ML20211K313
| ML20211K313 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/26/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211K318 | List: |
| References | |
| NUDOCS 9909070189 | |
| Download: ML20211K313 (26) | |
Text
hsC M%
[
UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20566 0001
%4.....,&
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.198 License No. DPR-51 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated
)
November 24,1998, as supplemented by letters dated February 25,1999, and July 14,1999, complies with the standards and requirements of the Atomic 1
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 j
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 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.
9909070189 990826 PDR ADOCK 05000313 P
PDR b
+
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this lice.1se amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 198, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
j i
l 3.
The license amendment is effective as of the date of issuance and shall be implemented
)
l within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
N Robert A. Gramm, Chief, Section 1 i
Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance: August 26, 1999 i
1
f I
I A'TTACHMENT TO LICENSE AMENDMENT NO.198 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 117 117 117a 117a 118 118 126 126 127 127 128 128 129 129 129a 129a 141 141 146a 146a f
i
)
u
i l
4 o
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The ANO-1 plant manager shall be responsible for overall unit operation l
and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 An individual with an active Senior Reactor Operator (SRO) license shall be designated as responsible for the control room command function while the unit is above the Cold Shutdown condition. With the unit not above the Cold shutdown condition, an individual with an active SRO license or Reactor Operator license shall be designated as responsible for the control room command function.
I 6.2 ORGANIZATION 6.2.1 OFFSITE 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 including the unit specific titles of those personnel fulfilling its responsibilities of the positions delineated in these Technical Specifications shall be documented in the Safety Analysis Report (SAR).
b.
The ANO-1 plant manager shall be responsible for overall unit safe l
operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
1 A specified corporate executive shall have corporate responsibility c.
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. The specified corporate executive shall be documented in the SAR.
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.
UNIT STAFF l
6.2.2 The operations manager or the assistant operations manager shall l
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.
Aniendment No. M,30,34,34,44,60, 1l~l G 64, BG, M,49, M9,443,434,444,444
6.2.2.1 Adminictrativa crntrolo chs11 b2 octchliched to limit ths 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.
FACILITY STAFF QUALIFICATION'S 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the designated radiation protection l
manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 DELETED 6.5 DELETED r
Amendment No. M,M,M,M,M,60,69, 117a H, SG,66,99, M9, He, H4,MB,4M, M6, M 9, 198
Table.6.2-1 ARKANSAS NUCLEAR ONE MINIMUM SHIFT CREW COMPOSITION #
UNIT 1 LICENSE COLD AND REFUELING CATEGORY ABOVE COLD SHUTDOWN SHUTDOWNS SOL 2
1*
OL 2
1 NON-LICENSED 3
1 1
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising refueling operations after une initial fuel loading.
- Shift crew 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 of on duty shif t crew members provided immediate action is taken to restore the shif t crew composition to within the ndnimum requirements of Table 6.2-1.
Additional Requirements:
1.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
2.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
3.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
4.
All refueling operations-after the initial fuel leading shall be 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.
5.
When the unit is above the Cold Shutdown condition, an individual shall provide advisory technical support for the unit operations shift supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the commission Policy Statement on Engineering Expertise on Shift.
Amendment No. M,M,M,M,H4,MB 118 (Next page is page 126) l 198
A 6.6 nrT.rtrn l
6.7 EkFFTY T.TMTT VTnf.ATTOM l
6.7.1 The following actions shall be taken in the event a safety Limit is violated:
a.
The facility shall be placed in at least hot shutdown l
within one hour.
l l
b.
The Nuclear Regulatory Commission shall be notified pursuant to 10 CFR 50.72 and a report submitted pursuant to the requirements of 10 CFR 50.36 and specification 6.6.
6.8 PROCEDimRS AMn PRoGRAME l
8 *1 Written procedures shall be established, implemented and maintained covering the activities referenced belows a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.
b.
Refueling operations.
c.
surveillance and test activities of safety related equipment.
d.
(Deleted) e.
(Deleted) f.
Fire Protection Program Implementation.
g.
New and spent fuel storage.
h.
Offsite Dose Calculation Manual and Process Control Program implementation at the site.
1.
Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and the containment atmosphere).
l l
l l
Amendment No. M,60,44,M,49,49,
.126 l
64,8G,99, Me,4G4, M3, M9,494, 198
Fi l
l l
6.8.2 (Dalsted) 6.8.3 (Deleted)
{
i 6.8.4 The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained:
l i
A program shall be established to implement the leakage rate testing l
of the reactor building as required by 10 CFR 50.54 (o) and 10 CFR 50,
[
Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in l
Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated reactor building internal pressure for the design basis loss of coolant accident, Pa, is 54 psig.
The maximum allowable reactor building leakage rate, La, shall l
be 0.20% of containment air weight per day at Pa.
Reactor building leakage rate acceptance criteria is s 1.0 La.
