ML20196G193
| ML20196G193 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/01/1988 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20196G190 | List: |
| References | |
| NUDOCS 8803070071 | |
| Download: ML20196G193 (30) | |
Text
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ENCLOSURE l' b c , , ,
PROPOSED TECHNICAL SPsCIFICATION ChiANGE' i
'SEQUOYAH NUCLEAR PLANT-UNITS 1 AND 2
- DOCKETcNOS;-50-327 AND.50-328 ,
-(TVA-SQN-TS-87-44)'.
LIST OF AFFECTED PAGES Unit 1.
6-l' ,
6-3 6-4 I- 6-6 6-7 '
6-9 6-10
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6-7 6-8 6-10 .
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1 1 The Plant Manager shall be responsible for overall unit operation f62 and shall delegate in writing the succession to this responsibility during his absence.
6.1. 2 The Manager of Radiological Control shall be responsible for imple- k62 menting the radiological environmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual (ODCM). ~
6.1.3 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Site Director, shall be reissued to all station personnel on an annual basis. R62 6.2 ORGANIZATION OFFSITE
- 6. 2.1.1 Ad4 The of fsite organization for en4t management and technical support shall be as shown in Figure 6.2-1.
(AltLZTif R62 4HH4- ST AFF FwI.43 6.2.2 The-On+b organization shall be as shown in Figure 6.2-2 and:
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- a. Each on-dutyA shif t shall be composed of at least the minimum shif t crew composition shown in Table 6,2-1. t un;f
- b. At least one licensed Reactor Operator shall be in the4 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.
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-J FACILITY ORGANIZATION - SEQUOYAH NUCLEAR PLANT x
__ _ __ _ _ _ _ . _ ._ _ _ _ _ _ . _ _ _ _ _ -.________i _ . . _ _ _ _ _ _ _ - . . __ .
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o OtRECTOR e D"'ECTOR D"'ECTU8E. N N DfvtStON of DMSN3N et SITE DIRECTOR E4,," Mw E ,"
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- MAINTENANCE SUPERVISOR ENGINEERING PROJECTS Pt ANNING ENGtNEERING SRO SUPERV1SOR SUPERVISOR SUPERVtSOR SUPERVISOR SHfFT TECHNICAL ADVISOR ASSESTANT MECHMilCA!_
smo SUP SOR UNIT SYSTEMS OPERATOR -
ENGINEERING LEGEND RO SUPERVISOR ADMINISTRATIVE AND TECHNICAL REPORTING FUNCTIONAL REPORTING SRO - Senior Reactor Operator, Uconee Required RO - Reoctor Operator, Ucense Required i FIGURE 6.2-2 FACIUTY ORGANIZATION - SEQUOYAH NUCLEAR PLANT
ADMINISTRATIVE CONTROLS 6.2.3~ INDEPENDENT SACETY ENGINEERING GROUP TISEG)
FUNCTION-6I2.'3.1. The lSEG shall function to examine plant operating characteristics, NRC issuances, industry. advisories, ' Licensee Event Reports and other sources . lR62 which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG-shall be composed of at least 3 dedicated full-time engineers R62 located onsite. These enfineers will be supplemented by 2 full-time engineers shared among all TVA nuclear sites.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant l'
activities to provide indepenaent verification" that'these activities are ,
r*rformed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, or other means of improvino plant safety to the R62 Director of Nuclear Safe., W Licensingx and 89u~4hy ACn.
- 6. 2. 4 SHIRT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA-shall serve in an advisory capacity to the shift supervisor R16 on matters pertaining to the engineering aspects of assuring safe operation of the unit.
FAtzt.zrd 6.3 4M4-STAFF OUAllFICATIONS 6.3.1 Each member of the VLtI4 un&& staff shall meet or exceed the minimum qualifi- i cations of ANSI N18.1-1971 for comparable positions and the supplemental reouirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Site Radiological Control Super- R62 intendent who shall meet or exceed the qualifications of Regulatory Guide 1.8,-
September 1975.
