ML19338D571

Proposed Tech Spec Changes Re Implementation of TMI-2 Lessons Learned Category a Items

ML19338D571
Person / Time
Site:	Dresden, Quad Cities
Issue date:	09/10/1980
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19338D569	List: ML19338D568 ML19338D571
References
NUDOCS 8009230466
Download: ML19338D571 (29)

Text

.

ATTACHMENT I Dresden Statior Unit 2 OPR-19 Proposed Technical Specification Changes Revised License Pages:

4 Revised Technical Specification Pages:

44 45 158 161 New Page:

44a 8 U U 9 2 3 0 /(40-1

_t I

( DPR-19 3.-

1.

The licensee shall' maintair. in ef fect and fully implement all provisions of the Commission-approved physical security plan, including amendments'and thanges made pursuant to the authority Am. 42' of 10 CFR 50.54(p). The approved security plan consists of 2/23/79 10 CFR 2.790(d) information, collectively titled, " Security Plan for the Dresden Nuclear Power Station," dated November 18, 1977, as revised May 19, 1978; May 27, 1978; July'28, 1978; and February 19, 1979.

J.

Systems Integrity The licensee shall implement a program to-reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as. low ~as' practical levels. This program shall include the following:

1.. Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.

Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

K.

Iodine Monitoring The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concen-tration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel, j

2.

Procedures for monitcring, and 3.

Provisions for maintenance of sampling and analysis equipment.

4 4.

This license is effective as of the date of issuance and shall ex-pire. eighteen (18) months from said date, unless extended for good cause shown, or upon the. earlier issuance of a superseding operating license.

'l i

FOR THE ATOMIC ENERCY CO?DfISSION

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G14_. 0. )~.

~

j Peter A. Horris. Director f

I m._.,

4

Enclosure:

Appendix' A ~ Technical Specifications Date of Issuance: DEC 2 21969

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DPR-19 TABLE 4.2.1 (cont)

Instrumeat Instrument Channel Functional Test (2)

Calibration (2)

Instrument check (2)

ISOLATION CONDENSER ISOLATION 1.

Sterm Line High Flow (1)

Once/3 Months None 2.

Condensate Line liigh Flow (1)

Once/3 Honths None jlPCI ISOLATION 1.

Steam Line liigh Flow (1)

Once/3 Honthe Hone 2.

Steam Line Area liigh Temperature Refueling Outage Refuelin'g Outage None 3.

Low Reactor Pressure (1)

Once/3 Honths None 1

REACTOR BUILDING VENTILATION SYSTEM VIOLATION AND STAhouY CAS TREATHENT SYSTEM INITIATION 1.

Ventilation Exhaust Duct Radiation (1)

Once/3 Honthe Once/ Day Honitors 2.

Refueling Floor Radiation Monitors (1)

Once/3 Months Once/ Day STEAM JET-air EJECTOR OFF-CAS ISOLATION 1.

Radiation Monitors (1) (3)

Once/3 Honths (4)

Once/ Day CONTAINHENT HONITORING 1.

Pressure a.

-5 in. lig to +5 psig Indicator Hone Once/3 Months Once/ Day b.

O to 75 pair; Indicator None Once/3 Months None 2.

Temperature None Refueling Outage Once/ Day 3.

orywe!!-T;ros Differential None Once/6 Months (two None Pressure (5)(6) channels op'erable)

(0-3 paid)

Once/Honth (one channel operable) 4.

Torus Water.v, vel (5)(6)

None Once/6 Months a.

+25 in. Wtde Range Indicator l

b.

18 in. Sight Class SAFETY / RELIEF VALVE MONITORING l

t 1.

Safety / Relief Valve Position Indicator (7)

None Once Per (Acoustic Monitor) (8) 31 Days 44

DPR-19 LU TABLE 4.,2.1 (con.)-

Instrume2t

~

Instrument Channel Functional' Test (2)

Calibration (2)

. Instrument Check'(2)

~

2.

Safety / Relief Valve Position None Once every "Once Per 31 Days:

' Indicator (Temperature 18 months Monitor) (8)

(

3.

. Safety'. Valve Position Indicator (7)

None Once Per.31. Days

(.\\coustic Monitor)-(8) 4.

Safety 1 Valve Position. Indicator None Once every Once Per 31 Days 18 months

.(Temperatute Monitor) (8)

L NOTES:

6 1.

Initially once per month until exposure, hours (M as defined on Figure 4.1.1) ia 2.0 x 10 ; thereafter, according to. Figure 4.1.1 with an interval not less than one month nor more ths.: three months. The compilation of. instrument. failure rate. data ma'y include data obtained from other Boiling Water.

Reactors for which the same design instrument operates in an'enviroument similan to that of Dresden Unit.-3.

2.

Function test calibrations and instrument checks are not required when'these instruments are not~re-quired to be operable or.are tripped. Functional tests shall be performed before each.startup'with a.

required frequency not to exceed once per week.. Calibrations shall be performed during each starcup or during controlled shutdowns with a required frequency not to exceed once per week. Instruuent

~

checks W il be performed at least once per week.

Instrument checks.shall.be performed at least once i

per day dut;ng those periods when the' instruments are required to be operable.

~

3.

This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel. See-Note 4.

4.

These instrument channels will be-calibrated using simulated electrical signals once every three.

months.

In' addition, calibration including the sensors will be performed'during each refueling outage.

3.

5.

A minimum of two channels is required.

6.

From and af ter the date that one of these parameters

(...either drywell-torus differential pressure or torus water level indication) is reduced to one indication, :.ontinued operation is not permissible beyond. thirty da~ys, unless such. instrumentation'.is sooner made operable.

In.the event that ali indica-

. tions of these paraineters (...eithei. drywell-torus dif ferential, pressure or torus water level) is dis-abled and such indication cannot be: restored.in six (6) houre, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty four hours.

