ML20033B127
| ML20033B127 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/09/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033B125 | List: |
| References | |
| TASK-1.A.1.1, TASK-TM NUDOCS 8111300414 | |
| Download: ML20033B127 (26) | |
Text
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[.+* %b UNITED STATES
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NUCLEAR REGULATORY COMMISSION I
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- r WASHINGTON, D. C. 20555 PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. DPR-34 i
4 1.
The Nuclear Regulatory Commission (the Commission has found that:
A.
The applications for amendment by Public Service Company of Colorado (the licensee) dated October 28, 1981 and October 30, 1981 comply with the standards and requirements of 'the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; I
B.
The facility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized l
by this amendment can be conducted without endangering the health j
and safety of the public, and (ii) that such activities will j
be conducted in compliance with the Com.ission's regulations; 0.
The issuance of this 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.
8111300414 011109 PDR ADOCK 05000267 P
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2.
Accordingly, the license is amended by change to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D(2) of Facility Operating License e
No. OPR-34',is hereby amended to read as follows:
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(2) Technical speci_fications The Techn[ cal Specifications contained in Appendices A and B, as revised through Amendment.No. 24, are hereby incor-porated,in the license. The license shall operate the facility,in. acto 7 ance with the Technical Specifications.
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3.
The license amend $ent-is er'fective as follows:
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Part 1:.PCRV Pressurization ' October 28, 1981 Part 2: AdministrativerCortrols - as of date of issuance.
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/.FOR THE NUCLEAR REGULATORY COMMISSION r
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Robert A. Clirk, Chief Operating Reactors Branch #3 Division,of Licensing
Attachment:
Changes to the
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Technical Specifications Date of Issuance:
November 9, 1981 s~.
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i ATTACHMENT TO AMENDMENT NO. 24 TO FACILITY OPERATING LICENSE NO. DPR-34
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DOCKET NO. 50-267 e
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Replace the following pages of the Appendix A Technical Specifications
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with the enclosed pages as indicated. The revised pages are identified by amendment number and conta1n vertical lines indicating the area of change.
Remove Insert y
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vi vi 4.2.4a 4.2.4a 7.1-1 through 7.1-13 7.1-1 through 7.1-13 e
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PAGE 4
'5.5
,. CONFINEMENT SYSTEM - SURVEILLANCE REQUIREMENTS............
5.5-1 Specification SR 5.5.1 - Reactor Building.................
5.5-i Specification SR 5.5.2 - Reactor Building Pressure Relief Device...........................................
5.5-1 Specification SR 5.5.3 - Reactor Building Exhause Filters.
5.5-2(a) l I
5.6 EMERGENCY POWER SYSTEMS - SURVEILLANCE REQUIREMENTS.......
5.6-1 Specification SR 5.6.1 - Standby Diesel Generator.........
5.6-1 Specification SR 5.6.2 - Station Battery..................
5.6-2 5.7 FUEL HANDLING AND STORAGE SYSTEMS - SURVEILLANCE REQUIREMENTS............................................
5.7-1 Specification SR 5.7.1 - Fuel Handling Machine............
5.7-1 Specification SR 5.7.2 - Fuel Storage Facility............
5.7-2 5.8 RADI0 ACTIVE EFFLUENT DISPOSAL SYSTEMS - SURVEILLANCE REQUIREMENTS............................................
5.8-1 Specification SR 5.8.1 - Radioactive Gaseous Effluent System..................................................
5.8-1 Specification SR 5.8.2 - Radioactive Liquid Effluent System..................................................
5.8-1 5.9 ENVIRONMENTAL SURVEILLANCE - SURVEILLANCE REQUIREMENTS....
5.9-1 Specification SR 5.9.1 - Environmental Radiation..........
5.9-1 5.10 FIRE SUPPRESSION SYSTEMS - SURVE1LLANCE REQUIREMENTS......
5.10-1 Specification SR 5.10.1 - Three Room Control Complex HVAC System.............................................
5.10-1 Specification SR 5.10.2 - Halon Fire Suppression System..................................................
5.10-1 Specification SR 5.10.3 - Smoke Detectors and Alarm.......
