ML20155B079

Proposed Tech Specs,Replacing Organization Charts W/More General Organization Requirements & Revising & Deleting Ref to Certain Corporate Mgt Positions to Remove Unnecessary Details

ML20155B079
Person / Time
Site:	Vogtle
Issue date:	06/01/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20155B065	List: ML20155B059 ML20155B079
References
NUDOCS 8806130070
Download: ML20155B079 (15)

Text

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' Georgia Power d ENCLOSURE 3 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE-NPF-68

, , REQUEST TO REVISE TECHNICAL SPECIFICATIONS INSTRUCTIONS FOR INCORPORATION The proposed change to the Technical Specifications- (Appendix A to Operating License NPF-68) would be incorporated as follows:

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Rgmove Page Insert Page XXII XXII 6-1 6-1 6-2 6-2

, 6-3 6-3 6-4 6-4 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 6-12 6-12 6-13 6-13 6-14 6-14 6-24 6-24 6-25 6-25 l

0957m E3-1 06/01/88 SL-4752 1

l 8806130070 880601 PDR ADOCK 05000424 i P DCD

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY................................................. 6-1 62 O R GA N I ZA T I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 I

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( 6.2.1 ONSITE AND OFFSITE ORGANIZATION.............................. 6-1 l

6.2.2 P L A N T S TAFF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 FIGURE 6.2-1 (0ELETED)............................................. 6-3 l FtGuaE 6.2 2 <0EtETEo)............................................. 6 -4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY.... 6-5 l y 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Fu n c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 Comp o s i t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 Responsibilities.......................... ..................

6-6 Records...................................................... 6-6 6.2.4 SH I F T TECHN I C AL ADV IS 0R. . . . . . . . . . ., . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 TRAINING....................................................... 6-6

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6.4 R EV I EW A N D A U DI T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 ........

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6.4.1 PLANT REVIEW BOARD (PRB)

Function..................................................... 6-7 Compo s i t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-7 Al te r n a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .6-7 ..

Meeting Frequency............................................ 6-7 Quorum....................................................... 6-7 Responsibilities............................................. 6 Records...................................................... 6-9 V0GTLE - UNIT 1 XXII Proposed TS/02090/125

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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY Gweral Man ge - N"cla$r 98'd-6.1.1 The general m nwr shall be resoonsible for overall plant ODeration l

and shall delegate in writing the succession to this responsibility during his absence.

GM Manner. Mactw Pierd.

6.1.2 The gencr:1 man 7cr will annually reissue a directive that emohasizes j the primary management responsibility of the onshift Operations Supervisor (or during his absence from the control roon, the individual designated to assume tne corrnand functions) for safe operation of the plant under all conditions on his shift and that clearly establishes his command duties.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 Onsite and offsite organizations shall be established for olant ooera-tion and corporate management, respectively. The onsite and offsite organiza-tions shall include the oositions for activities affecting the safety of the nuclear power plant,

a. Lines of authority, responsibility, and comunication shall be established and defined for the highest management levels through intemediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the fom of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documenta tion. Tnese requirements shall be documented in the FSAR.

Genu.i Mana l

b. The general man cr ;aec - Nmtea, shall plant be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

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c. The .v4ce-pres 44ent- shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure i

acceptable performance of the staff in operating, maintaining, and  !

providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out j health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have st.fficient organizational pressures. freedom to ensure their independence from operating PLANT STAFF 6.2.2 The plant organization shall be subject to the following:  !

a. Each on-duty shif t shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1;

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in liODE 1, 2, 3, or 4, at least one Ifcensed Senior Operator shall be in the control room; V0GTLE - UNIT 1 6-1 Proposed TS/0210g/125

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ADMINISTRATIVE CONTROLS PLANT STAFF (Continued)

c. An individual

• who has successfully completed the Initial Technician Training portion of the Health Physics Training Program or its equivalent shall be on site when fuel is in the reactor;

d. All CORE ALTERATIONS snall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. Administrative procedures shall be developed and implemented to limit the working hours of plant staff in performance of safety-related functions (e.g., licensed Senior Operators, licensed Operators, key.

Health Physics Technicians, key non-licensed operators, and key nafntenance personnel).

