ML19305E710

Proposed Amend to App A,Tech Specs,Incorporating Recent Corporate & Station Organizational Changes & Eliminating Two Organization Charts

ML19305E710
Person / Time
Site:	Dresden, Quad Cities
Issue date:	05/13/1980
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML17192A692	List: ML17192A691 ML19305E710
References
NUDOCS 8005200298
Download: ML19305E710 (33)

Text

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8 0052 00 [ff O

Dresden Station Unit 1 Proposed Technical Specification Changes Revised Pages:

124 125 126 I

131 l

132 146 Deleted Pages:

144 145

6.0 NFINIs1TWrIVE CON'ITOLS DPR-2 h

6.1 Organization, Review, Investication and Audit A.

The Station Superintendent shall have overall full-E.

Retraining and replaceaent training of Station time responsibility for safe operation of the facility.

, Personnel shall be in accordance with ANSI Durinr1 periods when the Station Superintendent is

.. N18.1 " Selection and Training of Nuclear Power unavailable, he shall designate this resconsibility Plant Personnel". dated harch 8. 1971.

'to an established alternate who satisfies the ANSI J

N13.1 experience requirements for plant manager.

A training prograra for the Fire Brigade shall be maintained inder the direction of the B.

The corporate management which relates to the operation operating Engint er and shall meet or exceed of this station is shown in Figure 1-6 of CE-1-A '1bpical the requirements of Section 27 of the NFPA Report. The Division Manager, Muclear Stations has code - 1975. except for Fire Brigade training responsibility for the Fire Protection Program, sessions which shall be held at least quarterly.

C "te normal functional organization for operation of

'the station shall be as shown in Figure 1-6 and Figure F.

Rettsining shall be conducted at intervals u t A of CE-1-A Topical Report. The shift manning for the, exceeding two years.

station shall be as shown in Figure 6.1.1.

The Ooerating Assistant Superintendent, Cperating Engineer, C.- Tle Review and Investigative Function and the SUt Ebgineer and Shift Foremen shall have a unct n activities affecting quality scbioroperatinglicense. The Fuel Handling Foreman

,"d Per i s shall be n i ed ns has a limited Senior Operating License. An Operating outlined below:

Engineer will te responsible for i:rplementation of the Fire Protection Program.

1.

The Supervisor of the Of fsite Review and Investigative Function shall be appointed A fire brigade of at least 5 members shall be maintained.

by the Vice President of Construction on-site at all times. This excludes the shift crew Production 1.f eensing and Faviron:cental necessary for safe shutdown of the plant, and any M fairs. The Audit function shall be the personnel required for essential functions during a responsibility of the Manager of Quality fire emergency.

Assurance and shall be independent of operations,

'o ' cualifications of the station management and operating staff shall meet minimum acceptable levels as described

_Offsite Review and Investigative Function s.

in M SI N18.1, " Selection and Training of Nuclear Power The Supervisor of the Of fsite Review and Plant Personnel", dated March 8, 1971 with the exception of the Rad-Chem Supervisor who shall meet or exceed Investigative Function shall: (1) provide Regulatory Guide 1.8' September,1975. 'Ihe individual directions for the review and investigative the cualificatioris of Radiation Protection Manager of unction and app Int a senior p:rticipant filling the position of Administrative and Sunport

]v e se ate direct

n. (11) t 1

Services Assistant Superintendent shall meet the minintan et en, gg g)

I acceptable level for " Technical Manager as described in 4.2.4 of NJSI N18.1 - 1971.

or.e p.trticipant who caricctively posse,.

background and qualifiestions in the s

subject ca.itter under.eview to pravf.Je

DPR-2 O

O o

Offsite Review and Investigative (2) Froposed changes to procedures, c;uip-eent or systems which involve an unreviewed a.

Function (Continued) safety question as defined in Section 50.59 10 CFR.

comprehensive interdisciplinary review coverage under this function (iv) independ-ently review and approve the findings and (3) Proposed tests or experiments which involve an unreviewed safety question as defined recomendations developed by personnel in Section 50.5910 CFR.

perforr.iing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with (4) Proposed changes in Technical Specifications tiRC requirements and provide recomendations or MRC operating licenses.

to the Station S;perintendent, Divisicn Manager fluclear Stations, Manager of ouality Assurance, (5) Noncompliance with NRC requirements, or of internal procedures or instructions having Vice Precident of I:uclear Ooerations, and the Executive nuclear safety significance.

Vice President of Construction, Production, Licensing, and Dwironmental Affairs. During periods when the St.pervisor of the Offsite Review (6) Significant operating abnomalities or deviations from nomal and expected performance of plant and In,estigative function is unavailable, he shall designate this responsibility to equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative an established alternate who satisfies the Function.

forral training and experience requirements for the supervisor of the Offsite Review (7) Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifi-and Insestigative Function.

cation to the Commission.

The responsibilities of the personnel perfoming this 'enction are stated below.

(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation The Off site Revit i and Investigative of safety related structures, systems or ccmponents.

Function shall review:

(1) The safety evaluations for 1) changes (9) Review and report findings and recomendations regarding all changes tc the enerating Stations to procedures, equipment or systems Emergency Plan prior to impic.neatation of such as described in the safety analysis report end 2) tests or experiments change.

cenpleted under the provision of 10 CFR Section 50.59 to verify that (10) Review and report findings and recemendations such actions did not constitute an regarding all items referred by the Technical I

unreviewed safety question.

Proposed Staff Supervisor Station Superintendent,

- Division Manager - Nuclear Stations and Manager changes to the Quality Assurance Program description shall be reviewed and approved of Quality Assurance.

by the Manager of Quality Assurance.

125

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O DPR-2 b.

Audit remetton_

The Audit Function shall be the responsibility of the (5) Audit of the Facility Dnergency Plan and Manager of Quality Assurance independent of the implementing procedures.

Production Departs.ent. -Such responsibility is delegated to the Director of Quality Assurance for (6) Audit of the Facilit'y Security Plan and Operating and to the Staff Assistant to the Manager imp cmenting procedures, of Quality Assurance for maintenance quality assurance activities.

(7) Audit onsite and offsite reviews.-

Either shall approve the audit agenda and checklists.

(8) Audit of the Facility Fuel Protectica Prtgram and implementing procedures at Icast once per 24, months, the findings and the report.of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits (9) Report all findings of noncompliance with NRC shall be performed to assure that safety-related requirements and recommendations and results functions are covered within a period of two years of each audit to the Station Superintendent.

the Division Manager-Huclear Stations. Manager or less as designated below.

of Quality Assurance, the Vice Presidcnt of Puc_ lear (1) Audit of the Conformance of facility operation Operations, Director of Nuclear Licensing f

to provisions contained within the Technical and to the Executive Vice President of Construction Specifications and' applicable license con-Production, Licensing and Environmental Affairs.

ditions at.least once per year.

' c.,

Authority (2) Audit of the adherence to procedures, training and qualification of the station staff at least The Manager of Quality Assurance reports to the l

Vice Chairman and the Supervisor of once per year.

the Offsite Review and investigative Function reports to the Vice President of Nuclear (3) Audit of the results of actions taken to

]

correct deficiencies occuring in facility i

Operations.. Either the Manager of Ouality '.

equipment. structures. systems or methods Assurance or'the Supervisor of the Offsite Review of operation that af fect nuclear safety at '

and investigative Function has the authority to least once per six months. -

order unit shutdown or request any other action which he deems necessary to avoid unsafe plant (4)^ Audit cf the performance of activities conditions, required by the Quality Assurance Program to meet the criteiria of Appendix *B," 10

.d. Records CFR 50.

(1) Reviews, audits and reconsnendations shall be documented and distributed as covered in 6.1.G.l.a and 4.T.G.l.b.

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126

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O DPR-2 6.2 Plant Op' crating Procedures A.

Octailed written procedures including 8.

