ML20147B345

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Forwards Proposed Changes to Tech Specs & Environ Tech Specs Listing New Job Titles & Organizational Duties
ML20147B345
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 09/22/1978
From: Cavanaugh W
ARKANSAS POWER & LIGHT CO.
To: Reid R, Stolz J
Office of Nuclear Reactor Regulation
References
1-098-8, 1-98-8, NUDOCS 7810100081
Download: ML20147B345 (5)
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'd A' RKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4422 September 22, 1978 WILLIAM CAVANAUGH lli -

Executive Director Generetion & Construction 1-098-8 2-098-14 L

Director of Nucicar Reactor Regulation  ;

ATTN: h!r. J. F. Stolz, Chief Light Water Reactors Branch #1 ATTN: Mr. R. W. Reid, Chief Operating Reactor Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

Arkansas Nuclear One - Units 1 6 2 Docket No. 50-313 50-368 License No. DPR-51 NPF-6 Proposed Technical Specifications (File: 1511.1)

Gentlemen:

Picase find enclosed proposed changes to the Arkansas Nuclear One l (Units 1 and 2) Technical Specifications and Environmental Technical Specifications for your review and approval.

The proposed changes precede an implementation of a ree p nization in the Arkansas Nuclear One (ANO) plant staff. Since inception, AN0's staff has expanded dynamically and with Unit 2 becoming operational, some organizational units were in need of new definitions of responsibilities.

These units were regrouped and new. position titles that better reflect

, functions were established. The following provides a summary of the-changes:

New Title Present Title General Manager Plant Manager Operations G Maintenance Manager Plant Administrative Manager Assistant Plant Manager Engineering 6 Technical Support Manager Instrumentation S Controls Superintendent Instrumentation G Controls Supervisor Operations Superintendent No Change Maintenance Superintendent No Change l N

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i 1-098-8 2-098-14 Mr. J. F. Stolz Mr. R. W. Reid Septhmber 22, 1978 New Title Present Title Quality Control Supervisor New Position Planning 6 Scheduling Supervisor Planning 6 Scheduling Coordinator Technical Analysis Superintendent Technical Support Engineer Plant Analysis Superintendent New Position Plant Engineering Superintendent New Position Records 6 Administrative Superviso: No Change Security Coordinator New Position lluman Resources Supervisor New Position Material Manas.ement Supervisor New Position Fire 6 Safety Control Coordinator New Position Nuclear Suppo:ct Supervisor Nuclear Engineer Plant Performance Supervisor Performance Engineer Supervisor Computer Support Supervisor Computer Engineer Mechanical Engineering Supervisor New Position Electrical Engineering Supervisor New Position We have also taken this opportunity to revise the Unit 1 Administrative Controls (Section 5) of the Environmental Technical Specifications. This revision will make the station (ANO) environmental technical specifications current and consistent between units.

We have determined these changes to be purely administrative in nature per 10 CFR 170. Therefore, the Unit 1 amendment is Class II and will require a #1200 fee. The Unit 2 amendment is a duplicate and is identified as Class 1, with a fee of S400. We have enclosed our check for $1600 as payment.

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i 1-098-8 2-098-14 Mr. J. F. Stolz Mr. R. W. Reid September 22, 1978 Very truly yours, 3 7

/ W William Cavanaugh III Executive Director Generation 6 Construction-WC: ERG:vb Enclosure 2 -

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STATE OF ARKANSAS )

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t William Cavanaugh III, being duly sworn, states that he is Executive Director, Generation 6 Construction, for Arkansas Power 6 Light Company; that he is authorized on the part of said Co=pany to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained ,

in such information, and that all such statements made and catters set

. forth therein are true and correct to the best of his knowledge, infor=a-tion and belief.

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William Cava III SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this 1% day of

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.My Comcission Expires:

February 17, 19S2 I

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1. The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1. Any changes will be submitted as a Technical Specification change request within 30 days of implementation.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2-2A, B, C, and D. Any changes will be submitted as a Technical Specification change request within 30 days of implementation.

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

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained and shall meet or exceed the require-ments 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 fire protection training shall be maintained and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 with the exception of frequency of training which shall be six times per year.

