ML20037B228

Change 21 to License DPR-2 Tech Specs Re Staffing,Gaseous Effluent Releases & Administrative Controls

ML20037B228
Person / Time
Site:	Dresden
Issue date:	06/13/1972
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20037B227	List: ML20037B226 ML20037B228
References
NUDOCS 8009080617
Download: ML20037B228 (25)

Text

{{#Wiki_filter:_ ,q N) ATTACHMEh7 A CHANGE NO. 21 TO TECHNICAL SPECIFICATIONS LICENSE NO. DPR-2 COMMONWEALTH EDISON COMPAhT DOCKET No. 50-10 1. Delete the remainder of paragraph B.S.c (Airborne Wastes) f ollowing the words "The sy=bols in the equations stand for the following:" and insert in its place the following: Q = release rate from Unit 1 plant chimney. y Q = release rate from Units 2 and 3 plant chimney with only 2 Unit 2 or only Unit 3 operating (not both). Q = release rate fr m Unite 2 and 3 plant chimney with 2,3 both units operating. Q = release rate from Mts 2 and 3 reactor Midng gg ventilation stack. (1) The release rate for gross activity, except for halogens and particulates with half lives longer than eight days, shall not exceed: I 9 (a) Q1 Q2 Q2,3 Om z 1.0 + or 0.56 0.70 0.90J O.09 - s where Q is measured in curies /second. (2) The su=mation of release rates of halogens and particulates with half lives greater than eight days released to the environs as part of the airborne effluents shall not exceed: Q1 Q2 Q2.3 QRS + or 4 4 1*0 2.4x10-6 3.5x10-6 4.3x10-6 0.12x10-6 where Q is ceasured in curies /second. 8009080bb7 ~ ^

- l (3) If the off-gas discharge rates experienced, averaged over any calendar quarter, are such that the estimated annual average release rate of gross activity is likely to exceed 0.056 curies /second or the estimated annual average release l rate of iodine 131 and p' articulates with half lives greater thnn eight days is likely tc exceed 2.4x10-7 curies /second, the licencee shall: r (a) make an investigation to identify the causes of such release rates; l (b) define and initiate a program of action to reduce such release rates to a level consistent with Section 8.c.(6); and l (c) report these actions to the Deputy Director for l Reactor Projects, Directorate of Licensing within l 30 days of the end of the calendar quarter. (4) An of f-gas discharge rate averaged over any 48-hour period exceeding 0.112 curies /second of gross activity or 4.8x10-7 curies /second of todine 131 and particulates j with half lives greater than eight days shall be considered to be an abnormal occurrence. I (5) If the limits of 8.c.(1) or 8.c. (2) are exceeded, an orderly l ' load reduction of the unit (s) causing these limits to be l exceeded shall be initiated immediately to reduce the j releases below the limits of 8.c. (1) and 8.c. (2). l l (6) It is expected that releases of radioactive caterial in ef fluents will be kept at small fractions of the limits specified in Section 20.106 of 10 CFR Part 20. At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependabic source of power even under unusual operating cenditiens which may te=porarily result in releases higher than such small fractions, but still within the 11=its specified in Section 20.106 of 10 CFR Part 20. It is expected that in using this operational flexibility under unusual oper-ating conditions, the licensee will use his best effort. to keep levels of radioactive materials in effluents

t .l' -b 4 9 ' I ',. ' r N 3 -- k' n This will include compliance y as low as practicable. 7, with the provisions of 10 CFR Part 50.36a(1) that require that equipment installed in the radioactive . waste system be maintained and used to its capacity f effluents to as low as practicable, -{toreducelevelso M. m,' Noie (a) in Equations in subparagraphs (1) and (2): Vnere lhe term in parentheses represents the operational e s tatus 'of-Units 2 and 3. If either Unit 2 or 3 is shut If tiown, then the first term (Q2/value) shall be used. bbth units are in operation, then the second term - (Q2,3/value) shall be used. - - s Delet,c., Sections C.b, C.d and Table III. 2. ,3. RGiee 'Se'ction'E.1 to read as follows: "1.90peratiigPrinciples .m All 9e[uoling and maintenance operations shall be carried out in accordance with all the applicable operating principles s" _,i Ite=s in Section C which are pr rticularly given in Section-C. pertinent to these operations are those lettered e, f, g, h, 1, j and 1." Add a new Section J to read as follows: 4. e-k s * \\ O e e, b' j s 6

