ML20153B330
| ML20153B330 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/13/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153B335 | List: |
| References | |
| NUDOCS 7812010374 | |
| Download: ML20153B330 (28) | |
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%g UNITED STATES J"
NUCLEAR REGULATORY COMMISSION 1
WASHINGTON, D. C. 20666 s
'j 49.....,6 ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE.
UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendnent No. 37 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) ha:; found that:
A. The applicatinn for amendment by Arkansas Power & Light Company (the licensee) dated September 22, 1978, as supplemented October 17, 1978, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 i
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon i
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.
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, i 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. DPRr51 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment Nc. 37, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the 3
j Technical Specifications.
3.
This license amendment becomes effective no later than 90 days after the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
N lh/. \\
Robert W. Peid, Chief Operating Reactors Branch #4 j
Division of Operating Reactors 1
i
Attachment:
Changes to the Technical Specifications l
Date of I!3uance:
November 13, 1978 i
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l ATTACHMENT TO LICENSE AMENDMENT NO. 37 i
FACILITY OPERATING LICENSE NO. DPR-51 f
DOCKET NO. 50-313 i
i i
l Replace the following pages of the Appendices "A" and "B" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the **ea of change.
Corresponding overleaf pages are also provided to inamtain i
document completeness.
I j
Appendix "A" Pages 3.
l 117 l
119 l
120 120-a (new)
I j
121 121-a (new) i i
122 - 124 126 & 127
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l Appendix "B" Pages i
i ii & iii 1
l 2-5 4
j 5 5-9 f
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6.d ADMINISTRATIVE CONTROLS j
6.1 RESPONSIBILITY i.
6.1.1 The General Manager shall be responsible for overall facility j
operation and shall delegate in writing the succession to this l
responsibility during his absence.
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6.2 ORGANIZATION i
0FFSITE l
6.2.1.
The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
i FACILITY STAFF a
6.2.2 The Facility organization shall be as shown on Figures 6.2-2A, l
B, C, and D.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
6.3 FACILITY STAFF QUALIFICATIONS t
j 6.3.1 Each member of the facility staff shall meet or exceed the minimum j
qualifications of ANSI N18.1-1971 for comparable position, except i
for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
j l
j 6.4 TRAINING i
6.4.1 A retraining and replacement training program for the facility j
staff shall be maintained and shall meet or exceed the require-ments and recommendations of Section 5.5 of ANSI N18.1-1971 and 1
j Appendix "A" of 10 CFR Part 55.
t l
6.4.2 A training program for fire protection training shall be maintained i
and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 with the exception of frequency of training which shall 4
i be six times per year.
i 6.5 REVIEW AND AUDIT l
6.5.1 Plant Safety Committee (PSC) Function l
6.5.1.1 The Plant Safety Committee shall function to advise the General l
i Manager on all matters related to nuclear safety,
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COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:
Amendment No. J,' ;MI,,3 7 d
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' EXECUTIVE DI:tFCTOR CENEllAlION 4 CONSIPtiCTION SAFETY REVIEW y
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DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR CLNER\\ TION GDIERATION CENERATION PROJFCTS TECIINICAL &
ADMINISTRATIVE TICllNOLOGY OPERATIONS ENGINrt: RING HANAGEllENT ENVIROTtENTAL SERVICES C PROJECT SERV!CES SUPPORT I
'o MUWUIER OF NUCLEAR OPERAT10R$
1 PLANT SAFETY GENERAL MANAGER COSHITTTE
- Corporate responsibility for Fire Protection Progran l
FIGURE 6.2-1
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FIRE CONTROL SECURITY COORDINATOR C 0.
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PHYSICS ENGINEERING SUPERVISOR ~
SUPERVISOR NUCLEAR SUPPORT ASSISTAtlT SUPERVISOR ETRM HEALTH ENGINEERING SLPERVISORS NUCLEAR ENGINEERS RADIO CREtt!STRY SUPERVISOR COMPUTER SUPPORT SUPERVISOR CHEMICAL &
EtlVIRONMENT SUPERVISOR COMPUTER ENGlHEERS Figure 6.2-2C
-121-Amendment No' 37 4
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GENER/L
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Amendment No. 37f
-121-a-
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. Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations and reports l
thereon as requested by'the General Manager.