6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Committee shall function to advise the General l Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Safety Cocmittee shall be composed of the:

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H EXECUTIVE DIRFCTOR i-CENT.RATIGN 5 CCN3IRt!CT10'1 SAFELY REVIDi Cor71ITTFE k

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Chairman: Operations and Maintenance Manager Member: Technical Analysis Superintendent Member: Instrumentation and Controls Superintendent -'

Member: Operations Superintendent .

Member: Maintenance Superintendent ,

Member: Plant Analysis Superintendent #

Member: Health Physict Supervisor l The General Manager shall appoint in writing an acting chairman in the absence of the Operations and Maintenance Manager.

ALTERNATES j

6.5.1.3 All alternate members shall be appointed in writing by_the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities ,

at any one time.

MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least once per calendar month and as con-vened by the PSC Chairman or his designated alternate.

QUORUM i

6.5.1.5 A quorum of the PSC shall consist of the chairman and three members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:

a. Review of !) all procedures required by Specification 6.8 L

and revisions thereto, 2) any other proposed procedures or revisions thereto as determined by the General Manager to l. [

affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.  ;
c. Review of all proposed changes to the Appendix "A" Tech-nical Specifications.
d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. ,
e. Investigation of all violations of the l'echnical Specifi--
  • cations involving activities under the responsibility of the General Manager, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager. .  ;

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f. Review of those Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ,

notification of the Commission. j

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g. Review of facility operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations and reports thereon a3 requested by the General Manager. l
i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the General Manager.

J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the General Manager. l AUT110RITY 6.5.1.7.1 The Plant Safety Committee shall:

a. Recommend to the General Manager written approval or dis- l approval of items considered under 6.5.1.6(a) through (d) above.
b. Render determinationr in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.

6.5.1.7.2 In the event of a disagreement between the recommendations of the Plant Safety Committee and the actions contemplated by the General Manager, the course determined by the General Manager l to be more conservative will be followed. Records of the dis-agreement will be sent for review to the Director, Generation Operations, or Manager, Nuclear Operations and the Chairman of the Safety Review Committee by the General Manager on the next working l day.

RECORDS 6.5.1.8 The Plant Safety Committee shall maintain written minutes of each meeting and copies shall be provided to the Chairman of the Safety Review Committee by the General Manager.

6.5.2 Safety Review Committee (SRC)

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

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry ,

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d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. environmental considerations
1. other appropriate ficids required by the unique characteristics of the nuclear power plant.

COMPOSITION 6.5.2.2 The SRC shall be composed of the:

Chairman: Director, Generation Operations Member: Director, Generation Technology Member: Director, Technical and Environmental Services Member: Manager of Safety Member: Arkansas Nuclear One General Manager l Member: Manager, Technical Analysis Member: Arkansas Nuclear One Plant Analysis Superintendent l Member: Director, Generation Engineering Member: Radiation and Health Physics Consultant Member: Nuclear Safety Consultant In his absence, the Chairman shall appoint an Acting Chairman.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utili:ed as determined by the SRC Chairman to provide expert advice to the SRC.

MEETING FREQUENCY 6.5.2.5 The SRC shall meet a least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum of SRC shall consist of the Chairman or his designated alternate and four members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

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REVIEW 6.5.2.7 The SRC shall review:

a. The safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
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 in Technical Specifications or licenses.
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. Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission.
h. Reports and meeting minutes of the PSC.

AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at 1 cast once per year.
b. The performance and retraining of all members of the plant management and operations staff, and the performance, training, and qualifications of new members of the entire plant staff at least once per year.
c. The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d. The Facility Emergency Plan and implementing procedures at least once per two years.
c. The Facility Fire Protection Program and implementing pro-cedures at least once per 24 months.

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f. The Facility Security Plan and impicmenting procedures at Icast once per two years.
g. Any other area of facility operation considered appropriate by the SRC or the Executive Director, Generation 6 Construction (EDG6C).