During the first unit startup following each test performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and s 0.75 La for Type A tests.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Frogram.
l The provisions of Specification 4.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.
l l
Amendment No. M,M,M, M,M,M, 127 M, M, M, M9, 4-24,4+3, 444, M9, M&,
-4 %,4 M,198
6.9 DELETED i
Amendment No, M,48,He,198 128
1 l
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.11 HIGH RADIATION AREA 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10CTR20, each high radiation area (as defined in 20.202 (b) (3) of 10CFR20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and shall be controlled by requiring the issuance of a 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.
A radiation monitoring device which continuously indicates the 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 pre-set integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
An individual qualified in radiation protection procedures who c.
is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.
i Amendment No. M,M,H,10/0!/OO 129 eedee, H, M, M, MG, H4, Ma, 198
l 6.11.2 Th3 requirements of 6.11.1 cbsva, ohn11 cico cpply to occh high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. 'In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control of the shift supervisor on duty
]
and/or the designated radiation protection manager.
I l
1 i
l i
Amendment No. 44,444, 198 129a(Next page is 140) 1
Tho dsso eseignments to v:ricus duty functicna may bo ostLmatco baccd en pocket dosimeter, TLD, or film badge measurements. Small exposures j
totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received fram external sources shall be assigned to specific major work functions.
6.12.2.3 Monthly operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis by the 15* of each month following the calendar month covered by the report.
6.12.2.4 Annual Report' i
1 All challenges to the pressurizer electromatic relief valve (ERV) and pressurizer safety valves shall be reported annually.
6.12.2.5 Annual Radiological Environmental Operating Report
- The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends.of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted. noting and explaining the reasons for the udssing results.
The missing data shall be submitted in a supplementary report as soon as possible.
6.12.2.6 Radioactive Effluent Release Report **
The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
- A single submittal may be made for ANO.
The submittal should combine those sections that are common to both units.
- A single submittal may be made for ANO.
The submittal should c'ombine those sections that are common to both units. The submittal shall specify the releases of radioactive material from each unit.
Amendment No. 4,94,49,44,44,44,46, 141 444,444, 198
6.12.5 sp;cici Repsrts Special reports shall be submitted to the Administrator of the appropriate Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
a.
Tendon surveillance, specification 4.4.2.2 b.
Inoperable containment Radiation Monitors, specification 3.5.1, TabJe 3.5.1-1.
c.
Deleted d.
Steam Generator Tubing Surveillance - Category C-3 Results, Specification 4.18.
Miscellaneous Radioactive Materials Source Leakage Tests, Jpecification j
e.
3.12.2.
f.
Deleted g.
Deleted h.
Deleted l
1.
Deleted l
j.
Degraded Auxiliary Electrical Systems, Specification 3.7.2.H.
k.
Inoperable Reactor Vessel Level Monitoring Systems, Table 3.5.1-1 1.
Inoperable Hot Leg Level Measurement Systema, Table 3.5.1-1, Inoperable Ma'.n Steam Line Radiation Monitors, specification 3.5.1, m.
Table 3.5.1."..
r l
Amendment No. 48,M4,4M,MS,M3,
.146a 444, 198 I
l i
jacun i
il UNITED STATES l
j NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 2055 5 0001 n
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated November 24,1998, as supplemented by letters dated February 25,1999, and July 14,1999, 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 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 tre Commission's regulations and all applicable requirements have been satisfied.
l
. - - -... - - - -... _. ~
~ 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licen.se 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 Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
A Robert A. Gramm, Chief, Section 1 l
Project Directorate IV & Decommissioning Division of Licensing Project Management j
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of issuance:
August 26,1999 l
i e
ATTACHMENT TO LICENSE AMENDMENT NO. 209 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 l
l Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 6-1 6-1 l
6-2 6-2 6-4 6-4 6-5 6-5 6-12a 6-12a 6-13 6-13 6-14 6-14 l
6 16 6-16 6 22 6-22 6-23 6-23 6-24 6-24 l
l l
l l
i i
l I
j
6.0 ADMINXSTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The ANO-2 plant manager ANO shall be responsible for overall unit l
operations and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 An individual with an active Senior Reactor Operator (SRO) license shall be designated as responsible for the control room command function while the unit is in HODE 1, 2, 3, or 4.
With the unit not in HODE 1, 2, 3, or 4, an individual with an active SRO license or Reactor Operator license shall be designated as responsible for the control room command function.
6.2 ORGANIZATION 6.2.1 OFFSITE 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 i
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 including the unit specific titles of those personnel fulfilling its responsibilities of the positions delineated in these Technical Specifications shall be documented in the Safety Analysis Report (SAR).
b.
The ANO-2 plant manager shall be responsible for overall unit safe l
operation and shall have control over those onsite activities necessary for safe operation and naintenance of the plant, c.
A specified corporate executive shall have corporate responsibility for l 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.
The specified corporate executive shall be documented in the SAR.
l 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 independenet from operating pressures.
6.2.2 UNIT STAFF l
a.
Each on-duty shift shall be composed of at least the minimum shift 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.
l ARKANSAS - UNIT 2 6 Amendment No. 6, M,M,M,M,M, M,M4,MG, 209
l At least two licansed Oparctors chall be present in the control room e
c.