4 - 4 '- J. ADMINISTRATIVE CONTROLS y 1. Organization, Review and Audit The Station Superintendent has the overall full-time a. responsibility for safe operation of the facility. is During periods when the Station Superintendent unavailable, he may delegate this responsibility to - c the Assistant Station Superintendent. b. The pcrtion of the corporate management which relates to The the operation of this plant is shown in Figure I. functional organization is shown in Figure II. The required shif t manning is shown in Table III. d. The qualifications with regard to educational and ~ experience backgrounds of key supervisory and~~~ professional personnel'at the time of their l ' appointment to the active position shall'be as follows: (1) Station Superintendent - The Station Superintendent shall have ten years of responsible power plant l experience of which a minimum of three years shall be nuclear power plant experience. A maximum of four years of the remaining seven years of experience may be fulfilled by academic training on a one-for-one time basis. To be acceptable, this academic training shall be in an engineering or scientific field generally associated with the l j utility industry. He shall hold a Bachelor or l higher degree. When the Assistant Station i Superintendent meets the nuclear power plant experience and degree requirements, the require-ments of the Station Superintendent may be reduced such that only one of his ten years of l experience need be nuclear power plant experience i and.he need not hold a deg,rce. (2) Assistant Station Superintendent - The Assistant Station Superintendent shall have a minimum of eight years of responsible power plant experience of which a minimum of three years sha'1 he nuclear power plant experience. A maximum cf -Icur yer.re of the remaining five year'c of experienec may b::

I 1 fulfilled by satisfactorily completed accccmic or related technical training on a one-for-one time basis. He shall hold a senior operator's = license for Dresden. When the Station Superintendent holds a senior cperator's license, the Assistant Station Superintendent need not hold a license. (3) operating Engineer - The Operating angineer shall have a minimum of six years responsible power k plant experience of which a minimum of two years shall be nuclear power' plant experience. A maximum of two years of the remaining dour years of experience may be fulfilled by satisfactorily ~ completed academic or related technical training on a one-for-one time basis. He shall hold a senior operator's license for Dresden. (4) Technical Staf f Supervisor - The Technical Staf f Supervisor shall have.a minimum of eight years of responsible power plant experience of which a minimum of two years shall be nuclear power plant A maximum of four years of the experience. remaining six years of experience may be fulfilled by satisfactorily completed academic or related technical training on a one-for-one time basis. (5) Technical Engineers (Thermal, Instrument and Radiation-Chemical) - The Instrumedt Engineer, Thermal Engineer, and Radiation-Chemical Super-visor shall have a minimum of five years of experience in the area for which they will be responsible. In addition, these people shall have at least a high school diploma and a minimum of two of tae five years of experience should be related to technical or academic training and related technical training beyond the high school level. A maximum of four years of the five years of experience may be fulfilled by related technical or academic training. (6) Nuclear Engineer - The Nuclear Engineer shall in have a minimum of a Bachelor's Degree Engineering or the Physical Sciences and two years of experience in such areas as reac cr core heat transfer physics, core measurements, core physics testing programs. or

