ML19337B572

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Proposed Tech Specs,Section 6,reflecting Personnel Reorganization
ML19337B572
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 09/29/1980
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19337B571 List:
References
NUDOCS 8010070310
Download: ML19337B572 (25)
v • d • e


Text

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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 tech-nical support shall be as shown on Figure 6.2.-l.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2.-2.

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

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.

i 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 j frequency of training which shall be six times per year. l 6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Committee shall function to advise the General Hanager on all matters related to nuclear safety.

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

(See Page 122)

Amendment No. -117-0 01FIBjL4DLs l 1

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i Amendment No. -121-a

6.5.1.2 a. Operations Manager

b. Maintenance Manager
c. Engineering and Technical Support Manager
d. Manager of Special Projects e.

Administrative Manager

f. Technical Analysis Superintendent
g. Plant Analysis Superintendent
h. Plant Engineering Superintendent j i. Health Physics Supervisor

=

j. Station engineers assigned by the General Manager The General Manager shall designate in writing, the Chairman, and the Alternate Chairman from the membership of the Plant Safety Committee.

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

HEETING 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 i 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.

No more than one station engineer assigned by the General Manager shall participate as a voting member in PSC activities at any one time.

RESPONSIBILITIES

~

6.5.1.6 The Plant Safety Committee shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and revisions thereto, 2) any other proposed pro-cedures or revisions thereto as determined by the General Manager to affect nuclerr safety.
b. Review all of proposed tests and experiments that affect nuclear safety,
c. Review of all proposed changes to the Appendis "A" Technical Specifications.

Amendment No. -122-

i .

d. Review of all' proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technical Specifi-cations, including the preparation and forwarding of reports covering evaluation and recommendations to prevent

. recurrence to the General Manager.

I

f. Review of those Reportable Occurrences requiring 24-hour notification of the Commission.
g. Review of facility operations to detect potential nuclear safety hazards.
h. Performance of special reviews, invstigations and reports thereon as requested by the General Manager.
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 pro-cedures and shall submit recommended changes to the General Manager.

AUTHORITY 6.5.1.7.1 The Plant Safety Committee shall:

a. Recommend to the General Manager written approval or disapproval of items considered 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 (c) above constitutes an unreviewed safety question.
c. Provide written notification within one working day to the Director, Nuclear Operations and the Safety Review Committee of disagreement between the PSC and the General Manager; however, the General Manager shall have responsi-bility 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 I 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 Manager and Chairman of the Safety Review Committee. -

Amendment No. -123-

6.5.2 SAFETY REVIEW COMMITTEE (SRC)

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

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION 6.5.2.2 The SRC shall be composed of the: ,
a. Director, Nuclear Operations
b. Director, Generation Technology
c. Director, Technical and Environmental Services
d. Manager, Quality Assurance
e. Plant Safety Committee Chairman
f. Manager, Technical Analysis
g. Arkansas Nuclear One Plant Analysis Superintendent
h. Director, Generation Engineering
1. Manager, I&C Engineering i

J. Manager of System Nuclear Operations

  • The SRC Chairman and Alternate Chairman shall be appointed from among the Director level personnel of the SRC member-ship by the Vice-President G&C.

A_LTERNATES -

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.

  • Middle South Services AMENDMENT NO. 124-

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

MEETING FREQUENCY 6'. 5 . 2. 5 The SRC shall meet at 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 The minimum quorum of the SRC necessary for the performance of the SRC review and audit functions of these technical specifications shall consist of the Chairman or his desig-nated alternate and at least 4 SRC members including al-ternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7 The SRC shall review:

a. The safety evaluations for 1) changes to procedures, equipment 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 ur systems which involve an unreviewed safety question as defined 4.n Section 50.59, 10 CFR.
c. Proposed tests or experiments which involve an unreviewed safety questica as defined in Section 50.59, 10 CFR.
d. Proposed changes in Technical Specifications or licenses.
e. Violations of applicable statues, codes, reguitions, 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 unit equipment that '

affect nuclear safety.

g. Events requiring 24-hour notification to the Commission.

l Amendment No. -125-l l

h. All recognized indications of an unanticipated deficiency in some aspects of design or operation of structures, systems, or components that could affect nuclear safety,
i. Reports and meeting minutes of the Plant Safety Committee.