4 i.
Review of the Plant Security Plan and implementing procedures j}
and shall submit recommended changes to the General Manager.
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Review of the Emergency Plan and implementing procedures and shall submit' recommended changes to the General Manager.
l AUTHORITY i
j 6.5.1.7.1 The Plant Safety Committee shall:
1 a.
Recommend to the General Manar,er written approval or dis-l
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i approval of items considered under 6.5.1.6(a) through (d) above.
l b.
Render determinations in writing with regard to whether or l
not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.
6.5.1.7.2 In the event of a disagreement between the recommendations of the Plant Safety Committee and the actions contemplated by the General Manager, the course determined by the General Manager l
to be more conservative will be followed.
Records of the dis-4 agreement will be sent for review to the Director, Generation Operations, or Manager, Nuclear Operations and the Chairman of the Safety Review Committee by the General Manager on the next working l
j day.
1 RECORDS i
6.5.1.8 The Plant Safety Committee shall maintain written minutes of each meeting and copies shall be provided to the Chairman of the Safety I
Review Committee by the General Manager.
6.5.2 Safety Review Committee (SRC) i FUNCTION 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry Amendment No. h,
,37'
-123-
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t Chairman:
Operations and Maintenance Manager j
Member:
Technical Analysis Superintendent Member:
Instrumentation and Controls Superintendent
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Member:
Operations Superintendent 5
Member:
Maintenance Superintendent Member:
Plant Analysis Superintendent l
Member:
Health Physics Supervisor 7
i The General Manager shall appoint in writing an acting chairman in the absence of the Operations and Maintenance Manager.
1 ALTERNATES 4
i 6.5.1.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC activities at any one time.
MEETING FREQUENCY i
6.5.1.4 The PSC shall meet at least once per calendar month and as con-vened by the PSC Chairman or his designated alternate.
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QUORUM 6.5.1.5 A quorum of the PSC shall consist of the chairman and three members including alternates.
2 RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:
Review of 1) all procedures required by Specification 6.8 a.
and revisions thereto, 2') any other proposed procedures or revisions thereto as determined by the General Manager to l
a affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Appendix "A" Tech-nical Specifications, d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specif1-cations, including the preparation.and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager.
I f.
Review of those Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification of the Commission.
Amendment No.
4,37
-122-
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d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
environmental considerations i.
other appropriate fields re.ptired by the unique characteristics of the nuclear power plant.
COMPOSITION 6.5.2.2 The SRC shall be composed of the:
4
-Chairman: Director, Generation Operations j
Member:
Director, Generation Technology j
Member:
Director, Technical and Environmental Services Member:
Manager of Safety Member:
Arkansas Nuclear One General Manager l
Member:
Manager, Technical Analysis Member:
Arkansas Nuclear One Plant Analysis Superintendent l
Member:
. Director, Generation Engineering L
Member:
Radiation and Health Physics Consultant Member:
Nuclear Safety Cor.3ultant In his abser:e, the Chairman shall appoint an Acting Chairman.
ALTERNATES All alternate members shall be appointed in writing by the SRC 6.5.2.3 Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
FEETING FREQUENCY 6.5.2.5 The SRC shall meet a least once per calendar quarter during the i
. initial year of facility operation following fuel loading and at least once per six months thereafter.
j QUORUM-6.5.2.6 A quorum of SRC shall consist of the Chairman or his designated
. alternate' and four members including alternates. No more than
' a minority of the quorum shall have line responsibility for
. operation of the facility.
',[,37-Amendment No.
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4 f.
The Facility Security Plan and implementing procedures at least once per two years.
g.
Any other area of facility operation considered appropriate by the SRC or the Executive Director, Generation & Construction (EDG6C).
6.5.2.9 Special Inspections and Audits A.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
AUTHORITY 6.5.2.10 The SRC shall report to and advise the Executive Director, Generation and Construction (EDG6C) within 30 days following each meeting.
RECORDS 6.5.2.11 Records of SRC activities shall be prepared, approved and dis-tributed as indicated below:
a.
