Text

Amends 80 & 63 to Licenses DPR-58 & DPR-74,respectively, Changing Tech Specs & License Conditions Re Spent Fuel Pool Mod & Containment Sump Design
	ML17320B051
Person / Time
Site:	Cook
Issue date:	04/27/1984
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17320B052	List: ML17320B051;
References
	NUDOCS 8405170166
	Download: ML17320B051 (32)
	v • d • e

II

~gg Rfgy fp,0

+~

~

~O

++*<<+

UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 8405i70ih6 840427 PDR ADOCK 050003i5 P

PDR INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8O License No.

DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated December 15, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

C.

D.

E.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

,~+/

N ll

ATTACHMENT TO LICENSE AMENDMENT.

AMENDMENT NO. 80 TO FACILITY LICENSE NO.

DPR-58 DOCKET NO. 50-315 Revise Appendix A as follows:

~ll P

3/4 3-50 3/4 5-3 3/4 6-35 3/4 6-36 3/4 9-9 3/4 9-10 6

3 B 3/4 2-3 P

Insert Pa es 3/4, 3 50**

3/4 5-3 3/4 6-35 3/4 6-36**

3/4 9 9**

3/4 9-10 6-3

~

B 3/4-2-3**

P 1

Included for convenience; corrected to show deletion

~ of "Amendment 63" revision.P

~

~ tt't P

l

~

~ ~

INSTRUMENTATION SURVEILLANCE RE UIREMENTS (Continued)

'a ~

If the absolute value of is greater than'o

. another i3 J

~

J'

~

map shall be completed to verify the new F..- If.the second map shows the first to be in error, the first hap shall be dis-reoarded.

If the second map confirms the new R., four more maps (including rodded configurations allowed by the insertion limits) will be completed so that a

new.R. and a-can be defined from the six. new maps.

4.3.3.6.2 a ~

b.

The'PDMS shall be 'demonstrated OPERABLE:

s By performance of a CHANNEL FUNCTIONAL TEST within 7 days prior to its use and at least once'per 31 days thereafter when used for monitoring F (Z).

At least once per 18 months, during shutdown or bel,ow 5". of RATED THERMAL POWER, by performance of a CHANNEL'ALIBRATION.

I

~

I

~

I ar~

D. C.

COOK-UNIT1'/4 3-50

7.

t "I".ERiEHCY CDRE COOLIHG SYSTEHS ECCS SUBSYSTEHS - T ~ 350 F LIHITIHG COHD1TIOH FOR OPERATION

'i

~t 3.5.2 Two independent ECCS subsys'tms shall be OPERABLE with eacji subsystem comprised of:

One OPERABLE centrifugal charging pump, e

b.

One OPERABLE safety, injection pcnp,"

c.

One OPERABLE residual heat removal h at exchanger,,

d.

One OPERABLE residual heat renaval

pmap, and e.

An OPERABLE flow path capable of wking suction from the refueling water storag'e tank on a safety injection signa1 and

'transferring suction to the con aimhent sump during the recir-'ulation phase of operation.

APPLICABILITY'.

HODES 1, 2 and 3.

'ACiIDH:

I

, Mith one ECCS subsystem inoperab1e,. restore th'e inoperable sub-systm to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN

~ within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

In the event the ECCS is actuated and injects.wa~er into the Reac or Coolant Sys.em, a Special Report shall be prepared and submitted.to the Cornission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total ace+i~lated ac.uation cycles to date.

D.C. COOK-UHIT 1 3/4 5-3 A~en&jent Ho. 80

CONTAINMENT SYSTEMS CONTAINMENT AIR RECIRCULATION SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.5.6

'Two independent containment air recircu1ation systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one containment air recirculation system inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least.

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REnUI REMENTS I

'.6.5.6 Each containment air recircula'tion system shall be demonstrated OPERABLE at least "once per 3 months on a

STAGGERED TEST BASIS by a

~

C ~

d.