Adequate shift coverage shall be aaintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating. (This work week may consist of 12-hour shif t schedules.) However, in the event that unforeseen problems require substantial amounts'of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be Demitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shif t turnover time.

2. An individual should not t pemitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more tnan 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day pe, .od, all excluding shift turnover time.

3.- A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

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Any deviation from the above guidelines shall be authorized by the applicable department superintendent, or higher levels of manage-ment, in accordance with established procedures and with documenta-tion of the basis for granting the deviation. Controls shall be included in the procedures such that individual excess overtime shall be reviewed monthly by the general managee-or his designee to assure l that excessive hours were authorized and that they do not become routine.

Gened bAenay- Nuc6 Plant

• This individual may be absent for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided imediate action is taken to fill the required position.

YOGTLE - UNIT 1 6-2 Proposed TS/02100/125

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F!GURE 6.2-1 (DELETED)

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V0GTLE - UNIT 1 6-3 Proposed 70/02104/125

t' c s FIGURE 6.2 2 (DELETED) l V0GTLE - UNIT 1 6-4 Proposed TS/02100/125

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ADMINISTRATIVE CONTROLS 6.2.3 ' INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and coerating experience .information, which may indicateareas for inoroving plant safety. The ISEG shall make detailed recommendations for revised procedures, equienent modifications, maintenance activities, operations activities, or other means of inproving plant safety to the v4ce-pre:identy l

COMPOSITION ce sue,d.- Nudear 6.2.3.2 The ISEG snail se composed of at least five, dedicated, full-time engineers. Each shall have 3 bachelor's degree in engineering or related science and at least ? years professional level exoerience in his field, at least 1 year of which excertence shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for .naintaining surveillance of plant activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4 Records of activities perfomed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the-v4ee-pr+s44eek l

6.2.4- SHIFT TECHNICAL ADV j CR fesided - Nedear-6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of themal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the plant for transients and accidents, and in plant design and layout, including the capabilities of instrumentation and controls in the control room.

5.3 TRAINING I l

6.3.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Plant Training and Energency Prepared--

ness Manager. Personnel will meet the miaimum education and experience recom-mendations of ANSI N18.1-1971 and, for K ensed staff, Appendix A of 10 CFR 55 and the supplemental requirements speciffeo in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licenpes, before they are considered qualified to perfom all duties independently. 'rior to neeting the reconnend-ations o f ANSI N18.1-1971, personnel may be trained to perform specific tasks  ;

and will be qualified to perfom those tasks independently. '

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• Not responsiDle f 5F sign-of f function.

l V0GTLE - UNIT 1 6-6 Proposed TS/02104/125

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ADMINISTRATIVE CONTROLS 5.4 REVIEW AND AUDIT 6.4.1 PLANT REVIEW BOARD (PRB)

FUNCTION 6.4.1.1 The PRB shall function to advise the -9e00rd Sn49es on all matters related to nuclear safety. (

General Manager- Nudeur Plant COMPOS! TION

6. 4.1. 2 The PRB shall be conoosed of Department Superintendents or Managers, or supervisory personnel recorting directly to Department Superintendents or Managers from the departments listed below:

Operations

'M intenance Quality Control Health Physics Nuclear Safety and Compliance Engineering Support A senior health ohysicist is acceotable for the Health Physics Department DR8 representative. The chairman, his alternate and other members and their alternates of the PRB shall be designated by the yneral-manageer-l ALTERNATES 6eava\ Nod.3er - Malew Plant-

6. 4.1. 3 Na more than two alternates shall participate as voting members in PRB activities at any one time.

MEETING FREQUENCY 6.4.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.

QUORIN

6. 4.1. 5 The quorum of the PR8 necessary for the perfomance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chaiman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.4.1.6 The PRB shall be responsible for:

a. Review of 1) procedures which establish plant-wide administrative controls to implement the QA pFogram or Technical Specifications surveillance program, 2) procedures for changing plant operating  !

modes, 3) emergency and abnomal operating procedures, 4) procedures l for effluent releases of radiological consequences, and 5) fuel l handling procedures.