5.10-2 3recificaticn SR 5.10.' - Fire 3arrier Tene:ratien Seal...
5.10-3
. Specification SR 5.10.5 - Breathing Air System............
5.10-3 Specification SR 5.10.6 - Ff,xed Water Spray System........
5.10-3 Specification SR 5.10.7 - Carbon Dioxide Fire Suppression System..................................................
5.10-4 Specification SR 5.10.8 - Fire Hose Stations..............
5.10-5 Specification SR 5.10.9 - Yard Fira Hydrants and Hydrant w
Hose Houses.............................................
5.10-5 s s, 6.0 DESIGN FEATURES...........................................
6.0-1
- 7 6.1 REACTOR CORE - DESIGN FEATURES.............................
6.1-1 Specification 7F 6.1 - Reactor Core.......................
6.1-1
-l Ft. St. Vrain v
An andment No. 24 ay,
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- 6. 2 '*
REACTOR COOLANT SYSTM AND STEAM PLANT SYSTEM -
l DESIGN FEATURES.........................................
6.2-1 Sp'ecification DF 6.2.1 - PCRV.............................
6.2-1 Specification DF 6.2.2 - Steam Generator Orifices.........
6.2-3 Specification DF 6.2.3 - Steam Safety Valves..............
6.2-3 6.3 SITE - DESIGN FEATURES....................................
6.3-1--
Specification DF 6.3 - Site...............................
6.3-1 7.0 ADMINISTRATIVE CONTROLS...................................
7.0-1 7.1 ORGANIZATION, REVIEW AND AUDIT - ADMINISTRATIVE CONTROLS..
7.1-1 Specification AC 7.1.1 - Organization.....................
7.1-1 Specification AC 7.1.2 - Plant Operations Review Committee...............................................
7.1-6 l
Specification AC 7.1.3
' Nuclear Facility Safety Committee...............................................
7.1-11 7.2 SAFETY LIMITS - ADMINISTRATIVE CONTROLS...................
7.2-1 Specification AC 7.2 - Action to be taken if a Safety Limit is Exceeded.......................................
7.2-1 7.3 ABNORMAL OCCURRENCE - ADMINISTRATIVE CONTROLS..............
7.3-1 Specification AC 7.3 - Action to be Taken in the Event of an Abnormal occurrence..................................
7.3-1 i
7.4 RECORDS - ADMINISTRATIVE CONTROLS.........................
7.4-1
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Specification AC 7.4 - Records 7.4-1 7.5 REPORTING REQUIREMENTS....................................
7.5-1 Sp sification 7.5.1 - Rce:ine 7.apor:s.....................
7.5-1 Specification 7.5.2 - Reportable'0ccurrences..............
7.5-5 Specification 7.5.3 - Environmental Qualification.........
7.5-10 Ft. St. Vrain vi Amendment No. 24 s
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4.2.4a l'
Basis for Specification LCO 4.2.6 (continued)
In addition to the fire suppression function either of the fire pumps operating in conjunction with either fire water booster pump provides adequate capacity to operate a circulator water turbine and' supply emergency cooling water for safe shutdown cooling. With the 325 gallons of fuel in storage, the engine driven fire pump can operate at rated conditions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> which it adequate time to have more fuel delivered to the site. For further explanation, see Final Safety Analysis Report, Sections 1.4, 10.3, and 14.4.
Specification LCO 4.2.7 - PCRV Pressurization Limiting Conditions for Operation The PCRV shall not be pressurized to more than 100 psia unless:
a) The PCRV safety valve installation is operable, and there'is less than 5 psig between the rupture disc and relief valve, and both inlet block valves are locked open.
- b)
All primary and secondary penetration closur.es and hold down plates are in place and operable, per Specification LCO 4.2.9.
- c)
The interspaces between the primary and secondary penetration closures are maintained at a prassure greater than primary system pressure with purified helium gas.**
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- During the initial low power physics testing (<,0.1% of rated thermal power) with the PCRV pressurized and when helium circulators C and D are in the pre-nuclear Pelton wheel configuration, exceptions to provisions b) and c) of this LCO will be the installation of the secondary closures and pressurization of the primary secondary closure interspace of C and D helium circulator penetrations.