Tests and experiments.

applicable checkoff. lists covering items

. listed below sha'll be prepared, approved, 9.

Procedure to ensure safe shutdown of the and adhered to:

plant.

1.

I:orr.a1 startup, operation, and shutdown

10. Station Security Plan and implementing of the reactor ~and other systems and procedurcs..

ccrpenents involving nuclear safety of the facility,

11. Fire Protection Program inplementation.

2 Refueling operations.

B. " Radiation control procedures shall be main-tained. nade available to all statica persene.el

,4 3

Actions to be' taken to correct specific and adhered to.

These procedures shall show and forescen potential malfunctions of permissible radiation exposure and shall be systems or components including responses consist:nt with the requirements of 10 CFR to alarms, suspected primary system leaks,

20. Thir radiation protection progrc shall be.

and abnormal reactivity changes, orgntiacd to ecct the requirements of 10 CFR 20.

4.

Emergency ' conditions involving potential'

c. 1. Procedutes for items identified in S Mcification or actual release of radioactivity -

6.2.A and any changes to such procedures shall be

Generating Staticas Emergency Plan =

reviewed and anproved ty the operatino Encineer and station emergency and abnorcal and the Nchnical Staff Sunervisor in the areas procedurcs.

of operation and fuel handling, and bv the MaintenanceAssistantSuperintendent$nd 5.

Instrumentation operation which could have an effett on.the safety of the the Technical Staff Suoervisor in the areas of plant maintenance, instrtrrent maintenance, I

facility.

and plant inspection.

Drocedures for ite s identified in Specification 6.2.B and any changes 6

Preventive and corrective maintenance to such procedures shall be reviewed and accroved operations which could have an effect i

by the Technical Staff Sunervisor and the Ed-chem en the safety of the facility.

Supervisor. At least one person accroving each of the above procedures shall hold a valid senior 7.

Surveillance and testing requirements..

operating license.

In addition, these procedures and changes thereto must have authorization by the Station Superintendent before being implenented.

131 e

e

-Q 0

DPR-2 2.

Work and instruction type procedures which ~

irplerant approved =inten:nce er codification precdures shall be approv.2d and cuthorized by the l

'4aintenance Assistant Superintendent where the written authority has been provided by the Station Superintendent. The " Maintenance /Fodification Procedure" utilized for safety related work shall be so a.cproved only if proccdcres referenced in the "y.aintenance/M;dification Procedure" have been approved as required by 6.2.A.

Procedures which 6 not fall within the requirements of 6.2.A or 6.2.B may be approved by the Department Heads.

D.

Tesoorary changes to procedures 6.2.A and 6.2.0 above :nay be cade provided:

1.

The intent of the original procedure is not altered.

l 2.

The change is approved by two cctbers 1

s J

of the plant er.anager. ant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

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3.

The change is documented, reviected by the Or. site Review and Investigative Function cr.d apprcved by the Station Superintendnet

_ ithin 14 days of implementation.

w E.

Drills'of the emergency proccdures described in Sc::ification 6.2.A.4 shall be condected quar'terly. Tnese drills will be planned so that during -the course of the year, coraunica-13 tion links are tested and outside agencies (Next page {s 138) are contacted.

L

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DPR-2

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MINUfyM ClllPT MK!1.T. C't -

g Condition condition of

, ren. o f T'en in Each Por.ition

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of one Non-Rad 1

1: nit Second Unit Third Unit Ili'.*._,,,, LO * '

Lic

, Men

.l Cold Cold

,___.S hu tdpwn Shutdown

.,1_.__,

3 5 ~

l Cold 3

5 1

.thutdown Refuel

_____1 COLD 6

Cold Above cold i

Shutdown Shutdown

_ _1 3

5 1

.V!tTfDOWN 5

Refuel Refuel 2

3 1

Re fuel Above Cold Shutdown 2

3 5.

1 Above Cold Above Cold

~ 5 1

Chutdbun 2

3' Shutdown i

O Re fuel Re fuel 2

4 5

1 P.EFUEL Re fuel

'Above Cold Shutdown 2

4

_5 l'

Above Cold Above Cold Sh q qn Shutdown 2

4 S

1 A'10VE COI4 Above Cold Above Cold F*lt!TDOWN Shutdown Shutdown 3

4 5

1

~i,SO '

. Licensed Senior Operator

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- Licensed Operator

" 6N--LIC

- Equipmcat Operators and !:<Tuipm'ent Att endants l

RAD HEN

- Rad-Chem Technician

- Shall r.ot operate units on which they are not licensed.

f Figure 6.1.1 i

6

Dresden Station Unit 2 Proposed Technical Specificaton Changes i

Revised Pages:

158 161 162 163 l

168 l

169 I

Deleted Pages:

159 160 4

[

i 4

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O 6.0 AERIMISTPATIVE COh'PROLS 6.1 Organization, Review, Investigation and Audit A.

The Station Suoerintendent shall have overall full-E.

Retraining and replacement training of Station time responsibility for safe operation of the facility.

personnel,shall be in accordance with Assi Curing periods when the Station Superintendent is

, N18.1.

Selection and Training of Nuclear Power unavailable, he shall designate this responsibility Pla"C Personnel. dated March 8, 1971.

to an established alternate who satisfies the ANSI N19.1 experience requirements for plant manager.

A training program for the Fire Brigade shall B.

The corporate management which relates to the operation be maintained under the direction of the of this station is shown in Figure 1-6 of CE-1-A 2ptcal Operating Engineer and shall meet or exceed Deport. The Division Manager, Mutlear Stations has the requirements of Section 27 of.he NFPA Code - 1975, except for Fire Br.3ade training 1

restonsibility for the Fire Protection Program, sessions which shall be held at least quarterly.

C.

We' normal functional organization for operation of the station shall be as shown in F.,gure 1-6 and Figure F.

Retraining shall be conducted 4 intervals not A of CE-1-A Topical Deport. The shift manning for the, station shall be as shown in Figure 6.1.1., %e Coerating Assistant Superintervlent, Oparating Engine?r' C.

The Review and Investigative

.: tion and the Shift Encineer, and Shift Foremen shall,have a Audit Function of activities attecting quality senior onerating license. The Fuel Handling Foreman during facility operations shall be constituted has a liInited Senior operating License. An Operat1ryl and have the responsibilitics and authorities outlined below:

Engineer will te responsible for implementation of the Fire Protection Program.

1.

The Supervisor of the Offsite Review and A fire brigade of at least 5 members shall be maintain'd.

Investigative Function shall be appointed e

on-site at all times. This excludes the shift crew by the Vice President of Construction, necessary for safe shutdown of the plant, and any Production, Licensing and Environmental, Affairs.

personnel required for essential functions during a The Audit Function shall be the I W 050f90*Y' responsibility of the Manager of Quality Assurance and shall be independent of operations.

U*

of the station management and operatirvi s f 1

et minirum acceptable levels as described 8.

-offsite neview and Investigative Funetten in MSI NIR.1, " Selection and Training of Nuclear Ibwyr Plant Personnel", dated varch 8,1971 with the exception of the Rad-Chem Supervisor who shall meet or exceed the cualifications of Padiation Protection. Manager of Rcqulatory Guide 1.8, Sep. ember, 1975. he individual dimim fu & es W hs%%

function and appoint a senior participant to provide appropriate direction, (11) filling the position of Administrative and Support,

Services Assistant Superintendent shall meet the miniaun select cach partict' ant for this function, p

acce^ntahle level for " Technical Manager" as described (iii) seicet a complement of enre than in 4.2.4 of ANSI N18.1 - 1971 or.c participant who co11cetively posaces s

background and qualifications in che 158 subject matter under review to provide

l

, y h.