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TABLE 4.2.1 (c:ct) pop _19 N(YTES:

7.

Functional tests will be conducted before startup at the end of each refueling t.utage or af ter maintenance is performed on a particular Safety / Relief Valve.

8.

If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however, if the reactor is in a shutdown condition, it may not be started up until all position indication is restored.

In the event that all position indication is lost on one or more valves and auch indication cannot be returned in thirty days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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F

6TO ADMINISTRATIVE CONTROLS p

f 16.1 l Organiz'a' tion,' Review,[ Investigation and Audit

.y.

A. [The Station Superintendent.'shall have overall E.

Retraining and-replacement training 'of Station-

~

'I full-time responsibility.,for. safe operation of personnel shall be in'accordance'.with ANSI N18.1, the facility..During pe'riods when'the Station-

" Selection and Training of Nuclear _ Power Plant..

9SuperintendentEin unavailable,,he.shall'desig-Personnel,'? dated March 8,1971'.

nate-this responsibility to an estab1' 'ed alternate who satisfies the ANSI N18.1 exper-A training program for the fi:c brigade'shall be

ienca

requirements for plant manager.

. maintained under the direction of the operating Engineer and'shall meet or exceed the requir~ements?

B. 5The corporate management:which relates to.the of Section'27.of the.NFPA Code - 1975, except;forl operation of this' station' is shown in Figure fire brigade training sessions which'shall be-held

~

6.1.1.

at least quarterly.

C. ~The normal functional organization for opera-F.

Ret. raining shall be conducted at intervals not ex- '

tion of the station. sh'all. be as shown in ceeding two years.

Figure 6.1.2. ;The shift: manning for the station shall be as:shown-in' Table 6.1.1.

G.

The Review and Investigative' Function and the Audit Function of activities affecting quality during y !

. D.. Qualifications of the station management and facility operations'shall be constituted and have the.

operating' staff sh'all meet minimum acceptable responsibilities and authorities ~ outlined below:

levels as described ~in ANSI N18.1, " Selection ji

.and. Training of1 Nuclear. Power Plant Personnel,"-

1.

The Supervisor of the Offsite Review and Investi-L dated March 8, 1971 with the exception of the gative Fenction shall be appointed by the Vice i

Radiological Chemical Supervisor President of Construction-, Production, Licensing,'

,who shall meet or exceed the qualifi-and Environmental Affairs. -The Audit Function-cations of Regulatory Guide 1.8, September, 1975 shall be the responsibility of the Manager.of and

• the Shif t.. Control Poom Engineer who shall Quality Assurance and shall be independent of' I

have-a. bachelor's degree or equivalent in'a operations.

scientific or engineering discipline with speci-fic training in plant design, and response and a.

Offsit.e Review and Investigative' Function

. analysis of the: plant for transients and acci-i '

denta'. - The individual filling the position ~of The Supervisor of the Offsite Review'and In-Administrative Assistant shall meet the minimum vestigative Function shall:

(i) provide acceptable. level for " Technical Manager" as de-

-directions for the' review and investigative-scribed in 4.2.4 of ANSI N18.1 - 1971.

function and appoint a senior participant to provide appropriate direction. (ii) select'

[

A fire brigadefof.at least'5 members shall,be each participant for this function, (iii)-

. maintained on-site at'all: times..This excludes.

select a' complement.of more than one parti '

the shift crew necessary for safe shutdown of cipant who collectively possess background the plant and any personnel ~ required for.essen-and' qualifications in the subject matter-

~

tial. functions during a fire emergency.

under review to provide

• The ' Shift Control Rocxn Engineer requirementLwill be 158'

.,eff.ective 6/1/81...

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TABLE 6.1.1

' MINIMUM SHIFT MANNING CHART #

i:

9 CONDITION. I CONDITION OF-t NO. OF MEN IN EACH POSITION NON-

. RAD

.OF ONE

-lLIC.

+

i LS0*

SCRE i LO*

NEN i

UNIT ~

~ SEC')ND UNIT THIRD UNIT

.- t s Cold Shutdown.

Gold Shutdown 1*

-0 3

i 5

1-l l

t j.

1**[O~

Cold Shutdown-Refuel 3

5 l

1 t

1 lj t-COLD

.! Cold ',hutdown Above Cold 1

1 3

5 j

p' 8, ;

1 1

~

Shutdown i

[

j

['

J SHUTDOWN 2**;g.

o 3

I 5

1 l:

-Refuel Refuel r

i 4

l Refuel Above Cold 2

1 3

5 1

I I

L Shutdown' i

}

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l 4

g-l Above Cold i

Above Cold 2

l 1

3 5

1 t

g r

I l

Shutdown Shutdown I

Refuel Refuel 2

0 i

4 5

1 I

1 REFUEL Refuel Above Cold 2

1 4

5 1

Shutdown f

I 4

5 1

Above Cold Above Cold 2

1 l

-Shutdown Shutdown l

P,,

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t 4

5 1

-l l ABOVE COLD

Above Cold Above Cold 3

1 g

SHUTDOWN Shutdown Shutdown SCRE

- Shift Control Room Engineer

-LSO

- Licensed Senior Operator-

LO

-Mtensed Operator

-NON-LIC. - Equipment-Operators-and Equipment Attendants

' RAD MEN - Radiation. Protection Men

'O

'- Shall not operate units on which they are not licensed.

J**

-- Does not' include thel licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling,'. supervising CORE OPERATIONS.

~

---Shift' crew composition may be 1ess.than the minimum' requirements for a-

~

. period of-time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />'in order to accommodate unexpected absence lof~on duty' shift crew members provided-'immediate action is

~.aken to ' restore the 'shif t crew composition to within the minimust re-

)

-quirements..of Table l.6.2.2-li 1

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-ATTACHMENT II.