, *Not responsible for sign-off function.
e_____t__ ,r ,ne-SEQUOYAH - UNIT 1 6-6 A kbb$$t $$. fd, 50 R61
_A_D.MINISTRATIVE CONTROLS
" 6. 4 TRAINING 6.4.1 f faaI 1 A retraining and replacement training program (forshall the unw;l:O
- staff be maintained under the direction of the % ;lcer Pe.ir Ple,t (MP") Superin- 362 tendent and shall meet or exceed the requirements and recommendations of Sec-tion 5.5 of ANSI N18.1-1971.and Appendix A" of 10 CFR Part 55 and the supple-mental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience. R62 6.5 REVIEW AND AUDIT 6.5.0 't5e Manager of Nuclear Power is responsible for th? safe operation of all TVA pt.wer plants. The functional organization for Review and Audit is R62 shown on Figure 6.2-1.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 related The PORCsafety.
to nuclear shall function to advise the Plant Manaaer on all matters R62 COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman: Plant Manaaer Member: R62
-kp;rintenE:nt (MP" er Maintenen:0) Operas 8V #*/"'"
Member:
Operations W Manager-er '.::!:t:nt 0?:r tienF C eup
-M:ns;;r Member: Site Radiological Control Superintendent Member:
Jyeo' dad"Y a
Member:
Member:
Technical Support i Serv;;::,: Maintenance Creu; M:n:g:r Orcu; Mene Quality Engineering-:nd Centrol Manager inem!v: z),y;,;.. ol'iV,,,/w Ey,<< a:j A<pr<u Id^
I h p u -- b 2 0 , I '. ' R62 SEQUOYAM - UNIT 1 6-7 '-::n ::ri S.53
ADMINISTRATIVE CONTROLS
- h. Performance of special reviews, investigations or analyses and i
- reports thereon as requestea by the Plant Manager or the Nuclear Safety Review Board.
- i. Review of every unplanned onsite release of radioactive material to *'
the environs including the preparation and forwarding of reports-covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Site Director and to~the Nuclear Safety Review Board.
AUTHORITY 6.5.1.7 The PORC shall:
- a. Recommend in writing to the Plant Manager approval or disapproval of items considered unaer 6.5.1.6(a), (b) and (c) above.
b.
Require a determination in writing with regard to whether,or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question, 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 Site Director and the Nuclear Safety Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsi-bility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Director and the Nuclear Safety Review Board.
6.5.1A TECHNICAL REVIEW AND CONTROL ACTIVITIES R62 i
- 6. 5. lA. l. Activities which affect nuclear safety shall be conducted as follows:
- a. Procedures required by Specification 6.8.1 and other procedures I which affect plant nuclear safety, and changes thereto, shall be l prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by a qualified individual other than the individual who prepared the procedure or procedure change, but who may be from the same organization as the individual who prepared the procedure or procedure change. Procedures shall be approved by the appropriate responsible manager as designated in writing by the Plant Manager.cr Sit: Direct:r :: :ppr:pri:te. The Sit: Dir;;t:r, Plant Manager, M Superintendent, -ee Maintenance Superintendent shall approve ,desi nated Administrative Procedures. jI OP "' W 'Taksul &p* /f L
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SEQUOYAh - UNIT 1 '6-9 ' ena nt N:. SS
ADM]NISTRATIVE CONTROLS (Continued) b.
Workplans used to implement proposed changes or modifications to
' structures, systems, and components that affect plant nuclear safety shall be reviewed by a qualified individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed -
the modifications. Proposed modifications to structures, systems.
C u 4h,.n and components that affect plant nuclear. safety.and the implementing workolans shall be approved prior to implementation by the Plant R62 Manager % JP-Superintendent, o ,. Tr. L ;../ y p / J-p riA <A-1'. e Maintenance Superintendent, c.
Individuals' responsible for reviews performed in accordance with Specifications 6.5.1A.la and -b, shall be designated by approved written procedures.
Each-such review shall be performed by qualified personnel of the appropriate discipline and shall' include a determination review of whether or not additional, cross-disciplinary is.necessary. 4 Each review shall also include determination of whether or not an unreviewec) safety question is involved pursuant to Section 20 CFR 50.59.
