ML20082N214
| ML20082N214 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-152, DPR-79-A-142) |
| Issue date: | 08/22/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082N216 | List: |
| References | |
| GL-82-16, NUDOCS 9109090040 | |
| Download: ML20082N214 (34) | |
Text
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x MJ. i NUCLEAR REGULATORY COMMISSION o,
WASHINoTON. D A 20%5 TFt:NESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAHNUCLEARPLA_NTdNIT1 AMENDHENT TO FACILITY OPERATING __ LICENSE Amendment No.152 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedDecember 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will,be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon d3fense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9109090040 910822 PDR ADOCK 05000327 i
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.152, are hereby incorporated in the license. The licensee shall operate the facility-in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be imp 1mnented within 60 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a$.
.f i
Frederick J. Hetidon, Director I
Project Directorate-11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
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Attachment:
-Changes to the Technical Specifications f
Date of Issuance: August 22,.1991 i
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.152 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of enange.
Overleaf pages* See provided to maintain document completeness.
REMOVE INSERT 6-1 6-1 6-2 6-2 6-5 6-5 6-6 6-6 6-7*
6 -7
- 6-8 6-8 6-9 6-9 6-10*
6-10*
6-11*
6-11*
I 6-12 6-12 6-13 6-13 6-14 6-14 6-21 6-21 6-24 6-24
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Corporate Manager of Radiological Control shall be responsible for implementing the radiological environmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual (ODCM).
6.1. 3 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function.
A management directive to this effect, signed by the Site Vice President, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant, Lines of authority, responsibility, and communication shall be a.
established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR and will be updated in accordance with 10 CFR 50.71(e),
b.
The Senior Vice President, Nuclear Group shall have corporate responsibility for overall plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
The Plant Manager shall be responsible for overall unit safe operation c.
and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF a.
Each on-duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor.
In addition, while the unit is in H0DE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
SEQUOYAH - UNIT 1 6-1 Amendment No. 32, 58, 74, 152
ADMINISTRATIVE CONTROLS s
A Radiological Control technician # shall be onsite when fuel is in the c.
reactor.
d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
AFireBrigadeofatleast5membersshallbemaintainedonsiteat e.
all times.
The Fire Brigade shall not include the Shift Supervisor and 2 other members of the minimum shif t crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
f.
The Operations Manager shall hold a Senior Reactor Operator license, g.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (i.e., senior reactor operators, reactor operators, assistant unit operators, Radiological Control, and key maintenance personnel).
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a normal 8-hour day, 40-Sour week while the unit is operating.
However, in the event that unforseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintanance, or major plant modification, on a temporary basis the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work perieds, including shift turnover time.
4.
Except during extended shutdown periods, the use of overtime l
should be considered on an individual basis and not for the i
entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager (or Duty Plant Manager), or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
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- The Radiological Control technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
SEQUOYAH - UNIT 1 6-2 Amendment No. 32, 58, 74, 152
ADMINISTRATIVE CONTROLS 6.2.3 JNDEPENDENT SAFETY ENGINEERING (ISE)
FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for_ improving plant safety.
COMPOSITION 6.2.3.2 - The ISE shall be composed of at least 3 dedicated full-time engineers
-located 'onsite.-
These engineers will be supplemented = as necessary by full-time engineers shared among all,TVA nuclear sites to achieve an equivalent staffing of 5 full-time engineers; performing the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of_ plant activities to provide _ independent verification
- that these activities are performed correctly and that human errors are reduced as much es practical.
AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for. revised procedures, equipment modifications, or other means of improving plant safety to the Manager of Nuclear Managers Review Group.
6.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve inran advisory capacity to the Shift Supervisor
'l on matters pertaining to the engineering aspects of assuring safe operation of the unit.
6.3~ FACILITY STAFF QUALIFICATIONS 6.3.1 Each membi.r of the ' facility staff shall meet or exceed the minimum qualifi-cations of ANSI N10.1-1971 for comparable positions and the supplemental requirements specified in Section-A and C of Enclosure 1 of the_ March 28, 1980 NRC letter to all licensees, except for the Site Radiological Control Manager who shall meet or exceed the qualifications of' Regulatory Guide 1.8,
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September.1975.-
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- Not responsible for sign-off function.
