ML20087D329

Proposed Tech Specs,Revising Titles of Various Administrative Positions Found in Section 6.0 of TSs

ML20087D329
Person / Time
Site:	Sequoyah
Issue date:	08/07/1995
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20087D327	List: ML20087D324 ML20087D329
References
NUDOCS 9508100281
Download: ML20087D329 (20)

Text

{{#Wiki_filter:_ l1.. , 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and 162 shall delegate in writing the succession to this responsibility during his absence. R182 6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room com-mand function. A management directive to this effect, signed by the Site Vice R156 President, shall be reissued to all station personnel on an annual basis. 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be estab-lished and defined from the highest management levels through inter-mediate levels to and including all operating organization positions, R78 These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR and will be e g d in g e with 1 @ 50. jyp yo Cur Hua.ru OFFRER

b. The Senior Vice President tgNuclearg aicr shall a corporate respon- R182l s tTTity for'UveraTT plew ntrr e ety. is individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in R78 the plant so that continued nuclear safety is assured.

c. The Plant Manager shall be responsible for overall unit safe opera-tion and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d. The individuals who train _the operating staff and those who carry out health physics and quality assurance functions may report to the 3

appropriate onsite manager; however, they shall have sufficient Jg organizational freedom to ensure their independence from operating o c e. pressures. 88 pg 6.2.2 FACILITY STAFF

  $d                      a. Each on-duty unit shift shall be composed of at least the minimum gg                            shift crew composition shown in Table 6.2-1.

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   $                      b. At least one licensed Reactor Operator shall be in the unit Control gg                           Room when fuel is in the reactor. In addition, while the unit is in o' oA                        MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

March 31, 1994 SEQUOYAH - UNIT 1 6-1 Amendment No. 32, 58, 74, 152, 178

}; '. ,

                                                                                                                   ^l ADMINISTRATIVE CONTROLS 6.2.3   INDEPENDENT SAFETY ENGINEERING (ISE)

FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety. R123 I COMPOSITION  ! 6.2.3.2 The ISE shall be composed of at least 3 dedicated full-time engineers located onsite. These engineers will be supplemented as necessary by full-time  ! engineers shared among all TVA nuclear sites to achieve an equivalent staffing of S full-time engineers performing the ISE functions applicable to Sequoyah. RESPONSIBillTIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant activities to provide independent verification

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

AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures, Manager,,_ . S.C* _ rs$ . ., mm... f.. M rm.

                                                            $u[m.,YN, . . m s.M, u ,3 . . .m m ,bY. .,3R167 DefevDc?vr       eM AND          L.yst.S 6.2.4   SHIFT ItcHNicADT>vi50Rhi                ~              ^

6.2.4.1 The STA shall serve in an advisory capacity to the Shift Operations R182l Supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit. R16 6.3 FACILITY STAFF OVAllFICAT10NS 6.3.1 E i ps,ar.h-membee-of-thaJac411tptaff ations of ANSI N18.1-1971 for comparable shal],positions meet cr ^ for the except R167 1.clogica' Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. j # R156 i

                     ' kAD fon) {llB//SIRf        ,-      -

II

             *Not responsible for sign-off function.                                                                 ,

SEQUOYAH - UNIT 1 6-5 dEe$mentYo.'12,58,74, 119, 152, 163. 173 l

y,; /, ,

  ~

l l ADMINISTRATIVE CONTROLS i

         6,4
                  -TRAINING                                                                                    j 6.4.1 A retraining and replacement training program for the facility staff                        ,

shall be maintained under the direction of the Plant Manager and shall meet or R156 ) exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971  ; and 10 CFR Part 55 and shall include familiarization with relevant industry R167 operational experience, l 6,5 REVIEW AND AUDIT - ' qyp gno Cgity Nucwul 0FFlCEN 6.5.0 The Senior Vic: President, A ucleara Pewee is, responsible for the safe N R78 operation of all TVA power plants, j A. _+ f 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) 1 l 1 FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety. R62 COMPOSITION 6.5.1.2 The PORC shall be composed of the: Chairman: Plant Manager Member: Operations Manag RmCw/ e Member: R:dicl ;ic 1 " hemistry[$aIIag,ccot er R182l Member: Maintenance anager . Ano #10D/MM#5 Member: Technical Support Manager Member: Sirr Quality tdit :nd .t;;;;mer.t Manager Member: -94e EngineeringvRepresentative R182