Sucf 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 adecuacy of designated activities in the areas of: R62
- a. nuclear power plant operations
- b. nuclear engineering
- c. chemistry and radiochemistry
- d. metallurgy e.
instrumentation and control
- f. radiological safety i
g.
mechanical and electrical engineering
- h. quality assurance practices I I
COMPOSITION 6.5.2.2 ~
Chairman. The NSRB shall be composed of at least five members, including the other TVA organization or external to TVA. Members of the NSRB may be from-t R6
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. ADMINISTRATIVE CONTROLS
- f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
- g. All REPORTABLE EVENTS. -
lR62 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,
l R62 AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of unit operation to provisions ccntained within the Technical Specifications and applicable' license conditions at least once per 12 months.
b.
The staff performance, training at least once per and qualifications of the entire e4 -[ut/dh 12 months, c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e.
The Site Radiological Emergency Plan and implementing procedures at least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least one.e per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB or the Manager of Nuclear Power, Re>2 h.
The Facility Fire Protection Program and implementing procedures at 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.
seged : 10, 1987 SEQUOYAH - UNIT 1 6-12 ?=ndmcat-No-68 62;
a .
ADMINISTRATIVE CONTROLS 6'10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made Report.to systems ar~ quipment described in the Final Safety Analysis
- b. Records of new and irradiated fuel inventory, fuel . transfers and assembly burnup histories,
- c. Records of radiation exposure'for all individuals entering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
- f. Recoras of reactor tests and experiments.
- g. Records of training and qualification for current members-of the Sw M 3 Am a staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. . Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Manual. sb2
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
Records of analyses required by the radiological environmental monitoring program.
m.
Records of secondary water sampling and water quality.
n.
Records of the service life monitoring of all safety-related hydraulic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life, o.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(b) of License No. OPR-77.
146 6.11 RADIATION PROTECTION PROGRAM i
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 exposur'e.
E# :t:: 10, 1987 SEQUOYAH - UNIT 1 6-25 5.:ne,ent"c.pf,50 R62
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6.0 ADMIN 15':ATIVE CONTROLS i
6.1 RESPONSIBILITY 6.1.~ 1 The Plant Manager.shall be responsible for overall unit operation anc~
shall delegate in writing the succession to this responsibility during his.
absence.
R50 6.1.2 The Manaaer of Radiological Control shall be responsible for implement-ing the radiological environmental program and dose -calculations and projec. R50 tions as described in the Of fsite Dose Calculation Manual (ODCM).
6.1.3 The Shif t Supervisor (or during his absence 'from the. Control Room, a designated individual) shall be. responsible for the Control Room command func-tion. A management directive to'this effect, signed by the Site Director shall R50 be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE Asakl3 6.2.1.1 The offsite organization for wait management and technical support shall be as shown on Figure 6.2-1.
FACILZTy R50 U!: STAFF faubly 6.2.2 The 4k44 organization shall be as shown on Figure 6.2-2 and:
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- a. Each on dutydshif t shall be composed of at least the minimum shift crew composition shown',in Table 6.2-1. ;
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- b. At least one licensed Reactor Operator shall be in thedControl Room :
when fuel is in the reactor. 10 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.
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CHEMtSTRY MECHANICAL I" C TRO El.ECTRICAL h spo SUPERVISOR SUPERVISOR SUPERVISOR SUPEW M 1- ; pose user i. unst a aseo coensons souspesum SNtFT REACTOR SPECIAL MAINTD4ANCE SUPERV!<3R ~ MAINTENANCE ENotNEERING PROJECTS PtANNING ENGINEERING SRO SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SHtFT 1ECHNICAL AuvtSOR NA887 WECHANICAt marv TEST i aseo SUPERVISOR UNIT N OPERATOR -
ENOGNEERING LEGEND RO SUPERVISOR ADMINISTRATIVE AND TECHNICAL REPORTING FUNCTIONAL REPORTING i
i SRO - Senior Reoctor Operator, IJconee Required RO - Reactor Operator. Uconee Required FIGURE 6.2-2 FACIUTY ORGANIZATION - SEQUOYAH NUCLEAR PLANT
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ADMINISTRATIVE CONTR0L'S
~*'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 t50
-which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 Tne ISEG shall ue composed-of at least 3 dedicated full-time engineers located onsite. These engineers will be supplemented by 2. full-time engineers R50 shared among all TVA nuclear sites.~
RESPONSIBILITIES 16.2.3.3 The ISEG 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 ISEG shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Director of Nuclear 5:f;( : ; Licensingw Anal [fjubi 9y A4tst l R$u, l 6.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve in an advisory capacity to the shift supervisor on I
matters pertaining to the engineering aspects of assuring safe operation of the unit.
