ML20073B557
| ML20073B557 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/18/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20073B555 | List: |
| References | |
| NUDOCS 9104240262 | |
| Download: ML20073B557 (12) | |
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l PRol'OSED TECHNICAL SPECIFICATION CilANGES j
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6.0 AD111tilSTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President, Operations ANO shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and of fsite organizations shall be established for unit operation and corporate management, respectively. The onsite and of fsite organizations shall include the positions for activities af fecting 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 Icvels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the Carm of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivaletit forms of documentation.
These requirements shall be documented in the QA Manual Operations.
b.
The General Manager, Plant Operations shall be rnsponsibic for l
overall uait safe operation and shall have control over those onsite activities necessary for safe operation 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.
The individuals who train the operating staf f 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.
FACILITY STAFF 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 shif t crew composition shown in Table 6.2-1.
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Amendment No. Jf,15,74,$1, 117 F1,50,59,ff,ft.f5,99,lty,111,116,1F1, 1
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6.2.2.1 Administratise controls shall be established to limit the amount of overtime worked by plant staff performing safety-related functions.
These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter 82-12).
6.3.
FACILIIY STAFF OUALIEJCATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for (1) the designated radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall havn a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staf f 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 Tart 55, 6.4.2 A training proprim for the Fire Brigado shall be maintained under the db action 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 Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUD1I 6.5.1 Plant Safeev Committeo (PSC) Function 6.5.1.1 The Plar.t Safety Committee shall function to advise the Gennen! danager, Plant Operations and Plant Manager, ANO-1 on l
all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Committen shall be composed of eight members and ANO onsito management organization at the superintendent level or above.
The PSC Chairman shall ensure that adequate expertiso is present during meetings to evaluate material before the PSC.
In addition, the General Manager, Plant Operations shall j
designate in writing a PSC Chairman and at least one A1tornato Chairman.
Amendment No. J6,75,EA,$/,
117a A7,EP.17,6A,Et,EE,77,107,JJ2,12A,JA3,
ALTERNATES 6.5.1.3 All altr>rnate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participato as voting members in PSC activities at any one time.
tiEETItiG_EEEQEERCl 6.5.1.4 The PSC shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternatn.
Qll0RM 6.5.1.5 The minimum quorum of the PSC necessary for the performance of the PSC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:
I a.
Review of 1) all procedures required by Specification 6.8 and changes in intent. thereto, 2) any other proposed procedures or revisions thereto as determined by the General Manager, Plant Operations
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or Plant Manager, ANO-1 to affect nuclear safety, b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the Appendix "A"
c.
Technical Specifications.
d.
huview of all proposed changes or modifications to plant systems or equipment that affect nucicar
- safety, Investigation of all violations of the Technical c.
Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Plant Manager, ANO-1, General Manager, Plant Operations and
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to the Chairman of the Safety Review Committee.
f.
Review of REPORTABLE EVENTS.
g.
Review of facility operations to detect potential nuclear safety hazards.
Amendment No. E5,77,Jf7,JJ1,JJE,J24, 121
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h.
Perfora nce of sp2cici revicws, investigstions, or analyses and reports thereon as requested by the Plant Manager, ANO-1, General Manager, Plant Operations or the Safety Review l
Committee.
1.
Review of the Plant Security Plan and implementing procedures and submittal of recoemended 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 the Safety Review Committee.
k.
Review of changes to the Offsite Dose Calculation Manual and the Process Control Program.
AUTil0RITY 6.5.1.7.
The Plant Safety Committee shall:
Recommend in writing their approval or disapproval of items a.
considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unroviewed 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 between the PSC and the Plant Manager, ANO-1 or the General Manager, Plant Operations; however, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of all PSC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Plant Manager, ANO-1, General Manager, Plant Operations and Chairman of the Safety Review Committee.
6.5.2 Safety Review Committee (SRC)
FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
a, nuclear power plant operations b.
nuclear engineering l
c.
chemistry and radiochemistry i
Amendment No. J6,34,51,47,55,52, 122 55,99,199,17?,1F),
6.8.2 Each procedure of 6.8.1 cbove, and chang s in intent thsrsto, chall be reviewed by the PSC and approved by the General Manager, Plant Operations, Plant Manager, ANO-1 or responsible Major Department llend 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:
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 licenne 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 rasr nisible Major Department llead, within 14 days of implementation.