Verifying that the'return air fan starts on an auto-start sig'nal after a 9 -+

1 minute delap,and operates for at least 15 minutes, Verifying that with the return air fan discharge backdraft damper locked closed and the fan motor energized, the static pressure between the fan discharge and the backdt.aft damper is

~ 4.0 inches, water gauge.*

Verifying that with the fan off, the return air fan damoer opens when a force of < 11 lbs is applied to the counter-

weight, and Verifying that the motor operated valve in the suction line to

'he containment's lower compartment opens:after a. 9

+

1 minute de)ay.

D. C.,COOK-UNIT 1 3/4 6-35 Amendment No. SO

CONTAINMENT SYSTEMS FLOOR DRAINS LIMITING CONDITION FOR OPERAT'ION 3.6.5.7 The ice condenser fIoor drains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the ice condenser floor drain inoperable, restore the. floor drain'o OPERABLE status prior to increasing the Reactor Coolant System tem-perature above 200 F.

SURVEILLANCE R EOU IREMENTS 4'.6.5.7 Each ice condenser floor drain shall be demons'trated OPERABL'E at least once per 18 months during shutdown by:

'li b.

c ~

Verifying that valve gate opening is not impaired by ice, frost or debris, Verifying that the valve seat is'ot damaged,'

g Verifying that the valve gate opens when a force of <,100 lbs is applied, and d.

Verifying that the 12 inch drain line from the ice condenser floor to the containment lower compartment is unrestricted.,

I I

~

~ i D.

C.

COOK-UNIT 1 3/4 6-36

REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At least one residual heat removal loop shall be in operation.

APPLICABILITY:

MODE 6.

ACTEON:

7 a.

b.

C.

With less than one residual heat removal loop in operation, except as provided in b. below, suspend all, operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the p'erformance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

The provisions of Specif1cation 3.0.3 are not applicable.

I

~

SURVEILLANCE REgUI REMEHTS 4.9.8 A residual heat removal loop shall be determined to be in operation and circulating reactor coolant a't a flow 'rate of > 3000 gpm at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; D.

C.

COOK - UNIT 1

3/4 9-9

4 REFUELIHG OPERATIONS COHTAINMEHT PURGE AHD EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge and Exhaust isolation system shall be OPERABLE.

APPLICABILITY: During Core Alterations or movement of irradiated fuel within the containment.

ACTION:

With the Containment Purge and Exhaust isolation system inoperable, close each of the Purge and Exhaust penetrations providing direct access from the containment atmosphere 'to the outside atmosphere.

The provision of Specification 3.0.3 are not applicable.

H H

'SURVEILLANCE RE.UIREMEHTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 100 bours prior to the start of and at least

. once per 7 days during CORE ALTERATIOHS by verifying that containment Purge and Exhaust isolation occurs on manual initiation"and on a high radiation signal from each of the containment radiation instrumentation monitors."

~

D.

C ~

COOK -, UNIT 1

~

3/4 9-10 Amendment Ho. 80

Cl C)

C)

~

M PLANT MANAGER OPERATION ADMINISTRATIVE MAINTENANCE SUPERINTENDENT SUPERVISOR SUPERINTENDENT TECHNICAL SUPERINTENDENT ChI STAFF TRAINING COORDINATOR STAFF PROD. SUPV.

OPERATIONS SOL SHIFT OPERATING ENG.

SOL OA SUPERVISOR OPERATING ENGINEER OL PERFORMANCE CONTROL AND SUPERVISOR INSTRUMENTATION ENGINEER ENGINEER PLANT CHEMICAL SUPERVISOR PtANT RADIATION PROT. SUPV.

EGEND:

OL - SENIOR OPERATOR LICENSE OL ~ OPERATOR LICENSE.

~ - KEY SUPERVISORY PERSONNEL UNIT SUPERVISOR OL PERFORMANCE PKRFORMANCE ENGINEER ENGINEER INSTRUMKNT MAINTENANCE

~

CHEMIST SUPERVISOR RADIATION P ROTE N

SUPE

'R EQUIPMENT OPERATOR TECHNICIANS TECHNICIANS 0

GC CD AUXILIARY EQUIPMENT OPERATOR Figure 624 Faclllty Organization - Donald C. Cook - Unit No. ]

1

~

o

~

~~

~

~o o Pescant et Raff

~Thernus Power IOC.~

5%

5'%

p w

I r

Ta~t Flux Oitf~

4 lt I

r I

~

1(5s

+It%

INOICATED AXIAL,FLUX OIFFERENCK Fiqun B 0/4 2-1 TYPICAL INOICATEO AXIALFl.UX OIFF=RENCK VERSUS THERMAL, PC'hGR AT BOG, 0.

