ML20129C239

Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage

ML20129C239
Person / Time
Site:	Dresden, Quad Cities
Issue date:	10/16/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20129C178	List: ML20129C174 ML20129C192 ML20129C239
References
NUDOCS 9610230260
Download: ML20129C239 (23)

Text

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DRESDEN 11 DPR 19 Amtndm:nt No. 141 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)

6.2 Proceduras and Proarams i

A. Written procedures shall be established, implemented and maintained covering the f

activities referenced below:

/

1. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; The ' morgency Operating Procedures required to implement the requirements of 2.

i NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33; i

3.

Station Security Plan implementation:

4.

Generating Station Emergency Response Plan implementation:

5.

PROCESS CONTROL PROGRAM implementation; 6.

OFFSITE DOSE CALCULATION MANUAL implementation; and l

7.

Fire Protection Program implementation.

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PR-19 j

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oppe, -rw, &fom e CONTROLS ICont'd

.3. 3.I f Technical Re typprafhjLAA Ch ' )L')

Procedures required byMci~ficationj and other procedure.s which affect nuclear safety, as determined by the @ Station Manager, and cha

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l es ther_eto, shall be j

reviewed as follows prior to implementation, except as noted in gecMicatierr61Q I

h Each procedure or procedure chance sholl be independently reviewed by a j

4.

qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change.' This review shallinclude a determination of whether or not additional cross-disciplinary reviews are i

necessary. If deemed necessary, the reviews shall be performed by review l

personnel of the appropriate discipline (s).

gay,jjjjec]

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Individuals performing these reviews shall meet the applicable experience requirements of ANSI N18.1-1971, Sections 4.2 and 4.4, and be approved by the Station Manager.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, c,

Plant Emergency Operating Procedurp and changes thereto shall be submitted to the'Onsite Review and1nvestigative Function for review and approval prior to c

4 implementation.

[

c/. h Review of the procedure or procedure change willinclude a determination of whether or not an unreviewed safety question is involved. This determination 4

i will be based on the review of a written safety evaluation prepared by a j

qualified individuafor documentation that a safety evaluation is not required.

Onsite Review, Offsite Review and Commission approval of items involving unreviewed safety questions shall be obtained prior to station approval for j

implementation.

The[epartmenthad approval authority shall be as specified in station f

C.

procedures.

-f.

Writtsn records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with(SpeciJtestierL6.5.AD CACO l

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p.

h Editorial and typographical changes shall be made in accordance with station procedures.

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3.3-Temporary changes to procedures (6.Mbo3may be made provided:

4 A. h The intent of the original procedure is not alteredy,

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DRESDEN, DPR-19 i

A ment No. 11 ADMINIS BA 19FtONT

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ff, The change is approved by two members of the plant management staff, at

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l least one of whom holds a Senior Reactor Operator's License on theJ nit

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affectogg

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The change is documented, reviewed, and approved in accordance with 3,3, (Eg=ME074$within 14 days of implementation.

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Drills of the emergency procedures described in Specification 6.2.A.4 shall be 1

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conducted at the frequency s ecified in the Generating Station Emergency Plan.

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These drills will be planned so that during the course of the year, communication i

links are tested and outside agencies are contacted.

i

, 6.3 Action to.be Taken in the Event of a REPORTABLE EVENT; in Plant Operation 1

I I

Any REPORTABLE EVENT shr'l be promptly reported to the Sits Vice President or his i

designated alternate. The ii.

't shall be promptly reviewed by the Onaito Review and i

j investigative Function and a v aate report for each reportable event shall t's preparsd f

j in accordance with the requirteents of Specification F s.B.

h 6.4 Action to be Taken in the Event a Safety 1.imit is Exceeded if a safety limit is exceeded, the reactor shall be shut down immediately and reactor f

j operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Site Vice President or his designated alternate. The incident shall be reviewed by the Onsite and Offsite Review and investigative Functions j

and a separate report for each event shall be prepared in accordance with Specification 6.6.B.

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3.l0 Plant Operating Records J,lo.f h ' Records and/or logs relativedthe following items shall be kept in a manner convenient for review and shall be retained for at least five year @

goy LocafED To THE WN'

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DRESD DPR-19 Amendmen o.

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l 6.0 ADMINISTRATIVE-CONTROLS _(Cont' d. ))

x and periods of operation at each power level.

Records of normal plant operation, including power levels

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A h Records of principal maintenance activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety.