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SEQUOYAH - UNIT 1 6-5 Amendment No. 12, 58, 74 152
ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Plant Manager and shall meet or l
exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 The Senior Vice President, Nuclear Power is responsible for the safe operation of all TVA power plants.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:
Operations Manager Member:
Site Radiological Control Manager Member:
Maintenance Manager Member:
Technical Support Manager Member:
Quality Engineering and Monitoring Supervisor Member:
Nuclear Engineering Representative l
SEQUOYAH - UNIT 1 6-6 Amendment No. 58, 74 152 J
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l ADMINISTRATIVE CONTROLS i
- ALTERNATES-6.5.1.3 LAll alternate members shall be appointed in writing by the PORC Chairman to serve on=a. temporary basis;-however, no more.than two alternates shall= participate as voting members in PORC activities at any one time..
MEETING FREQUENCY
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- 6.5.1.4 'The PORC shall meet at least once. per calendar month and as-convened-l by the PORC Chairman or his designated alternate.
. QUORUM
-6.5.1.5-The minimum quorum of the PORC necessary-for the performance of the PORC responsibility ard authority provisions of these technical specifications shall consist of-the' Chairman-or his_ designated alternate and four members
-including alternates.
5 e
IRESPONSIBILITIES 6.5.1.6 ~The-PORC shall be responsible for:
Providing for an oversight review of selected safety. evaluations I'1 a.
' f or:
(1) procedures and (2)-change to procedures, equipment,-
systems or facilitics to verify-that such actions d.id not constituta an_unreviewed safety question.
- b..
Review-of all proposed' tests and experiments'that affect nuclear safety.
Review of all proposed changes to Appendix "A" Techniedi' Specifications.
- c.
Review of proposed ' procedures and changes to procedures, programs, d.
equipment system or~ facilities which involve an unreviewed safety-question as defined in 10.CFR 50.59.
Review of reports covering evaluation and recommendations.to prevent e.
recurrence-of all violations of the Technical Specifications.
' f.
Review of all-REPORTABLE EVENTS.
p.
g.
Review of unit operations to detect potential nuclear safety hazards.
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SEQUOYAH - UNIT 1 6-7 Amendment No. 4874- - - - - -
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ADMINISTRATIVE CONTROLS h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the Nuclear Safety Review Board, i.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and fo marding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Site Vice President and to the l
Nuclear Safety Review Board.
AUTHORITY 6.5.1.7 The PORC shall:
Recommend in writing to the Plant Manager approval or disapproval of a.
items considered under 6.5.1.6(a), (b) and (c) above.
b.
Require a determination in writing with regard to whether or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question, 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 Site Vice c.
President and the Nuclear Safety Review Board of disagreement l
between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Vice President and the Nuclear Safety Review Board, 6.5.1ATECHNICALREVIEWANDCONTROJ ACTIVITIES 6.5.1A.1.
Activities which affect nuclear safety shall be conducted as follows:
Procedures required by Specification 6.8.1 and other procedures a.
which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure change shall be reviewed by a qualified individual other than the individual who prepared the procedure or procedure change, but who may be from the same organization as the individual who prepared the procedure or procedure change.
Procedures shall be approved by the appropriate responsible manager as designated in writing by the Plant Manager.
The Plant Manager, or Duty Plant Manager shall approve designated Administrative Procedures.
SEQUOYAH - UNIT 1 6-8 Amendment No. 50, 74 152
I ADMINISTRATIVE CONTROLS (Continued)
.b.
Proposed changes or modifications to structures, systems, and.
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components that affect plant nuclear safety shall-be reviewed by a qualified _ individual / group other than the-individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications.
Proposed modifications to structures, systems, and components that affect plant nuclear safety shall be approved prior to implementation by the Plant Manager, or Duty Plant Manager.
Individuals responsible ~for reviews performed in accordance with c.
Specifications 6.5.1A.la and -b, shall be designated by approved written procedures.
Each such review shall be performed by qualified personnel of the appropriate discipline and shall include a determination of whether or not additional, cross-disciplinary review.is necessary.
Each such review shall also include determina-l tion of whether or not an unreviewed safety question is involved pursuant to Section-10 CFR 50.59.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1' The NSRB shall_ function to provide for independent review and audit to assure adequacy of designated activities in the areas of:
a.
nuclear power. plant operations b.
nuclear engineering i
c, chemistry and radiochemistry d.
metallurgy e,
instrumentation and control
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f.
radiological safety-g.
mechanical and electrical engineering h.
quality assurance practices COMPOSITION 6.5.2.2 The NSRB shall be composed of at least five members, including the Chairman.
Members of the NSRB may be from Nuclear Power, or other TVA F
organization or external to TVA.