CPR-19 MINU@t S11TFT Mfa:;11 :c ct_* g,

~ ~ '

Condition condition of No. of f/en in Each Por.ition Non-Rad of one

..Un it Second Unit Third Unit Lso*

Lo*t-Lic

, Men I

Cold Cold 1

Shutdown

_shutdoun 1

3 5

Cold

~

5' 1

Shutdown Refuel 1

3_

COLD Cold Above cold Ghutdoyin shutdown 1

3 5

1 f

JI!!TfDOWN 5

I

_ Refuel Refuel 2

3 1

Refuel Above Cold Shut _down 2

3*

5.

1 Above Cold Above Cold i

Chutdown 2

3

5 1

Ch'utd,own Re fue),_

Refuel 2

4 1

5 1

P.EFUSL Refuel

'Above Cold Shutdown 2

_5 l'

4

• f Above 'old Above Cold Sh_u_tdf._ n Shutdown 2

4 S

1 AnOVE COIS Above Cold Above Cold

_f,*Ilgg)WN Shutdown Shutdown

3. _

4 5

1

~~

~i,S'O' Licensed Senior Operator g-.

Licensed Operator

~50N LIC ^

Eqt'ipmeint Operators and !Muipment Attendants I

l

. RAD MEN Rad-Chem Technician

- 3 hall r.ot operato units on which they are not licensed.

l Figure 6.1.1 s0 2

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DPR-19 O

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(2) Proposed changes to proced;;res, c;uip-Off site Peview and Investigative ment or systems which involve an unreviewed a,

Function (Continued) safety question as defined in Section 50.59 10 CFR.

comprehensive interdisciplinary review coverage under this function (iv) independ-(3) Proposed tests or experiments which involve ently review and approve the findings and an unreviewed safety question as defined recontendations developed by personnel in Section 50.59 10 CFR.

performing the review and investigative function, (v) approve and report in a timely (4) Proposed changes in Technical Specifications manner all findings of noncompliance with or URC operating licenses.

HRC requirements and provide recomnendations to the Station Superintendent, Division (5) Noncompliance with NRC requirements, or of T

. Manager Nuclear Stations, Manager of nuality Assurance, internal procedures or instructions having Vice President of Nuclear Ooerations, and the Dcecutive.

nuclear safety significance, Vice President of Construction, Production, Licensing, (6) Significant operating abnormalities or deviations and Environmental Affairs. During periods when the Supervisor of the Offsite Review from nonnal and expected performance of plant and in,estigative function is unavailable, equipment that affect nuclear safety as referred he shall designate this responsibility to to it by the Onsite Review and Investigative an estBlished alternate who satisfies the Function.

formal training and experience requirements for the supervisor of the Offsite Review (7) Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notiff-and Insestigatise Function.

cation to the Commission.

The responsibilities of the personnel (8) All recognized indications of an unanticipated perfoming this function are stated below.

deficiency in some aspect of design or operation The Off site Review and Investigative of safety related structures, systems or components.

Function shall review:

(9) Review and report findings and recommendations

' c safety evaluations for 1) changes regarding all changes to the 6enerating Stations (1) to procedures, equipment or systems Emergency Plan prior to implementation of such as. described in the safety analysis change.

report and 2) tests or experiments corpleted under the provision of (10) Review and report findings and recomendations 10 CFR Section 50.59 to verify that regarding all items referred by the Technical such actions did not constitute an Staff Supervisor, Station Superintendent, l

unreviewed safety question.

Proposed Division Manager - Nuclear Stations and Manager changes to the Quality Assurance Program of Quality Assurance.

description shall be reviewed and approved by the Manager of Quality Assurance.

162

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o.-

o DPR-19 b.

Audit Functfen The Audit Function shall be the responsibility of the (S) Audit of the Facility Onergency Plan and Manager of Quality Assurance independent of the implementing procedures.

Production Department. Such responsibility is delc<pted to the Director of Quality Assurance for (6) Audit of the Facilit'y Security Plan and Operating and to the Staff Assistant to the Manager impicmenting procedures.

of Guility Assurance for maintenance quality assurance acti.ities.

U) Audit onsite and offsite reviews.-

Either shall approve the audit agenda and checklists.

(8) Audit of the Facility Fuel Protection Program and impicmenting procedures at least once per 24 months.

the findings and the report.of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits (9) Report all findings of noncompliance with NRC shall be perfonted to assure that safety-related requirements and recorrendations and results fur.ctions are covered within a period of two years of cach audit to the Station Superintendent, the Division Manager-liuclear Stations, Manager or less as designated below.

of Quality Assurance, the Vice President of %2 clear (1) Audit of the Confoncance of facility operation Operations, Director of Nuclear Licensing to provisions contained within the Technical and to the Dcecutive Vice President of CcEstruction Specifications and' applicable license con-Production, Licensing and Environmental Affairs.

ditions at.least once per year.

~

" Authority c.

(2) Audit of the adherence to procedures, training and qualification of the station staff at least The Manager of Quality Assurance reports to the I Vice Chairman and the S2pervisor of once per year.

the Offsite Review and Investigative Punction (3) Audit of the results of actions taken to reports to the Vice President of Nuclear correct deficiencies occuring in facility Operations. U.itSier the.stanager of Oualiti

~

equipment, structures, systems or methods Assurance or'the Supervisor of the Offsite Review of operation that af fect nuclear safety at,

end investigative Funct. ion has the authority to least once per six months.

order unit shutdown or request any other action which he deems necessary to avoir unsafe plant (4) ' Audit.of the performance of activities conditions.

required by the Quality Assurance Program to a:eet the Criteria of Appendix "B." 10 d.

Records CFR 50

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(1) Reviews, audits and recomendations shall be documented and distributed as covered in 6.1.G.1.a and 6.T.G.1.b.

163'

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DPR-19 6.2 Plant Operating Proce'dures A.

Octailed written procedures including 8.

Tests and experi=cnts.

applicable checkoff. lists covering items

. listed below sha'11 be prepared, approved, 9.

Procedure to ensure safe shutdown of th,e and adhered to:

plant.

10. Station Security Plan and implementing 1.

Normal startup, operation, and shutdown procedures..

of the reactor'.and other systems and ccrperents involving nuclear safet

11. Fire Protection Progrca implementation.

of the facility.

2.

Refueling operations.

B.

Radiation control procedures shall be main-tained, made available to all station personnel 3

3.

Actions to be'taken to correct specific and adhered to.

These procedures shall show and foreseen potential malfunctions of permissible radiation exposure and shall be syste.as or coreponents including respon>cs consist:nt with the requirements of 10 CFR

20. This radiation protection program shall be.

to alarms, suspected primary system leaks, and abnormal reactivity changes.

orge:fiacd to cces the requirements of 10 CFR 20.

4.

Emergency conditions involving potential' C. 1. Procedures for itists identified in Specification or actual relcase of radioactivity.

6.2.A and any changes to such procedures shall be

Generating Staticns Emergency Plan reviewed and anproved b/ *he (Yeratino Enoineer a

~

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and station emergency and abnorraal and the mechnical Staff Suoervisor in the areas procedurcs.

of operation and fuel handling, and by the 1

Maintenance Assistant Superintendent and 5.

Instrumentatjon operation which could the Technical Staff Supervisor in the I

~

have an effect on.the safety of the areas of plant maintenance, instrument maintenance, facility.

and plant inspection. Drocedures for itens identified in Specification 6.2.B and any changes 6

Preventive and corrective mitntenance to such procedures shall be reviewed and aoproved opcrations which could have an effect l

by the Technical Staff Suoervisor and the ' ad-Chem P

Supervisor. At least one person aporoving each on the safety of the facility.

of the above procedures shall Fold a valid senior 7.

Surveillance 'and testing requirements. -

operating license.

In addition, these procedures and changes thereto must have authorization by the Station Superintendent before being implemented.

~

168

DPR-19 2.

Work and instruction type pmcedures which a

trolecent approved..aintenance er codification i

pr:cadures shall be approved and cuthorized by the Maintenance Assistant Superintendent where the written

~

authority has been provided by the Station Superintendent. The " Maintenance / Modification Procedure" utilized for safaty rehted work shall be so approved only if proccdures referenced in the ..aintenance/E;dification Procedure" have been approved as required by 6.2.A.

