ML19320A453
| ML19320A453 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/22/1978 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| References | |
| NUDOCS 8006060081 | |
| Download: ML19320A453 (41) | |
Text
{{#Wiki_filter:. .- i
,, .. (
-
.
THIS DOCUMENT CONTAINS 6.0 ADMINISTRATIVE CONTROLS P00R QUAU1Y PAGES 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence. 6.2 ORGANIZATION . OFFSITE 6.2.1. The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1. Any changes will be submitted as a Technic.a.1 Specification change request within 30 days of implementation. FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2-2A, B, C, and D. Any changes will be submitted as a Technical Specification change request within 30 days of implementation. 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 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 llcalth Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained and shall meet or exceed the require-ments and recommendations of Section 5.S of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A training program for fire protection training shall be maintained and shall me'et or exceed the requirements of Section 27 of the NFPA Code-1975 with the exception of frequency of training which shall be six times per year. 6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Committee shall function to advise the General l Manager on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the: i
.8006060 08/ [
. -. .. ._ _. - . . - . . ._-
-
.
.-
"
.
..
.
' EXECUTIVE DIRFCTOR CENDIAlION 6 CONS 1RUCT10N SAFETY REVIEW C0fNITTFE_ ,
DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR GENERATION CDIERATION CENERATION PROJECTS TECIINICAL 6 ADMINISTRATIVE OPERATIONS ENGINEERING MANAGDIENT ENVIRON *.tENTAL SERVICES 6 PROJECT
. TI:CllNOLOGY SUPPORT I SERVICES I
M
- MMMER OF
- NCLEAR OPEMTIONS 1
, PLANT GENERAL SAFETY ,
HANAGER _ COMITTEE
- Corporate responsibility for Fire Protection Program i
FIGURE 6.2-1
. __ _- -
. _ _ _ _ _ _ __
,e
.
-
.
.
* -
GENERAL MANAGER QUALITY _ CONTROL ENGINEER. FLANNING & QUALITY
-
SCHEDULING CONTROL SUPERVISOR SUPERVISOR
^
QUALITY j CONTROL INSPECTORS
,
ENGINEERING &
. OPERATIONS & PLANT TECHNICAL C MAINTENANCE ADMINISTR.
S j ? MANAGER MANAGER I
^
, 1
+ - Senior Operator License Required
# - Operator License Required
( ) - Desirable, but not Required Figure 6.2-2A
______ _ ____ _ _- ________ - _ - - _ . _ _ _ _ - -
. - . ( (
- .
GENERAL MANAGER __ PLANT ' ADMINISTR. MANAGER RECORDS HUMAN MATERIALS
& ADMINISTR. RESOURCES MANAGEMENT SUPERVISOR SUPERVISOR SUPERVISOR FIRE CONTROL SECURITY COORDINATOR C00. A OR I
figure 6.2-2B
-120-a
_ __ . .__ _ . . _ . _
*
( ( .
*
.-
.
GEtlERAL ,
'AtlAGFP l
I I I I I I ENGINEERING & TECHNICAL l SUPPORT I MNAGER l i I I i TECHNICAL PLANT PLANT l -
* -
ANALYSIS - ANALYSIS ENGINEERING SUPT. SUPT. SUPT. I I
) PLANT
~
! HEALTH MECHANICAL SUPER SOR L- --- - PHYSICS
-
ENGINEERING SUPERVISOR SUPERVISOR NUCLEAR
-
SUPPORT ASSISTANT SUPERVISOR ELECTRICAL HEALTH - ENGINEERING PHYSICS SUPERVISOR SUPERVISORS
,
NUCLEAR ENGINEERS RADIO
-
CHEllISTRY SUPERVISOR COMPUTER
-
SUPPORT SUPERVISOR _ CHEMICAL &
-
EllVIRONMENT COW UTER SUPERVISOR ENGlHEERS Figure 6.2-2C
-121-
_ _ _ .
-
..
'
,
* ( (
-
.
'
GENERAL MANAGER
.
OPERATING & MAINTENANCE MANAGER I I E 1
+
OPERATIONS SUPEP. INT. MAINTENANCE SUPERINI
- I"hT SUPERINT.
ASSISTANT + ELEC. ASST.
~
OPERATIONS MAINT.. ISC S!!PERINTS. supyg, supygs, UNIT 1 + + ' UNIT 2 E ECT* SHIFT gggg* SUPVR. l SHIFT SUPVR. SupyRS, PLANT PLANT - SERVICE OPER. OPER. SUPVR.
# #
ASST. ASST. MECH.
-
PLANT PLANT MAINT. OPER. SUPVR, OPER. ASST. WASTE WASTE
- - MECH.
CONT. CONT.
!
OPER. OPER. [UVS'.
'
AUX. AUX.
- -
OPER. OPER. Figure 6.2-20
-121-a
. _ , _. .. ._ .-. . . . . _ - . _--
,' *
,. -
_ ( l
'
.
-
Chairman: Operations and Maintenance Manager Member: Technical Analysis Superintendent Member: Instrumentation and Controls Superintendent Member: Operations Superintendent Member: Maintenance Superintendent Member: Plant Analysis Superintendent l Member: Health Physics Supervisor The General Manager shall appoint in writing an acting chaiman in the absence of .the Operations and Maintenance Manager. ALTERNATES 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 6.5.1.4 The PSC shall meet at least once per calendar month and as con-vened by the PSC Chaiman or his designated alternate. QUORUM 6.5.1.5 A quorum of the PSC shall consist of the chaiman and three members including alternates. RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:
- a. Review of 1) all procedures required by Specification 6.8 and revisions thereto, 2) any other proposed procedures or revisions thereto as detemined by the General Manager to l 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 l systems or equipment that affect nuclear safety,
- e. Investigation of all violations of the Technical Specifi-cations involving activities under the responsibility of I the General Man.:ger, including the preparation and fonarding of reports covering evaluation and recommendations to prevent recurrence to the General Manag'e
- f. Review of those Reportable Occurrences requiring 24 hour notification of the Commission.