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i SEQUOYAH - UNIT 1 6-9 Amendment No. 58, 74 f
152
4 ADMINISTRATIVE CONTROLS QUALIFICATIONS.
6.5.2.3 The Chairman, members, and alternate members of the NSRS shall be appointed in writing by= the Senior Vice President, Nuclear Power and shall have an academic degree in engineering or a physical science field, or the equiva-1ent; and in addition, shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to
. provide expert advice to the NSRB.
MEETING FREQUENCY:
6.5.2.5 The NSRB shall meet'at'least once per calendar quarter during the initial-year of unit operation following fuel loading and at least once per
'six months thereafter.
QUORUM-6.5.2.6 The minimum quorum of the'NSRB necessary for the performance of the NSR8 review and audit functions of these technical specifications shall consist of more than half-the NSRB membership or at least 5 members, whichever is greater.
This quorum shall' include the Chairman or his appointtd alternate and the NSRB members, including appointed alternate members, meeting the requirements of
-Specification 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 -The-NSRB. shall be ' cognizant of review of:
a.
The safety evaluations for 1) changes to procedures, eq'uir 1t or systems and 2) tests or experiments completed under the'p.. vision 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 i
question as defined in Section 50.59, 10 CFR.
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d.
Proposed changes to Technical Specifications or this Operating License, e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
SEQUOYAH - UNIT 1 6-10 Amendment No, m.74
i
-ADMINISTRATIVE CONTROLS 1
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Significant operating abnormslities or d2viations from nomal and expected performance of unit equipment that. affect nuclear safet).
I g.
All PEPORTABLE EVENTS.
h.
All recogni:ed indications of an unanticipated deficiency in some aspect of' design or operation of structures, systems, or components that could affect nuclear safety, 4
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Reports and meetings minutes of the PORC and the SQN RARC.
AUDITS 4
i 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
i
~The conformance of unit operation to provisions contained within the a.
Technical Specifications and applicable license conditions at least once per 12 months, b._
The performance, training and qualifications of the entire facility,
l staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in c.
unit equipment, structures, systems cr a:..';od of operation that af feet nuclear safety at lekst once per 6 months.
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.d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "8",10 CFR 50, at least once per 24 months,
.The Site Radiological Emergency Plan and implementing procedures at i
e.
least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.'
g.
Any other area of unit operation considered appropriate by the NSRB or the Senior Vice President, Nuclear Power.
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 and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
SEQUOYAH - UNIT 1 6-11 Amendment No. 88 74
ADMINISTRATIVE CONTROLS k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE 00SE' CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL-PROGRAM and implementing procedures for m.
SOLIDIFICATION of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance n.
Program to meet the criteria of Regulatory Guide 4.15 December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev. 1, 1975, at least once per 12 months.
4 AUTHORI*/Y 6.5.2.9 The NSRB shall report to ano OJVise the Senior Vice President, Nuclear Power those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRB meeting sh6 t be prepared, 3pproved and forwarded to the Senior Vice President, hoc 1*,ar hover within 14 days following i
each meeting, b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President, Nuclear Power and to the management positions responsible for the areas audited within 30 days after com-pletion of the audit.
6.5.3 RADIOLOGICAL ASSESSMENT R,EVIEW COMMITTEE (RARC)
Function 6.5.3.1 The SQN RARC shall function to advise the Corporate Manager of Radio-l logical Control and the Plant Manager on all matters related to radiological
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assessments involving dose calculations and projections and environmental monitoring.
i Composition 6.5.3.2 The SQN RARC shall be composed of the:
Chairman: Technical Assistance Section Supervisor Member:
Health Physicist, Gaseous, Radiological Control Member:
Health Physicist, Liquid, Radiological Control SEQUOYAH - UNIT 1 -
6-12 Amendment No. 42, 58, 74 152
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4 ADMINISTRATIVE CONTROLS Member: -
Meteorologist, Air Quality Branch-Member:
Chemical Engineer, Chemistry Section, SQN Member:
Health Physicist, Environmental Monitoring, Radiological Control Ahernates
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6.5.3.3 All alternste members shall be appointed in writing by the SQN RARC
'f Chairman to *erve on a temporary basis; however, no more than two alternates shall participate as voting members in SQN RARC activities at any one time.
Meeting Frequency 6.5.3.4-The SQN RARC shall meet at least once per six months or as requested by the SQN RARC Chairman, his designated alternate, or a plant representative..