6.5.2.9 Special Inspections and Audits A. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm. ,

AUTHORITY 6.S.2.10 The SRC shall report to and advise'the Executive Director, Generation and Construction (EDG6C) within 30 days following each meeting. (

RECORDS i 6.5.2.11 Records of SRC activities shall be prepared, approved and dis-tributed as indicated below:

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the Executive Director, Generation 6 Construction i (EDG6C) within 30 days following each meeting.  ;
b. Reports of reviews encompassed by Section 6.5.2.7.c, f, g and h above, shall be prepared, approved and forwarded to the Executive Director, Generation 6 Construction. (EDG6C) within 30 days following completion of the review. ,
c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Director, Generation 6 Construction (EDG6C) and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 RUPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for Reportable Occurrences:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.
b. Each Reportable Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PSC and submitted to the SRC and the Manager, Nuclear Operations by the General l Manager.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

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a. The facility shall be placed in at least hot shutdown within one hour.
b. The Nuclear Regulatory Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.12.3.1 6.8 PROCEDURES 6.8.1 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, November,1972.
b. Refueling operations.
c. Surveillance and test activities of safety related equipment.
d. Security Plan implementation.
e. Emergency Plan impicnentation.
f. Fire Protection Program implementation.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the General Manager prior l to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.
b. The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c. The change is documented, reviewed by the PSC and approved by the General Manager within 14 days of implementation. l

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1 ii TABLE OF CONTENTS (Cont'd)

Page 3.0 DESIGN FEATURES AND OPERATING PRACTICES . . . . . . . . . . . . . 3-1 3.1 Intake System . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Discharge System . . . . . . . . . . . . . . . . . . . . . 3-1 3.3 Chemical Usage . . . . . . . . . . . . . . . . . . . . . . 3-1 3.4 Plant Shutdown . . . . . . . . . . . . . . . . . . . . . . 3-1 3.5 Land Management . . . . . . . . . . . . . . . . . . . . . . 3-1 4.0 ENVIRONMENTAL SURVEILLANCE . . . . . . . . . . . . . . . . . . 3-1 4.1 Nonradiological Environmental Surveillance . . . . . . . . 4-1 4.1.1 Abiotic . . . . . . . . . . . . . . . . . . . . 4-1 4.1.2 Biotic . . . . . . . . . . . . . . . . . . . . . 4-7 4.2 Radiological Environmental Monitoring . . . . . . . . . . . 4-13 4.2.1 Air Sampling . . . . . . . . . . . . . . . . . . . 4-13 4.2.2 Direct Radiation . . . . . . . . . . . . . . . . . 4-13 4.2.3 Precipitation Sampling . . . . . . . . . . . . . . 4-13 4.2.4 Lake Dardanelle . . . . . . . . . . . . . . . . . . 4-14 4.2.5 Ground Water Sampling . . . . . . . . . . . . . . . 4-14 4.2.6 Russellville City Water . . . . . . . . . . . . . . 4-14 4.2.7 Reservior Bottom Sediments . . . . . . . . . . . . 4-14 4.2.8 Aquatic Biota . . . . . . . . . . . . . . . . . . . 4-14 4.2.9 Fish Bone . . . . . . . . . . . . . . . . . . . . . 4-14 4.2.10 Milk Sampling . . . . . . . . . . . . . . . . . . . 4-15 4.2.11 Vegetation Sampling . . . . . . . . . . . . . . . . 4-15 4.2.12 Soil Sampling . . . . . . . . . . . . . . . . . . . 4-15 5.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Responsibility . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 Organization . . . . . . . . . . . . . . . . . . . . . . 5-1 5.3 Review . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.3.1 Plant Safety Committee . . . . . . . . . . . . . . . 5-1 5.3.2 Safety Review Committee . . . . . . . . . . . . . . . 5-2 5.4 State and Federal Permits and Certifications . . . . . . . 5-3

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iii Page 5.5 Procedures . . . . . . . . . . . . . . . . . . . . . . . 5-3 5.6 Station Reporting Requirements . . . . . . . . . . . . . . 5-4 5.6.1 Routine Reports . . . . . . . . . . . . . . . . . . 5-4 5.6.2 Non-Routine Reports . . . . . . . . . . . . . . . . . 5-5 5.7 Changes . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6 5.7.1 Changes in Environmental Technical Specifications . . 5-6 5.7.2 Changes in Permits and Certifications . . . . . . . . 5-6 5.7.3 Changes in Procedures, Station Design or Operation . 5-7 5.8 Records Retention . . . . . . . . . . . . . . . . . . . . . 5-8 5.8.1 Records and Logs Retained for Life of the Plant . . . 5-8 5.8.2 All Other Records . . . . . . . . . . . . . . . . . . 5-8 6.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES . . . . . . . 6-1 6.1 Thermal Plume Mapping . . . . . . . . . . . . . . . . . . . 6-1 6.2 Fish Spawning Characteristics of Dardanelle Reservoir . . . 6-2 6.3 Diel Changes in Impingement Levels . . . . . . . . . . . . 6-3 6.4 Cove Rotenone Surveys . . . . . . . . . . . . . . . . . . . 6-4