FACZL273 6.3 4444 STAFF QUALIFICATIONS 6.3.1 Auldt Each member of the sait staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental' requirements specified in Section A and C of Enclosure 1 of March 28, 1980 NRC letter to all licensees, except for the Site Radiological Control Superintendent g3a who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
l-4 "Not responsible for sign off function.
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SEQUOYAH - UNIT 2 67 "$0 0
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- A'O MINISTRATIVE CONTROLS
- 6. 4 TRAINING Cptqaknr 3.4.1 Aretrainingandreplacementtrainingprogramjfor .
the *M4 staf f shall be maintained under the direction-of the "uclear "e c. "lert (F"") Superintendent l R50 and shall meet or exceed the requirements and recor,nendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental require-ments specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.
kR50 6.5 REVIEW AND AUDIT 6.5.0 The Manager of Nuclear Power is responsible for the safe operation of all TVA power plants. The functional organization for Review and Audit is lR50 shown on Figure 6.2-1.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety. (R50 COMPOSITION 6.5.1.2 The PORC sna11 be composed of the:
R50 Cha i' rma n: Plant Manager Member: h.p '-t ne:-t ( F" e r ": i - t e ne n : ) Oper* Oat J*/"la
Member: Operations 4*e Manager : '::!:t:rt Cp;r tier: C :;;
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Member: Site Radiological Control Superintendent Member: Maintenance Cr ;; "On:g: , (!), (:) c. (F.) 1-/t"d '
Member: Technical Support Ser~ ice: Creu: ".:n:g: 7 4,,,*, M- f Member: Quality Engineering are C:ntre' Manager
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AD41HISTRATIVE CONTROLS i.
Review of every unplanned onsite release of radioactive material to
- ' the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action Review Safety to prevent recurrence to the-Site Director and to the Nuclear Board.
AUTHORITY
- 6. 5.1. 7 The PORC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of items considered under 6.5.1.6(a), (b) and (c) above, b.
Require a determination in writing with regard to whether or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question.
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 Site Director and the Nuclear Safety Review Board of disagreement between the PORC and the Plant Manager; however, the. Plant Manager shall have respon-sibility for resolution of such disagreements pursuant to 6.1.1 above. R50 RECORDS 6.5.1.8 a minimum, document the results of all PORC activities performe responsibility and authority provisions of these technical sDecifications.
Copies Board. shall be provided to the Site Director and the Nuclear Safety Review 6.5.1A TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1A.1. Activities which affect nuclear safety shall be conducted as follows:
a.
Procedures required by Specification 6.8.1 and other procedures which affect plant reviewed andnuclear approved. safety, and changes thereto, shall be prepared, Each such procedure or procedure change shall be revieweo by a qualified individual other than the individual who prepared the procedure or procedure change, but whc may be from the -same organi:a-tion as the individual who prepared the procedure or procedure change.
Procedures shall be approved by the appropriate responsible manager as h"'j'. desionated i_n writino by the Plant Manager,or Sit:
'" The ::- .~.i r:r.a Plant flanager,*i@f' Superintendent, .e MaintenanceCirc; tor ;; ;;;repH te Superintendentus hall approve designated Adminjstrative Procedures.
- b. u ;,,/ j.pp d J.por:n d" 4 n Jo% A W y haf & bol Jy u.h U d Workplans used to implement proposed changes or modifications to struc-tures, systems, and components that affect plant nuclear safety shall be reviewed by a cualified individual / group other than the individual / group l' which designed the modification, but who may be from the same organization SEQUOYAH - UNIT 2 6-10
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ADMINISTRATIVE CONTROLS as the individual / group which designed.the modifications. Proposed
. modifications to structures, systems, and components that affect plant' -
nuclear safety and.the-implementing workol ns shall be approved prior to implementation by the Plant Manager,-MPA Su rintendent, e- Maintenance Superintendent y or Eh/ 4p e d Jy ,.a/ M . R50 g
c.