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 ap-plicable license conditions at least 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 Emergecy Plan and implementing procedures at least once per two years.,
e. The Facility Fire Protection Program and implementing procedures at least once per two years.
f. The Facility Security Plan and implementing procedures at least once per two years.
g. Any other area of facility operation considered appropriate ly the SRC or the Vice President, Generation & Construction (VP, G&C).
h. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice Presideut, Generafton

& Construction (VP, G&C) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

, Amendment No. -126-l l -

i

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared, ap-proved and forwarded to the Vice President, f.enera-tion & Construction (VP,G&C) within 30 days isllow-ing each meeting.
b. Reports of reviews encompassed by Section 6.5.. 7.e, f, g, h, and i above, shall be prepared, approved l and forwarded to the Vice President, Generation & ,

Construction, (VP, G&C) within 30 days following completion of the review.

I

c. Audit reports encompassed by Section 6.5.2.8 above,

. shall be forwarded to the Vice President, Generation

& Construction (VP, G&C) and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE 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 Specifi-cation 6.12.
b. Each Reportable Occurrence requiring 24-hour notifi-cation to the Commission shall be reviewed by the PSC and submitted to the SRC and the Director Nuclear Operations by the General Manager.

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

l Amendment No. Page 126a l

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 ac-counted 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.

6.12.2.3 Monthly Operating Report Routine reports of operating statistics which include:

1. Average Daily Unit Power Level
2. Operating Data Report
3. Unit Shutdowns and Power Reductions
4. Narrative Summary of Operating Experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, by the fif teenth of each month following the calendar month covered by the ;eport.

6.12.3 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC as required below.

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.

6.12.3.1 Prompt Notification Vi: Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24-hours, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropric+e Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. A i

copy of the confirmation and the written followup report shall also be sent to the Director, Office of Management and Program Analysis USNRC.

The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented as needed, by additional narrative material to provide complete explanation of the circumstances sur-rounding the event. .

I i

l Amendment No. -141-

h. Errors discovered in the transient or accident analyces or in the methods used for such analyses as described in the safety analysis report or in the bases for the Technical Specifications that have or could have permitted reactor operation in a manner less con-servative than assured in the analyses.

i Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during plant life of conditions not specifically con-sidered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

NOTE: This item is intended to provide for reporting of po-tentially generic problems.

6.12.3.2 Thirty Day Written Reports The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within thirty days of occurrence of the event. A copy of the written report shall also be sent to the Director, Office of Management and Program Analysis. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be s,upplemented, as needed, by <

additional narrative material to provide complete explanation of the circumstances surrounding the event.

a. Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those es- '

tablished by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems,

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

NOTE:

Routine surveillance testing, instrument calibration, or pre-ventative maintenance which require system configurations as described in items a. and b. above need not be reported except where test results themselves reveal a degraded mode as described l above.

  • l l
c. Observed inadequacies in the implementation of administrative or I procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

I Amendment No. -144- l l

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Figure 6.2-2 Functional Organization for Plant Operation

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the uuit 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 qualifications 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 and shall meet or exceed the requirements and recom-mendations 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 requirements of Section 27 of the NFPA Code - 1975, except for Fire Brigade training sessions which shall be held

'at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)

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

COMPOSITION 6.5.1.2 a. Operations Manager

b. Maintenance Manager
c. Engineering and Technical Support Manager
d. Manager of Special '/rojects
e. Administrive Manage r
f. Technical Analysis Superintendent
g. Plant Analysis Superintendent
h. Plant Engineering duperintendent '
i. Health Physics Supervisor
j. Station engineers assigned by the General Manager.
k. Nuclear Software Expert
  • l The General Manager shall designate in writing the Chairman l and the Alternate Chairman from the membership of the Plant i Safety Committee.
  • See page 6-Sa ARKANSAS - UNIT 2 6-5 Amendment No.

i

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSC Cnairman 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.