                                                       /\ND PIRTERIALS March 31, 1994 SEQUOYAH - UNIT 1                             6-6         Amendment No. 58, 74, 152, 163, 178

7,,-

                . ADMINISTRATIVE CONTROLS QUALIFICATIONS                                                                                                           (p,g7 fjuetcg,OrggE
                .6.5.2.3 The Chairma members, and alternate me                                                                                11 appointed in writin by the Ecnier_Vicc President an academic degree in eng neering or a p ysica softh('NSRBs have cl ea r %we+

ence leid, or the equiva-nd shall R78

                ' lent; and in addition, shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1. No more than two alternates shall participate as voting members in NSRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to provide expert advice to the NSRB. MEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter. . QUORUM , 6.5.2.6 The minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shal? consist of more than half the NSRB membership or at least 5 members, whichever is greater. This quorum shall include the Chairman or his appointed alternate and the NSRB , members, including appointed alternate members, meeting the requirements of Speci fication 6.5. 2. 3. No more than a minority of the quorum shall have line responsibility for operation of the unit. REVIEW 62 6.5.2.7 The NSRB shall be cognizant of review of: . i

a. The safety evaluations for 1) changes to procedures, equipment 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 unrevi~ewed 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 to Technical Specifications or this Operating License.

t e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

• R78.

SEQUOYAH - UNIT 1 6-10 Amendment No. X)6 74 June 30, 1988

 ).

ADMINISTRATIVE CONTROLS

f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.

g. All REPORTABLE EVENTS. R62

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports.and meetings minutes of the PORC. R182' AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass:

R202 !

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.

b. The performance, training and qualifications of the entire facility staff.

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety.

d. The performance of activities required by the Nuclear Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50.

e. (Deleted)

f. (Deleted l g. Any other area of unit operation considered appropriate by the NSRB or the Rr.ier '!ica President,VNuclearVh W _4 rvA Ano tdtr Nuttene Orrient

h. The Facility Fire P dt M am and i g men r ures at R78 least once per 24 months.

i. An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

J. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at . - intervals no greater than 3 years. l l May 10, 1995 SEQUOYAH - UNIT 1 6-11 Amendment No. 58, 74, 178, 198

J,,. .: /, a. ADMINISTRATIVE CONTROLS R202

                        ' k. The radiological environmental monitoring program and the results thereof.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.  ;

m. The PROCESS CONTROL PROGRAM and implementing procedures for l SOLIDIFICATION of radioactive wastes. <

                                                          ~

n. The performance of act1vities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, l Rev. 1, 1975.

V V 'TYA 6.5.2.9 The NSRB shall report to and advise the S=icr Vie: President,A Nuclear R202 l fewee of those areas of responsibility specified in Sections 6.5.2.7 and l l l 6*5.2 f Ano CHIEF Nuctoin. Omccx , RECORDS N_ f 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Scier Via President,VNuclearSPowee within 14 days lR78. j following each meeting. rya Ano CHirr Nucus Orrierz. i

                                                ,                    %        -&             ,-                        1

b. Reports of ]r'eviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Sai r Yic: President, TVA lR78  ;

NucleariPewee within 14 days following completion of .the review. I huo C.HIET NutLO1R. OfRtER l

c. Audit reports encompassed by Section 6.5.2.8 above, shall be for- )

warded to the S=icr Vic: President R78 ment positions responsible for therd, eas Nuclear audi hwee-and within to the 30 days aftermanage-completion of the audit. l

                                         ^                  ^        /                Ano 0HIET NuCLEAP-6.5.3 THIS SPECIFICATION IS DELETED            TVA                           0 FFitCR.