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2-5 2.2 liydraulic 2.2.1 Intake Velocity A study will be undertaken as described in Section 4.1.2 to determine means of limiting fish impingement on the traveling water screens.

2.2.2 Discharge Velocity Not Applicable.

2.2.3 Reservior Drawdown Not Applicabic.

2.3 Chemical Objective (General)

To protect the local biota from lethal and sublethal effects or chemical discharges. To assure that the most sensitive use of the receiving medium by human populations is protected. To minimize degradation of the quality of the receiving medium.

Specification (General)

All plant chemical discharges except that from the plant sanitary system shall be diluted by the plant circulating water during release to assure that the stated objective can be achieved. No release of demineralizer waste shall be made without a dilution equivalent to one-half (approxi-mately 383,000 gpm) the full flow of the Unit I circulating water pumps.

Any limitation on the quality of plant effluents and requirements for monitoring the same imposed under conditions of the Federal Water Pollution Control Act shall be a part of these Technical Specifications.

All reports to State or Federal agencies regarding compliance with any such limitation shall also be provided to NRC as described in Specification 5.4. 1 l

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s 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility Corporate responsibility for implementation of the Environmental Technical Specifications, and for assuring that station operations are controlled to provide protection for the environment has been assigned to the Executive Director of Generation and Construction.

The ANO General Manager, through the Engineering and Technical Support Manager, and Technical Analysis Superintendent shall be responsible for compliance with the Environmental Technical Specifications at the plant level.

The Manager of Technical Analysis shall be responsible for radio-logical analysis of environmental samples.

5.2 Organization Figure 5-1 shows the organization chart at both plant and corporate levels relative to environmental matters.

5.3 Review 5.3.1 Plant Safety Committee The Planc Safety Committee (PSC) shall be responsible for review of the lo11owing:

a. Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes.
b. Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's environmental impact.

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c. Proposed changes or modifications to plant systems or equipment which would affect the plant's environmental impact.
d. Results of the Environmental Monitoring Programs.
c. Investigation of all reported instances of violations of Environmental Technical Specifications invulving activities under the responsibility of the General Manager. Where in-vestigation warrants, instances shall be evaluated and recommendations formulated to prevent recurrence.

5.3.2 Safety Review Cormnittee The Safety Review Committee (SRC) shall be responsibic for review of the following:

a. The environmental evaluations for 1) changes to pro-cedures, equipment or systems and 2) tests or experiments completed under Section 5.7.3, to verify that such actions did not constitute an unreviewed environmental question.
b. Proposed changes to procedures, equipment or system which involve an unreviewed environmental question as defined i

in Section 5.7.3.B.

c. Proposed changes to the Environmental Technical Specifi-l l cations and the evaluated impact of the changes.
d. Results of the Environmental Monitoring Programs.
c. Investigation of all reported instances of violations of Environmental Technical Specifications.

5-2

V 5.4 ' State and Federal Permits and Certificates .

' Copies of reports to federal and state agencies regarding compliance of limitation on quality of liquid effluent from ANO-1 shall be I sent to Director of Regional Inspection and Enforcement Office (cc Director, NRR).

5.5 Procedures Detailed written procedures shall be prepared and followed for E all activities performed by Arkansas Power and Light. involved in carrying out the sampling, instrument calibration, analysis, and actions to be taken when limits are approached or exceeded. ,

Testing frequency of any alarms shall be included. Theso fre-quencies shall be determined from experience with similar ,

instruments in similar environments and from manufacturers' -

technical manuals.

Plant standard operating procedures shall include provisions to ensure the plant and all its systems and components are operated in compliance with the limiting conditions for operations established as part of the-environmental technical I specifications.