Quorum 6.5.3.5 The minimum quorum of the SQN RARC necessary for the performance of the SQN RARC responsibility and authority provisions of these technical specifica-tions shall consist cf the Chairman or his designated alternate and 4 members.
(including alternates) as long as one is a plant representative.
i Responsibilities 6.5.3.6 The SQN RARC shall be responsible for:
Review of changes to the OFFSITE DOSE CALCULATION MANUAL.
a.
b.
Review of procedures required by Specification 6.8.4 and changes r
thereto.
Review for information purposes of the results of any audits, c.
reviews, or evaluations of the Quality Assurance Program for effluent and environmental monitoring and radiological assessments involving i
dose evaluations and projections.
d.
Review of proposed changes to the Technical Specifications related to radiological assessments involving dose calculations and projections
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and environmental radiological monitoring.
I Authority 6.5.3.7 The SQN RARC shall:
I
- t i
Recommend-in writing to the Corporate Manager of Radiological Control l
E a.
and the Plant Manager, approval or disapproval of items considered under 6.5.3.6 above.
b.
Render determinations in writing with regard to whether or not each
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item considered under 6.5.3.6 constitutes an unreviewed safety question.
SEQUOYAH - UNIT 1 6-13 Amendment No. 58, 74 152 i'
ADMINISTRATIVE CONTROLS 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 Senior Vice President, Nuclear Power and the Nuclear Safety Review Board of dis-agreement between the SQN RARC and the Corporate Manager of Radio-logical Control; however, the Corporate Manager of Radiological Control shall have responsibility for resolution of such disagreement pursuant to 6.1.2 above.
Records 6.5.3.8 The SQN RARC shall maintain written minutes of each SQN RARC meeting that at a minimum, document the results of all SQN RARC activities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Senior Vice President, Nuclear Power; PORC; and the Nuclear Safety Review Board.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified and a report submitted pursuant a.
to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Site Vice President.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions 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 NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Site Vice President l
and the NSRB shall be. notified 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 i
be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation i
l upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
I d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Site Vice President within 14 days of the violation.
l 6.8 PROCEDURES & PROGRAMS l
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
i a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
SEQUOYAH - UNIT 1 6-14 Amendment No. 36, 58, 74 152
ADMINISTRATIVE CONTROLS HONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
I RADIAL PEAKING FACTOR LIMIT REP 0".
6.9.1.14 The W(z) function for normal operation shall be pt M ded at least i
60 days prior to cycle initial criticality.
In the event t V *hese values would be submitted at some other time during core life, it w.. Le submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.
SPECIAL REPORTS 6.9.2.1 Special reports shall be submitteo within the time period specified for each report, in accordance with 10 CFR 50.4.
6.9.2.2 DieselGeneratorReyabilityImprovementProgram As a minimum the Reliability Improvement Program report for NRC audit, required by LCO 3.8.1.1, Table 4.8-1, shall include:
(a) a sumaary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed (b) analysis of feilures and detern tion of root causes of failures (c) evaluation of each of the rece
..idations of NUREG/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"
with respect to their application to the Plant (d) identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action from d) above (f) an assessment of the o isting reliability of electric power to engineered-safety-feature equipment SEQUOYAH - UNIT 1 6-21 Amendment Nos. 42, 58, 72, 74, 117, 152 1
I ADMINISTRATIVE CONTROLS 6.11 RADIATION PM ". TION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
G.12 HIGH RADIATION AREA 6.12,1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspi %.y posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special (Radiation)
Work Permit *,
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
i b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms wt.en a preset integrated dose is received.
Entry into such areas with this ronitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of tham.
An individual qualified in radiation protection I.-:cadures who is c.
equipped with a radiation dose rate monitoring device.
This individual
~
shall be responsible for providing positive control over the activities l
within the area and shall perform control over the activities within L
the area and shall perform periodic radiation surveillance at the frequency specified by the facility Site Radiological Control Manager l
in the Special (Radiation) Work Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 ri. rem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such arecs and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Site Radiological Control Manager.
l 1
i
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with appreved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with aoproved radiation protection procedures for entry into high radiation areas.
SFT10YAH - UMT 1 6-24 Arngment No. 42, 58, 74
~
- X kqa eso h; o
15 UNITED STATES n
NUCLEAR REGULATORY COMMISSION
. WASHINGTON o.C. 20eI6 TENNESSEE' VALLEY AUTHORITY-DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FCILITY OPERATING LICENSE Amendment No.142 License No. DPR-79 1.
The Nuclear Regulatory Comission-.(the Conunission)~ has found that:
A.