- except for module B-2-3 interspace pressure which will be slightly above cold reheat steam pressure for the period October 28, 1981 to November 27, 1981, only. At the end of this time, the original Technical Specification will again be effective.
Ft. St. Vrain Amendment No. 22, 24
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-ge 7.1-1 7.1 ORGANIZATION. REVIEW AND AUDIT-ACMINISTRATIVE CONTROLS Apolicability Applies to the lines of authority and responsibility for the operational safety of the facility, and the organization for periodic review and audit of facility oceration.
Objectives To de fi n e~" the principal' lines of authority and reshensibility for providing continuing. review, evaluation and improvement. of the plant operational. safety.
SPECIFICATION AC 7.1.1 - ORGANIZATION, ADMINISTRATIVE CONTROLS 1.
CRGANIZATICN The organi:ation and lines of responsibility wnich govern ciant coeration shall :e as fell;ws:
a.
In all matters certaining to coeration and maintenance of :ne pian; anc to tnese Tecnnical Scecifications, the Station Manager shall recort 1
to, anc be directly responsible to, the Manager, Nuclear production.
The Administrative and Departmental Management Organization is shown in Figure 7.1-1.
Ft. S t. Vrain Amendment No. 24
0 Page 7.1-2 b.
The Staticn Manager is directly responsible for overall facility operation and in all matters concerning the Plant Operations Review Committee l
(PORC).
He shall delegate in writing-this i
l responsibility during his absence.
I l
l c.
The Technical Advisors shall report to,andbe directly responsible to, the i
Technical / administrative Services Manager.
The Technical Advisors shall maintain independence from normal plant operations as necessary to make objective evaluations of plant conditions and to advise or assist plant management in correcting conditions that may ccmcromise safety of f
ocerations.
Tne Iecnnical Acvisors are resconsicie for:
(') Maximi:ing plant safety curing and after l
accicents, transients and emergencies ty incecencently assessing piant concitions and by providing technical assistance to mitigate and minimi:e the effects of such incidents and make recommendations to the Superintendent of
' Operations.
(2) Review abnormal and emergency proce'dures.
Ft. St. Vrain Amendment No.-24 t
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Page 7.1-3 (3) Assist the operations staff in applying the i
requirements of the Technical Specifications.
l (4) Provide evaluation of Licensee Event Reports from other plants as assigned.
1 d.
Organization for conduct of operations of the plant i
is shown in Figure 7.1-2.
2.
UNIT STAFF.
a.
A licensed senior operator shall be present on site at all times when there is fuel in the reactor.
b.
A licensed operator must be in the control room at all times when fuel is in the reactor.
During reactor startuo.
- snutcown, and recovery from reactor trip. two licensed operators must be in the control room, ALL CORE ALTExATIONS after tne iritial fuel loacing c.
snail ce airectly sucervisec cy eitner a iicensec Senior Reactor Caerator or Senior Reactor Ocerator limited to Fuel Handling who has no other i
concurrent responsibilities during this operation, d.
An operator or technician qualified in radiation protection crocepures shall be present at the facility at all times that there is fuel on site.
Ft. St. Vrain Amendment No. 24
Page 7.1-4 l
e.
A site Fire Brigade of at least 5 members shall be l
I maintained on site at all times". The Fire Brigade shall not include (3) members of the minimum shift crew necessary for safe shutdown of the unit and f
I any personnel required for other essential functions during a fire emergency.
- Fire Brigade composition may be less than the mir.imum 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 accomodate unexpected absence of Fire Brigade members proviced immediate action is taken to restore the Fire Brigade to within the minimum recuirements.
I f.
The Tecnnical Acvisor snali be in.tne control room si-hin one cur af er an e ergency call.
The Technical Advisors shall work a normal day work schecule out will e placea "on call" after no rmal working hours.
Ft. St. Vrain Amendment No. 24 i..
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Page 7.1-5 g.
Upon commencement of commercial operation-the l
staffing of the plant shall be in accordance with American National Standards Institute N18.1-1971,
" Selection and Training of Personnel for Nuclear Power Plants."
h.