-122-l l
l _ . __- _ _ _ _
.
'
. C ( (
'
.
- g. Review of facility operations to detect potential nuclear safety hazards,
- h. Perfomance of special reviews, investigations and reports thereon as requested by the General Manager. l
- i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the General Manager. l
- j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the General Manager. l AITTl!0RITY 6.5.1.7.1 The Plant Safety Committee shall:
- a. Recommend to the General Manager written approval or dis- l approval 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 (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-agreement will be sent for review to the Director, Generation Operations, or Manager, Nuclear Operations and the Chaiman of the Safety Review Committee by the General Manager on the next working l day. RECORDS 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 Review Committee by the General Manager. l . 6.5.2 Safety Review Committee (SRC) FUNCTION f 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 4
- c. chemistry and radiochemistry
-123-
_ .- ,
.
( (
.
.
.
%
- d. metallurgy
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. environmental considerations
- i. other appropriate fields required by the unique characteristic s of the nuclear power plant.
COMPOSITION l The SRC shall be composed of the:
'
6.5.2.2
.
Chairman: Director, Generation Operations Member: Director, Generation Technology ! Member: Director, Technical and Environmental Services ! Member: Manager of Safety Member: Arkansas Nuclear One General Manager l , Member: Manager, Technical Analysis 1 Member: Arkansas Nuclear One Plant Analysis Superintendent l Member: Director, G.?neration Engineering Member: Radiation and Health Physics Consultant l Member- Nuclear Safety Consultant In his absence, the Chairman shall appoint an Acting Chairman.. ALTERNATES I 6.5.2.3 All alternate members shall-be appointed in writing by the SRCJ: Chairman to serve on a temporary basis; however, no more than rtwo alternates shall participate as voting members in SRC activitiries at any one time. CONSULTANTS 1 6.5.2.4 Consultants shall be utilized as. determined by the SRC Chairmazan to ' provide expert advice to ths L.sC. MEETING FREQUENCY 6.5.2.5 The SRC shall meet a least once per calendar quarter during thiue initial year of facility operation following fuel loading and : at least once per sir, months thereafter. QUORUM 6.5.2.6 A quorum of SRC shall consist of the Chairmui or his designate:ed alternate and four members including altertu.tes. No more than:n a minority of the quorum shall have line responsibility for operation of the facility.
-124-
. , . - - - . . . --
-. __
-
'
.- ( (
.
.
REVIEW l i 6.5.2.7 .The SRC shall review: l
- a. The safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- d. Proposed changes in Technical Specifications or licenses.
- e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
- f. Significant operating abnormalities or deviations from normal and expected perf'ormance of plant equipment that affect nuclear safety.
- g. Reportable occurrences requiring 24 hour notification to the Commission.
- h. Reports and meeting minutes of the PSC.
AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
- b. The performance and retraining of all members c f the plant management and operations staff, and the perfer, snce, training, and qualifications of new members of the entire plant staff at least once per year.
- c. The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
- d. The Facility Emergency Plan and implementing procedures at least once per two years.
- e. The Facility Fire Protection Program and implementing pro-cedures at least once per 24 months.
-125-
_ _ _ _ _ _ . _ _ _ . _ _ . _ , , . _ , - -
_ _ - - _ _-__ _ _ _ _ _ _ _ _ - - _ - __
.
*
.
- I (
-
.
- 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 6 Constructior.
(EDG6C). 6.5.2.9 Special Inspections and Audits A. An i..jependent 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. Alml0RITY 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 (EDG6C) 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 preparcd, approved and forwarded to the Executive Director, Generation 6 Construction, (EDG6C) within 30 days following completion of the review.
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Director, Generation 6 Constrt.ction (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 Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.12.
- b. Each Reportable Occurrence requiring 24 hour 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 The following actions shall be taken in the event a Safety Limit is violated:
-126-
__ -. , . , . . _ , . _ .
-
.
-
.
( (
-
.
- a. The facility shall be placed in at least hqt'::hutdown within one hour.
- b. 'Ihe Nuclear Regulatory Cocaission shall be notified and e.
report submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.12.3.1 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, November, 1972.
- b. Refueling operations.
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation.
- e. Emergency Pla's implementation.
- f. Fire Protection Program implementation.
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 administrative procedures, t 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of the 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. l
-127-
- -
. -. - , . - ... .. . - . - , . - - - - . . .
.
'
.. . t (
.
. iii 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 Chsnges 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 1
,
,
I
- - . . - _ . - . . . - - . - - . . , -..
____ .--______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
.,' ,
-
( ( 5 2-5
-
,
..
2.2 Ilydraulic 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 Not Applicable. 2.2.3 Reservior Drawdown Not Applicable. 2.3 Chemical o 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 pcpulations 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 ! l waste shall be made without a dilution equivalent to one-half (approxi- l mately 383,000 gpm) the full flow of the Unit I circulating water pumps. I 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. All reports to State or Federal agencies regarding compliance with any such limitation shall also be provided to NRC as described in Specification 5.4. l
-__ __ -.
.
-
..
( (
*
.
.
.
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: l l
- a. Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes. j
- b. Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's environmental impact.
5-1 i
.
