ML20138R112

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Proposed Tech Specs,Reflecting Organizational Changes & Making Spec 6.5.2.8 Consistent W/Sts
ML20138R112
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/20/1985
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20138Q963 List:
References
NUDOCS 8512300389
Download: ML20138R112 (12)
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Text

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1' The Director, Site Nuclear Operations shall be responsible for -

overall facility operation and shall delegate in writing the  ;

succession to this responsibility during his absence. I 6.2 ORGANIZATION OFFSITE x

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

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

6.2.2.1 Administrative controls shall be e n /ilished to limit the amount of overtime worked by plant staff ,erforming safety related functions. These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).

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 (1) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant s for transients and accidents.

N 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director, Site Nuclear Operations and shall meet or exceed the requirements and y 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 Director, Site Nuclear Operations 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.

Amendment No. 26, 30, 34, 37, 117

  1. 7, 50, 59, 64, 82, 85 8512300389 851220 ~~

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'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 Director, '

Site Nuclear Operations on all matters related to nuclear safety.

COMPOSTION.

6.5.1.2 The Plant Safety Committee shall be composed of the: (See Page 121)

E Amendment No. 85 117a

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) DIRECTOR SITE (1) THE NUCLE AR QUALITY GENER AL M AN AGE 0B j NUCLEAR REPORTS TO THE VICE PRESIDENT OF OPERATIONS NUCLEAR OPERATIONS. HE HAS INTERFACE NUCLEAR WITH THE DIRECTOR SITE NUCLE AR l NUCLEAR S E R VIC E S OPER ATIONS IN D AILY COMMUNIC ATIONS, Q U ALIT Y -----------

(1) GENERAL AND HAS DIRECT ACCESS TO THE SENIOR I GENERAL MANAGER VICE PRESIDENT ENERGY SUPPLY ON ANY g MANAGER MATTERS CONCERNING NUCLEAR QUALITY.

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wN Nm NUCLEAR ww CI NUCLEAR PROGRAMS MANAGER HAS NUCLEAR NUCLEAR ENGINEERING N ,G RESPONSIBILITY FOR THE CORPORATE

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.. AND THE CORPORATE FIRE PROTECTION PROGRAM MANAGER wN y*

FIGURE 6.2-1 MANAGEMENT ORGANIZATION CHART ,

ARKANSAS POWER & LIGHT COMPANY

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PL A NNING g g SUPERINTENOENT SUPERINTENDENT COORDIN A TOR S s

OPERATION 9 OPERATIONS INSTRUMENT

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TECHNICA4 TECHNICAL AND E NGINE ERING TECHNICAL SUPPORT SUPPORT CONTROL -

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ANALYS13 SUPERYlSOS SUPERVISOR SUPERINTENDENT SUPERVISOR SUPERINTENDENT OPERATIONS SHIFT E X PE RIE NCE MAINTENANCE - _

ASSESSMENT SUPERINTENDENT GROUP SUPERINTENDENT SENIOR WAINTE N ANCE _

COORDINA TOR JE SENIOR OPER ATOR LICENSE REQUIRED (1) THE HEALTH PHYSICS SUPERINTENDENT REPORTS TO THE TECHNICAL SUPPORT MANACER IN ADMINISTR ATIVE MATTPa9 AND RouttNE HEALTH PHYSICS CONCERNS AND HE REPORTS TO THE DIRECTOR SITE NUCLE AR OPER ATIONS IN MATTERS OF RADIOLOGICAL HEALTH SAFETY AND POLICY.

(2) THE HEALTH PHYSICS SUPERINTENDENT HAS DIRECT INTERF ACE WITH THE NUCLE AR PROGRAMS MAN AGER IN MATTERS OF RADIOLOGICAL HE ALTH AND SAFETY HE WILL HELP FORMULATE CORPORATE HE ALTH PHYSICS POLICY AND ENSURE THAT IT IS PROPERLY IMPLEMENTEO.

(3) THE NUCLE AR QUAllTY GENER AL MANAGER REPORTS TO THE VICE PRESIDENT OF NUCLE AR OPERATIONS. HE HAS INTERF ACE WITH THE DIRECTOR SITE NUCLE AR OPERATIONS IN DasLY COMMUNICATIONS.