C.

COOK-UNIT.1 8 3/4 2-3

+3v%

't

~

gpS RECT~

~4 0

Cy

~i 0O vl 4p V/

~

4~ 'O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY

'OCKET.NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.63 License No.

DPR-74 The Nuclear Regulatory Commission (the Commission) has found that:

A.

TIIe application for amendment by Indiana and Michigan Electric Company (the licensee) dated December 15, 1983, complies with the, standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations

set, forth in 10 CFR Chapter,I; t

t B.

'The facility. will operate in conformity with the appli'cation,, the provisions of the Act, and the rules and.'regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the. public, and (ii) that such activities will be con'ducted in compliance with the Commi.ssion's regulations; t

~

D.

The i'ssuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and t

E.

The iss'vance of this amendment is. in accordance with 10 CFR Part 51 of the ComIission's regulations.and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes..to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.,DPR-74 is hereby amended to read as follows:

(2)

Technical S ecifications 3.

4.

h The Technical Specification's contained in, Appendices A and B, as revised through Amendment No. 63 are 'hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

t THe license is also, amended by the deletion of License Conditions 2.C.(3)(h). on "Containment Sump Design Verification, '2.C.(3)(1) on "Residual Heat Removal System Low Flow Alarm," 2.C.(3)(t) on "Spent Fuel Pool Modifications," and 2. E.

on condition to protect the environment.

r The license is further amended by changes to License Condition 2.C.(1) by changing the maximum power level 'of 3391 to 3411 megawatts thermal.

1 Th'e change in Technical Specificatidns is to become effective within.30 days of r'eceipt of the amendment.

In the period between receipt of -the amendment and the effective date of the new Technical Specifications, the licensee shall adhere to the Technical Specifications for the systems,'omponents, oi'peration existing at the time.

The period of 'time during changeover of systems, components or operation shall be minimized or compensated for by suitable temporary alternatives.

I This license amendment is effective as-of the date of 'its issuance.

'OR THE NUCLEAR REGULATORY COMMISSION 9

A.

ar a

Ch't even g

Operating Reactors an k No.

1 Division of Licensing

'I

~ '

Attachment:

Changes to the Technical Specifications s '

I Date of Issuance:

April 27, 1 gB4

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

TO FACILITY LICENSE NO. DPR-74 DOCKET NO. 50-316 3/4 1-1 3/4 2-15 3/4 3-4

'/4 3-42 3/4 4-26

3/4 5-5 3/4 I

I II 3/4 6-11 6-39 3/4 6-40 3/4 '6-43 8 3/4 2-3 8 3/4 6-3 8 3/4 6-4 6-3 Revise Appendix A as follows:

Remove Pa es Insert Pa es iii**

3/4 1-1**

3/4 2-15**

3/4 3 4**

3/4 3-42**

3/4 4-26**

~

3/4 5-5**

3/4 6-11**

3/4 6-39 3/4 6-40*

3/4 6-43*~

8 3/4 2-3**

8 3/4 6-3 8 3/4 6-4*

3*%.

6-4"

~

I Included for convenience Included for convenience; corrected to show deletion of "Amendment 63" revision.

~

1 II

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMEHTS SECTION :

'Pa e

3/4.0 APPLICABILITY.........................................;...

' 3/4 0-1 3/4.1 REACTIYITY CONTROI S YSTEYiS 3/4.1.1 BORATIOH CONTROL Shutdown Margin - T

> 200 F........

avg Shu down Margin - T

< 200'F......'...

avg Boron Dilution..

I Moderator T'emperature Coeffici ent..

Minimum Temperature for Criticality...