Dresden Station Unit 3' DPR-25'

. Proposed Technical Specification-Changes

. Revised License.Pages:

-A New License Page:

5 Revised Technical Specification Pages:

44 45 158-161 New Page:

44a i

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d)

• E

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- DPR-25 A

b 3.

LF. iEqualizer Valve:Restri-tionu' 2

t Am. 5 -

.The valves.in the equalizer: piping between the recirculation 1

8/29/75 loops shalf be closed at all.tites during: reactor operation.

G.

The licensee may proceed with and'is required to complete the modifications identified in Paragraphs 3.1.1:through 3.1.23 of-

.the NRC's Fire Protection Safety-Evaluation (SE)' dated March,-

Am.33

.1978 on the' facility. All modificationi, are to be completed 23/22/78

-by:startup fo11owinglthe 1979: Unit 3 refueling' outage; In a:

1 addition,-the' licensee shall submit the additional.information-

~

identified in-Table 3.1.of this SE in accordance with the 4

jL schedule contained therein. In the event these' dates for sub-

[

mitts 1 cannot be met, the licensee'shall submit a report, ex-plaining the circumstances, togetherlwith a revised schedule, l:

y b

H.

The licensee shall maintain-in effect and' fully. implement all

[

' provisions of the Commission-approved physical security plan, i

f including. amendments and changes made pursuant to the authority y

Am. 38 of 10 CFR 50.54(p). 'The approved security plan consists of

[

2/23M9 10 CFR 2.790(d) information, collectively titled, " Security 1

Plan for.the Dresden Nuclear Power Station," dated November 18, 1

1977;1as revised May '19,1978; May 27,1978; July 28,1978; and :

February 19,'1979.'

I.

Systems Integrity The licensee'shall implement e program to reduce leakage from systems outside con _tainment that.'would or could contain highly radioactive fluids'during a serious transient or accident to as low as practical levels.' This program'shall include the following:

1.

Provisions establishing preventive maintenance and periodic visual inspection' requirements, and

-2.. Leak. test requirements for each system at a frequency not

[

.to exceed refueling cycle intervals.

?,

e t

J.-

Iodine Monitoring b

The licenseelshall implement a program which will ensure the

~

capability to accurately determine-the airborne iodine concen-g l

tration'in vital; areas.under accident conditions. This program shall include.the-following:

li i4' 1.: Training of personnel;.

^

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2. " Procedures for monitoring, and

3..Prr.isions for maintenance of sampling and analysis' equipment.

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' '.DPR-25 I

,. 'This license is effective-as of the date of issurance and shall ex-pire at midnight on October 14, 2006..

i' FOR THE ATOMIC ENERGY COMMISSION o

t t -

Peter A. Morris, Director

~

Division of Reactor Licensing

+

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Inclosure:

Appendix A - Technical Specifications

.-}.

Date of Issuance: JAN 121971

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- TABLE 4.2.11(cont);

-DPR-25; Instrument.

' Instrument' Chantiel Functional Test (2)

Calibration (2)'

Instrument" Check:(2)i

-ISOLATION CONDENSER ISOLAT SON ~

C 1.

Steam Line High Flow:

'(1)

Once/3 Months None 2.-

Condensate'Line High Flow (1)

Once/3 Months-None

~

. HPCI ISOLATION Lt.

Steam Line.High Flow.

(1)

Once/3 Months None 4

42.. Stease Line Area High Temperature

. Refueling Outage Refueling Catage.

None.

33. Low Reactor' Pressure (1)

Once/3 Honths

- None REACTOR BUILDING VENTILATION SYSTEM' VIOLATION AND STANDBY CAS TREATHENT SYSTEM INITIATION

21. IVentilationMNieustDuctRadiation

-(1)

Once/3' Months Once/ Day.

Monitors 2.

Refueling Floor Radiation Monitors

'(1)

Once/3 Nonths Once/ Day-STEAM JET-air EJECTOR OFF-CAS ISOLATION 1.

Radiation Monitors (1) (3)

Once/3 Months (4)

Once/ Day

.CONTAINNENT HONITORING

1. ' Pressure a.

-5 in. Hg to +5 psig Indicator None Once/3 Months-Once/ Day i-

. b~.

0.to 75 psig Indicator None Once/3 Months" None s

2.

Temperature None Refueling Outage Once/ Day 3.

Drywell-Torus Differential None Once/6 Months (two None 1

Pressure (5)(6) channels.opferable)

]'

(0-3 paid)

Once/ Month (one channel operable) 4.

Torus Water Level (5)(6)

None Once/6' Months a.

+25 in. Wide Range Indicator b.

18 in. Sight-Class 1

SAFETY / RELIEF VALVE MONITORING 1.

Safety / Relief Valve Positian Indicator (7)

None Once Per (Acoustic Monitor) (8) 31 Days i;

44

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'l TJullE 4.2.1 (cont)

Instrument R

Instrument Channel Functions! Test (2)

Calibration (2)

Instrument' Check (2) 2.

Safety / Relief Valve' Position None Once every.-

Once Per.31' Days

Indicator (Tempes4dere 18 months Monitor) (8)

'3.

Safety Valve Position Indicator (7)

None Once Per 31 Days-(Acoustic Monitor) (8)

'4.

Safety Valve Position Indicator Mose Once every Once Per 3.*

.:ays 18 months

.(Temperatute Monitor) (8) a e

MDTES:

6 Initially once per month until exposure, hours (M as defined on Figure 4.1.1) is 2.0 x 10 ; thereafter,-

1.

according to Figure 4.1.1 with an_ interval not less than one month nor more than three months. 'The~

cocpilation of instrument failure rate data may include data obtained from othar Boiling Water' Beactors for which'the same design instrument. operates in an environment similar to that of Dresden-Unit 3..

Function test calibrations and instrument' checks are not required when these instruments are not re-2.