-,
. ( (
..
*
.
- c. Proposed changes or modifications to plant systems or i ,
equipment which would affect the plant's environmental impact.
'
- d. Results of the Environmental Monitoring Programs.
- e. Investigation of all reported instances of violations of Environmental Technical Specifications involving activities under the responsibility of the General Manager. Where in-vestigation warrants, instances shall be evaluated and i
recommendations formulated to prevent recurrence. 5.3.2 Safety Review Committee
'
The Safety review Committee (SRC) shall be responsible for review of tho following:
-
- a. The environmental evaluations for 1) changes to pro-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 system which involve an unreviewed environmental question as defined in Section 5.7.3.B.
- c. Proposed changes to the Environmental Technical Specifi-cations and the evaluated impact of the changes.
- d. Results of the Environmental Monitoring Programs.
- e. Investigation of all reported instances of violations of Environmental Technical Specifications.
5-2 -
- _ _ _ _ _ _
r ]
- i. -
.
( (
'
.
5.4 State and Federal Permits and Certificates Copies of reports to federal and state agencies regarding compliance l of limitation on quality of liquid effluent from ANO-1 shall be sent to Director of Regional Inspection and Enforcement Office (cc Director, NRR) . 5.5 Procedures Detailed written procedures shall be prepared and followed for all activities performed by Arkansas Power and Light involved in carrying out the sampling, instrument calibration, analysis, and actions to be taken when limits are approached or exceeded. Testing frequency of any alarms shall be included. These fre-quencies shall be determined from experience with similar instruments in similar environments and from manufacturers' technical manuals. Plant standard operating procedures shall include provisions to ensure the plant and all its systems and components are operated in compliance with the limiting conditions for operations established as part of the environmental technical specifications. , 5-3 e ! l
-- --
,_,. . . _ . _ _ __
9 .-
'
. l (
,
5.6 Station Reporting Requirements 5.6.1 Routine Reports Annual Environmental Operating Report A single report on the environmental monitoring programs conducted in association with ANO-1 (Docket No. 50-313) and ANO-2 (Docket No. 50-368) operations for the previous calendar year shall be submitted to the NRC by May 1 of each year. The report shall include summaries, analyses, interpretations, and, where appropriate, statistical evaluation of the results of the environmental monitoring and an assessment of the observed I impacts of the station operation on the environment. If harmful effects or evidence of irreversible damage are suggested by the monitoring or special programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem. The Annual Report shall also include a summary of:
- 1) All ETS noncompliances and the corrective actions taken to remedy them.
- 2) Changes made to state and federal permits and certificates.
- 3) Changes made to the procedures or design described in accordance with Subsection 5.7.3.
.
- 4) Changes in ETS.
,
5-4
!
1 i
-r , r ,
. -
t ( (
.
.
5.6.2 Nonroutino 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 hours by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days. I 5.6.2.b Thirty Day Report Non-routine events not rem 2 iring a prompt report as described in Subsection 5.6.2.a, shall be reported to NRC within 30 days of their occurrence. 5.6.2.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, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of occurrence, and (c) indicate the cor ective 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. 5-5 , l
[, ' ,
'
(
.
,
5.7 Changes 5.7.1 Changes in Environmental Technical Specifications Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90. The req 2 cst shall include an evaluation of the environmental impact of the proposed changes and a supporting justification. 5.7.2 Changes in Permits and Certifications Changes or additions to required federal, state, local, and 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 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
.- ,'- (- (
.
.
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 . Subsection 5.5, and 3) conduct tests and experiments not described in accordance with Subsection 5.5, without prior Commission approval, unless the proposed change, test or experiment involves a change in the objectives of the ETS, or an unreviewed environmental question of substantive impact. B. A proposed change, test or experiment shall be deemed to in-volve an unreviewed environmental question if it concerns 1) - a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental impact statement as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements thereto, environmental impact appraisals, or in initial or final adjudi-catory decisions; or 2) a significant change in effluents or power icvel as specified in 10 CFR 51.5(b)(2); or 3) a matter not previously reviewed and evaluated in the documents specified in 1) of this section which may have a significant adverse en-vironmental impact. C. The licensee shall maintain records of changes in procedures and in the facility design or operation made pursuant to this Subsection, to the extent that such changes constitute changes l
'
t l 5-7 l !
,
_ _ _ _ - __ _
,J+ .- ( (
.
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 which 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 thase 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 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.
- b. Records of environmental surveillance data,
- 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
.
- r , , n m v r
_ ._. ___
,
*
.
*
( (
.
'
'
EXECUTIVE DIRECTOR f GENERATION AND CONSTRUCTION
'
I I I DIRECTOR DIRECE R GENERATION OPERATIONS 'IECHNICAL AND ENVIRONMENTAL SERVICES l ARKANSAS NUCLEAR ONE MANAGER GENERAL MANAGER TECilNICAL ANALYSIS }
.
ARKANSAS NUCLEAR ONE CHEMISTS ENGINEERING AND TECIINICAL SUPPORT AND BIOLOGISTS ARKANSAS NUCLEAR ONE TECIINICAL ANALYSIS SUPERINTENDENT - 1
'.
ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE CilEMICAL AND RADIOCIIEMISTRY HEAL'Ill PHYSICS ENVIRONMENTAL SUPERVISOR SUPERVISOR SUPERVISOR
.
, ARKANSAS POWER 6 LIGirr CO. ENVIRONMENTAL SURVEILLANCE FIG. NO. , ARKANSAS NUCLEAR ONE ORGANIZATION CHART S-1 S-9
.
-
.
o
- - .
,
( (
'
.
