ML20081L637
| ML20081L637 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/19/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20081L641 | List: |
| References | |
| DPR-51-A-147, NPF-06-A-119 NUDOCS 9107050224 | |
| Download: ML20081L637 (20) | |
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DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO.1-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 18, 1991, complies with-the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act),
and the Commission'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 Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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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-51 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.147, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ku$tu h b"cp Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V.
Office of Nuclear Reactor Regulation Attachrent:
Changes to the Technical Specifications Date of Issuance:
June 19,1991 l
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ATTACHMENT TO LICENSE AMENDMENT NO.- 147 FACILITY OPERATING LICENSE-NO. DPR DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technica*, Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change, REMOVE PAGES INSERT PAGES 117 117 117a 117a 121 121 122 122 127 127 i
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President, Operations ANO shall be responsible for overall f acility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 6.2.1 OTTSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall'be established for unit operation and corporate management, respectively. The onsite and of fsite organizations 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 for 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 organization charts, functional descriptions of departmental responsibilities and reletionships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the QA Manual Operations, b.
The General Manager, Plant Operations shall be responsible for l
overal) unit safe operation and shall have control over those ensite activities necessary for safe operatior. and maintenance of the plant.
c.
The Vice President, Operations ANO shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
Tbn 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.
TACILITY STATT 6.2.2 The Manager, Operations and Shift Supervisor shall hold a senior reactor operator license. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
Acendment No. Jf,?f,74,77, 117 4 7.f f.f f,f A,f 2,71 P P, J f f, J J2,124,147,147
ALILIL'BITJ 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 TREQUENCY 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.
000 RUM 6.5.1.5 The minimum quorum of the PSC necessary for the performance of the PSC responsibility and authority provisions of these techt.ical specifications shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES e.;.1.6 The Plant Safety Committee shall be responsible for:
Review of 1) all procedures required by Specification a.
6.6 and changes it. intent thereto, 2) any other preposed procedures or revisions thereto as determined by the General Manager, Plant Operaticas
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or Plant Manager, ANO-1 to affect nuclear safety, b.
Review of all proposed tests and experiments trat affect nuclear safety, Review of all proposed changes to the Appendix "A" c.
Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical e.
Specifications, including the preperation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Plant Manager, ANO-1, General Manager, Plant Operations and j
to the Chairman of the Safety Review Committee, f.
Review of REPORTABLE EVENTS, Review of facility operations to detect potential g.
nuclear safety hazards.
Am e nd r e r: t No. f],97.Jff.JJ2,JJP,12A, 121 14?,147
6.8.2 Each procedure of 6.8.1 above, cnd ch:ngos in intent theroto, shall be reviewed by the PSC and approved by the General Mtnagst, Plant Operations, Plant Manager, ANO-1 or responsible Major Department Head prior to implementation and reviewed periodically as set forth in administrative procedures.
- 6. 8. 3 -
Changes to procedures of 6.8.1 above may be made and implemented prior to obtaining the review and approval required in 6.8.2 above provided:
The intent of the original procedure is not altered.
a.
b.
The change is approved by two members of the plant management staf f, at least one of whom holds a Senior Reactor Operator's license on' Unit 1.
The change is documented, reviewed by the-PSC, and approved by c.
the General Manager, Plant Operations, Plant Manager, ANO-1 or-responsible Major Department Head, within 14 days of implementation.
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Arendment No. Jf,2f,34,77, 7f,f2,ff, 127 P4,7 7,1f 7,224,143,147 l
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DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. NPF-6 1.
The Nuclear Regulator) Comission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc.
(the licensee) dated April 18,1991, conplies with the standards and i
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 op? rate in conformity with the application, the provisions of the Act, and the rules and-regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted ir, compliance with the Commission's regulations; D.
The ' issuance of this license 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 Commission's regulations and all applicable requirements-have been satisfied.
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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.
NPF-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical. Specifications contained in Appendix A, as revised through Amendnent No.119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m.bw d1. 4 3 Theodore R. Quay, Director.
Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 19, 1991 4
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ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the_ area of-change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 6-1 6-1 j
6-5 6-5 6-6 6-6 6-7 6-7 6-13 6 6-14 6-14 l
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(. 0 ADMINISTRATIVE CONTROLR
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s 6.1 RESPONSIBILITY 6.1.1 The Vice President, Operations ANO shall be responsible for overall facility operations and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 6.2.1 OTTSITE AND ONSITE OPG&SIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations 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 fer 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 organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the QA Msnual Operations.