, quired to be operable or are. tripped. Functional tests shall be performed before each startup with a

' required frequency not to exceed once per week. ' Calibrations shall be performed during each startup or during controlled shutdowns with a required; frequency not to exceed once per week.-

Instrument 4

checks shall be performed at least once per week.

Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operable.

This instrumentation is excepted from the functional test definition..The functional test will consist

?

3.-

See Note 4.

of injecting a simulated electrical signal into the measurement channel.-

These instrument channels will be calibrated using simulated electrical signals'once every three 4.

In addition, calibration including the sensors will be performed during each refueling outage.

months.

5.

A minimum of two channels is required,

.From and after the date that one of these parameters (...either drywell-torus differential pressure j -

6.

or torus. water level indication) is reduced to one indication, continued operation is not permissible

'In the event that all indica-beyond thirty days, unless such instrumentation is sooner made operable.

i tions of these parameters (...either drywell-torus differential pressure or torus water level) is dis-abled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the-reactor shall be in a cold shutdown condition in twenty four hours.

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TABLE 4.2.1 (cont)

DpR-25 4i NOTES:

7.

Functional tests will be conducted before startup at the end of each refueling outage or af ter maintenance is performed on a particular Safety / Relief Valve.

.8.

If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however, if the reactor is in a shutdown condition, it may not be started up until all position indication is restored.. In the event that all position indication is lost on one or more valves an(

such indication cannot be returned in thirty days, an orderly shutdown shall be initiated, and the.eactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 3

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'6)0 d ADMINISTRATIVE CONTROLS

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,1 (6fl[ Organization, Review',(Investigationand'Auditc

.u.

, - a

'm,

-A.: LThe.. Station Superintendent shall;have overall' E. ' Retraining and replacement. training-of, Station'*

1 full-timeiresponsibility'for._ safe. operation of

.personnelshall.bein'accordance:withANSilN18$1h dh-

.theafacility., During periods ) hen the: Station.

" Selection r.nd Training of Nucle'ar PowerfPlantj,

p L Superintende'nt in unavailable,-he'shall desig-Personnel'". dated March 8, 1971 inate'this' responsibility:to an established

,,, [

c La1 ternate whofsatisfie~s the ANSI N18.1:exper-A training program for.'th'eIfire brigade?shall?be, aence'requhrements-for: plant manager.

' maintained under'the' direction of!the Operating; E

n A

Engineer and shall meet or' exceed theircquiremente( '

B.- Tliefcorporace' management-which relates to the-of Section'27-of'theLNFPA Code.-_1975, exceptDfori fire-brigade.traininginessions-which'aliall[be'heldl :.

operation.of.this' station.is'shown in Figure

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.6.1.1.

at?least quarterly.; '

"~~

n C.

The normal ~ functional organization-for opera-F.

Retraining.shall'be conducted'at' intervals notnex-c

~

tion'of the~ station shall be as'shown in~'

ceeding two years..

Figure 6~.1.2. "The.shiftLaanning:for therst'ation shallibelas 'shown in Table 6.1.1.

C.

The Review and. Investigative Functionz and the/ Audit t

F Function of activities. affecting qualityfduring

D.

Qualifications l of.the. station management and facility operations shall'be constitutedLand have the" operating staff shall meet minimum acceptable responsibilities _.and authorities' outlined below:

.c

.'levela as described'in ANSI N18.1, " Selection

'and2 Training.of Nuclear % Power Plant! Personnel,"

1.

The Supervisor of:the.0ffsite) Review'and/Investi '

G dated March:8";1971 with the exception of the gative -Functico shall 'bc" appointed:by the Vice '

Hadiological Chemical' Supervisor-President of' Construction,~Troduction,LLicensing,

who shall' meet or; exceed the qualifi-and:EnvironmentalLAffairs. The Audit Function cations of Hegulatory Guide 'l.8,' September; 1975 shall be.the responsibility of?the.Manageriof-

.and.

• the Shif t - Control' Poom Engineer who shall Quality Assurance and shall be independent of"

~

have a' bachelor's degree or equivalent in a operations.

. scientific or engineering discipline with speci-a.

Of f site Review and - Investigative Function:

fic training in plantidesign,' and.r'esponse and

. analysis-of the p.lant' for: transients and.acci-g.

dent s.- The ' individual filling Llic position o'f The Supervisor of the'Offsite'Iteview?and'In -

Administrative Ass ~istant shall meet the minimum vesti^gative Fun"ction'shall: ;(i)cprovidel

,{

acceptable. level for !' Technical Manager" as de-directions for.the revie; and investigative' scribed in 4.2.4'ofLANSF N18.1 - 1971.

function'and appoint'a ' senior' participant toJ provide appropriate direction, (ii) selec't

_ A fire-brigade' of.atcleast :5.meibers shall be each-participant for this.funt. tion,.'(iii) maintained on-site at all times'. LThis excludes' select a complement of more than'one parti "

tt2 shift' crew necessarynfor safe shutdown of-cipant.who-collectively' possess, background 2 the plant.and'any personnel. required'for'essen-and. qualifications.in the" subject matter tial functions during.a fire emergency, under. review tol provide,

~

sj

• ihe Shift Control Room Engineer requirement will be c, ',

158

effective;6/1/81'.

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.DPR-25.

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.T E '621.1

MINIMUM ' Si1IFT ' MANNING CHARTf p,

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C0!OITION 1

-CONDITION OF-NO. CF EN IN EACH 20SITION j, -OF-ONE NON-RAD

.I UNIT

SECOND UNIT

' THIRD UNIT LS0*

SCRE ~,-.

.lLIC.

' MEN LO*

L-i j

Cold Shutdown Cold Shutdown 1*

O-3 5

1 l

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]ColdShutdown

. ) 1** ],

0 3

5.

1 Refuel-i l

g j.. !

COLD i

l l Cold Shutdown.