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V0GTLE - UNIT I 6-7 Proposed TS/02104/125 ,

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RESPONS!81LITIES-(Continued)

b. Review of 1) orograms required by Specification 6.7.4 and changes thereto, and 2) proposed procedures and changes to procedures which involve an unreviewed safety question as per 10 CFR 50.59.

c Review of all prooosed tests and experiments that affect nuclear safety;

d. Review of all proposed charles to the Technical Specifications;

e. Review of all oroposed changes or modifications to plant systems or equionent th1t affect nuclear safety;

f. Investigation of all violatinns of the Technical Soecifications, including the orecarition and forwarding of reoorts covering evalua-tion and recomendations to prevent recurrence, to the vite-pretMent-and to the Safety Review Board; l Sec prmdent - bcled

g. Review of all REPORTABLE EVENTS;

h. Review of plant verttions to detect potential hazards to nuclear safety;

i. Perfornance of soecial reviews, investigations, or analyses and reports thereon as requested by the general-amagen-or the Safety {

Review Board; q,mc,3 p.anaye. Nuct.2c P Lt J. Review of the Security Plan a.1d imolementing procedures and submittal of recommended changes tc the -general =agee and the Safety Review Boa rd; l Ge%\ Mange- htm PM

k. Review of the Emergency Plan and implementing procedures and submittal of recorrnended changes to the general-managee and the Safety Review Boa rd; l General Mins 3ee Adear Plent

1. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, i recomendations, and disoosition of the corrective action to prevent '

recurrence and the forwarding of these reports to the v4ce-president- l and to the Safety Review Board; hp% g -%(eg, )

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v. Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems; and

n. Review of the Fire Protection Program and Implementing procedures ,

and submittal of recomended changes to the gener+1-man 49ee. l l

6.4.1.7 The PRB shall: 6nera) Mmyr- bdar bd General Nanayr-Nuclev Pltot

a. Recomend in writing to the 4eneral-man 49ea-approval or disapproval of l l itens considered under Specification 6.4.1.6a. through e. prior to their implementation; V0GTLE - UNIT 1 6-8 Proposed TS/0?l04/115

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ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.4.1.6a. through f. constitutes an unreviewed safety question; and Oce Presibt - Nuclear

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the vice-president- l and the Safety Review Board of disagreement between the PRB and the general manager; however, the gene +1-mana9ee shall have responsibility l for resolution of such disagreements ursuant to Specification 6.1.1.

RECORDS

\ 6. at Man.yc - Nveear Plad 6.4.1.8 The PRB shall maintain written minutes of each PR8 meeting that, at a minimum, document the results of all PR8 activities perfomed under the respon-sibility provisions of these Technical Specifications. Copies shall be provided to the v4ee-president and tne Safety Review Board. l Ytce Pressdad- NOdear' I 6.4.2 SAFETY REVIEW 90ARD (SRB)

FUNCTION 6.4.2.1 The SRB shall function to provide independent review and audit of designated activities in the areas of-

a. Nuclear onwer plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry,

d. Metall u rgy ,

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e. Instrumentation and control,

f. Radiological safety,

g. Mechanical and electrical engineering, and

h. Quality assurance practices.

6 Pres M - Modear-The SRB shall report to and advise the -vice-presidentan those areas  ! l of responsibility specified in Specifications 6.4.2.7 and 6.4.2.8. I COW OSITION 6.4.2.2 The SRB shall be organized as one boa'rd for all cPC Nuclear power 2

plants. The SRB shall be composed of a minimum of five persons who, as a group, provide the expertise to review and audit the operation of a nuclear power plant. The chairman and other members shall be appointed by the ice-presi4ent or other such person as he may designate. The composition of the SRB shall meet the requirements of ANSI N18.7-1976. l We Pre M - Mudear YOGTLE - UNIT 1 6-9 Proposed TS/02100/125

ADMINISTRATIVE CONTROLS AUDITS (continued) 9 The Radiological . Environmental Monitoring Program and the results thereof at least once per 12 months;

h. The OFFSITE DOSE CALCULATION MANUAL and implementfr:q procedures at least once per 24 months;

f. The PROCESS CONTROL PROGRAM and imolementing procedures for processing and packaging of radioactive wastes at least once per 24 months;

j. The perfomance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months;

k. The Emergency Plan and implementing procedures (at least once per 12 months);