R182 May 10, 1995 SEQUOYAH - UNIT 1 6-12 Amendment No. 42, 58, 74 152, 178, 198

f . ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and

• i adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In licu of the " control device" or " alarm signal" required by paragraph - 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of R178 radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be bar- ! ricaded and conspicuously posted as a high radiation area and entrance thereto R178 shall be controlled by requiring issuance of a Radiation Work Permit * (RWP). Any individual or group of individuals permitted to enter such areas shall be i provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform control over the activi-e t ef 173

                                                                               -         M u s a g w in the RWP.
            .12. The requirements of 6.12.1, above, shall also apply to each high radia-tion area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under                                   f hg._SjllftQperations    Supervisor on dut and or       Sitc "adici-i al "- "cl             2l i

Manager.

                         '

• AofMNNNy [ovuot A- R152
• Radiological Control personnel or personnel escorted by Radiological Control R62 personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

SEQUOYAH - UNIT 1 6-24 MenbmMtMD 42, 58, 74, 148, 152, 174, 178

    .                                                                                               1 6.0 ADMINISTRATIVE CONTROLS 6.1   RESPONSIBILITY 6.1.1    The Plant Manager shall be responsible for overall unit operation and       RM     l shall delegate in writing the succession to this responsibility during his absence.

R169 6.1 2 The Shift Operations Supervisor (or during his absence from the Control Romn, a designated individual) shall be responsible for the Control Room com- . mand function. A management directive to this effect, signed by the Site Vice R142 President shall be reissued to all station personnel on an annual basis. l l 6.2 ORGANIZATION l 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation l and corporate management. The onsite and offsite organization shall include l the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be estab-lished and defined from the highest management levels through inter-mediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as appropriate, R66 in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the FSAR and will be updated in accor IMEIL5ILllk W -Tib bo CHier Muttc# OM

b. \ The Senicr " ice President,(NuclearyPowe shall iave corporate respon R169l 4biitthaWTrhnt nuult:ar sait: . is individual shall  !

take any measures needed to ensure acceptable performance of the l staff in operating, maintaining, and providing technical support in I the plant so that continued nuclear safety is assured.

c. The Plant Manager shall be responsible for overall unit safe opera- R66 tion, and .shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d. The individuals who train the operating staff and those who carry out l health physics and quality assurance functions may report to the-appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

i 6.2.2 FACILITY STAFF

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

b. At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

March 31, 1994 SEQUOYAH - UNIT 2 6-1 Amendment No. 24, 50, 66, 142, 169

   ,,   ' ?-
 ..j       .,

ADMINISTRATIVE CONTROLS 4 6.2.3 INDEPENDENT SAFETY ENGINEERING (ISE) FUNCTION 6.2.3.1 The ISE shall function to examine plant operating chara'cteristics, NRC issuances, industry-advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety. COMPOSITION R108 6.2.3.2 The ISE shall be composed of at least 3 dedicated full-time engineers located onsite. These engineers will be supplemented as necessary by full-time engineers shared among all TVA nuclear sites to achieve an equivalent staffing of 5 full-time engineers performing the ISE functions applicable to Sequoyah. l RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant activities to provide independent verification

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

AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures,  ! q$pment#if4 cat 4cnsgr-other-means of dqprazipl.antg"'""'

                                                                      **          o the
                "**Yb5iEWlN'N'$?SI$fll$'"*#'**

6.2.4 5HIFf M i M

                                                                    ^

l 6.2.4.1 The STA shall serve in an advisory capacity to the Shift Operations R169l Supervisor on matters pertaining to the engineering aspects of assuring safe R66 l operation of the unit. 6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum

• 14&fcaLions-ofJMS1 N18.1-19 o comparable positions except for the R153 Radiclogical Contrcl anager who shall eet or exceed the qualifications o Regulatory Guide 1.8, September 1975.

hD0 HDrHShey Cournou

              *Not responsible for sign-off function.