The application for amendment by Tennessee. Valley Authority (the
. licensee) dated December 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as: amended (the Act).
and the Comission's rules and regulations set forth in 10 CFR-Chapter I;--
B.
The facility will operate in conformity with the application,.the gi provisions of the Act, and the rules and regulations of the Comission;
~
~
C.-
There-is-reasonable assurance (i) that the activities authorized by-this amendment can be conducted without endangering-the health and-
-safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.-
The issuance of this amendment will not be inimical to the common defense-and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
=-
-2.
Accordingly, the license is amended by changes to the Technical:
Specifications as indicated in the attachment to this license amendment-and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. -
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
b L A 1.1).d A Frederick J. Heb n, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 22, 1991 i
f i
ATTACHMENT TO ',1 CENSE AMENDNENT NO.14?
I
-FACll.lTY OPERATING t.lCENSE NO. OPR-79 l
i DOCKET NO, 50 328 l
l l
Revise the Appendix A Technical Specifications by removing the pages I
identified below and inserting the enclosed pages. The revised pages i
are identifind by the captioned amendment nusiber and contain surginal-lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
RFMOVE INSERT s
6-1 6-1 6-2 6-2 i
.6-5 6-5 l
r 6-6 6-6 6-7*
6 7*
6-8 6-8 69 6-9 i
6-10*
6-10*
i 6 11*
/-11*
l t
6-12 6-12
~
6-13 6-13 i
6-14 6+ 14
'(
6 22 6-22 5
6 25 6-25 l
E t
i
)
L
...,. -. ~. _..
. _ _ _.. - - _. _.... -, -. _. _. _. - _ _. _ _... _.. _ _.. _.... _ _ _ _ _,. _ -,. ~. _.
I
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1. 2 The Corporate Manager of Radiological Control shall be responsible for l
implementing the radiological environmental program and dose calculations and projections as described in the Gifsite Oose Calculation Manual (ODCM).
6.1. 3 The Shif t Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command func-tion.
A management directive to this effect, signed by the Site Vice President shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation and corpnrate management.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be a.
established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR and will be updated in accordance with 10 CFR 50.71(e).
b.
The Senior Vice President, Nuclear Group shall have corporate responsibility for overhil plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
I c.
The Plant Manager shall be respo'.sible for overall unit safe i
operation, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant, d.
The individuals who train the uperating staff and those who carry out
[
health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
i 6.2.2 FACILITY STAFF a.
Each on duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
i b.
At least one licensed Reactor Operator shall be in the unit Control l
Room when fuc1 is in the reactor.
In addition, while the unit is in MODE 1, 2, 3 or 4, at M ast one licensed Senior Reactor Operator shall be in the Control Room.
I I
SEQUOYAH - UNIT 2 6-1 Atendunt No. 24, 50, 66 142
. ~ -.
I r
ADNINISTRATIVE CONTROLS A Radiological Control technicicn# shall be onsite when fuel is in the c.
reactor.
All CORE ALTERATIONS shall be observed and directly supervised by I
d.
either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlin i
during this operation g who has no other concurrent responsibilities
(
AFireBrjgadeofatleast5membersshallbemaintainedonsiteat e-i all times.
The Fire Brigade shall not include the Shift Supervisor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential
^
functions during-a fire emergency.
i f.
The Operations Manager shall hold a Senior Reactor Operator license.
g.
Administrative procedures shall'be developed and implemented to
{
limit the workin functions (i.e.,g hours of unit staff who perfom safety-related senior reactor operators, reactor operators, assistant unit operators Radiclogical Control, and key maintenance i
personnel).
Adequate shift coverage shall be maintained without routine heavy
[
use of overtime.
The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.
i However, in the event that unforseen problems require substa'ntial l
amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintanance, or major plant modification, on a temporary basis the following guidelines shall be j
followed:
I 1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time, t
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.
3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work I
periods, including shift turnover time.
4.
Except during extended shutdown periods. +,he use of overtime should be considered on an individual basis and not for the l
entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Flant Manager (or Duty Plant Manager), or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the-deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant
~;
Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
t t
i
- The Radiological Control technician and fire brigade composition may be less than the minimum requiren,ents for a period of time not to exceed 2 hourt, in order to accommodate unexpected absence provided immediate action is taken I
to fill the required positions.