Minutes of each SRC meeting shall be prepared, approved and forwarded to the Executive Director, Generation 6 Construction (EDGSC) within 30 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7.e, f, g and h above, shall be prepared, approved and forwarded to the Executive Director, Generation 6 Construction, (EDGSC) within 30 days following completion of the review.
c.
Audit reports encompassed by Section 6.S.2.8 above, shall be forwarded to the Executive Director, Generation 6 Construction (EDG6C) and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for Reportable Occurrences:
- a. The Connission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.
- b. Each Reportable Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PSC and submitted to the SRC and the Manager, Nuclear Operations by the General l
Manager.
6.7 SAFETY LIMIT VIOLATION 6.7.1 Th, following actions shall be taken in the event a Safety Limit it iolated:
AmendmentNo.[,)d,
,3f 126-
c The facility shall be placed in at least hot shutdown within a.
one hour.
b.
The Nuclear Regulatory Commission shall be notified and a j
report submitted pursuant to the requirements of 10 CFR 50.36
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and Specification 6.12.3.1 s
l 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" a.
of Regulatory Guide 1.33, November,1972.
j b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
l 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the General Manager prior l
to implementation and reviewed periodically as set forth in 4
administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
4 a.
The intent of th'e original procedure is not altered.
b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, c.
The change is documented, reviewed by the PSC and approved by the General Manager within 14 days of implementation.
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AmendmentNo.)[pd.,37
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Effective January 19, 1975, activities under the U. 'S. Atonic Energy Commissi.on regulatory program were assumed by the U. S.
Nuclear Regulatory Comission in accordance'with the Energy Reorganization Act of 1974. Any references to the Atomic Energy Commission (AEC) contained herein should be interpreted as Nuclear Regulatory Co=nission (NRC).
4 TABLE OF CCNTErrS 1.0 D EF IN ITI ON S............................................... 1-1 1.1 S can dard Me th o ds...................................... 1-1 ~
1.2 Ga==a Isotopic Analysis...............................
1-1 1.3 Inviren=antal Samples.................................
1-1 1.4 Chlo rine De:and..................................... '..t 1-1 1.5 7:e e Availab le Chlori.se Residua 1......................
1-1 l
1.6 C::bined Availabla Ch terine Easiduc1................$. 1-1 1.7 To:s1 t.vailable Chlorina Easidua*.....................
1-1 1.5
.R!D..................................~../..............
1-1 1.9 F.aliation Moni:or Checks, Tes:s, and Calibra:1:n...... 1-2 1.13 Iquivalen: Dacay T1=a.................................
1-2 2.0 LIMITING CCL'DITIONS FOR 0?IR.C 3M.......................... 2-1 l
2.1 Ther=a1...............................................
2-1 2.1.1 Max 1=u: AT Across
- iensar....................
2-1 4'
2.1.2 Maxi =u= Dis cht:ga Ta:p arz:ure.................. 2-2 2.1.3 Ma:ci=u= 3 :U/ h r........... '......................
2-3 1
2.1.4 Race of Change of Cis:h::;a Ta:pera:ura........
2-3 2.1.5 Hez: T:sa:=ts: ef Cir::12:is; Wa:e Sys:::.....
2-4' 2.1.6 Dei:1:g,C;ar ti:ns.............................
2-4 2.2 Eyersulie.............................................
2-5 2.2.1 In:aka veloci:7................................
2-5 2.2.2 Discharge Ve1: city.............................
2-5 2.2.3 T1cv Ra:c Res:rie:icns.........................
2-5
)
2.2.4 Resarvoir D cudews.............................
2-5 2.3 Che=ica1..............................................
2-5 2.3.1 Biocides.......................................
2-5 2.3.2.
Celetsd..............
2-5 3
2. 3. 3 D e l e t e d............................... '...........
2-7 2.3.4 Deleted........................................
2-8 j
2.3.5 Deleted..........................................
2-8 2.4 Radio ctive Dischstge..................................
2-9 2.4.1 Liquid Diucher.m...............................
2-10 2.4.2 Caseous D1sc!arge.......................'..*.....