1. The Security olan and implementing orocedures (at least once oer 12 months); and RECORDS 6.4.2.9 Records of SRB activities shall be prepared, approved, and distributed as indicated below:

a. Minutes of each SRB meeting shall be prepared, approved, and forwarded to toe ,yfee presRent-within 14 days following each meeting; l Thce Presiden( - Nudear

b. Reports of reviews encompassed by Specification 6.4.2.7 shall be pre-pared, approved and forwarded to the-vice-president.within 14 days l

following completion of the review; and \fice presteknE - Mucte g r

c. Audit reports encompassed by Specification 6.4.2.8 shall be forwarded to the vice-president and to the management positions responsible for l the areas auditiEd'within 30 days after completion of the audit by the auditing organization.

Yce fr'esident. - Nwlear 6.5 REPORTABLE EVENT ACTION 6.5.1 The following actions shall be taken for REPORTABLE EVENTS:

3. The Cocrnission shall be notified and/or a report submitted pursuant to the requirements of Section 50.72 and Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PRB, and the results of this review shall be submitted to the SRB and the v4ce-president.

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ADMINISTRATIVE CONTROLS 6.6 SAFETY LIMIT VIOLATION f 6.6.1 The following actions shall be taken in the event a Safety Limit is violated:

a. In accordance with 10 CFR 50.72, the NRC Operations Center shall be notified by telephone as soon as practical and in all cases within one hour af ter the violation has been detemined. The vice-oresident, the SRB, PRS, and the genesi-manageA shall be notified within Qce peuM Mob M lotes.

Geneal Manger NvAr Nant I b. A Licensee Event Report shall be prepared in accordance with j 10 CFR 50.73.

i c. The Licensee Event Report shall be submitted to the Cor.nission in Gmr accordance witn 10 CFR 50.73, and to the PRB, SRB, the general-managen. a\ Anarpr-and the +4ee-pres 44ent within 30 days af ter discovery of the event. HocMPlant-

\ hee PrnM - %ctear

d. Critical operation of the unit shall not be resumed until authorized by the Nuclear Regulatory Commission.

6.7 PROCEDURES AND PROGRA'IS 6.7.1 dritten procedures shall be established, implemented, and nafntained covering the activities referenced below;

a. The applicable orocedures recomended in Appendix A of Regulatory.

Guide 1.33, Revision 2, February 1978;

b. The emergency operating procedures required to imolement the require-ments of NUREG-0737 and Supplement I to NUREG-0737 as stated in Generic Letter No. 82-33;

c. Security Plan implementation;

d. Emergency Plan implementation;

e. PROCESS CONTROL PROGRAM implementation;

f. OFFSITE DOSE CALCULATION MANUAL implementation; j

g. Quality Assurance for effluent and environmental monitoring; I

h. Fire Protection Program Implementation; and

1. Technical Specifications Improvement Program implementation.

6.7.2 Each procedure of 6.7.1 above, and changes thereto, shall be reviewed as set forth in administrative procedures and approved by either the genera 4

-managee or the department head of the responsible department prior to implementation with the exception of the following which shall be approved by the general : gw j

6eneral Manayr- NOCIEar PI3"k V0GTLE - UNIT 1 6-13 Proposed TS/02109/125

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l ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

1) procedures which establish plant-wide administrative controls (which '

implement the quality assurance program and the Technical Specifica-tions surveillance program),

2) unit operating procedures (U0Ps)

3) emergency operating procedures (EOPs)

4) abnomal operating procedures ( AOPs)

5) procedures for implementing the security plan, emergency plan, and the fire protection program, and

6) fuel handling procedures.

PRS responsibilities for procedures are delineated in Specification 6.4.1.