~

~ t

~

~ ~

~

~ ~ ~

~

~ ~

~ ~ ~ ~

~ ~

3/4 1-4 3/41 5

~

~ ~ ~

~

~ ~

~ o

~ ~ ~

~

~o'/4' 7

~ 'o'

~ ~ ~ ~ ~

~ e

~ ~ ~ ~ ~ ~ ~ ~

3/4;1 1

3/4 1-3 Fl.ow Paths -

Operating.....'...........'....'Charging Pump - Shutdown..................

Charging Pumps - Operating...'.............

Boric Acid Tr'ansfer Pumps -"'hutdown..'....

Boric Acid'Transfer Plumps - Operating......

Borated Water Sources

- Shutdown..........

~ ~

~

~ ~

~

~ ~

~

~ ~

~

~ ~ 0 I ~ ~ ~

~ ~

~ ~ ~

~

~ ~ ~ ~

~

~ ~

Borated Water Sources - Operating.............,...;..

3/4;1.2 BORATION,SYSTEMS Flow Paths - Shutdown.......;....;...'..'.........

3/4 3/4

'3/4 3/4 3/4 3/4 1.-.11.

1-12 1-13.

1-14 1-15 1-16 3/4 1-8, 3/4 1-9 3/4.1'.3

'. MOVABLE'CONTROL ASSEMBLIES Group Height............i..............

Position Indicatcrr'Channels

- Operating

'Position Indicator Channels - Shutdown.

P.od Drop Time.......;..........,........

~

~ ~

~

~ ~

~

3/4 1 ~l 8 3/4 1-21 3/4 1-22 3/4 "1-23 3/4 1-24 3/4 1>>25

~ ~

~

~ ~ ~

~

~ ~ ~ ~

~

~ ~

~

~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Control Rod Insertion Limits...........

~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~

Shutdown Rod Insertion Limit.......................'..

D. C.

COOK - UNIT 2 4

)

~ ~

'/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 80RATIO(N CONTROL SHUTDOWN MARGIN - T

> 200 F

LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be

> 1.6 ak/k.

APPLICA8ILITY:

MODES 1, 2,* 3, and 4.

ACTION'(:

With the SHUTDOWN MARGIN < 1.6~ ak/k, immediately initiate and continue boration at

> 10 gpm of 20,000 ppm boric acid s'olution or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE UIREPENTS 4.1.1.1.1 b.

C.

The SHUTDOWN MARGIN sha'll be determined to be

> 1.6~ hk/k:

Within one hour af er'etection of an inoperable control rod(s) and at least once per

12. hours thereafter while the rod(s) is inoperable.

If the i'noperable control rod is im-movable or untrippable; the above required SHUTDOWN MARGIN.

shall be increased by an amount at least equal to the with-drawn worth of the immovable or untrippable control rod(s).

g When in NODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , by verifying that control bank withdrawal is within the limits of Speci-fication 3.1.3.5.

When in MODE 2'

.within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.5.

I N

I I

~

See Special Test Exception 3.10.1 Jf"With K ff

> 1.0 fPWith K ff

<1.0'ff D. C.

COOK - UNIT 2 3/4 1-1

POWER 01 STRIBUTION LIMITS HB PARAMETERS IMITIHG CONDITION FOR OPERATIOH 3.2.5 The. following DNB related parameters shall be maintained within the limits sho~n on Table 3.2-1:

I a.. Reactor Coolant System T.

b.

Pressurizer Pr essure.

I APPLICABILITY:

MODE 1

ACT10H:

With any of the above parameters

'exceeding its limit, restore the param eter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 5." of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURYEILLAHCE REOU.IREHENTS

,4.2.5 Each 'of the parameter s of Table 3.2-1 shall b'e verified to. be within the'ir limits at least once

per, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I 0.

C.

COOK - UNIT 2 3/4 2>>15

CD TABLE 3.3-'I

. Continued REACTOR TRIP SYSTEM INSTRUMENTATION CD CD FUHCTIOHAL UNIT 16.

Undervoltage-Reactor Coolant Pumps 17.

Underfrequency-Reactor Coolant Pumps TOTAL HO.

OF CIIANNELS

'-1/bus 4-1/bus CHAHHELS TO TRIP MINIMUM CHANHELS APPLICABLE OPERABLE MODES ACTION 18.