J b.
The General Manager, Plant Operctions shall be responsible for l
f overall unit safe operation and shall have control over those onsite j
activities necessary for safe operation and maintenance of the j
plant.
The Vice President, Operations ANO shall have corporate c.
responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
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 STATT Each on-duty shift shall be composed of at least the minimum shift a.
crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
ARKANSAS - UNIT 2 6-1 Amendment No. 5,52,5/,77,55,57,75, 224, 119
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At least two licensed Operators shall be present in the cont'rol c.
room during reactor start up, scheduled reactor shutdown and during recovery from reactor trips, d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
All CORE ALTERAT10N5 shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
Administrative control shall be established to limit the amount g.
of overtime worked by plant staff performing safety-related fun:tions.
These administrative controls shall be in accorcance j
with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).
h.
The Manager, Operations and Shift Supervisor shall heid a senior reactor operator license.
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ARKANSAS-UNIT 2 6-2 Amendment No. 27,-25, 29, 32, 7J. 85. 87. 98.114 j.
ADMfNISTRATIVE CONTPOLS 6.3 UNIT STArr DUALITICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the designate.d radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.6, September 1975, and (2) the Shift Technical Advisor who shall have a bachelors degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Training and Emergency Planning and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Training and Emergency Planning and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for Fire Brigede training sessions which shall be held at least quarterly.
6.5 FEVIEV AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)
TUNCTIOS 6.5.1.1 The Plant Safety Committee shall function to advise the General Manager, Plant operations and Plant Manager, ANO-2 on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of eight members of ANO onsite management organization (except as discussed under 6.5.1.3) at the superintendent level or above. The PSC Chairman shall ensure that adequate expertise is present during meetings to evaluate material before the PSC.
In addition, the General Manager, Plant Operations shall designate in writing a PSC Chairman and at least one Alternate Chairman.
6.5.1.3 If Core Protection Calculator (CPC) Software is being reviewed a nuclear software expert shall be present as a voting member.
If one of the members of the Plant Safety Committee meets the qualification requirements for this position, the requirement to have this member is satisfied. This membership may be filled by two appropriately qualified individuals who shall ballot with a single combined vote.
Generic qualifications for this membership shall be as follows:
AKKANSAS - UNIT 2 6-5 Amendment No. E,22,17, 27,27,32,73,83, 75,124,119 l
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0*e Individugl The Nuclear Software Expert shall have as a minimum's Bachelor's degree in Science or Engineering, Nuclear preferred (in accordance with ANSI N18.3).
In addition, he shall have a minimum of four years of technical experience, of which a minimum of two years shall be in Nuclear Engineering and a minimum shall be in Software Engineering.
(software Engineering is that branch of science and technology which deals with the design and use of software.
Softward Engineering is a discipline directed to the production and modification of computer programs that are correct, eff tetent, flexible, maintainable, and understandable, in reasonable time spans, and at reasonable costs.) The two years of technical experience in Software Engineering may be general software experience not necessarily related to the software of the Core Protection Calculator System. One of these two years of experience shall be with certified computer programs.
Twe Individuals One of the individuals shall meet the requirements of the Nuclear Engineering portion of the above.
The second ir.dividual shall have a Bachelor of Science degree (digital computer speciality) and meet the Scftware Engineering requirements of the above.
The membership (the Nuclear Software Expert or the Digital Computer Specialist) shall be knowledgeable of the Core Protection Calculator Systre with regard to:
a.
Tht software modules, their interactions with each other and with the data base.
b.
The relationship between operator's module inputs and the trip variables.
The relationship between sensor input signals _and the srip c.
- variable, t
d.
The design basis of the Core Protection Calculator System, The approved software change procedure and documentation e.
requirements of a software change.
f.
The security of the computer memory and access procedures to the e
memory.
1 ARLANSAS-UNIT 2 6 ia Amendment No. 22,114
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t ADMINISTRATfVE CONTROLS 9
ALTERNATES 6.5.1.4 -
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 FREOUENCY 6.5.1.5.
The PSC shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternate.
OUOFUM 6.5.1.6 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 6.5.1.7 The Flant ":fety Committee shall be responsible for:
a.
P
.ew of 1) all procedures required by Specification 6.8 and c.-nges thereto, 2) any other proposed procedures or changes in incent thereto as determined by the Genetal Manager, Plant Operations or Plant Manager, ANO-2 to affect nuclear safety, b.