Procedures v;hich do not fall within the requirce.ents of 6.2.A or 6.2.8 may be approved by the Depart.T.ent Heads.

I D.

Tenporary changes to procedures 6.2.A and 6.2.0 above may be nade provided:

1 The intent of the original procedure is not altered.

I 2.

Tha chenge is approved by tv:0 c:ce.bers cf the plant rr.anage:r. ant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

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3.

The change is documented, revie.:23 by the Or. site Review and Investigative Function cr.d apprcved by the Station Superintendnet within 14 days of irnplcmantation.

~

E.

Drills of the er.ergency prr,ccdures dcscribed in Sc::ification 6.2.A.4 shall be conducted quar'terly. Tnese drills will be planned so that during the course of the year, connunica-tion links are tested and outside agencies are contacted.

- 169 (next page is 175) h

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Dresden Station Unit 3 ll.

p, Proposed. Technical Specification Changes 1

a i'

I Revised Pages:

158.

161 162 1

I 163 f

168 I

169 Deleted Pages:

159 160 lI l

1}I; 2:

$l s

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4

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p I

k i,

f' it 9

c.

3. 4

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D 6.0 N*m:Innwrivn n Nm W:

DPR-25 6.1 Organization, Review, Investigation and Audit A

The Station Superintendent shall have overall full-E.

titre responsibility for safe operation of the facility.

Retraining and replacement training of Station

~

personnel shall be in accordance with ANSI During periods when the Station Superintendent is

, N18.1.

Selection and Training of h*uclear Power unavailable, he shall designate this resoonsibility

• Plant rersonnet, dated March 8, 1971, to an established alternate who satisfies the ANSI N19.1 experience requirements for plant manager.

A training program for the Fire Brigade shall B.

The corporate management which relates to the operation be maintained under the direction of the of this station is shown in Figure 1-6 of CE-3-A Tbptcal Operating Engineer and shall meet or exceed Report. The Division Manager, *Iuclear Stations has the requirements of Section 27 of the NFPA Code - 1975. except responsibility for the Fire Protection Program, for Fire Brigade training sessions which shall be held at least quarterly.

"Se normal f'metional organization for operation of the station shall be_ as shown in Figure 1-6 and Figure F.

Retraining shall be conducted at intervals not A of CE-1-A 'Ibpical Peport. The shift manning for the exceeding two years.

station shall be as shown in Figure 6.1.1.

The (barating Assistant Superintendsqt, Operating Engineer' C.- The Review and Iriestigative Function and th Shift Engineer, and Shift Foremen shall have a Audit Function of activities affecting quali senior operating license. The Fuel IIandling Forman -

during fact 11cy operations shall be constituted has a limited Senior Operatirg License. An Operattnq and have the responsibilities and authorities Engineer will to responsible for implementation of outlined below:

the Fire Protection Program.

1.

The Supervisor of the Of fsite Revicu and A fire brigade of at least 5 ner.bers shall be maintained.

Investigative Function shall be appointed on-site at all times. 'Ihis excludes the shift crew by the Vice President of Construction, necessary for safe shutdcwn of the plant, and any Production, Licensing and Environ 2catal' Affairs.

personnel required for essential functions during a The Audit runction shall be the fire emergency.

responsibility of the Manager of Quality i

Assurance and shall be independent of operations.

O' Oualifications of the station management and operating staff shall meet minimum acceptable levels as describad in ANSI NIR.1, " Selection and Training of Nuclear Tw?r Offsite Review and Investirative Tunction a.

nlant Personnel", dated trch 8,1971 with the exception of the Rad-Chem Supervisor who shall meet or exceed The Supervisor of the Offsite Review end the qualifications of Radiation Protection Manager of Investigative Function shall:

(1) provide Regulatory Guide 1.8, September, 1975.

e 1'ndividual directions for the review and Investigative unct! n and appnint a senior participan-filling the position of Mministrative and Support Services Assistant Superintendent shall meet the minimum select (iii) select a coraplement of enre thaneach pa acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971 or.c participant who collectively possess s

158 bac1ctround ar.d qualificacions in the subject matter under review to provide

l DPR-25 MINL%fM SHIFT MANNING CH/.RT 4

Condition Condition of No. of Men in Each Position of one Non -

Bad 14*'

1; nit Second Ur:it Third Unit L50*

Lic

, Men Cold Cold Shutdown shutdown 1

3 5

1 Cold l

.ihu tdown Refuel 1

3_

5 1

COLD Cold Above cold

{

Ghu t_doyin shutdown 1

3 5

1

.i R rt.*>O W N t

Refuel Refuel 2

3 1

5 Refuel Above Cold Shutdown 2

3 5.

1 i

Above Cold Above Cold Shutdown i

Shutdown 2

3' 5

1 Re fue]

Refuel 2

4 5

1 "EFUSL Re fuel

~Above Cold Shutdown 2

4 5

1 Above Cold Above Cold Shtitd_q n Shutdown 2

4 S

1 A".OVE COIS Above Cold Above Cold

.t'*ll!Tr> W N Shutdown Shutdown 3

4 5

1

'LSO ~

Licensed Senior Operator

'LO '

jjcensedOperator

$6N-LIC Equipment Operators and Dmipment Attendants l

l RAD HEN Rad-Chem Technician lihall r.nt operato units on thich they are not licensed.

Figure 6.1.1

=~

b

o DPR-25 O

O o

(2) Proposed changes to procedures, equip-a.

Offsite Review and Investigative ment or systems which involve an unreviewed Function (Continued) safety question as defined in Section 50.59 10 CFR.

comprehensive interdisciplinary review coverage under this function, (iv) independ-ently review and approve the findings and (3) Proposed tests or experiments which involve an unreviewed safety question as defined reconnendations developed by personnel in Section 50.5910 CFR.

performing the review and investigative function, (v) approve and report in a timely mann2r all findings of noncompliance with (4) Proposed changes in Technical Specifications or NRC operating licenses, NRC reqairements and provide reconuendations to the 5:ation Superintendent, Division l'anager Nuclear Stations, Manager of ouality Assurance, (5) Noncompliance with NRC requirements, or of internal procedures or instructions having Vice Presider.t of Paclear Ooerations, and the Dcecutive nuclear safety significance, Vice Presider.t of Construct' ion, Production, Licensing, and Dwironmental Affairs. During periods.

when the Supervisor of the Offsite Review (6) Significant operating abnormalities or deviations from nomal and cxpected performance of plant and in u tigative Function is unavailable, equipment that affect nuclear safety as referred he shall designate this responsibility to to it by the Onsite Review and Investigative an estalished alternate who satisfies the Function.

forral training and experience requirements for th( supervisor of the Offsite Review (7) Reportable Occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notifi-and Insestigative Function.

cation to the Commission.

The responsibilities of the personnel perforning this function are stated below.

(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation The Offsite Raview and Investigative of safety related structures, systems or components.

Function shall review:

(1) The safety evaluations for 1) changes (9) Review and report findings and recomendations regarding all changes to the 6enerating Stations to procedures, equipment or systems Emergency Plan prior to implementation of such as described in the safety analysis report and 2) tests or experiments

change, completed under the provision of 10 CFR Section 50.59 to verify that (10) Review and report findings and recomrandations regarding all items referred by the Technical such actions did not constitute an l

unreviewed safety question.

Proposed Staff Supervisor, Station Superintendent,

- Division Manager - Nuclear Stations and Manager changes to the Quality Assurance Program description shall be reviewed and approved of Quality Assurance.

by the Manager of Quality Assurance.

162

a Q

Q*

Q DPR-25 b.

Audit Ftmetfon_

The Audit function shall be the responsibility of the (5) Audit of the Facility Onergency Plan and Manager of Quality Assurance independent of the implementing procedures.