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k i

e 5-3 I

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5.6 Station Reporting Requirements 5.6.1 Routine Reports Annual Environmental Operating Report A single report on the environmental monitoring programs conducted in association with ANO-1 (Docket No. 50-313) and ANO-2 (Docket No. 50-368) operations for the previous calendar year shall be submitted to the NRC by May 1 of each year. The report shall include summaries, analyses, interpretations, and, where appropriate , statistical evaluation of the results of the environmental monitoring and an assessment of the observed impacts of the station operation on the environment. If harmful effects or evidence of irreversible damage are suggested by the monitoring or special programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem.

The Annual Report shall also include a summary of:

1) All ETS noncompliances and the corrective actions taken to remedy them.
2) Changes made to state and federal permits and certificates.
3) Changes made to the procedures or design described in accordance with Subsection 5.7.3.
4) Changes in ETS.

5-4

5.6.2 Nonroutine Reports A report shall'be submitted in'the event that a " Limiting Condition for Operation" (Section 2), is exceeded, a report.

level as-specified in Section 3 or 4 is reached, or if an unusual event involving a significant environmental impact '

occurs. Reports shall be submitted under one of the report

  • schedules described below. ,

1 5.6.2.a Prompt Report Those events.specified as prompt report occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.

5.6.2.b Thirty Day Report Non-routine events not requiring a prompt report as described -

in Subsection 5.6.2.a, shall be reported to NRC within 30 days '

of their occurrence.

5.6.2.c Content of Non-routine Reports Written 30-day reports.and, to the extent possible, the pre-liminary telephone, telegraph, or facsimile reports shall a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of occurrence, and (c) indicate the corrective action (in-cluding any significant changes made in procedures) taken to  ;

preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

5-5 '

F

. , , - , . _ . . . , - . . - . . . . . . , _ . . . . . . . . _ _ . . . , . , , , , ~ , . . . , . , . _ . - . . . . . . . . , _ ~ , , . , * , . , , ,_m.. . . , , . _ , ... ,, ,,, ,

5.7 Changes 5.7.1 Changes in Environmental Technical Specifications Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90. The request shall include an evaluation of the environmental impact of the proposed changes and a supporting justification.

5.7.2 Changes in Permits and Certifications Changes or additions to required federal, state, local, and regional authority permits and certificates for the protection of the environment that pertain to the requirements of these ETS shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Section 401 or 402 of PL 92-500 which is also the subject of an ETS reporting requirement under Section 2, or 4 of this ETS, NRC shall be notified within 30 days. If the proposed change is initiated by the licensee, the notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.

5-6

a 5.7.3 Changes in Procedures, Station Design or Operation.

A. The' licensee may 1) make changes in the station design and operation, 2) make changes in the procedures described in Subsection 5.5, and 3) conduct tests and experiments not described in accordance with. Subsection 5.5, without prior Commission approval, unless the proposed change, test or-experiment involves a change in the objectives of the ETS, or an unreviewed environmental question of substantive impact.

t B. A proposed change, test or experiment shall be deemed to in- ,

1 volve an unreviewed environmental question if it concerns 1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final i environms. al impact statement as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements thereto, environmental impact appraisals, or in initial or final adjudi-catory decisions; or 2) a significant change in effluents or i power level as specified in 10 CFR 51.5(b)(2); or 3) a matter i not previously reviewed and evaluated in the documents specified in 1) of this section which may have a significant adverse en-vironmental impact.

C. The licensee shall maintain records of changes in procedures and l l

in the facility design ce operation made pursuant to this <

Subsection, to the extent that such changes constitute changes 5-7 l'

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in procedures as described in accordance with Subsection 5.5.

The licensee shall also maintain records of tests and experiments carried out pursuant to paragraph "A" of this Subsection. These records shall include a written evalua-tion which provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact or constitute a change in the objectives of these ETS. The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the license, a report containing de-scriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.

5.8 Records Retention 5.8.1 Records and logs relative to the following areas shall be retained for the life of the plant:

a. Records and drawing changes reflecting plant design modifications made to systems and equipment as de-scribed in Specification 5.7.3.
b. Records of environmental surveillance data.
c. Records to deronstrate compliance with the limiting conditions for operation in Section 2.