Turbine Trip A.

Low F) uid Oil Pressure 3

B.

Turbine Stbp Yalve Closure 4

19.

Safety Injection Input from ESF 2

3.

7II 20.

Reactor Coolant Pump Breaker Position Trip A.

Above P-8 O.

Above P-7 0

21.

Reactor Trip Breakers 22.

Automatic Trip Logic 1/breaker 1/breaker 1/breaker 1

1/breaker 1

per oper-ating loop 1,

2 and

ly 2 and*

10ll

~

INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote'hutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

a

~

b.

With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification,3.0. 4 are not applicable.

l

~

s SUR'lEILLANCE RE UIREMENTS J

~

4.3.3.5

. Each remote shutdown monitoring instrumentation chanrel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and.

CHANNEL, CALIBRATION operations at the frequencies shown in Table'4.3-6.

I

~

~ (

D.

C.

COOK - UNIT 2 3/4 3-42

2600 2400 2200

.a.. 2000 1800 o:

1600 1400 1200 1000 0O 800 6oo Lu 400 200 2ll:

II

~

ili!

!!iii:jj ijj

'rr' jj.

!jii iilj

,ijl Ri li:

lLij I:l:

lpillltralll!!!I!'!IIItI!j!I!!III!!IIII!IIII!

I'MATERIALPROPERTY BASIS I

I!,"

II!

III i:

IFIil'li I;I,j I:I; I:i; e

I".:

ji'.:

iiu jl ll l

j BASE METALCu ~ 0.15"/o

'NITIAI BTNDT 58oF

~ 5.09FFY PTNPT ('/Tl 129eF I

%T) ~ 107oF I:j

.I

.'I li'l I:i ul jj

-:ij

~ ~

>>':jl II)[ [

~ ~ ~

~ ~ ~ ~

~ ~ ~

~ ~

Ii!:":.:.:.::.:!':.

2 'I ijI

'::I i~i iji!

j

.:li!

llI:

i Ij:

.'9;;i."

~

ii!!

I:I:

I:::

l:::

lijl j::m:

lj'.

j:I jUNACCEPTABLE ll~

I liej

iil rII iiil

~

~ ~

~

OPERATION IP ijii

'Jll I:,2 ji!i gl; it I

Ije I!I

.!I.iii i"! iiii i.:.i i!':-

II Ii:

ju:

ill:

l ~ '.:

".9:

~ ~ ~I::

I

~

e ACCEPTABLE I

i

~

~ ~

I OPERATION

~

.::::.!! l::i:

PRESSURE TEMPERATURE

.:::: i::::!::-. LIMITS COOLDOWN RATE oF/HR. i: 'i!:!!!.: 2'.i'-'-

"Xl I!Ii el.'I ill!

.'9

~l

~ l j,'i-.:.Ij:..:

':: '25 ii:,: 50..

9 l

'-: 100:"

REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONSAPPLICABLE FOB FIRST 5.0 EFFECTIVE FULL POWFB YEARS. {MARGINSOF 60 I::i iPSIG AND 10 F ARE INCLUDED FOB POSSIBLE INSTRUMENT EBBOB.I i ~ii

"""j ii!

I:~::il l:;:

~ ~ ~ ~

I:::

0 0

100 200 300 AVERAGE REACTOR COOLANTSYSTEM TEMPERATURE (oF) 400 FIGURE 3.4-3

.REACTOR COOLANTSYSTEM PRESSURE TEMPERATURE LIMITSVERSUS COOLDOWN RATES

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREHENTS (Con inued) d.

At" least once per 18 months by:

l.

Verifying au'tomatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and" that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or corrosion.

e.

At least once per 18 months, during shutdown, by:

l.

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.

J.

I 2.

Verifying that hach'of the following pumps start automatically upon receipt of a safety injection test signal:

a)

Centrifugal charging pump b)

Safety injecti'on pump c)

Residual heat removal pump f.

By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested

'pursuant to Specification 4.0.5:

1.

Centrifugal. charging pump 2.

Safety Injection pump 2405 psig 1445 psig 3.