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Records and reports of eportabledhLs 6 liid!Q, y' h Records and periodic checks, inspection and/or cal brationsor tkTec4mic erformed to verify thegurveillancet(equirements

(_ec on+of;tFe) Specification @are being met.

equipment failing to meet surveillance requirements and the l

correctiva action taken shall be recorded.

e. h Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

f, h Records of radioactive shipments.

p. %

Records of ph sif tests and other tests pertaining to nuclear safet Specification $

4' h Records of changes to procedures required byhety, as determine[

and other procedures which affect nuclear sa by e p n Manager.

g Shift Enginee ogs.

3 j, h By product material inventory records and source leak test results.

'3,/v.2 Records and/or logs relative to the following items shall be j

recorded in a manner convenient for review and shall be 1

retained for the life of the plan g c2.,

Substitution or replacement of principal itas of equipment pertaining to nuclear safety.

.fr.

Changes made to the plant as it is described in the Safety Analysis Report.

C, h Records of new and spent fuel inventory and assembly j

histories.

te d, h Updated, corrected, and as-built drawings of the plant.

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l DRESDEN II DPR-19 Amendment'No. 82, 86 97, 105 q

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[6.0 ADMINISTRATIVECONTROLS_(Cont'd[

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Records of plant radiation and contamination surveys.

-f, h Records of off$ site environmental monitoring surveys.

J. h Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20.

h h<

Records of radioactivity in liquid and gaseous wastes released to the environment.

h Records'of transient or operational cycling for those

.A,

components that have been designed to operate safely for a limited number of transient or operational cycles.

g, h Records of individual staff members indicating qualifications, experience,trainigndretraining.

d. h Inservice inspections of the reactor coolant system.

J. % Minutes of meetings and results of reviews performed by-x c

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the Off4 site and On(site Review { unctions. gJ/Qgd.isge) t q

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Records for EnvironmentaLQualifiratiop which are covered under the provisions of {aragraph 6J,

M M TIb RE0 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the NRC unless otherwise noted.

A.

Routine Reports 1.

Startup Report T

A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an

/ gV'7 operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of gEt.oc N fuel that has a different design or has been manufactured 7o 7df ph/TN.

by a different fuel supplier, and (4) modiTications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of the tests identified in the FSAR and shall in general include a dest.: :ption of the measured values of the operating conditions or characteristics obtained g

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DRESDEN lli DPR 25 Amendment No. 135

[ 6.0 ADMINISTRATIVE CONTROLS ICont'd.)

6.2 Procedures and Proorams

/

A. Written procedures shall be established, implemented and maintained covering the activities referenced below:

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1.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1973; 2.

The Emergency Operating Procedures required to implement the requirements of f

NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of

\\,

Generic Letter No. 82-33; j

3.

Station Security Plan implementation; 4.

Generating Station Emergency Response Plan implementation; i

5.

PROCESS CONTROL PROGRAM implementation:

6.

OFFSITE DOSE CALCULATION MANUAL implementation; and y

7.

Fire Protection Program implementation.

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No 135 j

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6.0 ADMINISTRA7WE CONTROLS (Cont'dp,

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.3.3.1 h, Technical Review and Control or-ryfgrwrica.ft c kafc5)

S Procedures required'by3Specahcsitionh.

nuclear safety, as determined by the Stationj[d other procedures which affe an l

anager, and changes thereto, shall be reviewed as follows prior to implementation, except as noted(InJ0ecdecattorEff@

a..

/ Each procedure or procedure change shall be independently reviewed by a l-qualified individual knowledgeable in the area affected other than the individual l

who prepared the procedure or procedure change.' This review shalf include a determination of whether or not additional cross-disciplinary reviews are necessary. If deemed necessary, the reviews shall be performed by theVrevie, w personnel of the appropriate discipline (s).

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f,, - h Individuals performing these reviews shall meet the applicable experience requirements of ANSI N18.1-1971, Sections 4.2 and 4.4, and be approved by the Station Manager.

c.

Applicable Administrative Procedures recommended by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the Onsite Review and investigative Function for review and approval prior to

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l implementation.

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cl. h Review of the procedure or procedure change willinclude a determination of whether or not an unreviewed safety question is involved. This determination will be based on tg review of a written safety evaluation prepared by a qualified individush or documentation that a safety evaluation is not required.

i Onsite Review, Offsite Review and Commission approval of items involving unreviewed safety questions shall be obtained prior to station approval for implementation.

e. h Thegepartmentgead approval authority shall be as specified in station procedures.

l f'

Written records of reviews performed in accordanc be prepared and maintained in accordance witgpecIriestisnrs.AgD

,. ej ed,to,ia, and typog,a,hical changes shail beWce, dance with st procedures.