Each member of the facility staff shall meet or l
exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the l
Radiation Protection Manager who shall meet or l
exceed the qualifications of Regulatory Guide 1.8, S epten.ber, 1975.
3.
TRAINING l
a.
A retraining anc reciacement training crogram for l
the facility staff shall be maintained under the cirection :f ne Training Su:ervisor anc snall meet or exceed ne requirements anc recommenoations of Sec-icn 5.5 Of ANS! N15.1 '.571 anc at:ercix "A" of 10CFR Part 55. Compliance with Section 5.5 of ANSI N18.1-1971 snall be acnievec no later than six months following commencement of commercial operation.
Ft. St. Vrain Amendment No. 24
Page 7.1-6 b.
A training program for the Fire Brigade shall be l
maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the 'NFPA Code-1975, except for Fire Brigade training / drill sessions l
which shall be held at least once per calendar quarter.
c.
An initial training and retraining program for the Technical Advisors shall be maintained under the direction of the Training Supervisor.
The Technical Advisors shall receive specific' training in the response and analysis of the plant for transients and accidents. The Technical Advisors
's na li also receive :rsining ciant cesign anc 4-
- layout, including the capabilities of instrumentation anc :entrois in :.e control rocm.
SPECIFICATION AC 7.1.2 o LANT OPERAT:0NS REVIEW COMMITTEE (PCRC). ACMIN:STRATIVE CONTROLS The organization, responsibilities, and autnority of :ne PORC shall be as follows:
1.
MEMBERSHIP Fc. Sc. Vrain Amendmenc No. 24
w Page 7.1-7 The Plant Operations Review Committee shall be ccmposed of the following:
Chairman: Station Manager Technical / Administrative Services Man &ger Radiation Protection Manager Superintendent of Operations Superintendent of Maintenance Health Physics Supervisor Results Engineering Supervisor Shift Sucervisor Training Suoervisor Seneculing/OC/5 cres Suoervisor Tecnnical Se v :es Engineering Sucerv ser d
d Senior Maintenance-Sucervisor Maintenance Supervisor Security Supervisor Ft. St. Vrain Amendment No. 24 j
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Page 7.1-8 Reactor Engineer Technical Services Engineer Technical Advisors Training Instructor 2.
ALTERNATES An alternate chairman and alternate members, if required, i
shall be appointed in writing by the PORC Chairman to serve in the absence of a chairman or a member; however, l
no more than two alternate members shall participate in PORC activities at any one time.
3.
MEETING FRECUENCY l
The PORC snall meet at least once per calencar month and as c:nvened by the Chairman.
j a.
CUCRUM i
A cuorum snali c:nsis-of :ne nairman or a'.
ernate Chairman, and four members including alternates.
Ft. St. Vrain Amendmenc No. 24
Page 7.1-9 5..
RESPONSIBILITIES The PORC shall be responsible for:
a.
Review of all procedures required by Technical Specification 7.4(a), (b) and (c) and changes
- thereto, and any other proposed procedure or i
l changes to approved procedures as determined by the Station Manager to affect luclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Technical Specifications.
c.
Review of all prooosec cnanges or mocifications to plant systems or equipment that affect nuclear
)
1 sarety.
e.
Investigation of all violations of the Technical Specifications inciucing tne pre;aration anc forwarding of reports covering the evaluation and l
recommendations to prevent recurrence to the i
Manager, Nuclear Production and to the Chairman of the Nuclear Facility Safety Committee.
Ft. St. Vrain Amendment No. 24
Page 7.1-10 f.
Review of events requiring 24-hour notification to the Commission.
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g.
Review of facility operations to detect potential nuclear safety hazards, h.
Performance of special reviews, investigations and reports thereon as requested by the Chairman of the Nuclear Facility Safety Committee.
i.
Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Chai rman of the Fort St.
Vrain Security Committee.
6.
AUTF]RITY The PORC shall:
a.
Function to acv4se the Manager. Nuclear P*ocuction on all matters that affect nuclear safety.
b.
Recommend to the Manager, Nuclear Production in i
- writing, approval or disapproval of items considered under 5.a through 5.d, above.