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FIGURE 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATIONS ARKANSAS - UNIT 1 ,

120 Amendment No. 37,f/,M,M

Chairman: Manager of Special Projects Member: Operations Manager Member: Maintenance Manager Member: Training Manager Member: Technical Analysis Superintendent Member: Engineering Manager Member: Quality Assurance Superintendent Member: Reactor Engineering Supervisor Member: Health Physics Superintendent The Director, Site Nuclear Operations should designate in writing the Alternate Chairman in the absence' of the Chairman.

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 desiglated 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 four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:

a. Review of 1) all procedores required by Specification 6.8 and revisions thereto, 2) any other proposed procedures or revisicns thereto as determined by the Director, Site Nuclear Operations to 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" Technical Specifications.

d Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Amendment No. 26,34,37,47,64,82 121

- e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Director, Site Nuclear Operations and to the Chairman of the Safety Review -

Committee.

f. Review of those Reportable Occurrences requiring 24-hour notification of the Commission.

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Amendment No. I6,34,37, 121a 51,64,82 s"

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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 Director, Site -

Nuclear Operations or the Safety Review Committee.

i. Review of the Plant Security Plan and implementing procedures

' and submittal of recommended changes to the Director, Site Nuclear Operations and the Safety Review Committee.

j. ' Review of the Emergency Plan'and implementing procedures and-submittal of recommended changes to the Director, Site Nuclear Operations and the Safety Review Committee.

! k. Review of changes to the Offsite Dose Calculation Manual and the Process Control Program.

AUTHORITY 6.5.1.7.1 The Plant Safety Committee shall:

a. Recommend in writing their 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 (e) above
constitutes 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 the Vice-President, Nuclear Operations and the Safety Review Committee of disagreement between the PSC and the Director, Site Nuclear Operations; however, the Director, Site Nuclear Operations 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 Director, Site Nuclear Operations and Chairman of the Safety Review Committee.

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 Amendment No. 16, 24, 27, 47, 122 58, 82, 88 k
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION 6.5.2.2 The Safety Review Committee shall be composed of a Chairman and eight members which collectively have the experience and competence required to review problems in the areas specified in Section 6.5.2.1, a-h.

The Vice President of Nuclear Operations shall designate, in writing, the Chairman and all SRC members.

The Chairman shall designate, in writing, the alternate Chairman in the absence of the SRC 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 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 designated alternate and at least 4 SRC members including alternates. No

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more than a minority of the quorum shall have line responsibility for operation of the unit.

Amendment No. 16, 34, 37, 47, 58, 82 123

REVIEW 6.5.2.7 Thu 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 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 questions 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 deviation from normal and expected performance of unit equipment that affect nuclear safety.
g. Events requiring 21-hour notification to the Commission.
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.
j. Changes to Offsite Dose Calculation Manual and Process Control Program.

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 unit operation to 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 actions taren to correct deficiencies occurring in unit equipment, structures, systems or methods of operation that affect nuclear safety at least once per 6 months.

Amendment No. 16, 30, 34, 47,88 124 o

. d. Tha performance of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50 Appendix "B", at least once per 24 months.

e. The Facility Emergency Plan and implementing procedures at least once per 12 months.
f. The Facility Security Plan and implementing procedures at -

least once per 12 months.

g. Any other area of unit operation considered appropriate by the SRC or the Vice President, Nuclear Operations.
h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i. An independent fire protection and loss prevention program inspection ana audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.
j. The Offsite Dose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.
k. The radiological environmental monitoring program and the results thereof at least once per 12 months.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Nuclear Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

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, Nuclear Operations, within 14 days following each meeting.
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, Nuclear Operations, 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, Nuclear Operations, and to the management positions responsible for the areas audited within 30 days after completion of the audit.

Amendment No. 16,30,34,37,42, 47, 58, 78, 82, 88 125

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 Specification 6.12.
b. Each Reportable Occurrence requiring 24-hour notification to the Commission shall be reviewed by the PSC and submitted to the SRC and the Vice President, Nuclear Operations by the Director, Site Nuclear Operations.

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

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 oursuant 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 implementation.
f. Fire Protection Program implementation.
g. New and spent fuel storage.
h. Offsite Dose Calculation Manual and Process Control Program implementation at the site.

Post accident sampling (includes sampling of reactor coolant,

i. l radioactive iodines and particulates in plant gaseous effluents, and the containment atmosphere).

Amendment No. 16,30,34,37,42, 126 47,58,82 6

x 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the Director, Site Nuclear Operations or the responsible General Manager prior 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 Director, Site Nuclear Operations or the responsible General Manager within 14 days of implementation.

Amendment No. 16, 20, 34, 37, 127 76, 82, 88 94 6

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