Above Cold 1

1 3

I 5

1 Shutdown t

SHUTDOWN-l Refuel

_[

Refuel 2**

O 3

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i

[-

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l Reftel Above Cold 2

l 1

3 I' 5 i

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Shutdown i

i i

if Above Cold Above Cold 2'

1 3

5 1

1[;.

I i

Shutdown-Shutdown o

h

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0, i-4 5

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i REFUEL Refuel Above Cold 2

1 4

5 1

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1 Above Cold Above Cold 2

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- Shif t Control Room Engineer LSO

- Licensed Senior Operator..

LO'

- Licensed' Operator u

.NON-LIC. - Equipment Operators and Equipment Attendants RAD MEN :- Radiation, Protection Men-

0'

ShA11'not operate units on which they are not licensed.

p

-:Does not' include the' licensed Senior Reactor Operator or Senior Reactor F

Operator Limited to Fuel Handling,' supervising CORE OPERATIONS.

f.

- Shift crew-composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpacted absence of-on' duty' shift crew members provided.immediate1 action is'

+

~taken-to restore the' shift crew composition to within the minimum re-

'quiremerts'of: Table 6.2.2-1.-

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-ATTACHMENT'III

-QuadLCities-Station Unit 1-

.DPR-29

= Proposed Technical. Specification Changes Revised License-Page:

5

- New License Page:. 6 Revised"Technica1LSpecification Pages: - 3. 2 / 4._2 -15 3.2/4.2-15a 3.2/4.2-18 g

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The Ifcensee may proceed with' and is requi ed to complete the modifications identified in Paragraphs 3.1.1 throu h 3.1.13

_Am. 52' of the f1RC's Fire Protection Safety Evaluatien'(SE, dated July 27,1979 for the facility. These modifications will-be:

8/16/79 sompleted'in;accordance with the schedule in Table 3.1 of the SE and supplements thereto.

In addition', the ifcensee shall subr.it the additional infonna-tion identified in Table 3.2 of-this SE in accordance with the Issued schedule. contained therein.

In the event these dates for sub-7/27/79 mittal cannot be met. the lic3nsee shall submit a report, explaining the. circumstances, together. with a revised schedule.

The' licensee is required to implemnt thi administrative contiol:, ident.ified in Section 6 of the SI.'.

The administra-tive controls shall be in effect imediately, ext.cpt f or tho..c r

modifications indicated in Section 3.1 of the SL, which shall become effective on the dates indicated in Table 3 ' of the SE.

f 3.G. Systems'Integeity h

%e licensee shall imolement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient to as low as practical levels. his program shall include the rollowing:

-}

1, Provisions establishing praentive maintenance and periodic visual inspection requirements, and u

2 Integrated leak test requirenents for each system at a frequency not to' exceed refueling cycle intervals.

3.H' Iodine Monitorina

% e licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident coMitions. %is J

-j l program shall' include the following:

1 Training of personnel,

.-l 2.

Procedures for monitoring, and l

3.

Provisions for maintenance of samplirr; and w

analysis' equipment.

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This license is effective as of the date of issuance, s'nd shall expire at midnight, February 15, 2007.

F08 THE AT@ TIC (NERCY CCHMISSION 6t) closures : Appendices A and B..

Technical spectfacetions Date of 1ssuanc., cecember 14 1972 O fog,,,,4."

A. Clembuseo, rep..ty <> rect.c f ar Rese f o r Pre....c a,

Ottectorate et t.it e ns t an D**D "D

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tammsment channels required during poseer speretten e monitor postaccident conditions.

2. ' FWeeieiens are me$e for local templing and monitoring of drywell atmosphere.

3.

in the event any of the instrumentation becomes inoperable for more than 7 days during reactor coers-

' tion, initiate en orderly shutdown and be.n the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 From and af ter the date that one of.these parameters is reduced to one inoication. continued operation is not permissible beyond thir*v days. unfess sucn instrumentation is sooner made cparab!e. In the event that all ind' cation of treA-parameters es disablej and sucn indicaton cannot be restored in s's (6) hours.

en orderly shutdown shall be initiated and tne reactor shall be in a cold shutdown condition in twenty four (24) hours.

5. If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; how/er,

.if the reactor is in a shtitdown mrdition, it may not be started up until all position _ indication is restored. In the event that all position indication is lost on one or more valves and such indication cannot be restored in 30 days, an orderly shutdov,n shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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I TABLE 4.22 PO$fACCIDENT MONITORING l.".STRUMENTATION SURVEILLANCE REQUIREMENTS

. Instrument Minimum isaber.

Readest tacaties sf Operales '

Parameter Unit 1 tasanets'

..alibration lastrument peck r

1 Reactor pressure 901-5 ona every once per day 3 months 1

Hoector water tevel 901-3 once oery once per dey 3 months l

1 Torus water temperatur, 901-21 once every once per day l

3 months 1

Torus air temperature 901-21 ones every once per der 3 months Torus water tael 901-3 once aery once per 1**

(Indicetor) 3 months 2

, Torus water level N/A Hone (sight glass) 1 Torus pressure 901-3 once every once per day

~ 3. months t

orywen pressure 901-3 ona every once per coy 3 months 2

Dryweil tempers ture 901-21 ' once avery once per day 3 rnonth:

2 Neutron anonitoring 901-5 once every once per day 3 months 2

Torwe to drywell ones every None differential pressure 6 months I ain Steam IN 901-21 Once ocr M

Pesition acoustic 31 days l

m nitor 2/ valve Main Steam RV 901-21 Once every Once per

Position, 18 rroaths 31 days temperature monitor

[MainSteamSV 901-21 Once per i Position, acoustic-31 days tronitor 2/ valve Main Steam SV 901-21 Once every Once per f Position, 18 months 31 dayn i

temp 2rature -

_ (tronitor

'Instrufrent channe!s required durrg pewtr cocratot to momtor petaccident ccnditions.