Residual heat removal pump' 195'psig By verifying the correct position of each mechanical stop for the the following Emergency Core Cooling System throttle valves:

l.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking'peration or maintenance on the valve when the ECCS sub- '

systems are. required to be OPERABLE.

D. C.

COOK - UNIT 2 3/4 5-5

CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The, spray additive system shall be OPERABLE with:

a.

A spray additive, tank containing a volume of between 4000 and 4600 gallons of between 30 and 34 percent by weight NaOH solution,. and b.

Two spray additive eductors each capable of adding NaOH solu-tion from the chemical additi,ve tank to a containment spray system pump flow.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

I With the spray.additive'ystem inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6'ours; restore the spray additive system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be.in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

,SURVEILLANCE RE UIREMENTS 4.6.2.2 The'spray additive system shall be demonstrated OPERABLE:

a.

At least once.per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position..

b.

At least once per 6 months by:

1.

Verifying'the contained'solution volume 'in the tank, and 2.

Verifying the concentration of the NaOH solution by chemical analysis, D.

C.

COOK - UNIT 2 3/4 6-11

h ICE COllDEttSER D

S LIHITING CONDITIOli FOR OPERATION 3.6.5.3 The ice condenser inlet doors, intermediate deck doors,';

and top deck doors shall be closed and OPERA LE.'PPI ICABILITY:

NODES 1,.2, 3 and 4.

I'CTION

~

=-'..

"."'"'-z'. "

~

~:

~ '

~ ~

With one or. more ice condenser doors open or. otherwise.'inoperable; POWER OPERATION may continue for up to 14 days'rovided the ice bed temperature is.monitored at least once per 4.hours and'the maximum ice bed temperature.

is maintained

< 27'F; otherwise, restore the doors to their closed. posi-:-:.

~

tions or OPERABLE status (as applicable) within 48'hours or be. in at'1easf HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the.

following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURYEILLAllCE REOUIREMENTS 4.6.5.3.

1 a ~

I ~

~

r Inlet Doors - Ice condenser in1et doors shall be:

Continuously monitored and determined closed by the-inlet door position'm'onitoring system, and

'Demonstrated OPERABLE during shutdown at. least once per 3

months during the first year after the ice bed is fully loaded.

and'at 1'east once per 6 mo'nths'hereafter by: "

Verifying that the torque required to initially. open each door is

< 675 inch pounds.

2. 'erifping that opening of each door is not impaired by ice, -frost or debris.

3.

Testing a sample of at least 25% of the'oors and verifying that the torque required to open each door is less than l95 inch-pounds when the door is 40 degrees open.

This

~

torque':is defined's the "'door'pening torque" and is.

equal to the nominal door torque plus a frictional 'toroue component.

The,'doors selected for determination of the "door opening torque" shall be selected to ensore. that all doors are tested at least once during foui test intervals.

D.

C.

COOK - UNIT 2

/

3/4 6-39

- Amen]ment tlo,63

CONTAINYiENT SYSTEYiS SURVEILLANCE RE UIRENENTS Continued Testing a 'sample of at least 255 of the doors and verify-.

i ng that the torque required to keep each door from closing

.is greater than 78 inch-pounds when the door is 40 degre'es open.

This torque is defined as the "door closing torque"

~

and is equal to the nominal door torque minus a frictiona'1 torque component.

The doors selected for determination of '..

the "door closi'ng torque" shall be "selected to ensure that all doors are tested at least once during four test intervals.

f Calculation of the frictional torque of each door tested in 'accordance

'with 3 and 4, above.

The calculated fric-tional torque shall be

$0'. inch-pounds.

C I

4.6.5.3.2 Intermediate Deck Doors - Each.:;ice condenser. inte'rmediate deck.

door shall be II 1

a.. Verified closed and "fr'ee of frost accumulation by a visual inspection at =least once per 7 days, and t

I t

b.

Demonstrated OPERABLE at least once per 3 mo'nths'uring the

first year after the'ice bed is fully loaded and at least once

~

per..l8.mont'hs,. thereafter by visually verifying no'structural deterioration, by. verifying free movement of the vent assemblies,'nd by ascertaining free movement when lifted with the applicable

..force=- shown. below':

Door tuttiLF

< 31.8 lbs.