,
6.0 ADMINISTRATIVE CONTROLS . 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility l operation and shall delegate in writing the succession to thiss responsibility during his absence. 6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical; support shall be as shown on Figure 6.2-1. Any changes will bee submitted as a Technical Specification change request within 30 days of implementation. FACILITY STAFF 6.2.2 The Facility oganization shall be as shown on Figures 6.2-2A - B, C and D. Any changes will be submitted as a Technical Spechi-fication change request within 30 days of implementation.
- a. Each on duty shift shall be composed of at least the miniminun shift crew composition shown in Table 6.2-1.
- b. At least one licensed Operator shall be in the control rocom when fuel is in the reactor.
- c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recevery from reactor trips.
- d. An individual qualified in radiation protection proceduress shall be on site when fuel is in the reactor,
- e. ALL CORE ALTERATIONS shall be directly supervised by eitheter a licensed Senior Reactor Operator or Senior Reactor Operrator Limited to Fuel Handling who has no other concurrent re-sponsibilities during this operation.
- f. A site Fire Brigade of at least 5* members shall be main -
,
tained 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.
- Fire Brigade shall consist of at least 5 members after October 16, 1978 p ;
prior to October 17, 1978, the Fire Brigade shall consist of at least 3 members. 6-1 l
-
, - -
_ _ _ . _ _ _ _ _ _ _ _
,
.
.
~.
.
N
- ARKANSAS POWER & LIGHT COMP ANY ARKANSAS NUCLEAR ONE - UNIT 7
- EXECUTIVE DIRECTOR 2 GENERATION &
$ ,
CONSTRUCTION
-
m SAFETY REVIEW COMMITTEE 1 I I I I OIRECTOR I D! RECTOR ADMINISTRATIVE DIRECTOR OIRECTOR TECHNICAL & SERVICES & OIRECTOR DIRECTOR GENERATION PROJECTS ENVIRONMENTAL PROJECT GENERATION GENERATION OPERATIONS ENGINEERING MANAGEMENT SERVICES SUPPORT TECHNOLOGY
?
"
.
1 GENERAL PLANT
- Corporate Resporebility for
+
- SAFETY Fire Protection Preysm MANAGER . COMMITTEE i
, Fione a.21 mensomment oremirseen chart
!
. I
_ _ _ _ _ _ _ _ _ _ - _ _
- - .
..
GENERAL MANAGER QUAlliY CONTROL ENGINEER PLANNING & QUALITY CONTROL SCHEDULING SUPERVISOP SUPERVISOR
^
QUALITY CONTROL INSPECTORS
.
ENG N NG & PLANT b
"
OPERATIONS & ADMINISTR. SUPPORT MAINTENANCE MANAGER MANAGER MANAGER
..
.
< f
+ - Senior Operator License Required i
f - Operator License Required ()-Desirable,butnotRequired Figure 6.2-2A 1 _____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
-
^-P
,- .
'- ( (
.
,
,
t GENERAL MANAGER l
.
.
.
.
PLANT ADMINISTR. MANAGER RECORDS HUMAN MATER!ALS
& ADMINISTR. RESOURCES MANAGEttENT SUPERVISOR SUPERVISOR SUPERVISOR FIRE CONTROL SECURITY C00RDINATOP. C 0. A OR
/
1 i l
, Figure 6.2-28 l
6-3b
. . . _-.
. _ _ _ . .
. _--..
._ . __
'
'
", ( .. . .
I GENLRA; l NANf GE D , I I l l 1 l ENGINEERING & l TECHNICAL
. SUPPORT
PANAGER i
;
l I 1 l TECHNICAL PLANT PLANT
- + -
ANALYSIS - ANALYSIS EINGINEERING
! SUPT. SUPT. SUPT.
i
!
l PLANT
!
-
E P NCE HEALTH p .. MECHANICAL L - .- __ PHYSICS SUPER - E ENGINEERING Sl!PERVISOR ' SUPERVISOR
.
NUCLEAR
-
SUPPORT ASSISTANT SUPERVISOR E ELECTRICAL HEALTH - E' ENGINEERING 1 PilYSICS SUPERVISOR l SUPERVISORS NUCLEAR EtlGINEERS RADIO
-
CHEMISTRY SUPERVISOR C0.MPUTER
- '
SUPPORT SUPERVISOR CHEMICAL &
-
ENVIRONMENT LOM E
-
SUPERVISOR ENGINEEF, S Ficure 6.2-2C - 6-3c
- - _ _
.' .
- ( (
-
.
'
"
GT.EF?L CNAGER l OPERATING A FAIN 1ENANCE MANAGER I I
+
I OPERAT10ftS MAINTENANCE - N SUPE P. INT. SUPERINT. SUPERINT. s
.
+ ASST.
ASSISTANT ELEC. OPERATIchs MAINT.
-
I&C S11PERINT. SUPVR. SUPVRS.
,
+ + ^ "
UNIT 1 UNIT 2 EL CT' SHIFT SHIFT MAINT. SUPVR. SUPVR. stjpyps, PLANT PLANT SR Cr OPER. OPER. SUPVR[
# # MECH.
ASST. ASST.
-
PLANT PLANT PAINT. OPER. SUPVP. OPEF. ASST. WASTE WASTE i1ECH.
-
-
CONT. CONT. IT . OPER. OPER. Sfpfp ,
'
AUX. AUX.
-
.
-
OPER. OPER. Figure 6.2-20 l 3d-l l
~ - - -- .. r . , - , _
.* -
a- ( (
'
.
'
.
ADMINISTRATIVE CONTROLS
.