2-12 ggg 13
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i TABLE OF CONTENTS (Cont'd) t i
i' s
1 i
3.0 DESIGN FEATURES AND OPERATING PRACTICES............
3-1 1
3.1 Intake System..
3-1 3-1 i
3.2 Discharge System.
3-1 l
3.3 Chemical Usage...........
3-1 l
3.4 Plant Shutdown.........
3-1 3.5 Land Management l
i 4.0 ENVIRONMENTAL SURVEILLANCE.
4-1 e
4 4.1 Nonradiological Environmental Surveillance.
4-1 l
{
4.1.1 Abiotic....................
4-1 4
4.1.2 Biotic..............
4-7 4
1 1
4 4.2 Radiological Environmental Monitoring........
4-13 4.2.1 Air Sampling....................
4-13 4.2.2 Direct Radiation.................
4-13
)
4.2.3 Precipitation Sampling..............
4-13 i
4.2.4 Lake Dardanelle.
4-14 i
4-14 4.2.5 Ground Water Sampling.....
l 4.2.6 Russellville City Water.............. 4-14 l
4.2.7 Reservior Bottom Sediments............
4-14
)
4.2.8 Aquatic Biota................... 4-14 4
4-14 4.2.9 Fish Bone....
4.2.10 Milk Sampling................... 4-15 4.2.11 Vegetation Sampling................ 4-15 4-15 4.2.12 Soil Sampling..
5.0 ADMINISTRATIVE CONTROLS....................
5-1 5-1 i
5.1 Responsibility 5-1 5.2 Organization 5-1 5.3 Review.......................
5.3.1 Plant Safety Committee...............
5-1 5-2 5.3.2' Safety Review Committee....
5.4 State and Federal Permits and Certificates 5-3 1
Amendment No. 37
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Table of Contents (Cont'd)
Page 5.5 Procedures................
5-3 5.6 Station Reporting Requirements............
5-4 5.6.1 Routine Reports.
5-4 5.6.2 Non-Routine Reports..
5-5 5.7 Changes................
. 5-6 5.7.1 Changes in Environmental Technical Specifications..
5-6
- 5. 7. 2 Changes in Permits and Certifications..
5-6 5.7.3 Changes in Procedures, Station Design or Operation.. 5-7 5.8 Records Retention...........
. 5-8 5.8.1 Records and Logs Retained for Life of the Plant 5-8 5.8.2 All other Records..
5-8 6.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES.
. 6-1 6.1 Thermal Plume Mapping.
. 6-1 6.2 Fish Spawning Characteristics of Dardanelle Reservoir.
6-2 6.3 Diel Changes in Impingement Levels..........
6-3 6.4 Cove Rotenone Surveys................
6-4 4
'l u
4 Amendment No. 37f r
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l 2.2 Hydraulic 2.2.1 Intake Velocity A study will be undertaken as described in Section 4.1.2 to determine means of limiting fish impingement on the traveling water screens.
2.2.2 Discharge Velocity l
Not Applicable.
l 2.2.3 Flow Rate Restrictions Not Applicable.
2.2.4 Reservior Drawdown
""~
Not Applicable.
2.3 Chemical Objective.(General)
To protect the local biota from lethal and sublethal effects or chemical discharges. To assure that the most sensitive use of the receiving medium by human populations is protected. To minimize degradation of the quality of the receiving medium.
Specification (General)
All plant chemical discharges except that from the plant sanitary system shall be diluted by the plant circulating water during release to assure that the stated objective can be achieved. No release of demineralizer waste shall be made without a dilution equivalent to one-half (approxi-mately 383,000 gpm) the full flow of the Unit I circulating water pumps.
Any limitation on the quality of plant effluents and requirements for monitoring the same imposed under conditions of the Federal Water Pollution Control Act shall be a part of these Technical Specifications.
1 All reports to State or Federal agencies regarding compliance with any such limitation shall also be provided to NRC as described in Specification S.4.
l Amendment No.3]F ny-w
2-Se 2.3.1 Biocides Specification Chlorine (Circulating Water System) a.
Chlorination of condenser cooling water shall be intermittent (1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> each day or as may be necessary). Total available chlorine residual in the plant affluent shall be less than 0.1 mg/1.
If the total available chlorine residual in the discharge ennni exceeds 0.1 mg/1, the chlorine feed rate 'shall be reduced to a rate at which this specification can be met.