Individuals tions responsible
- 6. 5.1A. la and -b, for reviews performed in accordance with Specifica-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. Eac review shall also incluce determination of whether or_ not an unreviewed fety question is inv'olved pursuant to Section 10 CFR 50.59.
g 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: g$o
- a. nuclear power plant operations
- b. nuclear engineer'ng
- c. chemistry and radiochemistry
- d. metallurgy i e.
instrumentation and control
- f. radiological safety g.
mechanical and electrical engineering
- h. quality assurance practices COMPOSITION I 6.5.2.2 Chairman. The NSRB shall be composed of at least five members, including the Members of the other TVA organization NSRB may or external be from the Office of Nuclear Power, or to TVA. R50 j OUALIFICATIONS 1 6.5.2.3 The Chairman, memoers, and alternate members of the NSRB shall be !
appointed in writing by the Manager of Nuclear Power and shall have an academic degree in engineering or a physical science field, or the equivalent; and in v 0 addition, more areas shall have given a minimum of five years technical experience in one or; in 6.5.2.1.
voting members in NSRB activities at any one time.No more than tuo alternates shall '
i SEQUOYAM - UNIT 2 6-11 :r .E K50l
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. ADMINISTRATIVE CONTROLS AUDITS-6.5.2.8 Audits of unit activities shall be performed under_the cognizance of the NSRB. These audits shall encompass:
- a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire tm44. dddYg staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in unit equipment, structures,--systems or method of operation that affect nuclear safety at-least once per 6 months.
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
- e. The Site Radiological Emergency Plan and implementing procedures at least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
g.
Any other 3rea of unit operation considered appropriate by the NSRB or the Manager of Nuclear Power. RSO h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection -
and audit shall ce performed annually utilizing either qualified of f site licensee personnel or an outside fire protection firm. j
- 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. j
- k. The radiological environmental monitoring program and.the results thereof at least once per 12 months, i
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least once per 24 months.
n.
The performance of activities 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, R34 Rev. 1, 1975, at least once per 12 months.
SEQUOYAH - UNIT 2 6-13 hp::en 8 e M=eM W^
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ADMINISTRATIVE CONTR0'.S 6.10.2 The following records shall be. retained'for the duration of the Unit
-Operating License: R28
- a. Records and drawing changes reflecting unit design modifications.made to systems and equipment oescribed in the Final Safety' Analysis Report.
, b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories,
- c. Records of radiation exposure for all individuals entering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the environs.
- e. Records of transient or operational cycles for those unit components identifiea in Table 5.7-1. '
- f. Records of reactor tests and experiments,
- g. Records of training and qualification for current members of the
.(lc(;Q-uMA-staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Manual. R50
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
R50
- 1. Records of analyses required by the radiological environmental monitoring program.
September 10, 1987 R$
, SEQUOYAH - UNIT 2 6-26 Amendment No. 50 l
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ENCLOSURE 2
., PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-44)
DESCRIPTION AND JUSTIFICATION FOR THE REVISION OF SECTION 6 "ADMINISTRATIVE CONTROLS"
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ENCLOSURE'2
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-Description of Change
-Tennessee Valley Authority proposes to modify the-Sequoyah Nuclear Plant l-U, nits 1 and 2 Technical Specifications to revise Section 6 "Administrative Controls," to reflect corporate and site organizational changes. ,
Reason for Change ~
.Several organization changes-have been implemented, or wi11 be implemented, that differ from the organization currently described in section 6 of the technical specifications. The revisions-are made to '
properly identify the desired organizational structure for'both' corporate and site staffs. The proposed changes are identified ~below. e '
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- 1. The'name of Nuclear Safety and_ Licensing has been changed to Nuclear Licensing and Regulatory Affairs for clarification of responsibilities.