5.8.2 All other records and logs relating to the environmental technical specifications shall be retained for five years.

t 5-8

EXECUTIVE DIRECTOR GENERATION AND CONSTRUCTION l ,

I l DIRECTOR DIRECTOR GENERATION OPERATIONS TECILNICAL AND ENVIRONMENTAL SERVICES ARKANSAS NUCLEAR ONE' MANAGER GENERAL MANAGER TECilNICAL ANALYSIS ARKANSAS NUCLEAR ONE GIEMISTS ENGINEERING AND TEC11NICAL SUPPORT AND BIOLOGISTS ARKANSAS NUCLEAR ONE TECIINICAL ANALYSIS SUPERINTENDENT ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE Ci!EMICAL AND llEALTH PHYSICS RADI0 CHEMISTRY ENVIRONMENTAL SUPERVISOR SUPERVISOR SUPERVISOR i

J l

ARKANSAS POWER 6 LIGliT CO. ENVIRONMENTAL SURVEILLANCE FIG. NO. ,

ARKANSAS NUCLEAR ONE ORGANIZATION OIART S-1 S-9

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 1he General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1. Any changes will be submitted as a Technical Specification change request within 30 days of implementation.

FACILITY STAFF 6.2.2 The Facility oganization shall be as shown on Figures 6.2-2A B, C and D. Any changes will be submitted as a Technical Speci-fication change request within 30 days of implementation,

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 shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d. An individual qualified in radiation protection procedur shall be on site when fuel is in the reactor.
c. ALL CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling who has no other concurrent re-sponsibilities during this operation.
f. A site Fire Brigade of at 1 cast 5* members shall be main-tained 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 personnel required for other essential functions during a fire emergency.
  • Fire Brigade shall consist of at least 5 members after October 16, 1978; prior to October 17, 1978, the Fire Brigade shall consist of at least 3 members.

6-1

4 x

ARKANSAS POWER & LIGHT COMPANY w ARKANSAS NUCLE AR ONE - UNIT 2 w

EXECUTIVE DIRECTOR E

~ GENER ATION &

CONST RUCTION N

SAFETY R E V1EW COMMITTE E I I I I I I DIRECTOR DIRECTOR ADMINISTR ATIVE DIRECTOR DIRECTOR DIRECTOR TECHNICAL & SERVICES &

DIRECTOR PROJECTS GENERATION GENERATION ENVIRONMENT AL PROJECT GENE R ATION ENGtNEERING MANAGEMENT TECHNOLOGY OPERATIONS SERVICES SUPPORT T

m GENERAL PLANT

- SAFETY

  • Corporate Responsibility for MANAGER Fire Protection Prcyam.

COMMITTEE f~igure 6.21 Management Organization Chart 4

4

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i 4

f GENERAL MANAGER

-QUALITY

! CONTROL rNGII;EEP.

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. i PLA'it;ING & QUALITY SCHEDULING CONTROL SU ERVISOR -SUPERUISOR I l

QUALITY t CONTROL i INSPECICRS

)  :

5. OPERATIONS & PLANT ENGINEERING &

t MAINTENANCE ADMINISTR. TECHNICAL

, MANAGER IMNAGER SUPPOR:

. NAGER i

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- Senior Operator License Required

  1. - Operator License Pequired 4 ( ) - Desirable, but not Required ,

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& ADMINISTR. RESOURCES t!ANAGEf1EflT c SUPERVISOR SUPERVISOR SUPERVISOR j f

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FIRE CONTROL l (ECURITY

& SAFETY ,

CdORDINATOR COORDINATOR- .

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l TECHNICAL

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[ TECHNICAL PLANT PLANT j ANAL.YSIS -

ANALYSIS -

ENGINEERING I

SUPT SUPT. SUPT.