Production Ocpartr.ent. Such responsibility is delepted to the Director of Quality Assurance for (6) Audit of the Facility Security Plan and Operating and to the Staff Assistant to the Manager impicmenting procedures.

of Quility Assurance for maintenance quality assurance acti.itics.

(7) Audit onsite and offsite reviews.

Elt!.er shall approve the audit agenda and checklists.

(8) Audit of the Facility Fuel Protection Program and the finiings and the report.of each audit. Audits impicmenting procedures at least once per 24 months, shall be performed in accordance with the Company Qu=1ity Assurance Program and Procedures. Audits (9) Report all findings of noncompliance with NRC shOl be performed to assure that safety-related requirements and recomendatiens and results funct ions are covered within a period of two years of each audit to the Station Superintendcat, the Division Manager-Huclear Stations, Manager or icss as designated below.

of Quality Assurance, the Vice President of Nelect (1) Audit of the Conforinance of facility operation aperations, Director of ?:uclear Licensing to provisions contained within the Technical and to the Executive Vice President of Construction Specifications and' applicable license con-Prcxiuction, Licensing and rnvircrrental. Affairs, ditions at.least once per year.

~ c.*

Authority ~

(2) Audit of the adherence to procedures, training and qualification of the station staff at least The Manager of Quality Assurance reports to the once per year.

l Vice Chairman and the Sapervisor of the Of fsite Review ar.d ;nvestigative Penction (3) Audit of the results of actions taken to l

reports to the Vice President of Sclear correct deficiencies occurir.g in facility l

Co2 rations. Either d.e :sacer og e,m;ity equipment, structures, systems or methods Assurance or'the Supervisor of the Of fsite Review of operation that af fect nuclear safety at and inve,tigative Function has the authority to least once per six months.

order unit shutdown or request any other action which he deems necessary to avoid unsafe plant (r.) Audit of the performance of activities conditions.

required by the Quality Assurance Program to meet the Criteria of Appendix "B." 10 d.

Records CFR 50

~.

(1) Reviews, audits and recomendations shall be documented and distributed as covered

.in 6.1.G.l.a and 6.T.G.l.b.

~

163

t O

O O

DPR-25 6.2 Plant operating Prece'dures A.

Detailed written procedures including 8.

Tests and experiments.

applicable checkoff.Itsts covering items

. listed below sha'll be prepared, approved, 9.

Procedure to ensure safe shutdcwn of th,e and adhered to:

plant.

1.

Normal startup, operation, and shutdown

10. Station Security Plan and implementing of the reactor ~and other systems and procedures..

ccrpenents involving nuclear safety

11. Fire Protection Progra:a implementation.

of the facility.

2 Refueling operations.

B. " Radiation control procedures shall be main-tained, made available to all station persc nel 3.

Actions to be taken to correct specific and adhered to.

These procedures shall shev and foreseen potential malfunctions of permissibic radiatica exposure and shall be systems or components including responses consist:nt with the requirements of 10 CFR

20. This radiation protection program shall be.

to alarms, suspected primary system leaks, and ?.bnormal reactivity changes.

orgertiaci to cect the reqeiren:ents of 10 CFR 20.

4.

Emergency conditicns involving potential ~

C. 1. Procedures for items identified in Snecification or actual relcase of radioact%ity.

6.2.A and any changes to such procedures shall be

'C:nerating Stations Emergency Plan" reviewed and Epproved by the Operating Enginaer and station emergency and abnorcal and the "echnical Staff Supervisor in the areas

~

procedurcs.

of operation and fuel handling, and by the Maintenance Assistant Superintendent and 5.

Instrumentat on operation which could the Technical Staff Suoervisor in the have an effe t on.the safety of the areas of plant maintenance, instrumert maintenance, facili ty.

and plant inspection. Drocedures for items identified in Soccification 6.2.B and any changas 6

Preventive and corrective mai.tenance to such procedures shall be reviewed and approved l

operations which could have an effect l

by the Technical Staff Suoervisor and the Pad-Chesa on the safety of the facility.

Supervisor. At least one person approving each l

of the above procedures shall hold a valid senior

7. Surveillance 'and testing requirements..

operating license. In addition, these procedures i

and changes thereto must have authorization by the Station Superintendent before being implemented.

168

g

'h DPR-25 2.

Work and instruction type procedures which ir-plecent approved.T.cinten:nce er codification i

I precedures shall be approvad cnd cuthorized by the Maintenance Assistant Superintendent where the written authority has been provided by the Station Superintendent. The " Maintenance / Modification Procedurc" utilized for safety re13ted work shall be so approved only if proccdures referenced in the "?.aintenar.ce/E:dificatien Procedure" have been approved as rce.uired by 6.2.A.

Procedures which do not fall within the requirements of 6.2.A or 6.2.B may be approved by the Departs.cnt Heads.

D.

Temporary changes to procedures 6.2.A and.

6.2.0 above :nay be made provided:

1.

The intent of the original procedure is not altered.

2.

The change is approved by t>:0 ccchers of the plant rr.anagar. ant staff, at least i

one of whom holds a Senior Reactor i

Operator's License on the unit affected.

~

3.

The change is documented, revie.nd by the Onsite Reviett and Investigative Function j

cr.d apprcved by the Station Superintendnet within 14 days of irnplementation.

E.

Drills'of the e=argency prr,ccdures described in Sp:cification 6.2.A.4 shall be condocted

~

quarterly. Tnese drills will be planned so i

that during the course of the year, co rnunica-tion links are tested and outside agencies are CoRtacted.

169 (next page is 175)

1 Quad Cities Station Unit 1 Proposed Technical Specification Changes at I-

]

Revised Pages:

y 1

6.1-1 6.1-3 6.2-1

\\

l Deleted Pages:

Figure 6.1-1 Figure 6.1-2 Figure 6.1-3 1

New Page:

Figure 6.1-1 (was Figure 6.1-3)

'I

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l I

1 1

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ALPHA CCFP - 0000239 SAL ste J

QUAD-CITIES DPR-29 O

TECilNICAl,SPFCIFICATIONS APPENDIX A LIST OF FIGURES Numlier Title APRM Flow Reference Scram and APRM Rod Block Settings i

2.1-1 Peak LilGR vs. Core Thermal Power for a Limiting Total Peaking Factor 2.1-2 APRM Flow Bias Scram Relationship to Normal Operating Conditions i

2.1-3 Graphical Aid in the Selection of an Adequate Interval Between Tests 4.1-1 4.2-1 Test Interval vs. System Unavailability l

3.4-1 Standby Liquid Control Solution Requirements Sodium Pentaborate Solution Temperature Requirements 3.4-2 Maximuni Average Planar Linear ficat Generation Rate (hfAPLilGR) vs. Planar Average Exposure 3.5-1

.I 3.5-2 K,' Factor 3.6-1 Minimum Reactor Pressurization Temperature 3.12-1 Fire Detection Instruments 3.12-2 Sprinkler Systems q

CO Systems 3.12-3 2

Fire liose Stations 3.12-4 Chloride Stress Corrosion Test Results at 500-F*'

4.6-1 6.1-1 Minimum Shift Crew Ccxnposition i

e O

V

- QUAD CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS 0

6.1 OEGANIZATION, REVIEW, INVESTIGATION. AND AUDIT A. The Station Superintendent shall have overall full time responsibility tor safe operation of the facility. During periods when the. Station Superintendent is unavailable, he shall designate this responsibility to an established alternate who satisfies the.iN's! N!8.1 of March 8,1971 experience requirements fur plant manaf,ct.

%e ccriorate mnaqro.nt which relates to the onoration of thi'i station in chewn in Fiqure 1-6 of D.

CF.-1-A 'Ibpical Ivp)r t, %e ::ivision Punager, r:uclear Statinna has recpxwibility for the Fire

.j Protertion ProJrali.

We norrel functional organization for operation of the station shall be as chcun in Piqure 1-6 C.