• • FunctionaF tentn wilI be onluctwi leforo startisp at the r rvi of each reliselini ewitaire or af t er mintrrhux e in Ierformtvi on n

[urticular stifety or relief valve.

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-QUAD CITIPS DPR-29

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,f 6.0 ADMINISTRATIVE CONTR' IJW N 6 3 u ' -

6.1 dRGANIZATION, REVIEW, INVESTICATION, AND AUDIT A. The Station Superintendent shall have 'overaU full. time responsibihty for safe operation of the facihty. Duing

_ periods when the Station Supermtendent is unavailable, he shall designate this responsibthty to an estabhs!.ed alternate who satisfies the ANSI Nis.1 of \\ larch 8.1971 experience requuements lor plant m.mager.

B. The corporate management w hich relates to the operation of this station is shown in Figure 6.1 1.

C. The normal functional organization for operation of the station shall be as shown in Figure 6.12. The shift manntng for the station shall be shown in Figure 6.13. The individual tilhng the position of Adminis ative Assistant shall meet the minimum acceptable level for "Technie I 5!anager" as desenbed m Section 4.2.4 ot 3NSI N18.11971.

A fire brigade of at least 5 members shat! be maintained on. site at all times. This excludes the shift crew necessary for safe shutdown of the pl.nt, and any personnel required forother eacntial functions durmg a tire emergency.

D. Qualifications of the station manacement and operating staff shall meet minimum acceptable levels asdesenbed in ANSI NIS.1, " Selection and Training of Nuc! car Power Plant Personner'. dated March 8,1971. The Rad / Chem Supenisor shall meet the requirements of radiation protectioi, manager of Regulatory Guide I.8. The Shif t Control Room Engineer

• shall have a bachelor's degree or equivalent in a scieritific or enginecting discipline with specific training in plant design, 'and response and analysis of the plant for transients and accidents.

E. Retraining and replacement trainmg of Station personnel sha!! be in accordance with ANSI N18.1,"Silection and Training of Nuclear Power Plant Personnel", dated March 8,1971.

A training program for the fire brigade shall be maintained under the direction of the Station Fire Marshal. arid shall rneet 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 exceeding 2 years.

G. ~ The Review and Investigative Function and the Audit Function of activities affecting quality during facility opera.

tions shall be et nstituted and have the responsibthties and authorities outlined below:

1. The Supervisor of the Offsite Review and Investicative Function shall be appointed by the Vice President of Construction. Production. Ucensing and Environmental Affairs. The Audit Function shall be the responsibility of the Manager of Quahty Assurance and shall be independent of operations.

a.

Offsite Review and Investigative Function

^~

The Supervisor of the Offsite Review and Investigative Function shall:(1) provide directions for the review and investigative function and appomt a senior participant to provide appropriate direction.(2) select each participant for this function.(3) select a complement of more than one participant who collectively possess background and quahfications in the subject matter under review to proside com.

prehensive interdisciplinary review coverage under this function,(4) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function,(5) approve and repcrt m a time;y manner all findings of nor compliance with NRC require.

+

ments to the Station Supe *intendent.' Division Manager Nuclear Stations, Manspr of e istity Assurance, and the Vice President of Construction. Production. Licensmg and Environmental Affairs.

. During periods when the Suoervisor of 0ffsite Review and Investigatise Function is unavailable, he shall desit.nate this responubihty to an established alternate, who satisfies the forn:a! trammg and ex.

perienur requirements for the Supervisor of the Of fsite Review and Investigative Function. The

. responsibilities of the persmnet perfornung this function are stated beh>w. The Offsite Review and

• Investigatise linct.on shall resiew; i) - The safety' evaluanons for (1) thanges to pmcedores. cqmpment, or systems as dewribed m the T

safety analyus repost and (2) tests or expenments sompleted under the provnnm of 10 Cl R

. The Shif t Control ROTt Fnqineer requirement-will br ef fect ive 6fl /R1.

6.1 1 L

• e QUAO-CITIES

.DPR-29~

- MINIMUM SHIFT MANNING CHART CONDITION OF-O'4E. UNIT 9

(No Fuel in Second Unit)

License Initial Fuel Loading Cold Shutdown or Above Cold Catecory' or Durinq Refueling Refueling Snutdown Thutcown Senior

. Operator-License

'2-1 1

Operator.

License.

2 1

2 Rad.-Prot. Man 1

I-1 Non. Licensed -

-(As Required) 1 2-Shift Control Room Fngineer-

?bne 9Couiral bbne Rcouirrrl 1

CONDITION OF SECOND UNIT (One Unit at Hot Shutdown or at Power) 4

-License Initial Fuel. Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown 4

Senior

• Operator s.

License-2 2

2 Operator *-

License 3

2 3

4 -

. (

Rad. Prot.' Man

-1' 1

1 Ncn-Licensed' 3+ (As Required) 3*

4-Shift controli Renn Enaineer 1

1 1

CONDITION OF SECOND UNIT

~ (One Unit at Cold Snutdown or Refueling Shutdown)

. License Initial Fuel Loading Cold Shutdown or

~ Above Cold

-l Category or During Refueltnq '

Refuelina Shutdown

Shu tdown Senior

• Operatorz

-License-2 1

2

Operator

• I License-3 2

2

. Rad.-Prot. Man

.I 1

1 Mon-Licensed 3+-(As Required) 3 3

~

Shift Control Renn Pnnineer

• bne Required

• bne Pequired '

1

' Assumes each individual is licensed on each facility. During initial fuel loading or during refueling, one senior engineer'(limited license) will supervise fuel hand 1tr FIGURE 6.1-3 MINIMUM SHIFT MANNING CHART

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..'T 7 ATTACHMENT IV

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.Qu'ad.CitiesSStation UnitL21 W'

DPR-30; s

Propo sed ' Techn i cn if Sp'eci fi ca t i ori Cliange s -

V

< Revised: License Page: :5

~ NOw License.Page:

6 Revised' Technical Specification Pages:

3.2/4.2-1b

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- 3.- 2 / 4. 2 - 18 L

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3.F. ' The ifcensee may. proceed with and is required to complete-the

modifications identified in Paragraphs 3.1.1 through. 3.1.13 of the NRC's Fire Protectio. Safety Evaluation (SE), dated Am. 52 July 27, 1979 for-the-facility. These modifications will be 8/16/79 ompleted in accordance with the schedule'in Table 3.1 of the s

SE and supplements -thereto.