Ft. St. Vrain Amendment No. 24
Page 7.1-11 c.
Render determinations in writing with regard to whether or not each item considered under 5.a through 5.e above constitutes an unreviewed safety question.
d.
Provide immediate written notification to the Manager, Nuclear Production and the Chai rman of NFSC of dJsagreement between the PORC and the Station Manager; however, the Station Manager shall l
have responsibility for resolution of such disagreements pursuant to 6.a above.
l 7.
RECORDS The PORC shall maintain written minutes of each meeting anc cc:ies sr.ali :e :-Ovidsc ::
ne S'a n a;e r. Nuclear Production and Chairman. of the Fort St. Vrain Nuclear racility Safe y Committee.
SpECI:! CATION AC 7.1.3
- NUCLEAR :aCILITY SAFETY CCMMITTEE (NFSC). ADMINISTRATIVE CCNTROLS The organi:ation, responsibilities, and authority of the NFSC shall te as follows:
Ft. St. Vrain Amendment No. 24
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Page 7.1-12 l
l 1.
FUNCTION l
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The Nuclear Facility Safety Committee shall function to provide independent review and audit of designated i
activities in the areas of:
i l
a.
Nuclear Power Plant Operations-b.
Nuclear Engineering c.
Chemistry and Radiochemistry d.
Metallurgy e.
Instrumentation and Control f.
Radiological Safety g.
Meenanical and Electrical Engineering h.
Quality Assurance Practices i.
(0:ner accropriate fields. associated with the unique cnaracteristics of :ne nuclear power plant.)
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Ft. St. Vrain Amendment No. 24 i
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Page 7.1-13 2.-
MEMBERSHIP l
The NFSC shall be composed of the following:
Chairman: Vice President, Electric Production Manager, Nuclear Production Division Manager, Nuclear Engineering Division Quality Assurance Manager Manager, Claims, Safety and Security Division Consultants, as required and appointed by the Chairman 3.
ALTERNATES An alternate enairman anc alternate memoers, if requirec, shall be acocinted in wri ing cy the Chairman; however, no more inan two alternate me:cers snall carticioate in NFSC I
activities at any one time.
4 CONSULTANTS Consultants shall be utili:ed as determined by the Chairman, NFSC, to provide expert advice to the NFSC..
Ft. Sc. Vrain Amendment No. 24
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l Page 7.1-14 5.
MEETING FREQUENCY l
The NFSC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
6.
OUORUM l
A quorum of the NFSC shall consist of the Chairman or his designated alternate and a majority of the NFSC members including alternates.
No more than a minority of the quorum shall have line responsibilities for operation of the facility.
7.
RESPONSIBILITIES l
a.
The Nuclear r :ility Safety ::m-:::ee snali rev'ew:
a (1) The safety evaluations for changes to i
Orocecures, ecui: ment Or systems affecting nuclear safety and tests or exoeriments affecting nuclear safety completec uncer :ne crovision of Section 50.59,10CFR, to verify that such actions did not constitute an unreviewed safety question.
(2) Proposed changes to procedures, equiptent or j
systems which involve an unreviewed safety question as defined in Section 50.59, 10CFR.
Ft. Sc. Vrain Amendment No. 24
Page 7.1-15 (3) Proposed tests or experiments which involve an l
unreviewed safety question, as defined in Section 50.59, 10CFR.
(4) Proposed changes in Technical Specifications l
or licenses.
(5) Violation of applicable statutes, coces, l
regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions affecting nuclear safety.
l (6) Significant operating abnormalities or deviations from normal and expected cer#c-mance of clant ece ment t..at affect nuclear safety.
(7) All events wnien are requireo by -egulations or Technical Scecifications to be recorted to the EC in writing witnin 24 nours.
i (3) Any indication that nere may be a ceficiency l
in some aspect of design or operation of structures,
- systems, or components, that affect nuclear safety.
(9) Reports and.+.eeting minutes of the PORC.
l Ft. St. Vrain Amendment No. 24
age 7.1-16 b.
Audits of facility activities-shall be performed l
uncer the cognizance of the Nuclear Facility safety Committes. These audits shall encompass:
(1) The confo rmance of facility operation to all l
provisions contained within the Technical Specifications and applicable
_ license conditions at least once per year.