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PERFORMANCE elEALTil MECHANICAL SUPERVISOR L _ _. PHYS 1CS -

ENGINEERING SUP ERVISOR SUPERVISOR ,

NUCLEAR

~ '

SUPPORT ASSISTANT SUPERVISOR ELECTRICAL '

HEALTH -

ENGINEERING PHYSICS SUPERVISOR SUPERVISORS NUCLEAf E!!GINEERS ,

RADIO CHE!!!STRY SUPERVISOR COMPUTER SUPPORT SUPERVISOR CHEMICAL &

ENVIRONMENT COMPUT ER SUPERVISOR ENGINEE r, S E

Figure 6,2-2C , j 6-3c

GE "EU L MANAGER OPERATING &

MAINTENANCE MANAGER 1 i

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. OPERATIONS INSTRUM. &

! MAlflTENANCE ~

CON SUPERINT. SUPERINT.

3UPERINT.

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ASSISTANT ELEC. ASST.

OPERATIONS MAINT.

I&C St!PERINT. SUPVR. SUPVRS.

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UNIT 1 UNIT 2' EL CT' SHIFT SHIFT MAINT.'

S U' 'iR . SUPVR. supyps, I

PLANT PLANT S Cr OPER. OPER.

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Figure 6.2-2D 3d-a

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1 ADMINISTRATIVE CON 1ROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Supervisor who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the General Manager l 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 General Manager and shall meet or exceed the l requirements of Section 27 of the NFPA Code 1975, except for Fire Brigade training sessions which shall be held at Icast quarterly.

6.5 REVIEW AND AUDIT 6.5.1. PLANT SAFETY COMMITTEE (PSC)

FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the General Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:

Chairman: Operations and Maintenance Manager l Member: Operations Superintendent Member: Technical Analysis Superintendent l Member: Maintenance Superintendent Member: Instrumentation S Controls Superintendent Member: Plant Analysis Superintendent Member: Health Physics Supervisor The General Manager shall appoint in writing an acting chairman in the absence of the Operations and Maintenance Manager.

6-5

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the PSC necessary for the performance of the PSC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and three members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsibic for: ,

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the General Manager to affect nuclear l sa fety,
b. Review of all proposed tests and experiments that affect nuclear safety,
c. Review of all proposed changes to Appendix "A" Technical Specificaticus.
d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety,
c. Investigation of all violations of the Technical Specifications involving activities under the responsibility of the General Manager, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence

< to the General Manager and to the Chairman of the Safety Review [

Committee.

6-6 P

ADMINISTRATIVE CONTROLS

f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
g. Review of facility operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations or analyses and reports thereon as requested by the General Manager or the l Safety Review Committee.
i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Safety Review Committee.
j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Safety Review Committee.

AUT110RITY 6.5.1.7 The Plant Safety Committee shall:

a. Recommend in writing to the General Manager approval or disapproval l of items considered under 6.5.1.6(a) throJgh (d) above,
b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above consti-tutes an unreviewed safety question.
c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Director, Generation Operations and the Safety Review Committee of dis-agreement between the PSC and the General Manager; however, the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at a minimum , document the results of all PSC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the General banager and Chairman of the Safety l Review Committee.

6-7

. . _ - -~ ,

ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMIT'EE (SRC)

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

a. nuclear power plant operations
b. nuclear engineering l

l c. chemistry and radiochemistry

d. metallurgy
e. instrumentation and control
f. radiologicil safety
g. mechanical and electrical engineering
h. quality assurance practices.

COMPOSITION 6.5.2.2 The SRC shall be composed of the:

Chairman: Director, G; 'Merations Member: Director, e niogy Member: Directo. conmental Services Member: Manager.

Member: Arkansas huc Manager l Member: Manager, Tec: ,4s Member: Arkansas Nucle .4 ant Analysis Superintendent l Member: Director, Generation Engineering Member: Radiation and Health Physics Consultant

  • Member: Nuclear Safety Consultant
  • r *The Radiation and Health Physics Consultant and the Nuclear Safety Consultant shall have an academic degree in engineering or physical science field; and in addition, each shall have a minimum of five years technical experience, of which a minimum of three years shall be in their respective field of expertise.

6-8

s ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION

~

6.7.1 The following action shall be taken in the event a Safety Limit is violated:

a. The unit shall be placed in at least HOT STANDBY within one hour,
b. The Safety Limit violation shall be reported to the Commission, the Manager, Nuclear Operations and to the SRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSC. 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 SRC and the Manager, Nuclear Operations within 14 days of the violation.