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Amendepenth. 35 x

ADMjNISTRATf@, CONTROLS ICont l

g jglj g,3 3.3.1 @ Temporary changes to procedures

. 4bov may be made provided:

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The intent of the original procedure is not alteredj8f@

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2, The change is approved by two members of the plant management staff, at least one of_ hom holds a Senior Reactor Operator's License on thoffnit affecte h The_ change is documented, reviewed, and approved in accordance with c

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. k, oitication 6.2.5)within 14 dayr. of implementation.

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3 D.

Drills of the emergency. procedures described in Specification 6.2.A.4 shall be j

l conducted at the frequency specified in the Generating Station Emergency Plan.

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These drills will be planned so that during the course of the year, communication l

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links are tested and outside agencies are contacted.

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l 6.3 Action to be Taker. !r. ine Event of a REPORTABLE EVENT in Plant Operation f

Any REPORTABLE EVENT shall be promptly reported to t% Site Vice President or his i

designated alternate.' The incident shall be promptly reviewed by the Onsite Review and

]

Investigative Function and a separate report for each repostah:e event shall be prepared

)

f in accordance with the requirements of Specification 6.6.B.

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6.4 Action to be Taken in the Event a Safety Limit is Exceeded h

if a safety limit is exceeded, the reactor shall be shut down immediately and reactor l

l operation shall not ne resumed until authorized by the NRC. The conditions of shutdown l

shall be promptly reported to the Site Vice President or his designated siternate. The incident shall be reviewed by the Onsite and Offsite Review and investigative Functions and a separate report for each event shall be prepared in accordance with Specification 6.6.B,

/

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u.__- m smms-g-3.lc Q Plant Operating Records J,lo. ) h Records and/or logs relativs in the following items shall be kept in a manner I

convenient for review and shall be retained for at least five years [

h Records of normal plant operation, including power levels and periods of q,

operation at each power level.

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g ([ Records of principal maintenance activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety.

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C. h Records and reports ogrePortable f]nd at vent 3

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Records and periodic checks, inspection and/or calibrati s

performed to verify theifurveillanceJequirementsM_on(IonJ) l v~

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the(d'; Specifications $' are being met.

All equipment failing to me t Turve111ance requirements and the corrective action taken shall be recorded.

e.

6.

Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

p, h Records of radioactive shipments.

l Recordsofphysiftestsandothertestspertainingtonuclear 2,

safety.

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gmtu eekie.J r

ju % Records of changes to* procedures required by4Specificationf

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and other procedures which affect nuclear safety, as determ by the Station Manager.

l f, h Sh h

eeMpt'ogs.

l j~ h ) By-product material inventory records and source leak test

results, f

3. lv. 'l Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for tne life of the plant.

g,hSubstitutionorreplacementofprincipalitemsofequipment l

pertaining to nuclear safety.

i f,,hChangesmadetotheplantasitisdescribedintheSafety Analysis Report.

C.$Reckrdsofnewandspentfuelinventoryandassemblyhistories.

@W@

c), h Updated, corrected, and as-built drawings of the plant.

e, h Records of plant radiation and contamination surveys.

t, RecordsofoffMiteenvironmentalmonitoringsurveys.

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6-6'

s' N DRESDEN III DPR-25

,7

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75,

,92,100)

Amendmen+ #

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j 0 ADMINISTRATIVE' CONTROLS (Cont'd.))

,hRecordsofradicbonexposureforallplantpersonnel, including all contractors and visitors to the plant in accordance with 30 CFR 20.

i k, h Records of radiou_civity in liquid and gaseous wastes released to the environment.

[ h Records of transient or operational cycling for those components that have been designed to operate safely for a limited number of transfer.t or operational cycles.

j.

Records of individual staff members indicating qualifications,' experience,trainigndretraining.

jg, hInserviceinspectionsofthereactorcoolantsystem.

J ' h Minutes of meetings and results of reviews pe y

(

the Offgsite and On)(site Review FunctigM~Lra5 Md g

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MM, RecordsforEnvironmentalqualif a on which are covered undertheprovisionsofgragrap 6. f>.-v~~~

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e 6.6 REPORTING REQUIREMENTS QMYK e c4,u./c4.8 6 ecsy./cct

/

In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the NRC unless otherwise noted.

A.

Routine Reports 1.