(2) The performance, training, and qualifications, l
.of the facility staff at least once per year.
(3) The results of actions taken to correct
]
deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at leas: Once :er six months.
(A) The performance of activities recui.ed cy the Quality Assurance Program to ' meet the criteria of Accencix "5",
- CC.
- R50, a: leas: Once :er two years.
(5) The facility Emergency Plan and implementing l
procedures at least once per two years.
(6) The facility Security Plan and implementing procedures at least once per two years.
Ft. St. Vrain Amendment No. 24
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Page 7.1-17 l
(7) Any other area of facility operation considered appropriate by the NF5C.
I l
(8) An audit of the Fire Protection Program
]
f including a
fire protection and loss l
prevention inspection shall be performed
- annually, utilizing qualified off site licensee personnel, an outside fire protection firm, or an outside qualified fire consultant.
l This audit must be performed by an outside qualified fire consultant at intervals no
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greater than 3 years.
l 8.
AUTHORITY The NF5C small recort to ar.d acvise tre."ce Presican:,
l Electric Production on.tnose areas of responsibility l
l 50ecifisc in c.(7) acove.
l 9.
RECORDS l
Records of NFSC activities shall be prepared, approved and distributed as incicated below:
a.
Minutes of each NFSC meeting shall be prepared, approved and forwarded to the Vice President, Electric Production within 30 days following each meeting.
Ft. St. Vrain Amendment No. 24 1
Page 7.1-18
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b.
Reports of reviews encompassed by Section 7.a.
above shall be forwarded to the Vice President, Electric Production within 30 days following completion of the review.
c.
Audit reports encompassed by Section 7.b, above shall be forwarded to the Vice President, Electric Production and to the management positions responsible for the areas audited within 30 days after completion of the audit.
Ft. St. Vrain Amendmenc No. 24
FORT ST. VRAIN tillCI. EAR GENERATING STATION ADilINISTRATIVE AllD DEPARTilEllTAL MANAGEllENT ORGANIZATION CilART 7e Pit'iSIDENT AND ClllEF EXECUTIVE OFFICER b
SENIOR VICE PRES.
OPERATIONS e
8 VICE PRESIDENT NFSC El.ECTRIC PRODUCTION QUALITY ASSURANCE
?!AllAGER HAllAGER. MAINT.
MANAGER, PROD.,
MANAGER, NUCLEAR MANAGER tillCI.EAll EllGI NEEit i ti.;
- f. EllGINEERING FUEL.S. AND SERVICI lI PRODUCTloti DIVISION D I V I S IOli DIVISION y
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_._.._,.__I TECilNICAL/
IrADI ATIDIl STATION.
Pit 0TECTIOli MANAGER ADMINISTRATIVE rt
FT. ST. VRA f ra y
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- ---- ~ ~- -" -.--- -
PORC FIGllRE 7.1-1
tuRT ST. VrAafa 640Ct. EAR CENERATitec STATiott
(:DHIHk:r OF HFERATIOffS CHART
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itANAGER HUCt_ EAR t/s l'RODUCTION rt Sants 4
1 Agnbnennt D**
O Etation Radiation rectua tcal/Aelmin.
Manager trotectton Services Hanager Manager Staff l
Aentstant FURC SuperIntenlent Super f ut enile nt D'estelonn Itaint enance i
sl.
St.n I
Sr. flaint.
Results Training Slallt Water IIcal tle Cler.. cal Security SclieJ/
Engineering Supervisor" Enginee'rin g
",upe r v inor Sug.e s v l ent 4:henint rhyalce Supervisor Supervisar Stores /qC Supervisor 8"I'e r visor Supervisor Supervisor 1/*.In t i t [;5
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'la l u t enanc e Equipment Reactor Auxillary llealth Chief Technical Computer Licensing Finnt g
D Supervisor Operator operstar Teneler rhysictnt RaJto AJvisors Services EnRincer EnRineer 2/nhlft
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2/ shift Chestet b
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- Elther the Station Hanager or el.c SupesIntendent of operat ion s shall ponness a nenfor license.
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