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s 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility Corporate responsibility for implementation of the Environmental Technical Specifications, and for assuring that station operations are controlled to provide protection for the environment has been assigned to the Executive Director of Generation and Construction.
The ANO General Manager, through the Engineering and Technical Support Manager, and Technical Analysis Superintendent shall be responsible for compliance with the Environmental Technical Specifications at the plant level.
The Manager of Technical Analysis shall be responsible for radio-logical analysis of environmental samples.
5.2 Organization Figure 5-1 shows the organization chart at both plant and corporate levels relative to environmental matters.
5.3 Review 5.3.1 Plant Safety Committee The Plant Safety Committee (PSC) shall be responsible for review of the following-a.
Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes.
b.
Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's environmental impact.
Amendment No. 37f 5-1
s l
c.
Proposed changes or modifications to plant systems or equipment which would affect the plant's environmental impact.
d.
Results of the Environmental Monitoring Programs.
l e.
Investigation of all reported instances of violations of j
l Environmental Technical Specifications. Where investigation I
warrants, instances shall be evaluated and recommendations formulated to prevent recurrence.
5.3.2 Safety Review Committee The Safety Review Committee (SRC) shall be responsible for review of the following:
j The environmental evaluations for 1) changes to pro-a.
cedures, equipment or systems and 2) tests or experiments completed under Section 5.7.3, to verify that such actions did not constitute an unreviewed environmental question.
b.
Proposed changes to procedures, equipment or systenswhich involve an unreviewed environmental question as defined in Section 5.7.3.B.
j Proposed changes to the Environmental Technical Specifi-c.
cations and the evaluated impact of the changes.
d.
Results of the Environmental Monitoring Programs.
e.
Investigation of all reported instances of violatioris of Environmental Technical Specifications.
Amendment No.,3 *,
5-2 r
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i
.I 4
i S.4 State 'and Federal Fermits and Certificates s
)
Copies of reports to federal and state agencies regarding compliance 1
l of limitation on quality of liquid effluent from ANO-1 shall be I
sent to Director of Regional Inspection and Enforcement Office i
(cc Director, NRR).
1 5.5 Procedures
[i Detailed written procedures shall be prepared and followed for i-all activities performed by Arkansas Power and Light involved in l
carrying out the sampling, instrument calibration, analysis, and actions to be taken when limits are approached or exceeded.
l1 i
Testing frequency of any alarms shall be included. These fre-l quencies shall be determined from experience with similar instruments in similar environments and from manufacturers' technical manuals.
Plant standard operating procedures shall include provisions i
~
to ensure the plant and all its systems and components are operated in compliance with t'ae limiting conditions for 1
]
operations established as part of the environmental technical specifications.
Amendment No. 37I 5-3 A
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l 5.6 Station Reporting Requirements 5.6.1 Routine Reports l
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Annual Environmental Operating Report l
A single report on the environmental monitoring programs conducted I.
l in association with ANO-1 (Docket No. 50-313) and ANO-2 (Docket f
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No. 50-368) operations for the previous calendar year shall be submitted to the NRC by May 1 of each year. The report shall i
l include summaries, analyses, interpretations, and, where l
appropriate, statistical evaluation of the results of the 4-i environmental monitoring and an assessment of the observed impacts of the station operation on the environment.
If harmful j
effects or evidence of irreversible damage are suggested by the l
l monitoring or special p' a, the licensee shall provide a
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more detailed analysis P
data and a proposed course of i
l action to alleviate the problem.
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The Annual Report shall also include a summary of:
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1)
All ETS noncompliances and the corrective actions taken i
to remedy them.
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2)
Changes made to state and federal permits and certificates.
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3)
Changes made to the procedures or design described in accordance with Subsection 5.7.3.
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4)
Changes in ETS.
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Amendment No* 3I 5-4 i
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5.6.2 Nonroutine Reports A report shall be submitted in the event that a " Limiting Condition for Operation" (Section 2), is exceeded, a report level as specified in Section 3 or 4 is reached, or if an unusual event involving a significant environmental impact occurs. Reports shall be submitted under one of the report schedules described below.
5.6.2.a Prompt Report Those events specified as prompt report occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.
5.6.2.b Thirty Day Report Non-routine events not requiring a prompt report as described in Subsection 5.6.2.a, shall be reported to NRC within 30 days of their occurrence.