-6 (7) Maintenance Engineer At the time of y appointment to the active position, i the Maintenance Engineer shall have a minimum of seven years of responsible power plant experience, a minimum of one year which shall be nuclear power plant experience. A maximum of two years of this power plant experience may be satisfactorily com-pleted by related technical or academic training on a one-for-one time basis. In addition, he shall have the ability to direct the performance of maintenance in conformance with applicable codes. (8) Shift Engineer / Shift Foreman - At the time of appointment to the active position, the Shift Engineer / Shift Foreman shall have a minimum of a high school diploma and fcur years of power plant experience, of which a minimum of one year shall be nuclear power plant experience. They shall hold senior operator's licenses. Notes Listed below are the definitions of terms used in this paragraph and further elaboration as to requirements which are applicable to all r people: 1 l (1) Experience - Experience is actually working in i applicable areas of the design, engineering, l l construction, maintenance, operation, or supervision of nuclear and fossil power plants. Observation of I l others shall not be considered experience. To l classify as nuclear experience,the work must be l related to nuclear reactors. l Further, nuclear experience acquired at military t non-stationary or propulsion including prototype plants may qualify as equivalent experience on a one-for-one unlig.ited time basis. Nuclear experience acquired in non-power plants such as test cr l production reactors may qualify as equivalent to l nuclear power plant experience on a one-for one basis, but only one year of such experience shall be acceptable toward the total nuclear experience qualification. Intensive nuclear training may be considered as a substitute for up to two-thirds of the required nuclear experience on the basis of one month's training being equivaltnu to three month's experience. D**0 ]DT We alL J n

7 Related technical training, or on-the-job training may qualify as equivalent to nuclear power plant experience requirements for up to a maximum of one year's credit toward the nucicar power plant experience requirements. Such trcining may be used simultaneously as satisfying on a one-for-one basis both experience and training requirements as required and as limited by this standard. (2) Academic Trainina - Academic trainine is successfully completed college level course work which could lead I to a recognized degree. -(3) Related Technical Training - Related technical train-ing is classroom training in uechnical subjects associated with the position in question, acquired in training schools or programs conducted by the military, industry, utilities, universities, vocational schools or others. (4) On-the-Job Training - On-the-Job training is participation in nuclear power plant operation, maintenance, or technical services under the direction of appropriately experienced personnel. (5) Intensive Nuclear Training - Training which meets all the following requirements: (a) The training shall be conducted by a formal organization such as the licensee's training department, reactor system vendors, universities or the military; (b) The trainee shall be given a course of study of scheduled and planned length that includes text material, lectures and frequent examinations; and (c) The training ghall include practical experience on a reasonably comparable reactor, or a training simulator which duplicates plant response with a fidelity such that the trainee cannot distinguish that response from the actual plant.

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d. Organization units for the review and audit of fac ility operations shall be constituted and have the respon-sibilities and authorities outlined below: (1) Nuclear Review Board (NRB) (a) Membership - The NRB shall consist of a minimum of eight persons employed by Commonwealth Edison Company who as a group should collectively pro-vide expertise in: reactor operation, reactor engineering, chemistry and radiochemistry, metallurgy and radiation damage, inr.trumentation and control systems, radiological safety, mechanical and electrical systems, and any other appropriate fields required by the unique characteristics of the facility. The Chairman, Vice Chairman and other members shall be appointed by the Company President or such other_ person as he shall designate,. No more than two members shall be selected from the organization reporting to the Manager of Production. The NRB will obtain advice and counsel of scientific or technical personnel employed by the Company cr other organization whenever the Board considers it necessary to obtain further scientific or technical assistance in carrying out its responsibilities. (b) Meeting Frequency - The NRB shall mcet on call by the Chairman or as requested by individual members and at least semi-annually. (c) Quorum - Chairman or Vice Chairman plus three members. (d) Responsibilities

1. Review and approve for submittal to the AEC proposed changes to the station operating license, including technical specificaricas, unreviewed safety questions, and Safety Analysis Reports.

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2. Make or cause to be made at least sem -

annually audits of station operations to 1 verify that operation complies with the terms and conditions and intent of any license or permit and other app'icable regulations.- I

3. Review and approve proposed changes or modifications to plant systems or ccmponents referred to it by the Station Review Board (SRB) or by the Station Superintendent.

4. Review minutes of meetings of the SRB to determine if matters considered b;' that committee involve unreviewed safety questions or changes to the license, technical specifi-cations, and Safety Analysis Reports.