I
- 2. The site quality control (QC) and quality engineering:(QE) functions
.have been divided into separate lines of authority and responsibility.
to enhance the functions. .The Plant Operations Review Committee:
- l. (PORC) composition.is revised'to reflect this change in authorities .
-and responsibilities. !
- 3. The corporate and site security organizations were reorganized to provide corporate level programmatic guidance while elevating site security reporting to the Site Director.
- 4. Responsibility for the Fire Protection Program and fire brigade staffing is being removed frcm the industrial safety group and
~
operations group, respectively, and placed in an independent Fire ;
Protection Section to provide enhanced, dedicated ~ fire' protection !
management and coverage.
l S. An Assistant to the Plant Manager position has been added to the plant management structure.
- 6. A water and waste processing section is being established to separate this function from other shift operation duties,'and establish direct accountability to the Operations Superintendent.
- 7. A maintenance engineering group is being established to provide a measure of separation between the maintenance craf t and . engineering j disciplines.
l 8. The technical support function under the Plant Manager is to be elevated to a super otendent level. This provides enhanced authority d
and responsibility for the function, and makes the function directly ;
l reportable to the Plant Manager. The PORC composition is revised to j reflect this change in authorities and responsibilities.-
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- 9. . The Technical-Review and Control section-(6.5.1A) is' revised to reflect that_all activities which affect nuclear safety are ultimately the responsibility of the Plant Manager and the plant superintendents.
l'U. The Deputy Manager of Nuclear Power position is deleted from Figure 6.2-1 because it is not in the direct line of management for-plant operations.
In addition to the abcVe organizational changes, the planning and scheduling and the radiological control functions are revised on Figure 6.2-2 to reflect them as management positions.
Also, the references to unit staff and organization iu'section 6 are ;
changed to facility staff and organization for consistency with other information in section 6.
Justification for Change The first change is a title change only. The licensing staff title was changed from Nuclear Safety and Licensing to Nuclear Licensing and Regulatory Affairs. This was done to clarify the' independence of the Nuclear Safety Review Board from the licensing staff. There are no ,
changes in lines of authority or responsibility related to.this technical specification change.
The second change is the resuit of a change in the lines of responsibility and authority in the Division of Nuclear Quality Assurance (DNQA). The original organization had both QE and QC under the supervision of the Quality Engineering and Control Manager, who reported to the Site QA Manager. The DNQA reorganization separated the QE and QC functions, and establish 0d both a QE Manager and a QC Manager. Both of these positions report direc:tv to the Site Quality Manager. The QE ;
Manager is retained as a member of PORC.
The next change is the result of the restructuring of the corporate and site security staffs. Under the new organization, the Site Security e Manager receives functional direction from the Nuclear Security Branch of the Division of Nuclear Services. The Site Security Manager receives daily direction and management from the Site Director. This organization provides a centralized programmatic support group, in addition to the routine management provided by the Site Director. The Site Security Manager now reports to the Site Director instead of the Plant Manager because security is a function supporting the site.
Another change will be the result of separating fire protection' responsibilities from the industrial safety section. A Fire Protection Section is being developed that will provide the fire brigade personnel and maintain the site fire protection program. This change will enhance the management of the fire protection program, and provide dedicated fire protection coverage.
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Another change is made to reflect an additional management position at the Plant Manager level. The Assistant to the Plant Manager position was formed to increase management availability and attention at this level.
The Fire Protection Section and the Plant Operations Review Staff will report to the Assistant to the Plant Manager.
Two other changes are made to clarify the separation of responsibilities for.two plant sections. The Water and Waste Processing Group Supervisor position is added to Figure 6.2-2 to clarify that the water and waste
. processing function-is performed by a section separate from the shift operations personnel. Similarly, the maintenance engineering supervisor position is added to clarify the separate maintenance engineering and craft groups.
The remaining organizational changes are the result of elevating the technical support functions to a superintendent level. This was done to enhance the responsibilities and authorities of the function. It also makes che function report directly to the Plant Manager. Chemistry, reactor engineering, mechanical test, and systems engineering are all technical support groups that will report to the Technical Support Superintendent. As part of this realignment, the Nuclear Power Plant Superintendent position is changed to Operations Superintendent. This position is now responsible for the operations and the water and waste processing functions. Also, as part of this realignment, the Assistant Operations Supervisor position was removed. .This removes one layer of managtment, and establishes direct reporting of the Shift Supervisor to the Operations Nanager.