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 whsn fuel is in the reactor.
All' CORE ALTERATIONS 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.
In MODES 1, 2, 3, or 4, an individual shall provide advisory technical support for the unit operations shift supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
This individual shall meet the qualifications specified by the Commission Policy on Engineering Expertise on Shift.
g.
Administrative control shall be established to limit the amount of overtime worked by plant staff perforndng safety-related functions These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).
h.
The operations manager or the assistant operations manager shall hold
[
a senior reactor operator license.
ARKANSAS - UNIT 2 6-2 Amendment No. M,M,B9,M,M,M, M, M, H4, MB, 209 l
L_,
l TABLE 602-1 HINIMUM SHIFT CREW COMPOSITION #
LICENSE APPLICABLE MODES CATEGORY 1, 2, 3,
& 4 5& 6 2
1*
SOL 2
1 OL 3
1 Non-Licensed I
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.
- Shift crew 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 of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
I l
l ARKANSAS - UNIT 2 6-4 Amendment No. 34,444, 209 2
T.
ADMINISTRATIVE CONTROLS l
l.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum l
qualifications of ANSI N18.1-1971 for comparable positions, except for (1) l the designated radiation protection manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 i
6.4 DELETED 6.5 DELETED i
l l
l l
l 1
1 ARKANSAS - UNIT 2 6-5 Amendment No. 6,M,M,G4, (Next page,is page 6-12a)
GG, M, M, M, G4,444, H9, i
MG,444,HG, 209
- " + " '
den' aw w,* h e
- =r-p@
W =
-%ee
i f
i 6.6 DELETED l
l l
ARKANSAS - UNIT 2 6-12a Amendment No. m,gg, p
ADMZNISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
l 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 AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced belows a.
The applicable procedures recommend 6d 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.
(Deleted) e.
(Deleted) l 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 sof tware lindt values shall not be implemented without prior NRC approval.
h.
New and spent fuel storage.
i.
j.
Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluent, and the containment atmosphere).
6.8.2 Deleted l
I f
l l
ARKANSAS - UNIT 2 6-13 Amendment No. M,M,44,64,40,44, M, M, M, M,94,444, MG,444, M9, MG 4 M 209 i
1 ADMINISTRATIVE CONTROL 6.8.3 Deleted 6.8.4 The following programs shall be established, implemented, and maintained:
a.
Radioactive Effluent Controls Program This program conforms with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program shall be contained in'the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
i 1)
Limitations,on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and 1
setpoint determination in accordance with the methodology in the ODCM; 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2; 3)
Monitoring,. sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive naterials in liquid l
effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR'50, Appendix I; 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 dayss 6)
Limitations on the functional capability and use of the liquid and 1
gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the 1
guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary 4
conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; ARKANSAS - UNIT 2 6-14 Amendment No. 6, &B, M, M, M, M, M, m, H 7, M O, M 3,E M, 209
l ADMINISTRATIVE CONTROLS starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above
[
the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
MONTHLY OPERATING REPORT i
l 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month l
l following the calendar month covered by the report.
l SPECIAL REPORTS l
6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each repc:t.
These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications j
a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
l b.
Deleted c.
Deleted d.
Deleted i
e.
Deleted f.
Deleted l
g.
Deleted l
ARKANSAS - UNIT 2 6-16 Amendment No. M,M,M,M,MG, 4 M,4 M, 209
ADMINISTRATIVE CONTROLS
~6.10 DELETED
)
l l
ARKANSAS - UNIT 2 6_22 Amendment No. 40,M,94,GM, 2()9 n
a
ADMINISTRATIVE CONTROL I
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.
I 6.12 (DELETED)
MMSAS - UNIT 2
'6-23 Amendment No. M,M,G,M,444,MS 209
r
~.
i.
ADMINISTRATIVE CONTROLS 6.12.2 (DELETED) 6.13 HIGH RADIATION AREA 6.13.1. In lieu of the " control device" or "alaom signal" required by paragraph 20.203 (c) (2) of 10 CrR 20, each high radiation area (as defined in 20.202(b) (3) of 10 CFR 20) in which the intensity of radiation is 1000 mram/hr or less shall be barricaded and conspicuously posted as a high l
radiation area and entrance thereto shall be controlled by requiring the j
issuance of a radiation work permit. Any individual or group of I
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.
b.
A radiation monitoring device which continuously integrates the l
radiation dose rate in the area and alarum when a preset l
integrated dose is received. Entry into such areas with this l
monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.
6.13.2 The requirements of 6.13.1, above, shall also apply to each high radiation area in which the intensity of radittion is greater than 1000 mram/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control of the shift supervisor on l
duty and/or the designated radiation protection manager.
i l
l l
l l
ARKANSAS - UNIT 2 6-24 Gedee de4ed Oct:i;r 44, Mee Amendment No. 44,49,40,44,94,4M, 209
.