6.8 PROCEDURES 6.8.1 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. Refueling operations.
c. Surveillance and test activities of safety related equipment,
d. Security Plan implementation, i
e. Emergency Plan implementation. l
f. Fire Protection Program Implementation.

i 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be i reviewed by the PSC and approved by the General Manager prior to l implementation and reviewed periodically as set forth in adminis- '

trative procedures. I 6-13 ,

1 l

I

s ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.0.1 above may be made provided:

a. The intent of the original procedure is not altered.
b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's I,icense on the unit affected.
c. The change is documented, reviewed by the PSC and approved by the General Manager within 14 days of implementation. l 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be sub-mitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating 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 performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predic-tions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following re-sumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial l criticality, completion of startup test program, and resumption l or commencement of commercial power operation), supplementary re-ports shall be submitted at least every three months until all three events have been completed.

6-14 l

y_ - _

s

  • 1 ADMINISTRATIVE CONTROLS ANNUAL REPORTS 1/

6.9.1/4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be subnitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving ,

exposuresgreaterthan100 rem exposure according tomrem /yrandtheirassoJgatedman work and job functions,' e.g.,

reactor operations and survet.llance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions,

b. The complete results of steam generator tube inservice inspec-tions performed during the report period (reference Specifica-tion 4.4.5.5.b).

1/ 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.

2/ This taLulation supphments the requirements of 520.407 of 10 CF3 Part 20.

ARKANSAS - UNIT 2 6-15

5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility Corporate responsibility for implementation of the Environmental Technical Specifications, and for assuring that station operations are controlled to provide protection for the environment has been assigned to the Executive Director of Generation and Construction.

The ANO General Manager, through the Engineering and Technical Support Manager, and Technical Analysis Superintendent shall be responsible for compliance with the Environmental Technical Specifications at the plant level.

The Manager of Technical Analysis shall be responsibic for radio-logical analysis of environmental samples.

5.2 Organization Figure 5-1 shows the organization chart at both plant and corporate levels relative to environmental matters.

5.3 Review 5.3.1 Plant Safety Committee The Plant Safety Committee (PSC) shall be responsible for review of the following:

a. Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes.
b. Proposed written procedures, as described in Specification I 5.5, and proposed changes thereto which affect the plan "s  ;

environmental impact.

5-1

c. Proposed changes or modifications to plant systems or equipment which would affect the plant's environmental impact.
d. Results of the Environmental Monitoring Programs,
e. Investigation of all reported instances of violations of Environmental Technical Specifications involving activities under the responsibility of the General Manager. h'here in-vestigation warrants, instances shall be evaluated and recommendations formulated to prevent recurrence.

5.3.2 Safety Review Connittee The Safety Review Committee (SRC) shr.11 be responsible for review of the following:

a. The environmental evaluations for 1) changes to pro-cedures, equipment or systems and 2) tests or experiments completed under Section 5.7.3, to verify that such actions did not constitute an unreviewed environmental question.
b. Proposed changes to procedures, equipment or system which involve an unreviewed environmental question as defined in Section 5.7.3.B.
c. Proposed changes to the Environmental Technical Specifi-cations and the evaluated impact of the changes.
d. Results of the Environmental Monitoring Programs.
c. Investigation of all reported instances of violations of Environmental Technical Specifications.

5-2

F'

,e, l

EXECUTIVE DIRECTOR

) GENERATION AND CONSTRUCTION I

I I DIRECTOR DIRECTOR GENERATION brERATIONS TECHNICAL AND ENVIRONMENTAL SERVICES ARVANSAS NUCLEAR ONE )% NAGER GENERAL MANAGER TECl!NICAL ANALYSIS ARKANSAS NUCLEAR ONE CilEMISTS ENGINEERING AND TECIINICAL SUPPORT AND BIOLOGISTS ARKANSAS NUCLEAR ONE TECILNICAL ANALYSIS SUPERINTENDENT ARKANSAS NUCLEAll ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE CliEMICAL AND RADIOCl!EMISTRY llEALTil PlfYSICS ENVIRONMENTAL SUPERVISOR SUPERVISOR SUPERVISOR ARKANSAS POWER G LIGilT CO. ENVIRONMENTAL SURVEILLANCE FIG. NO.

ARKANSAS NUCLEAR CNE ORGANIZATION CilART 5-1 5-10 I

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