~

In addition,' the licensee shall subr.it the additional infonna-tion identified in Table 3.2 of this SE in accordance with the Issued schedule contained therein.

In the event these dates for sub-7/27/79 iJittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.

The licensee i.s required to implewnt the administrative control, identified in Sect. ion 6 of the SI:. The adniinistra-tive conf.rolt. shall. be in ef fect imediately, ext.ept f or thtv.c modification *, indicated in Sectic.n 3.1 of the SL, which shall become effective on the dates indicated in Table 3.1 of the SE.

't 3.G. Systems Inteqrity

'Ihe. licensee shall imnlement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient to as low as j

practical levels. This program shall include the following:

1 j.-

1 Provisions establishing preventive maintenance and periodic visual inspection requirments, and

[

2 ~ Integrated leak test requirements for each system 1

at a frequency not to exceed refueling cycle intervals.

3.H.Todine Monitorino-The licensee lshall implement a crogram which will ensure the capability to accurately determine the airborne iodine concentration,in vital areas under accident conditions. This j_

program shall include the following:

1.

Training of personnel,-

2 Procedures for nnnitoring, and

3. - Provisions for maintenance of sampling aryl analysis equipment.

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This Itcense is effective se of the date of tervance, and shall espire at midnight, Feb rua ry 15, 2007.

FOR TME ATGt!C ENERCY CDef!55!0N' 60 closures : Appendices A and B..

Technical specificettons Date of Issuance December 14. 1972 8 //,g e rf[-

• A. Claduseo, sep..ty ot rec t.c

• for pese to: P r e... c e,

Directorate et 1.t a e ne t na O

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Q AD-CITIES ce D '*D TYA O

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TABLE 3.24 POSTACCIDENT MONITORIMC IM5TRUMENTNiON REQUIREMENTS'?8 Mainem Rester Reedest tentes seman er sparess seit 2 Frevided Esage Channelsmm Parameter t

ne.ctor premre 902-5 1

Sisoopig 2

61200ps4 1

neecur.,eter w 902-3 2

-243 inches-+57 inches 1

Terw meter tempereture 902-21 2

S200* F t

Terveairwmperetum 902-21 2

Seco'r ITerve enter w.

902-3 1

25 ncews- + 25 iruma

(""'*"'

288 i.

Terw nowr w.

1 18 inch reage (sieht s' ens

{

t Tern prese,,e 902-3 1

4 lades He to 5 pas

. tj s

Devwon pre,re 902-3 1

4 incha He to 5 ps4 Sto75psg 2

Dryweit semperatvee 902-21 6

ocoo* F 2

powwon monitorine 902-5 4

o,1.td' ces 288 Torvise drymn 2

03 psid erverentist premre j

. [ Main Steam RV 902-21 1 per NA position, acoustic valve nonitor i

2/ valve lMain Steam RV 902-21 1 per 0-600 P I osition, valve

'i p

t mperature (monitor btainSteamSV 902-21 1 per NA position, acoustic valve imonitor ISI 2/ valve d

0 Main Steam SV 902-21 1 per 0-600 P

position, valve temocrature nonitor 3.2/4.2-15 i

w 4

.m QUAD-CITIES 30 oh b

.r oN.ha JO _=

c w Ju

- IIease A lasmsment ehennels reewired euring power operetten es monitor postaccident conditions.

3.

Freeieions'ere mese for toca: semoline eres monitoring of crywell atmosonore.

3, in the event any of the instrumentation becomes inoperable for more than 7 days curing reactor opera-tion, initiate an orderly shutdown and be en tne cold snutdown conditen within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A Frorn and af ter the date that one of these carameters is reduced to one indkation. continued coeration is not permiss bfe bever.d tNrtv d evs, unlms sucn instruivntation is soorser m.mse operacle. In the event that all indication of the',a carameters is casa'aled ano such indicaten cannot be restored in s*x 165 hours0.00191 days <br />0.0458 hours <br />2.728175e-4 weeks <br />6.27825e-5 months <br />.

Ort orderly shut' fawn shall bo initiJttd ark.1 tne reactor snatt De in a cold shu'.Jown concation in twenty four (24) hours.

S. If the number of position indicators is reduced to one indication on one or more valves, continucd operation is permissible; howver,

.if the ructor is in a shtitdown conclition, it may not be started up until all position indication is restored.

In'the event.that all position indication is lost on one or nore valves and such indication cennot be restored in 30 days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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POSTACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQU12EMENTS f

lastrument INamust 1emtier Readout sf Operable -

Location Channels'

' Parameter linit 2 Ca!itiration instrument Check 1

Reactor pressure 902 5 Once every once per day 3 months 1

Reactor water level 902 3 Once every Once per day 3 months 1

Torus water temperature 902 21 Once every once per day 3 months 1

Torus air temperature 902 21 Once every

.Once per day 3 months Torus water level 902 3 Once every Once per day Cadicator) 3 months 2

, Torus water levet N/A None (sight glass) 1 orus pressure 9024 Once overy Once per day

3. months 1

Orywell preseire 902 3 Once every Once per day 3 months 2

Drywell temperature 902-21 Once every Once per day 3 month:

2 Neutron monitoring 902 5 Once every Once per day 3 months 2

Torus to drywell Once every None differential pressure 6 months fMainSteamIN 902-21 Once oer Pesition acoustic 31 riays rionitor 2/ valve Main Steam IN 902-21 Once every Once per

-Position, 18 rronths 31 days tem

'kmon^oerature itor'

[MainSteamSV 902-21 Once per Position,. acoustic 31 dayn tronitor '

2, c,1ve -

Main Steam S7 902-21 Once every Once per

Position, 18 months 31 riays trfnptraturo frnni tor

• Instrument citannels requxed durmg rower operaton to momtor postaccatent conttons.