March 31, 1994 SEQUOYAH - UNIT 2 6-5 Amendment No. 50, 66, 108, 142, 153, 169

ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Plant Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 R153 and 10 CFR Part 55 and shall include familiarization with relevant industry operational experience. L5 REVIEW AND AUDIT

                                           -{ytl       jk>o QgiEr NuttcNA 0FF/CCh'-

6.5.0 Scr.icr " ice President, N f 66 tion of all TVA power plants.A uclearA ewee is responsible .x. for the#_safe opera-6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) FUNCTIOJ 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety. R50 i COMPOSITION 6.5.1.2 The PORC shall be composed of the: ' AND MoblFICRTIO!QS Chairman: Plant Manager Member: Operations Mana Member: Rnotoghdi:1cgic: 1 en+ Chemistry Manager R169 l Member: Maintenance < Manager L CoMTROL. Member: Technical Support Manager Member: SrrE Quality Audit er,d Assess = .t Manager Member: -54e- EngineeringgRepresentative R169 Ano MATEX/ALS March 31, 1994 , SEQUOYAH - UNIT 2 6-6 Amendment No. 50, 66, 142 153, 169

ADMINISTRATIVE CONTROLS as the individual / group which designed the modifications. Proposed modifications to structures, systems, and components that affect plant nuclear safety shall be approved prior to implementation by the Plant R142 Manager, or Duty Plant Manager.

c. Individuals responsible for reviews performed in accordance with Specifica-tions 6.5.1A.la and -b, shall be designated by approved written procedures.

Each such review shall be performed by qualified personnel of the appro-priate discipline and shall include a determination of whether or not additional, cross-dsciplinary review is necessary. Each such review shall also include determination of whether or not an unreviewed safety question R66 is involved pursuant to Section 10 CFR 50.59. 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) FUNCTION 6.5.2.1 The NSRB shall function to provide for independent review and audit to assure adequacy of designated activities in the areas of: R50

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 4

COMPOSITION 6.5.2.2 The NSRB shall be composed of at least five members, irYdTuding the Chairman. Members of the NSRB may be from Nuclear Power, or other TVA R142 organization or external to TVA. QUALIFICATIONS TVA b g7gggg t 6.5.2.3 The Chairman, members, and alternate memb rs of the NSRB shall be appointec in writing b the Senier VicrPresident, Nu lear-lber and shall ' R66 have an academic degreeNnNngTneeriiT 67a phystra sc1 G~TihTd, or the equivalent; and in addition, shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1. No more than two alternates shall participate as voting members in NSRB activities at any one time. August 22, 1991 SEQUOYAH - UNIT 2 6-9 Amendment No. 50, 66, 142 bl!C '

s .' ADMINISTRATIVE CONTROLS AU'DITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass: R189

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.

b. The performance, training and qualifications of the entire facility staff. .

    ,                c. The results of actions taken to correct deficiencies occ urring-in-unit equipment, structures, systems or method of operatton that affect nuclear safety.

d. The performance of activities required by the Nuclear Quality Assur-ance Program to meet the criteria of Appendix "B",10 CFR 50. . ,

e. (Deleted) 1 l

f. (Deleted)

N -

g. Any other area of unit operation considered appropriate by the NSRB R66 or the Str.icr " ice President,VNuclear' ,

                                                                 ;no w }juct.aa. Orricae.

g ~ l

h. The Facility Fire Protect on rogram and'impTementing procedures at )

least once per 24 months.

1. An independent fire protection and loss prevention program inspection l and audit shall be performed annually utilizing either qualified l offsite licensee personnel or an outside fire protection firm.

J. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years. R189

k. The radiological environmental monitoring program and the results thereof.

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.

   ~~

m. The PROCESS CONTROL PROGRM1 and implementing procedures for SOLIDIFICATION of radioactive wastes.

n. The performance of activities required by the Quality Assurance Pro-gram to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, REv.1,1974 and Regulatory Guide 4.1, Rev.1, 1975.