5. Investigate ins'tances of abnormal occurrences including' review of'the recommendations of the SRB.

6. Review and approve all changes to the Generating Stations Emergency Plan.

7. Review and approve all items referred to it by the SRB or the Station Superintendent.

l l (e) Authority - The NRB shall be advisory to the Company President. I ( (f) Records l

1. Minutes shall be recorded for all meetings of the FRB.

Meetings shall be nutbered in sequence and distribution shall be to the Company President, Manager of Prcduction, each Station Superintendent responsible for a nuclear reactor, Board Members, and others the Chairman or Vice Chairman may designate. l

2. Reports of all audits including reccmmendations l

of the Board shall be made in writing to the l Company President with copics to the Manager of Production and the Station Superintendent.

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3. The findings of all reviews of licenne and technical specification violations and recommendations to prevent recurrence shall be reported in writing to the Company President with ccpies to the Manager of

= Production and to the Station Superintendent. (g) Procedures - Written administrative procedures y for Bcard operation shall be prepared and maintained. These procedures shall cover the following:

1. Content and method of submission of presentations to the Board.

2. Use of subcommittees.

3. Review and approval by the members of Board actions.

4. Dissemination of minutes.

5. Detailed listing of items to be reviewed by the Board.

6. Scheduling of meetings.

(2) Station Review Board (SRB) (a) Membershio - The SRB shall consist of at the minimum the Station Superintendent, Assistant Superintendent, Op'erating Engineer, and two members of the NRB appointed by the NRB Chairman. The Station Superintendent shall be the Chairman and the Assistant Station Superintendent shall be the Vice Chairman. (b) Meeting Frequency - The SRB shall meet on call by Chairman or as requested by individual members and at least monthly. (c) Quorum - Chairman or Vice Chairman plus threc members. 6

(d) Reeponsibilitle:

1. Rnvicw and opprovo all Company and station orders as related to the statien license.

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2. Review and approve all proposed station and/or unit normal, abnormal, maintenance and emergency operating proccdures specified in J.2 and proposed changes thereto; and any other proposed procedures or changes thereto which affect nuclear safety or involve the license, technical specifications, and Safety Analysis Reports.

3. Review and approve all proposed tests and experiments which involve nuclear hazards not previously reviewed.

4. Review and approve for submittal to NRS proposed changes to :echn.ical specifications, license, and Safety Analysis Reports.

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5. Review and approve proposed changes or modifications to plant systems or equipment.

6. Investigate instances of abnormal occurrences or exceeding a safety limit and recommend corrective l

actions in writing to the Chairman of the NRS for action, j

7. Review plant operation to detect potential 1

i safety hazards.

8. Perform special reviews and investigations and render reports thereon as requested by the Chairman of the NRB.

('e) Authority - The SRB shall be advisory to the Station Supefintendent. 4 I (f) Records - Minutes shall be kept for all meetings of the SRB with copies to the Manager of Production, Station Superintendent and to the Chairman of the NRB. 9

I ( - 12 (g) Procedures - Written administrative proc'edures for Board operations shall be prepared and maintained. These procedures shall cover the following:

1. Content and method of submission of presentations to_the Board.

2. Use of subcommittees.

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3. Review and approval by members of Board actions.

4. Dissemination of minutes.

5. Detailed listing of item to be reviewed by Board.

6. Scheduling of meetings.

2. Plant Operatina Procedures a. Detailed written procedures, including applicable check-off tests and instructions, covering areas listed below shall be prepared, approved as specified in Section 1 and adhered to for operation of all systems and components involving nuclear safety. (1) Normal start-up, operation, and shutdown of systems and components involving nuclear safety of the facility. (2) Refueling. (3) Abnormal and emergency operations. (4) Emergency conditions involving potential or. actual release of radioactivity - (" Generating Station Emergency Plan'! and station emesgency and abncrmal procedures). .(5) Instrumentation operation which could have an a f fect on the safety of the plant. 1 1 )