6.3 UNIT STAFF QUALIFICATIONS 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 the Health Physics Supervisor who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the General Manager I and shall meet or exceed the requ,irements 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 General Manager and shall meet or exceed the l 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 AUDIT 6.5.1. PLANT SAFETY COMMITTEE (PSC) FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the General Manager on all matters related to nue. car safety. COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the: Chairman: Operations and Maintenance Manager l Member: Operations Superintendent Member: Technical Analysis Superintendent ! Member: - Maintenance Superintendent Member: Instrumentation 6 Controls Superintendent i Member: Plant Aaalysis Superintendent l Member: Health Physics Supervisor The General Manager shall appoint in writing an acting chairman in the absence of the _ Operations and Maintenance Manager. 6-S < 1
.
__ _
_ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ __
,.. .. . . ( (
'
.
ADMINISTRATIVE CONTROLS
.
AL,TERNATES 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 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. , QUORUM 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 three members including alternates. RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:
- a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes ,
thereto as determined by the General Manager to affect nuclear l safety.
- b. Review of all proposed tests and experiments that affect nuclear safety,
- c. Review of all proposed changes to Appendix "A" Technical 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 involving activities under the responsibility of the General Manager, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager and to the Chairman of the Safety Review l Connittee.
6-6 .- - _
* , ,) * , .
I
* '
.
(
.
ADMINISTRATIVE CONTROLS f. Review of Commission. events requiring 24 hour written notificatione to th h g. safety hazards. Review of facility operations to detect potential nu h. Performance of special reviews, investigations or analyses and reports Safety thereon as Review Committee. requested by the General Manager or th l 1. and shall submit recommended changes Committee. es to th j. Review of the Emergency Plan and implementing procedures a shall submit recommended changes to the Safety Review Co . Alml0RITY 6.5.1.7 The Plant Safety Committee shall: a. Recommend o# in writing to the General Manager approval o items considered under 6.5.1.6(a) through (d) abover disapproval l
- b. .
Render determinations in writing with regard to whether or not tutes an unreviewed safety question.each item considered c. Provide written Generation notification Operations withinReview and the Safety
.
24 hour- to theofDir ector, Consnittee di s-agreement between the PSC and the General Manager; ,however the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. I _ RECORDS
!
6.5.1.8 The Plant Safety Committee shall maintain written minutes of PSC activities performed under the rresponsibilit provisions of these technical specifications. y
'
Copies shall Review Committee.be provided to the General Manager y and Chairma i { I 6-7
'
'
'
' ' ( .
.
.
,
.
ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW C0bHIT'EE (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
- c. chemistry and radiochemistry
- d. metallurgy
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices.
COMPOSITION 6.S.2.2 The SRC shall be composed of the: Chairman: Director, Generation Operations Member: Director, Generation Technology ) Member: Director, Technical and Environmental Services l Member: Manager of Safety l Member: Arkansas Nuclear One General Manager l l Member: Manager, Technical Analysis , Arkansas Nuclear One Plant Analysis Superintendent
'
Member: l Member: Director, Generation Engineering Member: Radiation and llealth Physics Consultant
- Member: Nuclear Safety Consultant *
*The Radiation and Health Physics Consultant and the Nuclear Safety Consultant shall have an academic degree in engineering or physical science field; and in addition, each shall have a minimum of five years technical experience, of which a minimum of three years shall'be in their respective field of expertise.
6-8 l 1
-
- ,
. - - _ ____ - _ _ - _ _ _ _ - _ - .
.
-
c ( (~
.
ADMINISTRATIVE CONTROLS . 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following action 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 Safety Limit violation shall be reported to the Commission, the Manager, Nuclear Operations and to the SRC within 24 hours.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PSC. This report shall describe (1) applicabic circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Manager, Nuclear Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written prncedures shall be established, implemented and maintained covering the activi*i.es referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
- b. Refueling operations,
- c. Surveillance and test activities of safety related equipment.
dI. Security Plan implementation.
- e. Emergency Plan implementation.
- f. Fire Protection Program Implementation.
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 to l implementation and reviewed periodically as set forth in adminis-trative procedures. 't 6-13
. . . - -. - - _ . .
- n '. . ( {
.
.
,
e ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of the iginal 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 the unit affected.
- c. The change is documented, reviewed by the PSC and approved by the General Manager within 14 days of implementation. l 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be sub-mitted to the Director of the Regional Office of Inspection and ,
Enforcement unless otherwise noted.
'
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, i (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 supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include s description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predic-tions 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 reports shall be submitted within (1) 90 days following completion.of the startup test program, (2) 90 days following re-sumptior cr commencement of commercial power operation, or (3) 9 mor4ths.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), supplementary re-ports shall be submitted at least every three months until all
.three events have been completed.
.
6-14
.. . , - . - . _ - . - _ - - _ . . . . . -
'.' t* I ( -
.
4
.
ADMINISTRATIVE CONTROLS ANNUAL REPORTS1/ 6 . 9 .1.-4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of t 'le year following initial criticality. 6.9.1.5 Reports required on an annual basis shall include:
- a. A tabulation on an annual basis for the nunber of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their assopated man rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD, or film badge measurements. Small exposures totelling less than 20% of the individual total dose need not bc cc:ounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- b. The complete results of steam generator tube inservice inspec-tions performed during the report period (reference Specifica-tion 4.4.5.5.b).
1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. 2/ This tabulation suppitments the requirements of 520.407 of 10 CFR Part 20.
.
ARKANSAS - UNIT 2 6-15
-.
*
, ... - (. e i (
. .
,
.
.