Startup Report l

A summary report of plant startup and power escalation i

testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving s

a planned increase in power level, (3) installation of gs.T fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that ggtoc4 TEP may have significantly altered the nuclear, thermal, or

'T7> TN@

hydraulic performance of the plant.

The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained 3

during the test program and a comparison of these values j

4' with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any

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Amendment

1 QUAD-CITIES l

DPR-29 6.2 PROCEDURES AND PROGRAMS -

A.

Written procedures shall be established, implemented and maintained i

covering the activities referenced below:

1.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, I

2.

The emergency operating procedures required to implement the i

requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33, 3.

Station Security Plan implementation,

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4.

Generating Station Emergency Plan implementation, 5.

PROCESS CONTROL PROGRAM implementation, 6.

OFFSITE DOSE CALCULATION MANUAL implementation, and 7.

Fire Protection Program implementation.

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i NOT BGlocGTE D T T~"E P AfR

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/VoT RELoareo ro TM PGTR -

6.2-1 Amendment No. 135

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QUADhtTIES I

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fr.nhns a fr.y

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3.3

-PH00E00RES-AND-PROGRAMS p k nue h

[B.,NEEEM s

3,3, h '

Technical Review and Control aAn s rea-AJ s

Procedures required by3 pecificat au and other procedures which j

S affect nuclear safety, as determi,ad

)y le Station Mana thereto, other than editorial or typographical changes, ger, and changes s all,be reviewed as o] lows i

to-implementation,.except as..noted in Spetj(ficatrotD i

.D.:

3, 3, 2 w

< x a ' h Each procedure or procedure change shall be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or procedure change. This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.

If deemed necessary, the

-t reviews shall be performed by the qualified review personnel of the appropriate discipline (s).

f' Individuals performing these reviews shall meet the applicable experience requirements of ANSI 18.1, 1971, Sections 4.2 and 4.4, and be approved by the Station Manager.

Applicable Administrative Procedures recommended by Regulatory Guide c'

l.33, Plant Emergency Operating Procedures, and changes thereto shall i

be submitted to the Onsite Review and Investigative Function for review and approval prior to implementation.

c W' h Review of the procedure or procedure change will include a b

determination of whether or not an unreviewed safety question is involved. This determination will be based on the review of a written safety evaluation prepared by a qualified individual (s), or documentation that a safety evaluation is not required. Onsite Review, Offsite Review and Commission approval of items, involving unreviewed safety questions shall be obtained prior toftation i

approval for implementation..

I e'

The[epartment ad approval authority shall be as specified in station procedures.

y h.

Written records of reviews performed in accordance with this

@pecification J al.]iemenW.)be prepared and maintained in accord s

h isite RjvRrgl

{ feil Q

/. h Editorial and typographical changes shall be made in accordance with station procedures.

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QUADyITIES

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.2PROCEDURESJyIDPROGRAMS(ContinuedT) re p u. ire d 373I

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3 7 s

- ~~.s 3,3,( h Temporary changes to procedures 6. gA may be made provided:

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The intent of the original procedure is not altered.

g2 The change is approved by two members of the plant management l)icense on the unit affected.s aff, at least one of whom holds a Senior R f

c h ($p AMicaHiiiT@within 14 days of implementation.

l The cha e is documented, reviewed, and approved in accordance with (

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E.

Drills of the emergency procedures described in Specification shall be conducted in accordance with the GSEP manual.

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f QUAD-CITIES l

DPR-29 6.3 REPORTABLE EVENT ACTION 1

l A.

The following actions shall be taken for Reportable Events:

1.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.

2.

Each Reportable Event shall be reviewed by the On-Site Review Committee, and the results of this review shall be submitted to the Off-Site Review and Investigative Function and to the Site Vice President.

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6.3-1 Amendment No. 163 l l

QUAD-CITIES DPR-29 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately, and

)

reactor operation shall not be resumed until authorized by the NRC. The l

conditions of shutdown shall be promptly reported to the Site Vice President or his designated alternate. The incident shall be reviewed by the Onsite and Offsite Review and Investigative Functions and a separate report for each occurrence shall be prepared in accordance~ with Specification 6.3.A.I.

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N O T ]E L o C /YTED To THE pHM,

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@ T R El0&Gr6D To D/E p t/7g _

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l IN-6.4-1 Amendment No.163

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Dal Oye,J}ceo,J

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IES 3

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6.5 PLANT % RATING RECORDS

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Records and/or logs relative to the following items shall be kept in a -

l manner convenient for review and shall be retained for at least 5 years:

R h Records of normal plant operation, including power levels and l

periodsofoperationateachpowerlevelg

/,,

Records of principal maintenance hactivities, including inspection and repair, regarding principal items of equipment l

i pertaining to nuclear safetg, M

c, y Records,and_ reports of reportable events. @ K A,

occurrenc, es@)

>afety-limi t)

~

d S.

Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance require ts @of fkTub'c.4 QectTDn-43QheTOphecifications@are being me 1 equipment I

failing to meet ~ surveillance requirements and t orrective action taken shall be recorde e.

Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.5 @,

f, Recordsofradioactiveshipment$.

p h Records of physif tests and other tests pertainin g uclea W j

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safetyp, gjr[gui,e ; py.z skho-ETe. c

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Records;Df changes to operating procedure f

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(.,q o f,e r p r o c esyre; v4 ;cer ape e r muc neae n ye tg as j,

ngineers' log h.

Sh d e ley"sn in, fry #Ac e

w g.

Byfroduct material inventory records and source leak test results.

3, J o. 2.

Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of

(

the plant:

(

Substitution or replacement of principal items of equip pertaining to nuclear safetyp,

[..

Changes made to the plant as it is described in the c,

Records of new and spent fuel inventory and assembly historiesg, c/,

Updated, corrected,andas-builtdrawingsoftheplanti f

e. [

Records of plant radiation and contamination surveysy,

k Recordsofoffsiteenvironmentalmonitoringsurveyp,

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j,54 AmendpeY No, 11)

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/m QUAD-)DITIES OPR-29x y,

Records of radiation exposure for all plant personnel, including all contractorsandvisitorstotheplant,inaccordancewith10CFR20),

},,

Records of radioactivity in liquid and gaseous wastes released to the environmentp.

Records of transient or operational cycling for those components that j'

have been designed to operate safely for a limited number of transient oroperationalcyclesp.

d.

Records of individual staff members indicating qualifications,

/

A experience, training,andretrainingp, M.

Inserviceinspectionsofthereactorcoolantsystem$,

j, {T Minutes of meetings,and results pf r nction hud1 G per_ formed by_the iews (gnQ

/ffsite and phsite yeview i.

,gmsI.,gespyfue)

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Records for Environmental Apalification which are covered under the provisions of(paragraph 6.J7.

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AmendmekNo.1

s DPR-30 6.2 PROCEDURES AND PROGRAMS b

A.

Written procedures shall be established. Implemented and maintained covering the activities referenced below:

(

1.

The applicable procedures recommended in Appendix A of Regulatory

)

Guide 1.33, Revision 2 February 1g78, 2.

The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33, 3.

Station Security Plan implementation, 4.

Generating Station Emergency Plan implementation, 5.

PROCESS CONTROL PROGRAM implementation, 6.

OFFSITE DOSE CALCUATION MANUAL implementation, and k

7.

Fire Protection Program implementation.

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g E L o c a RED To THE QGTRi

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ART R Ela cnTED To T"' V#

6.2-1 Arendment No. 131 w--

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QUADyC1 TIES f

amJ f vs. ~ s DPR-30 2.3 % stocedure5m Mra (on{iAM Vr

, DELETED) 3.3.I g Te h cal Review and control a nanas hwcal ProceduresrequiredbyApecificationf6.. A and other S

Station Manager, and changes thereto, other th or typographical changes, shall be reviewed a toimplementationexceptasnotedin{pecffhsfollowsJ]rior I F C2.D :

ct,

Each procedure or procedure change shall be independently reviewed by a qualified individual 3,33 knowledgeable in the area affacted other than the individual who prepared the procedure or procedure change.

whether or not additional cross-disciplinary review are necessary.

be performed by the qualified review personnel of th appropriate discipline (s).

/f,

Individuals performing these reviews shall meet the applicable experience requirements of ANSI 18.1, Manager. Sections 4.2 and 4.4, and be approved by the Station

1971, C

Applicable Administrative Procedures recnemanded by Regulatory Guide 1.33, Plant Emergency Operating Procedures, and changes thereto shall be submitted to the Onsite Review and Investigative Function for review and approval prior to implementation, cd.. -

Review of the procedure or procedure change will' include a determination of whether or not an unreview safety question is involved.

This determination will be based on the review of a written safety evaluation prepared by a qualified individual (s),

that a safety evaluation is not required.or documentation Review, Offsite Review and Commission appr Onsite prior to station approval for implamantation.

p 6.bA Thehepartmentkaadapprovalauthorityshallbeas n

specified in station procedures.

f, M Written records of reviews performed in accordance with F

this specification shall be prepared and maintained in accordance with Q Review 2raqiiiEements?q.__

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)

'A.