I

< 31.0 lbs.

.. adjacent-to Crane Mall

< 37.4 lbs.

2".

Paired with Door Adjacent' 33.8 lbs.

to Crane Mall, 3.

Adjacent to Containment Mall

,I i

4.

Paired with Door Adjacent to Containment Mall 4.6.5.3.3 Top Deck Doors - Each ice condenser top deck door shqll be

'etermined closed and OPERABLE. at least once per 92 days by visually verifying:

D.

C.

COOK - UNfT 2 3/4 6-40

~ ~

COHTAINMEHT SYSTEMS DIVIDER BARRIER PERSONNEL ACCESS DOORS AHD E UIPMENT HATCHES LIMTIHG CONDITION FOR OPERATION 3.6.5.5 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be OPERABLE and closed.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With a personnel'ccess door or equipment hatch inoperab)e,or open except for personnel transit entry and T

> 200 F, restore the door or hatch to OPERABLE status or to its close3 /osition (as applicable) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOW within the following 30.hours.

h SURYEILLANCE REQUIREMENTS t

I 4.6.5.5.1 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be determined closed by a visual.inspection prior to inc'reasing the Reactor Coolant System Tav above 200 F and, after each personnel transit entry when the Reactor Coolant System T is above 200'F.

4.6.5.5.2 The personnel access doors and equipment hatches between the containment's upper, and lower compartments shall be determined OPERABLE by visually inspecting the seals and sealing surfaces of these penetra.-

tions and verifying no detrimental misal'ignments, cracks or defects in the sealing surfaces, or apparent deterioration of the seal material:

~

a;-

Prior to final closure of the 'penetration each time it has been opened, and b.

At least once 'per,l0 years for penetrations containing seals'abricated from resilient materials.

P~CPICOQ - UNIT 2 3/4 6-43

~,

~

h Percent of Retetf Tbef met Poeret 100'C 5'A 5Y 90K b0'A 70%600'lftltFlue 0 (I~I~ fCI

~

50+

40'%01'0%

10.5

~20%

+20'5

~CX 0

~10'NOICATED AXIAI.FI.UX DIFFERENCE Figure B 3I4 2-1 TYPICAl. INDICATED AXIAL,Fl.UX QIFFERENCE VERSrJS THERMAL PGWER I'. C.

COOK - Ul(IT 2 8 i/4 2-3

CONTAINMENT SYSTEMS BASES 3/4.6.2

'EPRESSURIZATIOH AHD COOLING SYST MS 3/4.6.2.1 CONTAIHMEHT SPRAY SYSTEM The OPERA'BILITY of the containment spray system ensures that contain-ment, depressurization'nd cooling capability will be available in the eyent'f a'OCA.

The pressure reduction and resultant lower containment..

leakage rate are consistent with the, assumptions used in the acciden a nalys es'.

3 4.6.2.2 SPRAY ADDITIVE SYSTEM The. OPERABILITY, of, the spray additive system ensures that sufficient NaOH is added to the'on'tainment spray in the;event of a LOCA.

The limits on HaOH volume and concentration ensure a

pH value of,between 8.5 and 11.0 for the solution recir'culated within contaipment after a

LOCA.

This pH band minimjzes the evolution of iodine and minimizes th'e effect of chloride and caustic stress" corrosion on mechanical systems-and components...

These assumptions are consistent with the iodine removal efiiciency assumed in the accident analyses.

The contained water volume lxmit includes an'allowance f'r water not usab1e because of 'tank discharge location or other physical characteristics.

3/4. 6.3 COHTAINNEHT ISOLATION VALVES I

The OPERABILITY of the containment isolation valves ensures. that the containr<ent atmosphere will be isolated from the'utside environm'ent in the evel'it of a release of radioactive material to the containment atmos-.

phere or pressurization of the containment.

Containment isolation within'he time limits specified'ensures that the release of radioactive material to the environment will-be consistent with the assumptions used in. the.

analyses for a LOCA.

D. C.

COOK - UNIT 2 I

B 3/4 6-3 Amendpjent No.