• • Funct ional. tor.t n' wi l l l ev er ohict <<l Iw hiro !:tarttip at t he errl of eact

?ftlel iW1 out arin or af t i r unint enistce -i!. forformni on a turticular f:af c ty or r 01 inf' valve.

3,2/4,2-19~

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CUAD CITIES DPR-30 g Gg}

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M 3dQgg 6.0 ADMINISTRATIVE CONTRO 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A. The Station Superintendent shall have overall full. time remonubihty for safe operation of the (Jcthly. Durmg periods when the Station Supermtendent is unavatlable, he shall designate this responsibihty to an estabbshed alternate who satisfies the ANSI N18.1 of Wrch 8.1971 experience requirements for plant maruger.

8. The corporate management which relates to the operation of this station is shown in Figure 6.1 1.

C. The normal functional orpnization for operation of the station shall be as shown in Figure 6.12. The shift manntry for the station shall be shown in Figure 6.l.3. 'the individual fdling the position of Admmistrative Assistant shall meet the minimum acceptable level for "fechnical Maneger" as desenbed in Section 4.:'.4 of ANSI N18.11971.

A fire brigade of at least 5 members shall be maintained on. site at all times. This excludes the shift crew necessary for safe shutdown of the plant, and any personnel required fotother enential functions during a tire emergency.

D. Quahfications of the station management and op+ rating stsif slull meet minimum acceptable levels as described in ANSI NI8.I, " Selection and Trainmg of Nuclear Power Plant Personnel", dated March 8,1971. The Rad / Chem Supervisor shall meet the requirements of radiation protection manager of Regulatory Guide 1.8. 'Ihe Shif t Control Room rngineer* shall have a tuchelor's degree or equivalent in a scientific or engineering discipline with nnocific traininq in plant design, and response and analysis of the plant for trannients arvi accidents.

E. Retraining and replacement traming of Station personnel shall be in accordance with ANSI N18.1,'51ection and Training of Nuclear Power Plant Personnel", dated March 8,1971.

A training program for the fire 5rigade shall be maintained undec the direction of the Station Fire Marshal. and

- shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that tratning sessions shall be at least quarterly.

~ i(,

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

G. The Review and investigative Function and the Audit Function of activities affecting quality during facility opera.

tions shall'a constituted and have the responsibilities and authorities outhned below:

I. The Supervisor of the Offsite Review and Investigative Function shall be appointed by the Vice President of Construction. Production, l.icensmg and Environmental Affairs. The Audit Function shall be the responsibility of the Manager of Quality Assurance and shall be independent of operations.

a.

Offsite ReSiew and Investigative Function The Supervisor of the Offsite Review and Investigative Function shall:(1) provide directions for the review and investigatise function and appoint a senior participant to provide appropriate direction,(2) select each participant for this function,(3) select a complement of more than one participant who collectively possess background and quahfications in the subject matter under review to provide com.

. prehensive interdisciplinary review coverage under this function.(4) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function,(5) approve and report in a tirnely manner all findmgs of noncompliance with NRC require.

ments to -the Station Supe *intendent. Division Enager Nuclear Stations. Manager of Quahty Assurance, and the Vice President of Construction. Production. Licensmg and Environmental Affairs.

~

During periods when the Supervisor of Offsite Review and investigative Function is unavailable, he shall designate this responsibdity to an established alternate,who satishes the formal trainingand ex.

perience requirements for the Supervisor of the Offsite Review and Investigative Funcen. The responsibilities of the personnel performing this function are stated below.The Offsite Review and

• Investigative Function dull reuew:

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

')

. *'Ihe Shift Control Rocrn Engineer rnluirement will be effective 6/1M1.

f 6.11 f,

~

%~

e WAD-CITIES Opg.'30 MIN! MUM SHIFT MANNING CHART CONDITION OF ONE UNIT (No Fuel in Second Unit)

License Initial Fuel Loading Cold Shutdown or Above Cold Ca teoor /

or Durino Refueling Refueling Shutdown

'hutcown Senior Operator License 2

1 1

Operator License-2 1

?'

Rad. Prot. Man 1

I I

Non-Licensed (AsRequired) 1 2

Shift Control Room Fngineer ibne Rc<ntiral Fone Reauired 1

CON 0! TION OF SECOND UNIT (One Unit at Hot Shutdown or at Power)

Initial F :e1.cading Cold Shutdown or Above Cold License or During g.'.eling Refueling Shutdown Shutdown Category Senior

• Operator 2

2 License 2

Operator

• License 3

2 3

(,

Rad. Prot. Man 1

1 1

Non-Licensed.

3+ (As Required) 3*

4 Shift Cbntrol norm Enoinee-1 1

1 CONDITION OF SEC0ND UNIT (One Unit at Cold Shutdown or Refueling Shutdown)

License Initial Fuel Loading Cold Shutdown or Above Cold Category or During Refueling Refueling Shutdown Shutdown Senior

• Operator

. License 2

1 2

Operator

• License 3

2 2

Rad. Prot. Man 1

1 1

Non-Licensed 3+(AsRequiredh 3

3

'l i

Shift Control'

nenn Encineer sbne Required

• bne Pequired 1

- ' Assumes each individual is licensed on each facility. - During initial fuel loading or

-during refueling, one senior engineer (limited license) will supervise fuel handling.

' FIGURE 6.1-3 MINIPtJM SHIFT MANNING CHART e _

_w