S.6.2.c Content of Non-routine Reports Written 30-day reports and, to the extent possible, the pre-liminary telephone, telegraph, or facsimile reports shall a) describe, analyse, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause, of occurrence, and (c) indicate the corrective action (in-cluding any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.
Amendment No. 37 5-5
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j 5.7 Changes a
5.7.1 Changes in Environmental Technical Specifications i
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Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per i
10'CFR 50.90.
The request'shall include an evaluation of the i
environmental impact of the proposed changes and a supporting i
j ustification.
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5.7.2 Changes in Parmits and Certifications Changes or additions to required federal, state, local, and i
regional authority permits and certificates for the protection of the environment that pertain to the requirements of these ETS shall be reported to the NRC within 30 days.
In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Section '401 or 402 of PL 92-500 which is also the subject of an ETS reporting requirement under Section 2, or 4 of this ETS, NRC shall be notified within 30 days.
If the proposed change
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is initiated by the licensee, the notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.
5-6 AmendmentNo.37I-
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5.7.3 Changes in Procedures, Station Design or Operation A.
The licensee may 1) make changes in the station design and operation, 2) make changes in the procedures described in t-i Subsection 5.5, and 3) conduct tests and experiments not l
described in accordance with Subsection 5.5, without prior Ct aproval, unless the proposed change, test or i
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ext tvolves a change in the objectives of the ETS, i
i or a wed environmental question of substantive impact.
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B.
A prop
.nge, test or experiment shall be deemed to in-i volve u.
.eviewed environmental question if it concerns 1) i a matter which may result in a significant increase in any I
j adverse environmental impact previously evaluated in the final l
environmental impact statement as modified by staff's testimony 8
l to the Atomic Safety and Licensing Board, supplements thereto, I
environmental impact appraisals, or in initial or final adjudi-t catory decisions; or 2) a significant change in effluents or i
power level as specified in 10 CFR 51.5(b)(2); or 3) a matter not previously reviewed and evaluated in the documents specified i
j in 1) of this section which may have a significant adverse en-f vironmental impact.
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C.
The licensee shall maintain records of changes in procedures and 1
l in the facility design or operation made pursuant to this
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4 Subsection, to the extent that such changes constitute changes 5-7 Amendment No. 37
in procedures as described in accordance with Subsection 5.5.
The licensee shall also maintain records of tests and experiments carried out pursuant to paragraph "A" of this Subsection.
These records shall include a written evalua-tion whi::h provides the bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question of substantive impact or constitute a change in the objectives of these ETS.
The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the license, a report containing de-scriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.
5.8 Records Retention l
5.8.1 Records and logs relative to the following areas shall be retained for the life of the plant:
a.
Records and drawing changes reflecting plant design modifications made to systems and equipment as de-scribed in Specification 5.7.3.
l b.
Records of environmental surveillance data.
l c.
Records to demonstrate compliance with the limiting conditions for operation in Section 2.
5.8.2 All other records and logs relating to the environmental technical specifications shall be retained for five years.
5-8 Amendment No. 37'
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l EXECUTIVE DIRECTOR k
GENERATION AND CONSTRUCTION i
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1 DIRECTOR DIRECTOR
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GENERATION OPERATIONS TECHNICAL AND ENVIRONMENTAL SERVICES 1
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ARKANSAS NUCLEAR ONE MANAGER GENERAL MANAGER TECHNICAL ANALYSIS
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ARKANSAS NUCLEAR ONE CHEMISTS
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ENGINEERING AND TECHNICAL SUPPORT AND BIOLOGISTS i
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(
ARKANSAS NUCLEAR ONE
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TECHNICAL ANALYSIS SUPERINTENDENT
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l ARPANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE 5
CHEMICAL AND RADI0 CHEMISTRY HEALTH PHYSICS 3
ENVIRONMENTAL SUPERVISOR SUPERVISOR SUPERVISOR i
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j ARKANSAS POWER 6 LIGHT CO.
ENVIRONMENTAL SURVEILLANCE FIG. NO.
ARKANSAS NUCLEAR ONE ORGANIZATION CHART 5-1 i
Amendment No. 37 '
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