63

CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL

~

~ ~

h The OPERABILITY of the equipment and systems requ'ired for the detec'-

tion and control of hydrogen gas ensures that, this equipment 'will.'be

'vailable to maintain 'the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.

Either re'combiner unit is capable of controlling the expected hydrogen generation associated

.with

1) zirconium-water reactions,

2) radiolytic decomposition of water and 3)'orrosion of metals within containment.

These hydrogen control systems are'onsols i>nt~ith-the-recommenda iions-of.ReguM&ry.Guide..l;7, "Cont) ol of Combustible Gas Concentrations in Containment Following a LOCA", Mar'ch 1971.

3/4.6'.5 ICE CONDENSER The requirements associated with each of the components of the ice condenser.

ensure that. the overall system will be available to provide sufficient pressure suppression capability 'to limit the containmqnt peak pressure transient. to less'han 12 'psig during LOCA conditions.

~

I

~34.6.I.1 iCE BED The OPERABIUTY of the ice bed ensures that the'equired. ice inven-tory will 1) be distributed evenly through. the containment

bays,

2) con-

.'ain su'fficient bo'ron to preclude dilution of the containment sump follow-'ng the

~ OCA and, 3) contain sufficient heat removal capability to condense the:reactor system volume released during a

LOCA.

'These conditions are'.

consistent with the assumptions used in the accident analyses.

The'minimum +eight figure of 1220.pounds of ice per basket contains a 10>> conservative allowance for ice loss through sublimatio'n which is,a

'fact'or of 30 higher than assumed for the ice condenser design.

In the event that observed sublimation rates 'ar e equal to or lower than design predictions after three years of operation, the minimum ice baskets weight may be adjusted downward.

In addition, the number of.ice baskets.

req'ui.red to be weighted each,9 months may be reduced after 3 years of

~

operation if such a reduction is supp'orted by 'observed 'sublimati'on'ata.

3 4. 6. 5. 2 ICE BED TEMPERATURE MONITORING SYSTEM The OPERABILITY-of the ice bed temperature monitoring system ensures that the capability fs available for monitoring the ice temperature..

In'he event the monitoring system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will.be retained within the specified time limits.

, D. C.

COOK - UNIT 2 B 3/4 6-.4 Amendment No, )

PLANT MANAGER Ol KRATION ADMINISTRATIVK MAINTENANCE SUPERINTENDENT SUPERVISOR SUPERINTENDENT TECHNICAL SUPERINTENDENT STAFF STAFF

- PROD. SUPV.

-OPERATIONS SOL QA

'UPERVISOR TRAINING COORDINATOR SHIFT OPERATWG KNG.

SOL OPERATING ENGINEER OL PERFORMANCE CONTROL ANO SUPERVISOR INSTRUMENTATION ENGINEER ENGNEER PLANT CHEMICAL SUPERVISOR PLANT

~

RADIATION PROT. 8UPV.

LEGEND:

SOL SENIOR OPERATOR LICENSE.

OL OPERATOR LICENSE

~ - KEY SUPERVISORY PERSONNEL UNIT SUPERVISOR OL PERFORMANCE PERFORMANCE ENGINEER ENGINEER INSTRUMENT MAINTENANCE

" CHEMIST SUPERVISOR RADIATION PROTECTION SUPERVISOR EQUIPMENT OPERATOR TECHNICIANS TKCHNICIANS AUXILIARY EQUIPMKNT OPERATOR Figure 6M Facility Organlzatlon - Donall C. Cook - Unit No. 2

t*

~

'ABLE 6.2-1 MINIHUH SHIFT CREE COt1POSETEOH5'ICENSE o

APPLICABLE MODES SOL OL Hon-Licensed

~ Shift Technical Advisor Hone required.

~

o I

~

"Does not include the li.censed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, super'vising CORE ALTERATIOHS.

~

~ dShift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift, crew'embers provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.P.-3

~Shared with 0.

C'., Cokk Unit'.

If C

D.

C.

COOK " UNiT 2 6-4 Arandrrent No. 34

ML17320B051

Text

Attachment:

Navigation menu

Search