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 Commit +.ee (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. 5-1 l
,. _- _ _ - . _ . . . - __
'
.. + 't'
,
( (
. ,
,
'
- 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.
.
Investigation of all reported instances of violations of
- e.
Environmental Technical Specifications involving activities under the responsibility of the General Manager. Where in-
'
vestigation 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:
- a. The environmencal evaluations for 1) changes to pro-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 system which involve an unreviewed environmental question as defined in Section 5.7.3.B.
- c. Proposed changes to the Environmental Technical Specifi-cations and the evaluated impact of the changes.
- d. Results of the Environmental Monitoring Programs.
- c. Investigation of all reported instances of violations of . Environmental Technical Specifications.
l i
, 5-2 l
,
-
._
.
( (
' . i . .c
,
.. .
_ EXECUTIVE DIRECTOR GENERATION AND CONSTRUCTION _ l ' . i I DIRECTOR DIRECTOR TECHNICAL AND CENERATION OPERATIONS - ENVIRONMENTAL SERVICES MANAGER ARKANSAS NUCLEAR ONE TECHNICAL ANALYSIS GENERAL MANAGER CHEMISTS ARKANSAS NUCLEAR ONE AND ENGINEERING AND TECifNICAL SUPPORT BIOLOGISTS ARKANSAS NUCLEAR ONE TECl!NICAL ANALYSIS SUPERINTENDENT ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE llEALTil PIIYSICS RADIOCilEMISTRY CilEMICAL AND SUPERVISOR f SUPERVISOR ENVIRONMENTAL SUPERVISOR l l
!
l
,
)
)
. 1 FIG. NO.
ENVIRONMENTAL SURVEILLANCE 5-1 ARKANSA5' TOWER 6 LIGirr CO. ORGANIZATION OIART ARKANSAS NUCLEAR ONE
..a
- ...
S-10
.
_ _ -- _ ._ _ _ . _ _ _ _. . _.
- -
.. -
,
-
. -
.
- e, 6 .
+ .
* -
.
[
*
; 5 '
6: : >
;
'
i p , s 5 * . ,- g - .* e . . - ; } .
,
3 ,
' .
- t g- .t ,
g , . e . , ; ,
.
,
. 4 . * . .
. . .
. , 3 .
@ . 1
*
.
- i ..a
.
.* . . .
I
- d. .
8
- I y *
.
I * ' j- T- . , , i *
- a i,
e l 3 J * . . l .
.
.
afi se
,
d ,di A gr
'
'. ,
, e 1 '*
,
O vb > ' C C c' i I ' '
'
*
+
d- > e - . o
,
*
,
t : '.
<-
** I
.
'
'
z. O
.'C. s. '
-
o i e
'
- !
t '
.:
.* I ,
,.
j 4
, g - j
.
I
.
e a
.
a It l -
-
1il! a !' 1
- f -
- i
.
n-
- m e. - n' I in ' * ' .
1
- i 1l.]
,
w.. e l..i l t :-
- ll
.
s - i
+
% e
,
.
., I 6 e
*
! -l 6 t +
' t,,i .
l c. a - ee i. 6 l 8 s ji , , ag 't N N Jk 4 I 3 3 o' e i l I
-
o
!!
o. e 15
,
l ;' 9 ; 4
.
.1a tl
. , ,
,
,
;
'
g e, # 8
,
-c *A 4 . I j I
- t
- 4 --
9 g o-
- -
'
- I .e- N.
[ .
<-
4 *
,
I e I t '
.
- i
! i
e 4 ie !.
.
. ee s.J
- .a t
- s r.
O *= c o
!
c
.
+
1e 4 l , C t. c ,.
,
,
C. C-
.
e 6
.
i !I
-
- i -
* *
,
. 6 . - ,
- I
.
;
.
- t,
.
l:
,
t. i 6
'
.
= ma ow e r > w. . > > + i ! le , *i . , '
;
l' , l l - .a J K e a
'g * * ? 2
- s
- e
* .
; e e' '
3 . r 1 * - : e n i o lI 8 '
.2 . I .L c. e Ig
! It 2 .4 T 8 s, ; I e !
,
-
4
- e .. v*- '
.e
. :
,
l i ; l.
.
. i l., l g
.
0- as v -
. -
i . . , .. ., l , .
'. gI !. .I i
. * * - '
l3 2 + - ' !
- 6 l
,
- i , l.. *
.
}'
i 8 .
<I , .
t l , 4
. t e
,
!l l . ,i i
!. e , , . C-
.
l ' 8 t i'
- I ' l i i 1
.
j t i At . l l 8. 8 i
' s '- i ! . gg i I t g a
'l .
-
.,e !
*t' n ,*.--
s' ' #. ' f. ' 8
*
*
- g, + l ' .
,
I, , , t As . .rs c - o o i ,
.e y
,
m I o c o o * ! ; , . j 8 l < l ' i l i
** a, - .
-
i .- - . g :' ' 1 , 3 gl;j ? . l
. r .=
es e-
I
.1'
'
8 N,
= f
.
I tv . : cq-j l
.
t !' t -
!
,i
'
, I g ii i a
*
! l';'l-
,
. 1
- l. .
t t
- 3
!
'P.
. fi !
*=."" i . 4 1
.-
.
OU !a-
- l
,
4-t *I j *' l8 l a
'
*
$
l t -
>3 *1 - $ * *6 i g g ; e l
lg ; i . l '1 lI i t U T . e O. l j *- I - lf . 6 8' i
' '
' t I
!