SEQUOYAH - UNIT 2 6-2 AmepntNo.50,66
[
2
i ADNINISTRATIVE CONTROLS l
6.2.3 INDEPENDENT SAFETY ENGINEERING (ISE)
FUNCTION
}
l 6.2.3.1 The ISE shall function to examine plant operating characteristics, i
NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety, j
COMPOSITION i
6.2.3.2 The ISE shall be composed of at least 3 dedicated full time engineers located onsite.- These engineers will be supplemented as necessary by full-time engineers shared among all TVA nuclear sites to achieve an equivalent staffing
-of 5 full-time engineers. performing the ISE functions applicable to Sequoyah.
l RESPONSIBILITIES-i
-6.2.3;3 The ISE shall be responsible-for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical, j
AUTHORIT,Y n
6.2.3.4 The ISE shall make detailed rh ommendations for revised procedures, equipment modifications, or other means of improving plant safety to the 7
j Manager of Nuclear Managers Review Group, i
6.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve in an advisory capacity _to the Shift Supervisor on l
I matters pertaining to-the engineering aspects of assuring safe operation of the unit.
f 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 positions and the supplemental r
requirements specified in Section A and C of Enclosure 1 of March 28, 1980 NRC
[
.-letter to all licensees, except for the Site Radiological Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.-
L i
i
- Not responsible for sign-off function.
SEQUOYAH - UNIT 2 6-5 Amendment No. 50, 66, 142
-.- - -I
ADMINISTRATIVE CONTROLS
- 6. 4 TRAINING 6.4.1 A retraining and replacement training program for the facility s.ff shall be maintained under the direction of the Plant Manager and shall meet or l
exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 Senior Vice President, Nuclear Power is responsible for the safe opera-tion of all TVA power plants.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:
Operations Manager l
Member:
Site Radiological Control Manager Member:
Maintenance Manager Member:
Technical Support Manager Member:
Quality Engineering and Monitoring Supervisor Member:
Nuclear Engineering Representative l
l t
i i
l SEQUOYAH - Ur.I 2 6-6 Amendment No. 50, 66, 142
ADMINISTRATIVE CONTROLS ALTERNATES
- 6. 5.1. 3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
MEETING-FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the Pt'RC Chairman or his designated alternate.
QUOQ 6.5.1.2
- he minimum quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall cov.ist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 Tne PORC shall be responsible for:
Providing for an oversight review of selected safety evaluations a.
for:
(1) procedures and (2) change to procedures, equipment, systems or facilities to verify that such actions did not constitute an unreviewed safety question.
b.
Review of all proposed tests and experiments that affeet nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
d.
Review of proposed procedures and changes to procedures, programs, equipment, system or facilities which involve an unreviewed safety question as defined in 10 CFR 50.59.
Review of reports covering evaluation and recommendations.to prevent e.
recurrence of all violations of the Technical Specifications, f.
Review of all REPORTABLE EVENTS.
g.
Review of anit operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the Nuclear Safety Review Board.
l l
SEQUOYAH - UNIT 2 6-7 Amendment No. 5A/ 66
1 ADMINISTRATIVE CONTROLS 1.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Site Vice President and to the Nuclear Safety Review Board, l
i AUTHORITY 6.5.1.7 The PORC shall:
Recommend in writing to the Plant Manager approval or disapproval of a.
items considered under 6.5.1.6(a), (b) and (c) above.
b.
Require a determination in writing with regard to whether or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question, 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 Site Vice c.
President and the Nuclear Safety Resiew Board of disagreement between l
the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS
- 6. 5.1. 8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Vice President and the Nuclear Safety Review Board.
l 6.5.1A TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1A.1. Activities which affect nuclear safety shall be conducted as follows:
Procedures required by Specification 6.8.1 and other procedures which a.
affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure ct.ange shall be reviewed by a qualified individual other than the individual who prepared the procedure or procedure change, but who may be from the same organiza-tion as the individual who prepared the procedure or procedure change.
Procedures shall be approved by the appropriate responsible manager as designated in writing by the Plant Manager.
The Plant Manager, or Outy Plant Manager shall approve designated Administrative Procedures.
b.
Proposed changes or modifications to structures, systems, and components that affect plant nuclear safety shall be reviewed by a qualified indi-j vidual/ group other than the individual / group which designed the modifi-cation, but who may be from the same organization SEQUOYAH - UNIT 2 6-8 Amendment No. 50, 66, 142
.___...___.m
[
t ADMINISTRATIVE CONTROLS I
as the individual / group which designed the modifications.
Proposed modifications to structures, systems, and components that affect plant i
nuclear safety shall be approved prior to implementation by the Plant Manager, or Duty Plant Manager.