Amendment No. 16,5$,34,37, 16,52,5E, 127 74,77,JP7,12A,143,
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t PROPOSED TECHNICAL SPECIFICATION CHANGgs UNIT 2 l
1 6.0 ADMINISTRATIVE CONTRnLR 6.1 RESP 0NSIBILITY 6.1.1 The Vice President Operations ANO shall be responsible for overall facility operations and shall delegate in writing the succession tc this i
responsibility during his absence.
6.2 ORGANIZATION 6.2.1 QFFSITE AND ONSITE ORGANIZATIONS 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, a.
Lines of authority, responsibility, and communication shall be 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 relationships, 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
overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the 3
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 i
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, tht/ shall havo. sufficient organizational' freedom.to ensure their independence from operating-pressures.
L 6.2.2 FACILITY STAFF.
1 i
a.
Each on-duty shift shall be_ composed of at least' the. minimum shift j
crew composition shown-in Table 6.2-1.
b.
At least one licensed Operator'shallibe-in the control room'when-
' fuel is in.the reactor.
l ARKANSAS - UNIT 2 1 Amendment No. 5,55,57,75,55,57,75,-
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ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OUALIFICATIONS 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 designated radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shif t Technical Advisor who shall have a bachelors degree or equivalent in a scientific or engineering discipline with specif(c training in plant design, and e
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 Brigade training sessions which shall be belo at least quarterly.
15 REVIFW AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)
FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the General Manager, 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 qualificationLrequirements: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:
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ARKANSAS - UNIT 2 6-5 Amendment No. 5,12,17,:
15,19,51,75,55, 95,11F,
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i ADMINISTRATIVE CONTROLS a
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.
HEETING FREQUENCY 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.
OUORUM 6.5.3.6 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 Plant Safety Committee shall be responsible fort Review of 1) all procedures required by. Specification 6.8 and a.
changes thereto, 2) any other proposed procedures or changes in intent thereto as -determined by the General 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.
c.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of
~
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,J/,52,1),85 15,
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6 AnMINISTRATIVE CONTROLS f.
Review of all REPORTABLE EVENTS.
g.
Review of facility operations to detect potential nuclear safety hazards.
h._
Performance of special reviews, investigations or analyses, and reports thereon as requested by the Plant Manager,.ANO-2, General Manager, Plant Operations or the-Safety Review Committee.
i.
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.
AUTHORITY 0.5.1.8 The Plant Safety Committee shall:
Recommend in writing their approval or disapproval of ' items a.
considered under 6.5.1.6(a) through.(d) above.
3 b.
Render determinat' ions 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, 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.
c.
Operations ANO and the Safety Review Committee of disagreement between the PSC and the Plant Manager, ANO-2 or the General Manager, Plant Operations; however, the General Manager, Plant _ Operations 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 minimumi 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.
ARKANSAS - UNIT 2-6-7
- Amendment No.'),J7,25,52,55, 15,55,91,=95,11f,
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ADMINISTRATIVE CONTROLS 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 Vice President, Operations ANO and 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 10CFR50.36 and Specification 6.6.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of-Regulatory Guide 1.33. Revision 2, February 1978.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
t f.
Fite 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 intsraction 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 t
reviewed by the PSC and approved by the General Manager, Plant Operations, Plant Manager, ANO-2 or responsible Major Department Head prior to. implementation and' reviewed periodically as set forth in administrative procedures.
1 ARKANSAS - UNIT'2:
6-13' AmendmentNo.24i25,$3,52, j
69,55,15,11,55,91, 95,llf s '
ADUREIRAIMEJQRIRQk 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.
1 b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reector Operator's !.icense on Unit 2.
c.
The change is documented, reviewed by the pSC and approved by the General Manager, plant Operations, plant Manager, ANO-2 or responsible Mt.jor Department lload within 14 days of implementation.
6.9 REPORTING REOUIREHFltIS R.00 TINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulat ions, the following reports shall be submitted to the Administrator of the Regional Of fice unless otherwise noted.
STARTUEREFAI 6.9.1.1 4 summary report of plant startup and power escalation testing shall be submitter'. following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplior, and (4) modifications that may have significantly altered the nucicar, thermel, or hydraulic performance of the plant.
6.9.1.2 The startup report.shall address each of the tests identified in the FSA2 and shall include a description of the measured values of the operating co.iditions or characteristics obtained 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.
6.9.1.3 Startup reporte shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial i
criticality, whichever is earliest.
If the Startup Report does not cover all I
three events (i.e..- Initial criticality, completion of startup test program, 'and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
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ARKANSAS - UNIT 2 6-14 Amendment No. 5,52,7),$5, 91,95silf, r
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