I e, . 1 T ; C- C . N .c
- o. *,c
, :r c:
- c. l[- '! l ,3 - '
! e
;
~ #9 i
!, > O i. c; I -- - - .r . ' - . 3 I f r !. i ,
,
,
,
. . ,
.* ,)
-
El s= ! ,s . ! g .
* .,
- . - x <3 - . . , , ' . ,
>- es e e i
, pO. e. : , .O- c +
l 4 . e c O z. ;
.
- 2 s/ e- * * .
*# 1 .J l . !7 [ f . ,
.
- i I- ,
1 s S e c c i .c c . I t , p . i 2 c4 l ' e J
,
N N c. ; ,
-
. < j c .a z
,
'- - - .n .
j t
*
' .
- W2 ~ *
- a
- 4 i '
l, 1
- >= -
- s *
,
+ l- e , -
' t
.
sa ce 4 O = I i g . . , .
- '
e ; g I , l Tc g= y. r l
- 4 e i . t ,
* '
t l ' Gw OH 1 ' 3 I
* .
*
' I .
-- Uc * '
t * !' w2 2 2 70 "1 O M M f. N C h l
"
e' , 6 ,; O == '4.1 F> I, == i f( P- p
- t * '
I
- j
i- 41 4,J 1 == c - .= * . m. - 'I f- I
-
; l D =X I ,g s . , l
' . 22
-
. . ? e s e s
,
A 4W ' ' ' s .
- I
, t
' !
'
. - 4. s O2 I .J i t o
,4
' -
!
I J6 A -
- 7 .
O1 1 O l 1U a# .: , , f= . I
' '
t.
# T (1 * '
>
- I
-
V- T2 = ' q f I i ' OO
- t
? . =3J 8
4 3 & l f -
' ,
' V :P Z3 -I 1
' }* e.
W. * * ' '! A
,
I ! TW i *
; ;
-
sa 42 ' ', I Y-
,
%0 .e e e e g e e, t U . ,
,
;
,
C e- . :4 ** , . r*
- U
?, , ! ,t
'
i l . 41
V k vu N F
=,e=
F '
-
- eu' l- N et ,e t t 1
'
. t
1, . i . I' E "J h i . t 6 - a ** Ua f'$ . 9 6
. . V. ; , , ,
l '
+
"
wk- -
- j 7 g a
r 1 'a. 1C '
, I , j . I I U I V> w . t , .
1J t O . . n l '
. '
as ' 1 . I 4 #
- j . la. ;
*
, , ,
.
'
C '
.
-
- . . , ,
i .
.-
r ! , i ?. ' v .
- w z ; . e ,
- e
- j
- J . _t -
I , , i t3 .* T- . . * ! I ' I g g se f* T n= fV e c. c. C .J g r 1 - C T . r'* - !
""
.@ ? , 2 (V' ,
'
e.
'
'
I .
- 8 !
i I
*
- r. 1d e * * * - *
- C " "
.T***
2 et a == . - tr* ~i .m o *- ry . se ,
* (* t ,
- I
'M 7 taJ ' P=
- 1
.
. * '
-' f *
, e- L' /y re. g '# - } * '
4> w _,- m !. ., . .w .
- -
i ,
+ c 2 e * * '
L; *= 'g u. h D. *
. . '
p . (
- i
,
! 41 SC e , 6 e
'
U e l . 1 e 4 il' > _'* ;#6 D= .g* s
- I J , . .
'* .. ==. O .n 7.t .- g e=> - * . ! u r N J ! .e . l I
- t% .
- 1t j *
* ; * *
- e ,
!1- , g- .
- l
.
n v > < - ;
- .
e 2 _t- [i .2 r- . . ! .t1 -
' . . -
!
i ! : _s, .
.e-
.
*
' ta s ,, O , .
** Y ..
. # t 3 tt i .
t
- C-4 W. C *
.V- C t' 7 e
> d' ; .** .- V e .
;
.e ** * . 1- 4' d V 2 V, ';# . .e 4 C *a % T -W s- 1- T 7: w .
- *
, j '
* , er , >=- ../ 'J e ,. , , . 8 ;
<I, - e. y v1 a31 V og
- C. . #. g C~ T. e s
_s e e e.
*
, ,
- '
'
.
9
,
'
.1 # . ta:
.~ =r =- e == .3' 'a 2
.f . O , .' l i * .
g.
.t !e
- 2 4w u N v ..
> / to
;
p- ,
-
,
'g *-
- e. :s .P.- v 3 -
f *
'3. 21 1 e-a -- '>=. 1- 3 .y e t
.
,
.,
'/~2' V' ;: . E V :? % ~
. . . . . - .. ._ A. .
.*. " . . < . ..
_ .. a ~. . . . . ,. .. . . . . - . _. -.
. ,; ,
'
' ' ' .
.
.. ,
. .
. . , ,
, . .
. - . .
}
j m .. .,. . ; i-
'
.
*
{'
' '
'
.
. . l . r
.-
t a 4 1 i-
'
m- *
. '
y '
, -
- p
*
- 8 J
4 Je i e d '1
'.. .
A
.
.A
'
d .
.
*
!. ,
!
a
.
- a
*
- o. # - - m e o .= - 'o e o . ; i I ( l l ^
- 4 '9 e* # c. C
--
C ,
; '
- t
. i ,
- t- , = , , l
+
g 8 N . -a i . .
- I M * * * ' ' ' I' g r '
- t'
- i *
I'
-
O . Pm ' D 1' 4, a= *
- . .- == , - i 6
) t e a
, l . * ,
p 4- 4 - { . f%. *.
,j
. g ,
. g
- 1. % 'e ; t . , . ;, . ,
,
. l . l l ,
I p. **
,
s , e e N v JW er 3
.