I Individuals responsible for reviews performed in accordance with Specifica-c.
tions 6.5.1A.la and -b, shall be designated by approved written procedures.
Each such review shall be performed by qualified personnel of the appro-priate discipline and shall include a determination of whether or not additional, cross-dsciplinary review is necessary.
Each such review shall also include determination of whether or not an unreviewed safety question is involved pursuant to Section 10 CFR 50.59.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION t
- 6. 5. 2.1 The NSRB shall function to provide for independent review and audit to assure adequacy 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 i
h.
quality assurance practices COMPOSITION 6.5.2.2 -The NSRB shall be composed of at least five members, including the Chairman.
Members of the NSRB may be from Nuclear Power, or other TVA organization or 4xternal to TVA.
QUALIFICATIONS-6.5.2.3 The Chairman, members, and alternate members of the NSRB shall be appointed in writing by the Senior Vice President, Nuclear Power and shall have an academic degree in engineering or a physical science field, or the equivalent; and in addition, shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
i SEQUOYAH - UNIT 2 6-9 Amendment No. 50, 66 142
l
+
ADMIN!STRAT!VE CONTROLS CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSR8 Chairman to i
provide expert advice to the NSR8.
4 MEETING FREQUENCY 6.5.2.5 The NSR8 shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter, bOORUM 6.5.2.6 -The minimum quorum of the NSR8 necessary for the performance of the NSR8 review and audit-functions of these technical specifications shall consist of more than half the NSR8 membership or at least 5 members, whichever is greater.
This quorum shall include the Chairman or his appointed alteraate and the NSR8 members, including appointed alternate members, meeting the requirements of Specification 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
l REVIEW 6.5.2.7_ The NSR8 shall be _ cognizant of revim of:
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 unresiewed safety question as defined in Section 50.59,;10 CFR.
Proposed tests or experiments which involve an unrevie'wed safety c.
question as defined in Section 50.59, 10 CFR.
d.
Proposed changes-to Technical Specifications or this Operating License,
- e.. - Violations of 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 unit equipment that affect nuclear safety.
g.
-All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
1.-
Reports and meetings n;inutes of the PORC and the SQN RARC.
SEQUOYAHf UNIT 2 10 Amendment No. 79 66
.3
e
(
ADMINISTRATIVE CONTROLS i
AUDITS
- 6. 5. 2. 8 Audits of unit activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
The conformance of unit operation to provisions contained within the a.
Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
L The results of actions taken to correct deficiencies occurring in c.
unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Operational Quality I
Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
The Site Radiological Emergency Plan and implementing procedures at,
e.
least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB or the Senior Vice President, Nuclear Power.
l, 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 and audit shall be performed annually utilizing either. qualified 3
i offsite licensee personnel or an outside fire protection firm, i
j.
An inspecti " and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological environmental monitoring program and the.results thereof at least once per 12 months, e
l 1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
l m.
The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least once per 24 months.
The performance of activities required'by the Quality Assurance n.
Program to meet the criteria of Regulatory Guide 4.15, December 1977 I
or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev.1,1975, at least once per 12 months.
i SEQUOYAH - UNIT 2 6-11 Amendment No. 34, 50/ 66 1
l' ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Senior Vice President, Nuclear Power on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
i i
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
i I
Minutes of each NSRB meeting shall be prepared, approved and forwarded i
a.
to the Senior Vice President, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be i
prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded c.
to the Senior Vice President, Nuclear Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.5.3 RADIOLOGICAL ASSESSMENT REVIEW COPHITTEE (RARC)
Function t
6.5.3.1 The SQN RARC shall function to advise the Corporate Manager of Radio-l
[
logical Control and the Plant Manager on all matters related to radiological assessments involving dose calculations and projections and environmental monitoring.
Composition 6.5.3.2 The SQN RARC shall be composed of the:
1 Chairman: Technical Assistance Section Supervisor Member:
Health Physicist, Gaseous, Radiological Control Member:
Health Physicist, Liquid, Radiological Control l
Member:
Meteorologist, Air Quality Branch i
Member:
Chemical Engineer, Chemistry Section, SQN Member:
Health Physicist, Environmental Monitoring, Radiological Control Alternates 6.5.3.3 All alternate members shall be appointed in writing by the SQN RARC Chairman to serve on a temporary basis; however, no more than two alternates i
shall participate as voting members in SQN RARC activities at any one time.
Meeting Frequency 6.5.3.4 The SQN RARC shall meet at least once per six months or as requested by the SQN RARC Chairman, his designated alternate, or a plant representative.