May 10, 1995 SEQUOYAH - UNIT 2 6-11 Amendment No. 34, 50, 66, 169, 189

( 3" J, .. I ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The NSRB shall report to and advise the S nicr Vicc President,4 Nuclear-l'wcr- those areas of responsibility specified in Sections 6.5.2.7 ana R66 6.5.2. .

ANo OHIEF NutLEAL OF FitEll-A / RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSR5 meeting shall be prepared, approved and R66 forwarded to the 4 crier Vice President,VNuclea within 14 days No d'ry 11uctrat following each mer ting. TVA 0FFid

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approve', and forwarded to the Seni r Vice President, l

Nuclearyhwee withiri 14 days following completion o he review. HND &HIEF NuCLCAR. OFFicc7L A

c. Audit reports encompassed by Section 6.5.2.8 above, shall be for-warded to the Scr.icr Vic President Nuclear and to the manage-ment positions responsible for the reas audited ithin 30 days afteri completion of the audit. ;q ANo 0HIEF HuttmL

                            ^
                               -      ^                                                    O FFICE9.

6.5.3 THIS SPECIFICATIN IS DELETED A R169 March 31, 1994 SEQUOYAH - UNIT 2 6-12 Amendment No. 50, 66, 142, 169

7, d ADMINISTRATIVE CONTROLS 6.8. f. Radioactive Effluent Controls Proaram (Cont.) of radioactivity when the projected doses in a 31-day period-would exceed 2 percent of the guidelines for the annual ' dose or R134 -1 dose commitment' conforming to Appendix I to 10 CFR Part'50,

7) Limitations on the dose rate resulting from radioactive-material. released in gaseous effluents from the site to areas R165 at or beyond the SITE BOUNDARY SHALL BE LIMITED to the. ,

fotlowing:

1. For noble gases: Less than or equal to' a dose rate of 500 mres/yr to the total body and less than or equal to a dose. ,

                                     -rate of' 3000 mres/yr to the skin, and -

2. For Iodine-131,-Iodine-133, tritium, and for all R radionuclides in particulate form with half-lives greater . ,

than 8 days: Less than or equal-to a dose rate of 1500 l L ' arem/ year to any organ. ,

                       - 8)      Limitations on the annual and quarterly air doses resulting                             :

from noble gases released in gaseous effluents from each unit gi34 t to areas beyond the SITE BOUNDARY conforming to Appendix I to  ; 10 CFR Part 50,

9) Limitations on the annual and quarterly doses 'to a MEMBER OF

                                'THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-                           !

nuclides in particulate form with half-lives greater than 8- 'l days -in gaseous effluents released from each unit to' areas  : beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR '! Part 50, and t

                                                                                                                           \

) 10)~ Limitations on the annual dose or dose commitment to any-MEMBER j 3 OF THE PUBLIC due to releases of radioactivity and to radiation from uranium-fuel cycle sources conforming to 40 CFR Part 190.

g. Radioloaical Environmental Monitorina Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant'. The program shall j- provide (1) representative measurements of radioactivity in the- j highest potential exposure pathways, and (2) verification of the )

accuracy of the effluent monitoring program and modeling of- . i environmental exposure pathways. The progrYllr shall (1) be contained 1 in the 00CM, (2) conform to the guidance of. Appendix I to 10 CFR Part 50, and .(3) include the following:  !

1) Monitoring, . sampling, analysis, and reporting of radiation and j radionuclides in the environment.in accordance with the methodology and parameters in the.ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifica-tions to the monitoring program are made if required by the  ;

results of this census, and -) December 9, 1993 SEQUOYAH - UNIT 2 6-18 Amendment No. 28, 50, 66, 134,-165

7-

 *h    .