As part of the technical support reorganization, the PORC composition will be revised to reflect the superintendent positions as members. The Operations Manager and QE Manager are also retained as members. A Division of Nuclear Engineering representative is added as a PORC member to provide engineering expertise. This PORC composition is consistent ,
with the PORC responsibility to provide a diverse, upper management i oversight review of act!vities affecting nuclear safety.
The revisions to section 6.5.1A are made because.the Plant Manager and the plant superintendents are ultimately responsible for the safe operation of the plant. As such, the activities that affect nuclear safety are under their supervision and control. Also, a wording change is made in section 6.5.1A.1.c for consistency with other wording in the section.
I The Deputy Manager of Nuclear Power position is deleted from Figure 6.2-1 j because it is not in the direct line of management for plant operations.
The position was created as part of TVA's management reorganization and development effort as described in the Nuclear Performance Plan Volume 1. It is not appropriate to represent it as part of the direct I management chain because the Site Director reports directly to'the ;
Manager of Nuclear Power in matters concerning safe operation of.the !
plant.
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The' planning function and radiological control functions are. revised.on Figure 6.2-2-to present.them as management positions. This is done for consistency with.the other positions presented on the figure. Planning and scheduling is under~the responsibility of the Planning, Scheduling.-
Ejtimating, and Financial Services Staff Manager. Similarly,.
radiological control functions are under the supervision of the Site Radiological Control Superintendent.
The references.in section 6 to unit staff and organization are changed to facility staff and organization. This is consistent with the title of,
_and the organization shown, on Figure 6.2-2.
.The changes described above represent corporate and site organizational changes that affect the technical specifications in section 6. The changes range from title changes only, to. revised lines of responsibility and authority..'The changes are made to maintain a proper representation .
of the corporate and site organizations in the technical specifications.
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. ENCLOSURE.3 ;
, , - PROPOSED TECHNICAL-SPECIFICATION CHANGES-SEQUOYAH NUCLEAR PLANT UNITS 1-AND 2 .,
~
DOCKET NOS. 50-327 AND'50-328'
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- (TVA-SQN-TS-87-44)- _
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-i DETERMINATION.0F N0'SIGNIFICANT HAZARDS CONSIDERATIONS -
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ENCLOSURE 3 Page 1 of 1 Significant Hazards Evaluation TVA has evaluated the proposed technical specification change and determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the proposed amendment will not (1) Involve a significant increase in the probability or consequences of an accider.t previously evaluated. This change is intended to accurately reflect the changes to the Administrative Controls section (section 6) of the technical specifications resulting from recent and plannea organization changes. The functions specified in section 6 important to the safe operation of SQN have not been altered or deleted. The changes to this section merely reflect title changes, new positions, and the realignment of positions that hold the expertise to perform these functions. The title changes are made for clarification. The roles of the individuals charged with the responsibility of safe operation of this facility are enhanced by the new positions and realignments. This change better identifies those positions occupied by individuals qualified to provide this technical assistance. There are no hardware, procedure, personnel, or analysis changes represented by this amendment proposal that adversely affect the probability of occurrence or the consequences of an accident previcusly evaluated in the safety analysis report.
(2) Create the possibility of a new or different kind of accident from any prev.;usly analyzed. This change represents title changes and changes in the administrative process in that new positions and responsibilities are identified. The functions important to safety will continue to be performed by those individuals who are technically competent to perform these functions; therefore, the potential for the increase of a possibility of an accident or a new or different type of accident is reduced rather than increased because of having the appropriate personnel designated for these functions.
(3) Involve a significant reduction in a margin of safety. The changes 4 in this amendment proposal serve only to clarify or enhance those l positior responsible for key safety functions specified in section 6 of technical specifications. No function has been impaired or deleted by this change. On the contrary, these functions are improved by the additional clarity and elevated levels of authority and responsibility afforded by the proposed changes.
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