- 13 (6) Preventive and corrective maintenance operations which could have an affect on the safety of the reactor. (7) Specific and foreseen potential malfunctions of systems or components, including alarms and abnormal activity. p (8) Surveillance and testing as required by these Specifi-cations. (9) A procedure to assure safe shutdown of the plant in the event of a flood designated as a Probable Maximum Flood (PMF). b. Radiation Control Standards and Procedures shall be maintained and made available to all station personnel. Station operation shall adhere to these standards and . procedures. c. Standing Orders to the operating staff shall require that the procedure s in a and b above are to be followed in conducting activities identified therein. d. Work instructions or special test procedures to the operating or maintenance staff shall require that the procedures in a and b above are to be followed in conducting activities identified therein. e. All procedures described in a and b above, and changes thereto shall be reviewed by the SRB and approved by the Station Superintendent or Assistant station Superintendent prior to implementation, ex' cept as provided for in f below. f. Temporary changes to procedures described in a and b above, which do not change tne intent of the original procedure may be made,with the concurrence of two individuals holding senior operator licenses. Such changes shall be documented and subsequently reviewed by the SRB and approved by the Station Superintendent. q g. Drills on portions of the emergency procedures described in 2.a. (4) and (7) shall be conducted quarterly.

l. o b .l: 3. Actions to be Taken in the Event of an Abnormal Occurrence [' in Plant Operation i,, I a. Any abnormal occurrence

• shall be promptly reported to the Manager of. Production or his delegated alternate and shall be promptly reviewed by the SRS.

This Board shall prepare a separate report for each abnormal occurrence. This report shall include an evaluatien of the cause of the occurrence and recommendations for appropriate action to prevent or reduce the probability =- of a repetition of the occu'rrence. e-b. Copies of all such reports shall be submitted to the Manager of Production and the Chairman of the NRB l for review and approval of any recommendations. t c. Tne Station Superintendent shall notify the AEC as specified in Specification 5. 4. Plant Operatina Records [. a. Records and/or logs relative to the following items 3 shall be kept in a manner convenient for review and j ~ longer period is required by applicable regulations

• shall be retained for at least five years unless a j

(1) Records of normal plant operation, including power levels and periods of operation at each power level. l (2) Records of principal maintenance activities, I including inspection and repair of principal items or equi' ment pertaining to nuclear safety. p (3) Records of abnormal occurrences. l (4) Records of periodic checks, inspection and/ci calibrations performed to verify that Surveillance 1 Requirements are being met. (5) Records of new and spent fuel inventory and cssembly histories.

• 5cc page 15.

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• Abnormal Occurrence - An abnormal occurrence means the occurrence of any plant condition that:

1. Exceeds a Limiting Condition for Operation as established in the Tech-nical Specifications, or 2. Causes any uncontrolled or unplanned release of radioactive material from the 61te, or 3. Results in safety system component failures which could, or threaten to, render the system incapabic of performing its intended safety function as defined in the Technical Specifications or SAR, or 4. Results in abnormal degradation of one of the several boundaries which are designed to contain the radioactive materials resulting from the j fission process, or .= l S. Results in uncontrolled or unanticipated changes in reactivity of greater than 1% 8 K, O l. l e l t l 2 k

t l' . 4 (6) Records of plant radiation and contamination surveys. (7) Records of of fsite environmental monitoring surveys. (8) Records of radioactivity in liquid and gaseous wastes released to the environment and radioactive waste shipments. b. Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained I permanently. (1) Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20. (2) Substitution or replacement of principal ite=s of equipment pertaining to nuclear safety. (3) Changes made to the plant as At is described in the Hazards Summary Report, as amended. ~ 5. P,lant Reporting Requirements In addition to reports required by applicable regulations, Commonwealth shall provide the following information: Events requiring notification _within 24 hours (by telephone or a. telegraph to Region III Regulatory Operations Office): (1) Incidents or conditions relating to operation of the station which prevented or could have prevented any systems designed to prevent or mitigate the consequences of nuclear accidents from performing as describcd in these specifications or the Hazards Summary Report. (2) Any significant variation of measured values of thermal, uuclear or hydraulic characteristics from a corresponding predicted value. 9 l