Editorial and typographical changes shall be made in )

m accordance with station procedures.

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N (Amendmen

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QUAhCITIES DPR:30 h[2 PROCEb h RAMSj Continued))re

,7 ad 'b 3-N V

3. 3. 7.

9 Temporary changes to procedures 6..

.A ve any be made provided:

q., b The intent of the original procedure is not altered.

dr. 'b The change is approved by two members of the plant management N

ficenseontheunitaffected. staff, at least one of whom holds a Se

,(SpjEW4catid6~EC)within 14 days of implementation.T C

3'3'1 E.

Drills of the emergency procedures described in Spectftcation 6.2.A shall be conducted in accordance with the GSEP manual.

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A)o7~ gfL c> c n TED To 7'H E Q M T R.

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QUAD-CITIES DPR-30 6.3 REPORTABLE EVENT ACTION A.

The following actions shall be taken for Reportable Ev'nts:

e 1.

The Comunission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.

2.

Each Reportable Event.shall be reviewed by the On-Site Review Comunittee, and the results of this review shall f

be submitted to the Off-Site Review and Investigative Function and to the Sit.e Vice President.

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Y Alo ' R w cHTED To THE @ k 7~R.

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( oc. p TE D TO 05 ?N

~W 6.3-1 Amendment No. 159 e~

~ _ _.

QUAD-CITIES DPR-30 N

6.4 ACTION TO BE TAKEN IN TEE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down inmediately, and reactor operation shall not be resumed until authorized by the NRC.

The conditions of shutdown shall be promptly reported to the Site Vice President or his designated I

alternate.

The incident shall be reviewed by the Offsite and Onsite Review and Investigative Functions and a separate report for each occurrence shall be prepared in accordance with

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Specification 6.3.A.1.

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f O L ATE D 1b THE AA Y-

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8 4~1 Amendment No. 159

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Ouad-Neo 378 3&

P u 1(he.m h&e t o r 4 f

?. /o (sf t****u.tra canep Records and/or logs relative to the followinD items shall be kept in a manner conventent 3.Io.l -

for review and shaii be retained for at ieast s yearo a,. h Records of norinal plant operatten including power levels and pertods of operatten at each poner level.

h Records of principal main'enancehttivities. including inspection and repatr.

ff.

t

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regarding principal items of eeutpment pertaining to nuclear safety.

C. gh Records and reports of reportable events,fidj sfbit [vr pacel2 ect A 4,

1 c J,

,$hs surveillance requirements (t_pectientenJ/or cattbra jons plege-Ene Cn 4 of the $ pecification ar Records and pertedic checks, ins orme o verify that Apl1 ewipment failing tp meetTurTelliance requtrements and the corrective actten taken shall be recordedil.

e,h Records of changes made to the equipment er reviews of tests and esperisents to camely with IR CFR 50.59.

i 4,p Records of radioactive shipments.

[ 'p@] gcgof changes to operating procedures. gyR

k. C 4 J regv.ir o"r g,

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,,, g of h e r grocedgrej j,ft)shftjpngineers' leg Q

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f. hRgroduct matertal inventory records and source leak test results.

g p,, () Records and/or logs relative to the following tiens shall be recorded in a manner convenient for review and shall be retained for the life of the plantp ;

cc, [

tutton er replacement of prtacipal itens of eeutament gtainingjo nuclear O

yS.Q e (*W 0

jr, Changes made to the plant as it is described in the j

C, Records of new and spent fuel inventory and assembly histortes, g, h Updated, corrected, and as-butit drawings of the plant.

C, [ Records of plant radiation and contamination surveys.

f, h Records of offstte environmental monitoring surveys.

)', p) Records of radtation exposure for all plant personnel including all contractors and

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vistters to the plant. in accordance with 10 CFR 20.

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Records of radioactivity in liquid and gaseous wastes released to the environment, f'

- Records of transient or operational cycling for those congonents that have been destpned to operate safely for a Itmited numeer of transient or operational cycles, g'

1.t. Records of individual staf f members indicating qualifications. superience. training,

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and retraining.

,A, T Inservice inspections of the reactor coolant system: and f,

sults of reytews f

AteAsfmeeat'~s.anynatonsgg=m} performed by thef site arid tew

.A.(

Records _f,ar I vironmental Oualtf tcation which are covered under the provisions of

($afattyph 6.1.

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