,t
,
- e g
.
c ] t.e ! l ' - g
, '
t .g l. 3 e I: m >o .3 .e . .e a l -e ,
,
4 g .-
,
.
!l
;
. .
l e- 0-p= w .a r -
-
[- i
.
;l . . !;8
*
- j i. '
t i . 8' ! !
- l. '
; !
- a w
-- rr
- .a r- e c .a.
=m.
o'
.
C
- -
c'. c, 'l- 'ci . c
- . -
*
*
'O, '
e i
,
*
,- ,
'
.l e .
.
. ,.
.
,.
8 t e ca Ka
.
>8 . .
- I .
- ,
. . t 8. s ,3 : I , c In c- e e c' t c o c . , ; ; a - . + . * *s s t
- i g
.
4 p g , e I
.
; ,i .
* * '
.
2 e ; -f I i 1
- e o .ss v ; ! : ; e ! ; t I r
, i
. : .
s 2 -
' ; I I' - 8 * -
g.'a e
! . .=
- -
-: ! i i i
.
,
,
!
.
-
,
n',
- i i !
l j
.
'
i t,.;e
.
~
. i i , .
i ,
,, 8 i 4 c
. l.j- 8 e ..
-
- e J
.
#
4'
> m s g ,s,
..#.
o
.
.
.A '
- o r.
,
i+ e
.
g t-
-
- l .i ; ' . t ; l'
.
1' I . e m e .o. .' , s' o e 'o ; i
'
;
- e.e a
l
- t g e
- t ==
.'
, e ,
* . ,
- ! a^
I- ).-. t
'*
. .
- l t ; i ll i ; !
- 3. e e-
.
e .- s
. m .s e
. e, ' '
- l. 8
+
; ,
e -+ - 8 6
. l
* * *
-
i
.
-{
C. f
-
a a a
;
-
.
i e l
,
, . , e
,
e e, >C y
-
y 6
- [
! e
- t r f i
,, !' #
.
, ; g
,
Il
. .
'
.
,
t er r e' o - e o i ci e. c ; I
!.
, Tw c.
-
I
.s
-
av e*
-
s
-
rs
- , a -
o c-
' ,-
l 't
- , .- .
, i e
i + l.l
- i i 1 .) e- ' 1 .
* '
'
a- - E eJ . 1 ' :
>= 44 CO C O.
.C C C 2- O . .' 'f ,
..g2 e
.% V. **4.
as e-
-
e t e= e- > - . *=
-6 i e 8
i
. ~1 C C .C C C C C g
,
.
'7 . c4 J :P . e 7 e c- *. it' '
O .a 2 - , y2 = = = g , .
*
.- -2 .
i , ,
> :s *t o -
- t t ' n
-ro up r ==
>
r I 8
. ,
&
l 1 me e vs. 1-
.J Z .22 OI N 4 T- t
- 7 e ? '
,
- o- =J 1>. >= c m < /- * *
. 47 .b 1 == .D -e .% .=. . ~. -
l
'j C a 2 . .
' . a
(
+' . a .
't 2 4 as w -
.
*
- ;
*
. j' i . w.s a. 02 Kr * *
- 8
- i '
- i i i . 2 . ,
3a 2 i - C . Au w/ ri
'
a. e-
.
# . .
P r , . 4 ' ec 2: 2
- la
-
' I . ,
PO 23 1 . ! t , e O ' Te > I r e .
-4' 4: O r %: .- . . . . . e u 3- C n. m. t == ~ C U i
'e -
vu . =
- a p. se pi. .t . -- e.
.
*
.
- Js w ** '
- f i 4 7 g
* *** .
I'
.T
==,.7 A .= .s
- V
.e.. y : .# , == . * '
a* .- a."- - 3 1C y p= - '
. 1 OI 4J J el .3 5
.a a 1 ' .
W t , C: a~ r } V *
, si '
k T< I + 1
. mi , I '
.g . at J . '
,
-6 ,' a g 4, I' 'm 4 1 e=, 3 t\ e. c C 3. f'm 9 .
C E J .
/ f 2 9'. f 9
- * * * * '
e * *
- Ta .** ' r# C.. er .c 4, e !.
> = -
= =
.
- x. : .
-:s-sf 1 i g
t a # . a3 i e t.2
; '
- D er 2
. em J
. U as
-e e t
.
'
E a
,
-g a -
* >w ta e- .J
*1. 3C . U ,
I ?T t- %- 2 I "
? O **
- g 8-e .O E / *
\ 2 *=
e s s n- ,
'/* . 3 ;
e . ' 3 -5 ./ .a. [, *1- 0 - == J
-
*T. 2 / r . - 4
- 5 I ~. *$ . ** ? . / '? /- **
,
- e s ./ ei- ; == *
- 4. . a .. -e 2 , a"t
'
' t *-- 3 t 4 .i /
- e'a . ;,
'a.- ..f. 1 **
,. *>. . . o . ; 7 N
'
* #
, I 'e' . I. 8S I '/ .d /
. -a/7- .sc 3
- i., /- == **
- ** == a- :
-.i.-
== *
? 4
~
. .
3- */ . s. - % ~ - s, - '/ .. a. .= i
,-
, 34 -a. % a. . 2
./ - O . *=
*.
e4g a- '- g - ,,,- 1
*
; e
/=. : / 0- 4 / '& ': 7. .
,
, . . . .g.y -= ==... .
-
,
,,. . . . .. ,
.....-
.. . - .
.
. . - .
. , . , - .- ,- ,
. - ~
- q . -
.
-}}