{

l an! Piqure A of Ct:-1-A Spical Report. 'rha chift reanninq for tf c station chall be as chown in

'i rigua c 6.1-1.

%e qiriating Accictant Superintrrvient, O[eratirq e nineer, Shif t Iblinectn, and r

Shif t Foremen shall have a senior operatirvi licence. The tw1 Pandlirn Forcman han a limited ll Senior Orcrating t.icence. nn Maintenance Annistant Superintervient will be renrnnaible for the 8

impicmentation of tbn Fire Protection Prc9tara.

-l

% is excludes the A fire brio.vte of at leant 5 mctnbers chall be traintained on-cite at all tirma.

j chif t crew nececcary for nafe chutdown of the plant, anr1 any rerconnel rujuired for other ecsential functions durity a fire einergency.

Oualifications of tbc ntation mnagetrent and orv ratino staff chall meet minimu'n accontahic levels D.

as deacribrd in ANSI N18.1, "Selretion ani Training of Tu<:Imr rWor ricnt Perrtsnnel", dated rurch 8, M71 We P.ul-chem Supervir:or chall rect the crysirtrente of radiation prottetton ianaqer of Segulatory Gui& 1.9 W intividual fillinn tbc pr:ition ot' Mminictrattve and sunnet Services Accictant Sep rititer lar.t :. hall me et the minimtrn acceptable tevel for Technical Ftan>]er" as dcocrited in f;mtion 4.2.4 of M.31 r:18.1-1971, Retraining and seplacement training of Station personnel shall be in accordance with. ANSI N18.1," S l

E.

Training of Nuclear Power Pla it Personnel", dated March 8,1971.

A training program for the fire brigade shall be maintained under the direction of the Station Fire M shall maet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training sessio be at least quarterly.

F. Retraining shall be conducted at intervals not exceeding 2, years.

G. The Review and Investigative Function ard the Audit Function of activities affecting quality during facility ope tions shall be constituted and have the responsibihties and authorities outlined below:

1. The Supervisor of the Offsite Review and Investigative Function shall be appointed by the Vice Presid of Construction, Production,1.icensing and Environmental Affairs. The Audit Function shall be the responsibility of the Manager of Quality Assurance and shallbe independent of operations, Offsite Review and Investigative Function s.

Se surervisor of the Of fnite neview and Inve.tinative Function challs (1) govide directirm for the review anci invectiqative funr-tion and opinint a renfor participant to provile armpriate direction, (2) select each forticipint for thic function, (3) select a ccuplement of rure than one participant who collectively possens background and qtolifications in the subject rotter un!ct review to provide comrirrhensive inter-diciplinary review coverage uncler this function, (4) inciependently revi<w and approve the finrlitvin anl renr:nendations d<teloprd by terr:onnel performing the revicw and I

inwestiqative function, (5) approve and report in a timely manner all finrlings of noncompliance with rnC requircreents to the Station Superintervient, Division Manager Puclear Stations, Manager of Ouality Assurance, Vice President of fluclear Operations, and the Pxecutive Vice President of Construction, Prculuction, Licensing arul Pnviron-

}

mental Affairs. During terludn when the Supervisor of Offsite Deview and Investigative function is smavailable, be shall designate this recponsibility to an established alternate, who satisfies the formal training and experience requircenents for the S@ervisor of the Offsite Iteview and Investigative Etnction, 2 e responsibilities of the perm m1 rvrfor*inq thic for*im are ntattv1 bnicw, R e Offsite Peview and Investi';ativo Ibneti n uhall r. view:

1) The safety evaluations for (1) changes to procedures, equipment. or systems as described in the

' safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 6.1 1

+

act nm.m u

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_u.._rw

1. ~

~

~.

QUA D.CI's ll'S DPR-29

9) Report all findinos cf nonccepliance with IC requis creents and reccrrerxt: tier.s ard results of caen audit to the Stitton Sup:ria.ter. dent, the Division "anarer7aclear Stations, r'.anaqct of OJatity Assura cc, Vice Presidert of **uclear Onerations, Director of P. clear Licer.sina, and to the Oxu utive Vice President of Construction, Freduction, Licensirvj, aM Frviroraental Affairs.

i'. AL,thority l

'the Manager of CJality Assurance rerorts to the Vice Chairman and the Supervisor of the Offsite tuview and Investia.itive Function l

reports to the Viec President of M.x lest ro.rattenn. ritter the Manager of Cuality treurance or the Surervinor of the Wriite Rwies and Investigative PJnCtion has t.te authCrity to order ullt Shutdown i

or request any r-her action which he deems necessary to avoid unsafe plant conditions.

l d.

Records l

I) Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.C.I.a and 6.1.G.I.b.

1 i

2) Copies of documentation, reports,and correspeadence shall b : kept on IL at the s'a for..

e.

Procedures l

Written administrative procedures shall be prepared and mair tained for the offsite reviews and in.

vestigative functions described in Specifications 6.1.G.I.a.Thow procedures shall cover the following:

!) Content and method of submission of presentations to th: Supervisor of the Offsite Review and investigative Function.

l

2) Use of committees and consultants.

3) Review and approval.

O~.

4) Detailed listing ofitems to be reviewed.

5) Method of (1) appointing personnel,(2) performing reviews, investigations,(3) reporting findings and recommendations of reviews and investistions,(4) approving reports, and (5) distnbuting reports.

,,6) Determining satisfactory completion of action required based on approved findings and recom.

mendations reported by personnel performing the review and investigative function.

f.

Personnel

1) The persons, including consultants, performing the review and investigative function,in addition to the Supervisor the Offsite Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated:

a) liuclear power plant technology, b) reactor ope,ations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safety,

3) reactor safety analysis, h) instrumentation and control,

1) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.

6.13

i QUAD-CITIES DPR-29 MINIMUM SHIFT MANNit'G CHA'lT CONDITION OF ONE UNIT (No Fuel in Second Unit)

License Initial fuel Loading Cold Shutdown or Above Cold Catecory or During Refueling Refueling shutdown Shutdra.r Senior Operator License 2

1 1

Opera tor l

License 2

1 2

l Rad-Chem Technician 1

1 1

Non-Licensed (As Required) 1 2

l CONDITION OF SECOND UNIT (One, Unit at Hot Shutdown or at Power) l License Initial Fuel Loading Cold Shutdown or Above Cold j

Category or During Refueling Refueling Shutdown Shutdown Senior

• Operator License 2

2 2

Operator

• License 3

2 3

O 1

8aa-caem rechaiciaa i

i i

i Non-Licensed 3+ (As Required) 3' 4

l CONDITION OF SECOND UNIT (One Unit at Cold Shutdown or Refueling Shutdown)

License Initial Fuel Leading Cold Shutdown or Above Cold Category

'or During Refueling Refueling Shutdown Shutdown Senior

• Operator License 2

1 2

Operator

• License 3

2 2

l Rad-Chem Technician 1

1 1

.Non-Licensed 3+ (As Required) 3 3

• Assumes each individual is licensed on each facility. During initial fuel loading or during refueling, one senior engineer (limited license) will supervise fuel handling.

e I

FIGURE 6.1-1 MINIMUM SHIFT MANNING CilNRT l

. _ ~

i QUAD. CITIES DPR-29 io 6.2 PLANT OPERATING PROCEDURES A. Detailed written procedures including applicable checkoff lists co<cring items Ifsted below shall be prepared.

approved,and adhered to:

1.

Normal startup. operation. and shutdown of the reactor, and other systems and components in olving nuclear safety of the facihty.

2.

Refueling operations

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or componeatsin.

cluding responses to al.irms suspected primary system Icaks and abnormal reactivity changes.

4 Emergency conditions involving potential or actual release of radioactivity

" Generating Stations g

Emergency Plan" and station emergency and abnormal procedures.

i 5.