Review of all proposed tests and experiments that affect nuclear safety, Review of-all proposed changes to Appendix "A" Technical c.
Specifications, d.
Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical e.
Specifications, including the_ preparation and_ forwarding of l
reports covering evaluation and recommendation to prevent recurrence to the Plant Manager, ANO-2, General Manager, Plant Operations and to the Chairman of the Safety Review Committee.
ARKANSAS - UNIT 2 6-6 Amendment No. 6,27.52,73,5) 75, i
114,119 i
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Review of all REPORTABLE EVENTS.
g.
Review of facility operations to detset potential nuclear safety hazards.
h.
Performance of special reviews, investigatiot.s or analyses, and reports thereon as requested by the Plant Manager,-ANO-2, General Manager, Plant Operations or the Safety Review Committee.
1.
Review of the Plant Security Plan and implementing' procedures and submittal of recommended changes to the General Manager, Plant Operations and the Safety Review Committee.
j.
Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the General Manager, Plant Operations and Safety Review Committee.
k.
Review of changes to the Offsite Dose Calculation Manual and Process Control Program.
Al'THOFITY 6.5.1.6 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 Vice President, Operations ANO and the Safety Review Committee of disagreement l
between the PSC and the Plant Manager, ANO-2 or the General Manager, Plant Operations; however, the General Manager, Plant Operations l
shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.9 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 Plant Manager, ANO-2, General Manager, Plant Operations and Chairman of the Safety Review Committee.
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-i ARKANSAS - UNIT 2 6-7 Amendment No. 5,27,25,52,ff, 73,55,7J, 7E JZA,119
ASWINISTRATIVE CONTROLS 6.5.2 $4rETY REVIEV COMWITTEE ($RC)
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 d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
Quality assurance practices CO*:011 TION 6.5.2.2 The Safety Review Committee shall be composed of a Chairman and eight to twelve members which collectively have the experience and competence required by ANSI /ANS-3.1-1981 to review problems in the areas specified in Section 6.5.2.1, a-h.
The Vice President, Operations ANO 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.
ARKANSAS-UNIT 2 6-8 Amendment No. 5. 27, 25, 52, 73, 77, 72,114
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ADMINISTRATIVE-CONTRnLR 4
6,7 SATETY 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 Vice President, Operations ANO ard the SRC 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.
The Nuclear Regulatory Commission shall be notified pursuant to 10CFR50.72 and a report submitted pursuant to the requirements of 10CTR50.36 and Specification 6.6.
6.8 PROCEDURES 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 operaticns.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implenientation, e.
Emergency Plan implementation.
f.
Fire Protection Program implementation, g.
Modification of Core Protection Calculator (CPC) Addressable Constants. These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable constants to avoid excessive operator interaction with the CPCs during reactor operation.
NOTE:
Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be performed in accordance with the most recent version of "CPC Protection Algorithm Software Change Procedure," CEN-39(A)-P that has been determined to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior.NRC. approval, h.
New and spent fuel-storage.
1.
- j. -Postaccident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluent, and the containment atmosphere).
6.8.2 Each procedure of.6.8.1 above, the changes. in intent thereto, shall be reviewed by the PSC and approved by-the General Manager, Plant Operations, Plant Manager, ANO-2 or responsible Major. Department Head prior ' o implementation and reviewed periodically as set forth in administrative procedures.
ARKANSAS - OSIT 2 6-13 Amendment No. 24,25,43,32, ft it,11,11,E),91, 95,114,119.
4DM_INISTRATIVE CONTROL 6.8.3 Changes to procedures of 6.8.1 above may be'made and implemented prior to obtaining the review and approval required in 6.8.2 above provided:
a.
The intent of the original procedure is not altered, b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on Unit 2.
The change is documented, reviewed by the PSC and approved by-the c.
General Manager, Plant Operations, Plant Manager, ANO-2 or responsible Psjor Department Head within 14 days of it.plementation.
6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of
)
Tederal Regulations, the following reports shall be submitted-to the 1
Administrator of the Regional Office unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation teating shall be submitted following (1) receipt of an operating license, (2) amendment to the licensa involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, therms 1. or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the TSAR and shall include a descripti:
'f the measured values of the operating conditions or characteristics obtainea during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.14 3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program,-(2) 90 days following resumption or l
commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementaty reports shall be submitted at least every three months until all~three events have been completed.
ARKANSAS - UNIT 2 6-14 Amendment No. 5,52,73,ff, 91,97,1)V.119'