SEQUOYAH - UNIT 2 6-12 Amendment No. 50, 66, 142
I i
ADMINISTRATIVE CONTROLS Quorum 6.5.3.5 The minimum quorum of the SQN RARC necessary for the performance of i
the SQN RARC responsibility and authority provisions of these technical speci*
l fications shall consist of the Chairman or his designated alternate and f
4 members (including alternates) as long as one is a plant rop.esentative, i
Responsibilities i
6.5.3.6 The SQN RARC shall be responsible for:
Review of changes to the OFFSITE DOSE CALCULATION MANUAL.
a.
b.
Review of procedures required by Specification 6.8.4 and changes l
thereto.
~
Review for information purposes of the results of any audits, reviews, c.
or evaluations of the Quality Assurance Program for effluent and i
environmental monitoring and radiological assessments involving dose i
evaluations and projections.
I d.
Review of proposed changes to the Technical Specifications relatert to j
i radiological assessments involving dose calculations and projections i
and environmental radiological monitoring.
Authority 5
I 6.5.3.7 The SQN RARC shall:
i q
Recommend in writing to the Corporate Manager of Radiological Control l
j a.
and the Plant Manager, approval or disapproval of items considered under 6.5.3.6 above.
e b.
Render determinations in writing with regard to whether or not each item considered under 6.5.3.6 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 Senior Vice
[
President, Nuclear Power and the Nuclear Safety Review Board of dis-i agreement between the SQN RARC and the Corporate Manager of Radio-logical Control; however, the Corporate Manager of Radiological Control shall have responsibility for resolution of such disa-greement pursuant to 6.1.2 above.
P Records I
6.5.3.8 The SQN RARC shall maintain written minutes of each SQN RARC meeting i
that at a minimum, document the results of all SQN RARC activities performed under the respcnsibility and authority provisions of these technical specifi-cations.
Copies shall be provided to the Senior Vice President, Nuclear Power; i
PORC; and the Nuclear Safety Review Board.
t SEQUOYAH - UNIT 2 6-13 Amendment No. 50, 66, 142 I'
_ _ ~. -
L ADMIN!$TRATIVE CONTROLS l
b 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified and/or a report submitted pursuant a.
to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Site Vice President.
6.7 SAFETY LIMIT VIOLATION i
i 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The unit shall be placed in at least HOT STANDBY within one hour.
a.
b.
The NRC Operations Center shall be notified by telephone as soon as i
possible and in all cases within one heur.
The Site Vice President l
and the NSRB shall be notified 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 PORC.
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 NSRB and the Site Vice President within 14 days of the violation.
l t
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations, c.
Surveillance and test activities of safety related equipment.
I d.
Plant Physical Security Plan implementation, e.
Site Radiological Emergency Plan implementation.
f.
Fire Protection Program implementation, g.
PROCESS CONTROL PROGRAM implementation.
I SEQUOYAH - UNIT 2 6-14 Amendment No. 28, 50, 66 l
142 i
I
ADMINISTRATIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
g RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided at least 60 days prior to cycle initial criticality.
In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.
Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.
SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4.
6.9.2.2 Diesel Generator Reliability Improvement Program As a minimum the Reliability Improvement Program report for NRC audit, required by LCO 3.8.1.1, Table 4,8-1, shall include:
(a) a summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid te.ts were performed (b) analysis of failures and determination of root causes of failures (c) evaluation of each of the recommendations of NUREG/CR-0660, "E.
.ement of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"
with respect to their application to the Plant (d) identification of all actions taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability (e) the schedule for implementation of each action frca d) above (f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment SEQUOYAH - UNIT 2 6-22 Amendment Nos. 44, 50, 64, 66, 107, 134, 142
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 _HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special (Radiation)
Work I'armit*.
Any individual or group of individuals pemitted to enter such areas shall be provideo with or accompanied by one or more of the following.
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated j
dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been estab-lished and personnel have been made knowledgeable of them.
I An individual qualified in radiation protection procedures who is c.
equipped with a radiation dose rate monitoring device.
This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform control over the activ-i ities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Site Radiological l
Control Manager in the Special (Radiation) Work Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high i
radiation area in which the intensity of radiation is greater than 1000 mrem /
h r.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative
{
control of the Shift Supervisor on duty and/or the Site Radiological Control t
Manager.
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SEQUOYAH - UNIT 2 6-25 Amendment No. 34, 50, 66 142