Instrumentation ope ation which could have an effect on the safety of the facility.

i g

i

6. Preventive and corrective maintenance operations which could have an effect on the ufety of the faci'ity.

7. Survei!!ance and testing requirements.

}

8.

Tests and experiments.

l 9.

Procedure to ensure safe shutdown of the plant.

i l

10. Station Security Plar. and implementation procedures.

II. Fire Protection Prog.am implementation.

7 B. Radiation control procedures shall be maintained, made available to all station personnel, and adhered to. These O'.

procedures shall show pernussible radiation exposure and shall be consistent with the requirements of 10 CFR 20.

This radiation protection pro.; ram shall be organized to meet the requiren:ents of 10 CFR 20.

t C.

1.

Procedures for iterns identiflei in Specification 6.2-A and any changes to such procedures I

shall te revirwed and aaproval ty the Conratity; Iwiineer and the 'rtchnical Staff Supervisor in the areas of operation and fuel handliry7, and by the ?'aintenance Assistant Superintendent and the Technical Staff Supervisor in the areas of plant unintenance, l

instrt: ment maintenarco, aryi plant inettetim. Prnentures tor items identified in Spccification 6.2.P aryl anv char *jes to such perceduren shall hn reviewed aryl anproved by the Technical Staff Suoervisor aM the IW1 Chem Supervisor. At least one perr:on auproving each of the above procedures chall hnid a valid senior operator's license. In addition, thcsc procMures and channes thereto, must have authorization by the Station Superintendent before Leing impic:rentei.

2 ttrk and ir.struction type procedures which Implernent approver! nointenance or mndification I

l proceduros shall be approval aryl authorized Ly the Klintenance Ansistant Superintendent where the written authority ha:; tren providol ly th<= Station Surx:rinte.> knt. The "BasintenanccMindification Procr< lures" utilizcd for sarcty-relatetl work t.tull to so nyovel only if procularon referonen) in the " Maintenance / Modification Proemiuro" have been approved as 5

I ecquirnl by (i.2.A.

Procivkirrn which do rot fall within thn rc<}uircecnts of 6.2.A or 6.".'.D may bc approval tr/ tle Dgartment !! cads.

D. Temporary changes to procedures 6.2.A and 6.2.A above may be made provided:

I. The intent of the original procedure is not altered.

2. The change is approved by two members of the plant management staff, at least one of whom holds a

~ Senior Reactor Operator's License on the unit affected.

3. The change is documented, reviewed by the Onsite Review and investigative Function and approveJ by the Station Supertntendent within 14 days ofimplementation.

E. Drills of the emergency procedures desenbed in Specification 6.2.A.4 sSall be conducted quarterly. These onlls

"' will be planned so that during the course of the year, communication links are tested and outside agencies are contacted.

6.21 I*

s.

4 k1; g.

I!

, t i

t ti Quad Cities Station Unit 2 Proposed Technical Specification Changes i

i Revised Pages:

v 6.1-1 6.1-3

t 6.2-1

i'I Deleted Pages:

Figure 6.1-1 Figure 6.1-2 Figure 6.1-3

.{

New Page:

Figure 6.1-1 (was Figure 6.1-3) l?

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4:

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,3 ALPHA coftr o 0000399 = Sat Ile 4

QUAD-CITIES DPR-30 i

TECHNICAL, SPFCIFICATIONS APPENDIX A LIST OF FIGURES Numl>er Title

,j 2.1-1.

APRM Flow Reference Scram and APRM Rod D!ock Settings 2.1-2 Peak LHGR vs. Core Thermal Power for a Limiting Total Peaking Factor i

l 2.1-3 APRM Flow Bias Scram Relationship to Normal Operating Conditions i

4.1-1 Graphical Aid in the Selection of an Adequate Interval Between Tests i

4.2 Test Interval vs. System Unavailability 3.4-1 Standby Liquid Control Solution Requirements 3.4-2 Sodium Pentaborate Solution Temperature Requirements 3.5-1 Maximuni Average Planar Linear Heat Generation Rate (hlAPLHGR) vs. Planar Average Exposure 3.5-2 K,' Factor

~

.I 3.6-1 Minimum Reactor Pressurization Temperature 3.12-1 Fire Detection Instruments 3.12-2 Sprinkler Systems CO Systems 3.12-3 2

Fire Hose Stations 3.12-4 4.6-1 Chloride Stress Corrosion Test Results at 500-F

6.1-1 Minimum Shift Crew Canposition 1

e i

~

O y

QUAD. CITIES DPR-30 6.0 AD5!!NISTRATIVE CONTROIS 6.1 OIMNIZATION. REVIEW, INVESTIGATION AND AUDIT A. The Station Superintendent : hall have overall full t!me responsibility nor eafe operation of the facility. During periods when the Station Superintendent is unavailable, he shall designat; this responsibility to an established

+

alternate who satisfies the AN!il N18.1 of Slarch 8.1971 experience requirements for plant manager.

D, De cerusrate tranw,"ont which relates to the oferation of thi9 clation in cMan in Figure 1-6 of CE-1-A 'nipical heinct. 'Ite Division runager, r:ucicar Statfore, has recronsibility for the Fire Protmtion PrnJr.w.

C.

The nortrol functional organization for operation of the station shall be as shown in Figure 1-6 j

anl rigure A of CI:-1-A 'P.:sical twinct, W chif t trannirvi for ti:e ctatfori chall be as r.hnwn in Figuie 6.1-1.

%e (per atinq k.qict ant Sup rintetylent, Olvratirq rMincer, Shif t IMinectn, and Shif t Ihremen shall have a senior operatirq license. The IW1 lbndling Forcmn han a limited -

Seniot Oteratini I,1cenac.

B" thintenance Annictant Sup rintenient wili be respxuible for the l

i impir%cntation of tbo Fire Protection Prcyram.

l A fire brigado *of at leant 5 rnembero chall to traintained on-nite at all tirros. S in excludes tho

.t l

chif t crew nececcary for Safe chuthn of the plant, aM any rerconnel rujuired for other essential functionn duriry a fire mergency.

l Oualifications of the ntation mnaqerrent and onerating staff nhall meet mininum accontat;le levels l

D.

as der.cribctl in NcSI N18.1, " Selection aM Traininq of t*ucloat IWor Flsnt Personnol", dated furch 8, 1971. We P.>1-Chem Sutcrviror nball rrect the r"Taircrrents of radi-tion protcction on.vjer of r<cquiatory Ou!Je 1.9 W inlividual fillirvi tbc p>cition ot A4ainistrattvc and Fur.nort Services Assistant Supfrir.tn tri.t d,all &c'. the minirrarn acceptchle level for "Tochnical Stanager" as described in Smtim 4./.4 of N.Si n1a 1-1971 l

Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1," Selection and l

E.

Training of Nuclear Power Plaat Personnel", dated Starch 8,1971.

A training program for the fire brigade shall be maintained under the direction of the Station Fire 5farshal, and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training sessions shall be at least quarterly.

F.

Retraining shall be conducted at intervals not exceedina 2. years.

G. The Review and Investigative Function and the Audit Function of activities affecting quality during facility opera-tions shall be constituted and have the responsibilities and authorities outlined below:

1. The Supervisor of the Offsite Review and Investicative Function shall be appointed by the Vice President of Construction, Production, l.icensing and Environmental Affairs. The Audit Function shall be the responsibility of the blanager of Quality Assurance and shall be independent of operations.

a.