6.7.3 Temporary changes to procedures of Specification 6.7.1 may be made pro-vided: 4

a. The intent of the original procedure is not altered;

b. The change is approved by twr members of the plant management staff, at least one of whom holds a Senior Operator license; and

c. The change is documented, reviewed in accordance with Specifica-tion 6.7.2 and approved by the gene (al-managee or department head of the responsible department within 14 days'of implementation. l L (,mes\ )A-anaye - Nudear h*"t 6.7.4 The following progran:s shall be established, implemented, and maintained:

1. Primary Coolant Soun;es Outside Containment A program to reduce leakage from those portions of systems outside containment that cou7d contain highly radioactive fluids during a serious transient or accident to 4s low as practical levels. The systems include the following:

1) Residual Heat Removal System

2) Containment Spray System (excluding NaOH Subsystem)

3) Safety Injection (excluding Boron Injection & Accumulators)

4) Chemical and Volume Control System (Letdown, Boron Recycle, and Charging Pumps)

5) Post Accident Processing System

6) Gaseous Waste Processing System

7) Nuclear Sampling System (Pressurizer steam and liquid sample lines, Reactor Coolant sample lines, RHR sample lines, CVCS Demineralizer and Letdown Heat Exchanger sample lines only)

V0GTLE - UNIT 1 6-14 Proposed TS/02100/125

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ADMINISTRATIVE CONTROLS ,

6.12 PROCESS CONTROL PROGRAM (PCP) (Continued)

3) Documentation of the fact that the change hu been reviewed a'nd ,

found acceptable by the PRB. ,<

b. Shall become effective upon approval by the general-mana9ee. l 6.13 0FFSITE DOSE CALCULATION MAWAL (ODCM) at Mmp- hu ,%

6.13.1 The ODCM shal8 be approved by the Comission prior to implementatf 60.

6.13.2 Licensee-initiated changes to the ODCM:

a. Shall be submitted to the Comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

1) Sufficiently detailed infomation to totally support the-rationale for the chanq? without benefit of additional or i supplemental informati n; Infomation submitted should consist >

of a package of those ? apes of the ODCM to be changed with each page numbered, dated and containing che revision number, together with appropriate analyses or evaluations justifying the change (s); e t '

2) A detemination that the change will not reduce the accuracy or reliability of dose calculations or Setpoint deteminations; ana

3) DocumentaWn of the fact \ hat the change has been reviewed and found ccceptable by the PRB.

b.

Shall become effective upon approval by the generabmenager. Cwm ,

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t 6.14 MAJOR CHANGES TO LIQUIO, GASEOUS, AND SOLIO RA0 WASTE TREATMENT SYSTEMS

• 6.14.1 licensee-initidted majcr changes to 4.ne Radwaste Treatment Systems

' liquid, gaseous, and solid):

a. Shall be reported to the Comiss1cn 4 i the Semiannual Radioactive Effluent Release Report for the peri >d in which the evaluation was reviewed by the PRB. The discussion of each change shall contain:

1) A sumary of the evaluation that led io the detemination that t the change f.ould be made in accordance with 10 CFR 50.59; '

2) Sufficient detailed infomation to totally support the reason 1 for the change without benefit of additional or supplemental informa tion; l

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• Licensees may choose to submit the infomation celled for in this Specification as part of the annual FSAR update.

V0GTLE - UNIT 1 6-24 Proposed TS/02100/125

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6.14 MiOR CHANGES TO LIQUIO, GASEOUS, AND SOLID RADWASTE3Y1EA"HENT SYSTEMS (Continued)'

3) A detailed descriptionpf the equipment, coconents, and processes involved and the interikes with other plant systems;

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4) An evaluation of the change, which shows the credicted releases -

of radioactive materials in liquid and ge,seousaffluents and/or quantity of solid waste that differ from,those previously predicted in the License application and amendments thereto;

5) An evaluation of the change, which sfiows the 'xpected e maximum i> exposurestoaMEMBEROFTHEPUBLICintheUkRESTRICTEDAREA.

and to the general population that differ from those previously estimated in the License application and amendments thereto;

' G) A comparison of the predicted releases of radinctive materials, in liquid and gaseous effluents and in solid kaste, to the actual releases for the period prior to when th'e change is to be made;

7) An estimate of tne exposure to plant operating personnel as a result of the change; and s 8) Documentation of the fact that the change was retfewed and i found acceptable by the PRB.

b. Shall become ef fective upon approval by the general-manager.

l Gnugt Manaye Modear Pant.

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j V0G1LE - UNIT 1 6-25 Proposed TS/0214/125 s e

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