l' y ] (3) Any abnormal occurrences. b. , Events requiring reports with_in 10 days (in writing to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545): (1) Any significant variation of measured values of thermal, nuclear or hydraulic characteristics from a correrponding predicted value. (2) Incidents or conditions relating to operation of the station which prevented or could have prevented any systems designed to prevent or mitigate the consequences of nuclear accidents from performing as described in these specifications or the Hazards Summary Report, as anended. (3) Any abnormal occurrences. c. E_ven_ts requiring reports _within 30' days (in writing to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545): (1) Any substantial variance in the performance of a system or component designed to prevent or mitigate the consequences of nuclear accidents from the performance described in these specifications or in the Hazards Summary Report, as amended. (2) Any significant change in the results of transient or accident analyses described in the Harards Summary Report, as amended. c. R_outine Operating Report (in writing to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545); (1)' A routine operating report shall be submitted at the end of each six-month period calculated from January 1, 1972. Such rep' orts are due within 60 days after the end of each reporting period. The following information summarized on a monthly bas.is shall be provided:

- 18 (a) Nuclear

1. Nurther of hours the plant was operated.

2. Number of times the reactor was made critical.

3. Gross thermal power generated.

4. Operating histogram, showing the therrcal power level of the reactor versus time for the report period.

(b) Electrical

1. Gross power generated (in Mwh).

2. Net power generated (in Mwh).

3. Length of time generator was on line (in hours).

(c) Shutdowns

1. Number of scrams and shutdowns.

2. Duration of down time (in hours).

3. Re'asons for outage.

(d) Maintenance (on systems or components designed to prevent or mitigate the consequences of nuclear accidents including fire main system components located at Unit 2 and Unit 3).

1. Nature of the maintenance; e.g.,

routina, emergency, preventive or corrective.

2. The effect, if any, on the safe operation of the reactor.

3. The cause of any malfunction for which corrective maintenance was required.

4. The effects of any such malfunctions.

5. Corrective and prev'entive z.c ;cn

cnen to preclude rec *urrCLCC cf

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1 i c.. 21,- (c) The amount of component (or system) redundancy remaining or the availability of other system (s) to perform the same function as the inoperable-component (or system). (d) Surveillance requirements on the operable component (or system). (2) Any significant cha'nges of the informaticn supplied in e(l) (a), (b),(c) or (d) shall be reported within i seven days. -(3) Reports on the following areas shall be submitted as indicated on the following page. G O e e e 9 o 9

r ~ T i q 22 q l SUBMITTAL DATS-AREA

n. Primary Containment Leak Rate Upon completion of cach test Tests (1)

b. Primary Coolant Leakage to Primary containment 2 years 6' c. In-Service Inspection Evaluation 5 years After each refueling outage d.

Summary Status of Fuel Performance Each integrated leakage rate test of the primary contain=cnt sha.11 be the (1) subject of a sumary technical report including results of the local leak

2.:

The report as described in proposed rate tests since the last report. Appendix J to 10 CFR Part 50 published August 27, 1971, shall include data, analysis and interpretations of the results which demonstrate compliance with the allowable leak rate limits. 6 4 e

4 gg / + T R. F A t T E. ir t G A 4 f C E f NI A C H C C N iA E T r 0 tf Ti A r E t L C k U N y N T n O N o I E i T D t C a. 4f U E R 7 D E i T T O i E n n T r t N t N R P n I a E G g o E i f D r c O N E O P N U E a R S G T i e r E N N O r r V G Y o A RI l I lJ[. I t T a 3 N C T A r c t P A R o t A ri U T E p r o N S P r r T O o o O l C r t I A c T T e A S r T I S A r S S o A N I i e r t in uh. F -Q y g ~ W_. t( C_ f V f I O R_ K E V T_ R E P o I f U D D n U R S / m A-A 'V r O e r D j-A w L L W r, t '( vi l l I V t. E c E E c R f>. C, i:a R ( I c i T c u A f S r YG6N 3M. p b 39 6