Offsite Review and Investigative Function The Supervisor of the Of fsite neview and Inventiqative Itnetton shall: (1) provide dircetitur for the review and invectiqativo luretion and opinint a cenior p rticipant to preni le appropriate direction, (2) select each lotticipint for thic function, (3) select a cmplement of rure than com particimnt wtu) collectively pnenens background g

and ytalificationn in the subjmt matter un!ct tr' view to provide ctmpreh(naive inter-diciplin1ry trNiew coveraqo urvler thic function, (4) irsleprendently revir.w and approve the finlirqn and rectrurndationn <tovelopn1 by p trronel performing the review and i

investigative function, (5) apprrwe and report in a timely manner all findings of nonerntpliance with I'IC requiretr.cnto to the Station Superintendent, Division Pbnager I

Nuclear Stationc, Punaqcr of nuality Accurance, Vice Prenident of hy:Icar Operations, and the rxccutive Vice President of Conntruction, Production, I,1 censing arul Environ-

]

mental Affairs. During srriods when the Supervir:or of Offsite Peview and Investigative Function is unavailable, he shall designate this renponsibility to an established alternate, who satisfies the formal training and experience requirenents for the Sopervisor of the Offcite neview and Investigative Ibnction. W e responcibilities of the perrmnel Fr forHrvi thic funct im are statr<1 triow. We Offsite noview and Investigative Itnctico chall review:

1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR

..i.i

i a.a n%..

I' QUAD.CliIES DPR-30

9) Repet all findirx23 cf noncrrpliance ith 'TC requiremants and re<xrrerc. tiers ard retultc of caen ar11t to the Statson Sup:ria.tt. dent, the Division "anrer-P.aclear Statinr.s, "anavr of Caslity Assurs cc, f

Vice Presidet of *;uclear (Wrations, Director of tbclest t.icer s sN,

ard to the f.wxutive klee F"eaident of Con:truction, PrMuetion, LicenstrFJ, and Fr.VircrWntal Af fair 0.

Ai,thority i.

l

'the Manager of Ciality Assurance reprts to the Vice CMirfnan and the Supervisor of the Offsite k= view and Irwestiaativa Nnction l

reports to the Vice Presidart of Nuclear Co.ratiens. Fithor tre Mareger of 0;ality issurasce or the Sumevisor of the efilte Pavice r

and Investigatit1 Nnction has the authcrity to order u.ist shutdown or request any r-her action which he dee s necessary to avoid i

unsafe plant conditions.

1 l

d.

Records

1) Reviews, audits, and recommendations shall be documented and distributed as covered in 6.l.G.I.a and 6.1.C.I.b.

2) Copies of documentation, reports,and corre:pondence sha!! b:kept on fue at the s'a lor..

e.

Procedures

)

Written administrative procedures shall be prepared and maintained for the offsite reviews and in-1 vestigative functions described in Specifications 6.1.G.l.a.Those procedures sha!! cover the following:

l

1) Content and method of submission of presentations to the Supervisor of the Offsite Review and investigative Function.

1 i,

2) Use of committees and consultants.

3) Review and approval.

O

4) Detailed listing ofitems to be reviewed.

5) Method of (1) appointing personnel,(2) pe: forming reviews, investigations,(3) reporting findings and recommendations of reviews and investigations,(4) approving reports, and (5) distributing reports.

,,6) Determining satisfactory completion of action requir d based on approved findings and recom-mendations reported by personnel performing the review and investigative function.

f.

Personnel

1) The persons, including consultants, performing the review and investigative function in addition to the Supervisor the Offsite Review and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated; e) nuclear power plant technology, b) reactor operations, c) utility operations, j

d) power plant design, c) reactor engineertng, f) tadiological safety, I

3) reactor safety analysis.

h) instrumentation and control,

1) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.

6.1 3

QUAD-ClilES DPR-30 MINIMUM SHiri MANNING CHA'IT

~'

CON 3tT10N OF ONE UNIT (No Fuel in Second Unit)

License Initial fuel LoJding Cold Shutdown or Above Cold Catecory or Durinq Refuel tnq Refueling Shutdewn T.hy t ee.o Senior Operator License 2

1 1

Opera tor j

License 2

1 2

l Rad-Chem Technician 1

1 1

Non-Licensed (As Required) 1 2

I CONDITION OF SECOND UNIT (One Unit at Hot Shutdown or at Power)

License Initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutc:an 1

Senior

• Opera tor License 2

2 2

Operator

• License 3

2 3

h l

Rad-Chem Technician L 1

1 1

Non-Licensed 3+ (As Recuired) 3*

4 CONDITION OF SECOND UNIT l

(One Unit at Cold Shutdown or Refueling Shutdo'an)

License initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutd:en j

Senior

• Operator License 2

1 2

Operator

• I License 3

2 2

l Rad-Chem Technician 1

1 1

.Non Licensed (As Required) 3 3

I

• Assumes each individual is licensed on each facility. During initial fuel loadir.g c-during refueling, one senior engineer (limited license) will supervise fuel hansling.

l FIGURE 6.1-1 MINIMUM SHIFT MAfiN!NG CilART

~..

QUAD. CITIES DPR-30 sb 6.2 PLANT OPERAIING PROCEDURES A. Detailed written procedures including applicable checkoff lists covering items listed below shall be prepad.

approved.and adhered to:

1.

Normal startup operation, and shutdown of the reactor, and other systems and components invohr; nuclear ufety of the facihty.

2.

Refueling operations j

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components c..

cluding responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

j 4.

Emergency conditions involving potential or actual iclease of radioactivity

" Generating Stat:.r.s l

Emergency P;an" and station emergency and abnormal procedures.

5.

Instrumentation ope ation which could have an effect on the safety of the facility.

g

6. Preventive and corrective maintenance operathns which could have an effect on the safety of the fae00

7. Suncillance and testing requirements.

8. Tests and experiments.

9.

Procedure to ensure safe shutdown of the plant.

10. Station Security Plan and implementation procedures.

II. Fire Protection Prog.am implementation.

i B. Radiation control procedures shall be maintained, made available to all station personnel. and adhered te. T5.ne procedures sha!! show permissible radiation exposuri and sha!! be consistent with the requirements of 10 CFR %.

This radiation protecticn pro.; ram shall be organized ta meet the requiren:ents of 10 CFR 20.

'~

t C.

1.

Procedures for itms identifieri in Specification 6.2-A and any i:banges to such procedures I

shall be reviewed and aaproved by the (ocrating Twsinear and the Technical Staff Supervisor in the areas of operation anr! fuel handling, and by the "sintenance Assistant Superintende.t and the Technical Staff Supervisor in the areas of plant maintenance,

{

instru: tent raintenanea, and plant inq octinn.

n ncedures for items identifiu! in r

Spccification 6.2.n arvi any char 1c3 to such prncolures chall he reviewed anel anproved by the Technical Staff Suocrvisor and the Rad Chem Supervicor. At least one percon aoproving each of the above proccdures shall hold a vali' cenior operator's license. In addition, these ptcccdures and chancles thereto, rnust ha.e authoriration by the Station Superintendent before being implementui.

2 tbrk and ir.struction type procelures whlah implement approved mintenance or m,dification kl procedures chall to approvwi arvi authorised by the M11ntenance Ancistant Superintendent where the written auttmrity hw frcn providal tr/ the. Stat ion Super inte.v t..nt. The "Mainterunce.*hitfication Procoluren" utilizul for car..ty-related Sorn :.h ill to m a,Trovei only if pro:nbren refer < rrol in t he *ttainterunce ?hlificat. inn rancedure" tuve teen art. roved as I

requirntis

.2.A.

Pocnluren which th rnt f all within t te rnjuirtwnts of 0.2.A or 6..11 ay r4 r

approvnt ty tia.* 14u tnent lkata.

D. Temporary changes to procedures 6.2.A and 6.2.A above may be made provided:

I

1. The intent of the oririnal procedure is not attesed.

2. The change is approved by two members of the plan. management staff. at least one of whom he:2s a Senior Reactor Operator's License on the umt atteeted.

3. The change is documented reviewed by the Onsite Review and Investigative Function and approseJ by the Station Superintendent within 14 days ot' implementation.

E. Drills of the emergency procedures described m Specification 6.2.A.4 shall be conducted quarterly. Thew 2 /h will be planned so that during the coune of the year commumcation links are tested and outside agenoes are contacted, t

6.21