ADMINISTRATIVE CONTROLS

         . 6.l1 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of R165 radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be bar-ricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work-Permit * (RWP). R165 Any individual or group of individuals permitted to enter such areas shall be . provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated 1 dose is received. Entry into such areas with this monitoring device i may be made after the dose rate level in the area has been estab- I lished and personnel have been made knowledgeable of them. i

c. An individual qualified in radiation protection procedures who is i equipped with a radiation dose rate monitoring device. .This indi-  ;

vidual shall be responsible for providing positive control over the l activities within the area and shall perform control over the activ-ities wit Q tSe area and perfor riod'c_radiat ur - lance at the Trequenc specifie by the faci ity ?it; Radi;1 gica' R165

                          ' 7 trol          r in the RWP.

Ago rmisTay t. jw / 6.12. e requirements of 6.12.1, above, shall also apply to each high radia- ) tion area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained unde dmW i heShi_f40perationsSuperyitnron t V 169[ V anager. and/or the Sit; Rediological 'c/rt: cihobn 0H A ^ A_

• Radiological Control personnel or personnel escorted by Radiologicai Control R142 personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation R165 protection procedures for entry into high radiation areas.

March 31, 1994 SEQUOYAH - UNIT 2 6-25 Amendment No. 34, 50, 66, 134, 142, 165,169

g.. , +- tc _ . _ . ,  : ' ; yl- n 4._ . ; ,  ::. i . ENCLOSURE 2 , PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-18) DESCRIPTION AND JUSTIFICATION FOR SECTION 6.0 TITLE REVISIONS i e i e

y - 4 Descriotion of Chanae TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) to revise administrative titles in TS Section 6.0 This change will change the titles of: Old New Senior Vice President, Nuclear Power President, TVA Nuclear and Chief Nuclear Officer Manager, i4uclear Experienc0 Manager, independent Review and Analysis Review / independent Safety Engineering Site Radiological Control Manager RadCon/ Chemistry Control Manager Radiological and Chemistry Manager RadCon/ Chemistry Control Manager Maintenance Manager Maintenance and Modifications Manager i Quality Audit and Assessment Manager Site Quality Manager Site Engineering Representative Engineering and Materials Representative These changes have been incorporated throughout Section 6.0 of the TS. An additional typographical error has been corrected in this revision request for Unit 2, Section 6.8.4.f where a continuation page was inadvertently labeled as 6.8.5.f. Reason for Chanae The TVA corporate and SON site organizational titles have been revised to the titles proposed in this request. This change is being proposed to provide consistency with the current TVA titles and the TVA Nuclear Organizational Topical Report, TVA-NPOD89 A, Revision 6. l Justification for Chances The proposed changes are administrative in nature and do not impact the daily operation and controls involving operation of the nuclear unit. The changes involve only the titles of management positions and the responsibilities of these positions have remained basically the same. There is no nuclear safety impact as a result of the proposed changes, i l i {

1 l 2-Environmental imoact Evaluation The proposed change does not involve an unreviewed environmental question because operation of SON Units 1 and 2 in accordance with this change would not:

1. Result in a significant increase in any adverse environmentalimpact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmentalimpact appraisals, or decisions of the Atomic Safety and Licensing Board.

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SON that may have a significant environmentalimpact. ,

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                                              -ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-95-18)

DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION 5 h k l l I l I ._

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J l l Significant Hazards Evaluation 1 1 1 1 TVA has evaluated the proposed technical specification (TS) change and has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SON) in accordance with the proposed amendment will not ,

1. Involve a significant increase in the probability or consequences of an accident ,

previously evaluated. ' The proposed changes only involve the administrative titles of management , positions in TVA. Plant equipment and operating practices are not affected by the l proposed administrative changes. Therefore, there is no increase in the l probability or consequences of an accident.

2. Create the possibility of a new or different kind of accident from any previously analyzed. I i

Plant features are not impacted by the proposed revision; therefore, this revision I can not create the possibility of a new or different accident

3. Involve a significant reduction in a margin of safety.

Plant setpoints and features that establish and maintain the margin of safety for SON are not involved in the proposed administrative TS change. Therefore, the margin of safety is not reduced by the proposed change. I

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