No more than one station engineer assigned by the General Manager shall participate as a voting member in PSC activities at any one time.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible 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 safety.
b. Review of all proposed tests and experiments that affect nuclear safety.
c. Review of all proposed changes to Appendix "A" Technical Specifications.
d. Rev'. w of all proposed changes or modifications to unit r1 stems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technical Speci-fications 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.

ARKANSAS - UNIT 2 6-6 Amendment No.

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 Safety Review Committee.
i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the General Manager and the Safety Review Committee.

J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the General Manager and the Safety Review Committee.

AUTHORITY 6.5.1.7 The Plant Safety Committee shall:

a. Recommend in writing to the General Manager approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b. Render detenminations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question,
c. Provide written notification within one working day to the Director, Nuclear Operations and the Safety Review Committee of disagreement 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 '

arity provisions of these technical specifications.

..es shall be provided to the General Manager and Chair-man of the Safety Review Committee.

6.5.2 SAFETY REVIEW COMMITTEE (SRC)

ARKANSAS - UNIT 2 6-7 Amendment No. -

1 ADMINISTRATIVE CONTROLS FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide in-dependent review and audit of designated activities in the areas of:

a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION 6.5.2.2 The SRC shall be composed of the:
a. Director, Nuclear Operations
b. Director, Generation Technology  ;
c. Director, Technical and Environmental Services
d. Manager, Quality Assurance
c. Arkansas Nuclear One Plant Safety Committee Chairman
f. Manager, Technical Analysis
g. Arkansas Nuclear One Plant Analysis Superintendent
h. Director, Generation Engineering
i. Manager, I&C Engineering
j. Manager of System Nuclear Operations
  • The SRC Chairman and Alternate Chairman shall be appointed from among the Director level personnel of the SRC member-ship by the Vice President, G&C.

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l Middle South Services ARKANSAS - ONIT 2 6-8 Amendment No.

1 I

ADMINISTRATIVE CONTROLS ,

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the Vice President, Generation & Con-struction (VP, G&C) within 14 days following each meet-ing,
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, Generation & Construction (VP, G&C) within 14 days following completion of the review.
c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Generation & Construc-tion (VP,G&C) and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE 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 I pursuaat to the requirements of Specification 6.9.
b. Each REPORTABLE OCCURRENCE requiring 24-hour notification to the Commission shall be reviewed by the PSC and sub-mitted to the SRC and the Director, Nuclear Operations.

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 unit shall be placed in at least HOT STANDBY l within one hour. I l
b. The Safety Limit violation shall be reported to the l Commission, the Director, Nuclear Operations and to the
  • SRC within 24-hours.

1 ARKANSAS - UNIT 2 6-12 Amendment No.

P ADMINISTRATIVE CONTROLS

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 Director, 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. j

d. Security Plan implementation.
e. Emergency Plan implementation.
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 to implementation and reviewed periodically as set forth in administrative procedures.

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l ARKANSAS - UNIT 2 6-13 Amendment No.

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'VICE FRESIDENT CDTAATION AND CONSTRUCTIDN I

I I LIRECTOR Di hCTOR EWWIR S ICES i

ARKANSAS hTCLE'R A Chi MAXACD CLXLRAL MANAC!R 1ECHNICAL ANALYSIS ARKAN3AS WUCLEAR Oh1

. DCI ATERING AND TECHNICAL SUFFORT B! ISTS 1

AAAANSAS NUC!2AR Cht

. TECHNICAL ANALYSIS SLTERINTENDENT l

8A8 bT OhT APXANSAS NUCLE'AR ONE ARKAESAS WUCLEAk ONE RADIOCMEMISTRY HEALTM FHTSlCS SuruviSOR Suruvr$0A i

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ARKANSAS POWER & LIGHT C0. ENVIR0tNENTAL SURVEILLANCE FIGURE NO.

ARKANSAS NUCLEAR ONE ORGANIZATION CHART 5-1 5-10 AMENDMENT NO. 1

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