~ r Dresden Station Superintendent / I m Ass't. Superintendent E 1D l I L.__ 3perating Engineer EO-Tech. Sta ff Supv. Maintenance Engineer Supv. 6 Traininc ~ 2D ...j ID i I Shift'{SO] lHFtNi}h_I l l ~ N. t. I Rad. liuclearl . Thermal lMa,sterMech. j 1:nti. 1D rng. 1S andling Chem. hng. j Eng. & g i 1D Foreman Foreman Foreman Supv.2D l 1D { , Computer l ' Maintenance ID IS 2D Foreman sst. l 2D. . Foreman l Asst.3D l l 3p--) IDI 3D e Co n t ro l. Muclear Fuel Radmen Engr'g Mechanical I;y r. l. w Station Man "A " Assist's A-15D T" c. h 2D Oper. 6D IS B-10D I nr.t r O 3S Fuel l 30 3D H-SD 11a n Equip. ' Man "B " "A" 'D Oper IS I Electrical 2D A-4D II-2D 1 n-1:qu i p. U-2D 'ia n A t f.end Y'li " >D 3S (M ~~~~[--~^ D l CODE; D-Days (Except Sattu/ day & Sunday) S-On Shift g 'l O-Operator's T.icen ;c ';ta t i o.1 men l S0-Senior Operato>'s License O 4 D,J

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fuel handling Foreman has a restricted senior operator's license. L9 @ ricunn it r:cemn ru::CTIOZmn ORGArH ZATION CHART W G==>

~ 20 (g) Solid Radioactive Waste

1. Total volume (in cubic feet) of solid waste generated.

2. Gross curie activity involved.

3. Dates and disposition of the material, if shipped off-site.

l (h) Environmental Monitoring

1. A narrative su==ary including correlation of effluent releases with the results of of fsite environmental surveys performed during the report period.

2. Tabulation of the results of the environmental monitoring program.

3. For any samples which indicate statistically significant levels of radioactivity above established background levels, a comparison with applicable 10 CFR 20 limits shall be provided.

_Special Reports _ (in writing to the Deputy Director for e. Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545): (1) In the event a redundant component (or system) covered by these Technical Specifications is determined to be out of service for periods longer than those speci~fied in.other sections, it shall be the subject of a special maintenance report. This report, requesting approval to continue plant operation shall be submitted prior to expiration of,the out of service time of the above, and shall describe: (a) The nature of the probi.em and the specific steps to be taken to remedy the situation. (b) An estir. ate of the time required to return the component ( or system) te an Opercbic Condition.

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6. Time required for completion.

(e) Radioactive Licuid Waste

1. Total curie activity discharge.

2. Total volume'before dilution (in gallons) of liquid waste discharged.

3. Total volume (in gallons) of dilution water used.

4. Average concentration '(injfc/ml) at outfall of discharge canal.

5. The maximum concentration released for any consecutive 24 hours during the reporting period including time and date.

6. Percentage of annual limit released.

7. Results of isotopic analyses and estimated total number of curies of each identified nuclide released.

8. Total curie activity of tritium discharged, (f) Gaseous Waste

1. Total curie activity discharged separated into noble gases, iodine, and particulates.

2. The maximum activity released for any consecutive 24 hours during the reporting period including time and date.

3. Percentage of each annual limit relenscd and MPC values.

4. Results of isotopic analyses and estimated

~ q total number of curies of each identified nuclide released.

5. Total curie activity of tritium dicchc:gcd.

~ e e TAllLE III S!!!FT MANNING CIIATIT ~ SIIIFT STAFFING FOlt NOtti\\iA1 OPEllATION Liccuse No. of Operating Units Staff Positions Tnic No. of Units 0 1 2 3 Shif t Engineer (SC) SO(l) 3 1 1 2 2 and/or ~ Siiift Foreman (SF) ~Eucicar Station Operator (2) O 3 1 2 3 4 (NSO) y ~ i Equipinent Operator 2 3 4 5 and/or ' Eqttipnient' Attendant 1 1 1 1 Itad. Protection Men ~.. ~ O. MINIMUM CONTItOI, ItOOM STAFFING O g tJo. of Ogrygting Unit:; 0 1 2 3 Staff Positions O} 1 1 1 0 SI:,'SF Ott t:SO I) 0 1 ?. 3 IISO u u.c

1. A 1.iernsed Seni..r t):.. rator wif t tw em site at all times.li,..a

< i c.c all th ce imits, he will only operata the unit (s) for which ha is ficensed. O I f en in,thi.Inat i. no 0W $ $ (1

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