT ACTION D6.6.1 The following action shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notifiec .nd a report submitted pursuant to the requirements of Section 50.73, 10 CFR Part 50, and

b. Each REPORTA8LE EVENT shall be reviewed by the OSRC, and the results of this review shall be submitted to the Vice President

- Nuclear Generation and to the NSG Supervisor.

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SAN ON0FRE - UNIT 1 D6.6-1 AMENDMENT N0: 158

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j D6.7 SAFETY LIMIT VIOLATION i D6.7.1 The following actions shall be taken in the event a Safety Limit is a violated.

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a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President - Nuclear Generation and the NSG Supervisor shall be l

} notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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b. A Safety Limit Violation Report shall be prepared. The report 4

shall be reviewed by the OSRC. This report shall describe (1) ;

applicable circumstances preceding the violation, (2) effects 1 1 of the violation upon facility components, systems or

structures, and (3) corrective action taken to prevent i recurrence.

1 i c. The Safety Limit Violation Report shall be submitted to the j Commission, the Vice President - Nuclear Generation, and the

NSG within 14 days of the violation.

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4 SAN ON0FRE - UNIT 1 D6.7-1 AMENDMENT N0: 158

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D6.8 PROCEDURES AND PROGRAMS D6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February, 1978.

b. Fuel handling operations.

c. Surveillance and test activities of safety-related equipment required to be operational for the safe storage and handling of irradiated fuel.

d. Security Plan implementation,

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, Revision 1, February, 1979.

J. " Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls and Quality Assurance," June 14, 1977, as specified in Section 6 of the Fire Protection Safety Evaluation Report dated July 19, 1979.

D6.8.2 Each procedure of D6.8.1 above, and changes thereto, shall be approved by the Vice President - Nuclear Generation; or by the l responsible Nuclear Division Manager; or by their designees as previously designated by the Vice President - Nuclear Generation, l prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

D6.8.3 Temporary changes to the procedures of D6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

1 SAN ON0FRE - UNIT 1 D6.8-1 AMENDMENT N0: 158

AM(!jAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

D6.9.1.4 Routine radioactive effluent release reports covering the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit. The report shall also include a summary of the quantities of solid radioactive waste shipped from the unit di-ectly to the disposal site and the quantities of solid radioactive waste shipped from the unit's intermediary processor to the disposal site. The material provided shall be (1) consistent with the objectives outlined in the ODCH and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.8.1 of Appendix I to 10 CFR Part 50.

SPECIAL REPORTS !

D6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory l Commission, Attention: Document Control Desk, Washington D.C. 20555 with a copy to the Regional Administrator of the Regional Office of the NRC, within the time period specified for each report.

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A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SAN ON0FRE - UNIT 1 D6.9-2 AMENDMENT N0: 158

D6.13 PROCESS CONTROL PROGRAM D6.13.1 The Process Control Program (PCP) shall be approved by the Commission prior to implementation.

D6.13.2 Licensee-initiated changes to the PCP:

1. Shall be documer,ted and records of reviews performed shall be retained as required by Specification D6.10.2. The documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s);

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations; and

c. Documentacion of the fact that the change has been reviewed and found acceptable pursuant to 06.5.2.

2. Shall become effective upon review and approval pursuant to 06.5.2 by the Vice President - Nuclear Generation.

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SAN ON0FRE - UNIT 1 D6.13-1 AMENDMENT N0: 158

4 D6.14 0FFSITE DOSE CALCULATION MANUAL D6.14.1 The Offsite Dose Calculation Manual (0DCM) shall be approved by the

Commission prior to implementation.

. D6.14.2 Licensee-initiated changes to the ODCH:

1. Shall be submitted to the Commission in the Annual Radioactive :

Effluent Release Report for the period in which the change (s) )

1 was made effective. This submittal shall contain: j

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s);

i l b. A determination that the change will maintain the level of

radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of j effluent, dose, or setpoint calculations; and

c. Documentation of the fact that the change has been reviewed and found acceptable pursuant to 06.5.2.

2. Shall become effective upon review and approval pursuant to D6.5.2 by the Vice President - Nuclear Generation.

3. Shall be submitted to the Commission in the form of a complete, l legible copy of the entire ODCM as part of or concurrent with I the Annual Radioactive Effluent Release Report for the period i of the report in which any change to the ODCM was made. Each !

change shall be identified by markings in the margin of the ;

affected pages, clearly indicating the area of the page that '

was changed, and shall indicate the date (month / year) the change was implemented.

SAN ON0FRE - UNIT 1 06.14-1 AMENDMENT N0: 158

ML20128L714

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