ML17320A883

Proposed Administrative Changes to Tech Specs Re Spent Fuel Pool Mods,Rhr Sys Low Flow Alarm & Containment Sump Design Verification

ML17320A883
Person / Time
Site:	Cook
Issue date:	12/15/1983
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17320A884	List: ML17320A883 ML17334A489
References
NUDOCS 8312200497
Download: ML17320A883 (36)

Text

Attachment No. 3 to AEP:NRC:0790 Donald C. Cook Nuclear Plant Unit No. l The Proposed Revisions to Unit No. l Technical Specifications 83l2200497 83i215 PDR ADOCN 050003i5 P PDR~

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ENERiiEHCY CORE COOLING.SYSTEMS ECCS SUBSYSTEtiS - T, ~ 35O F LIHITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall bc OPERABLE Rth each subsystem comprised of:

a. One OPF=;"ALE centrifugal charging,pump,

b. One OPE:.""'LE safety fgect<on punp,

~ c.- One OPERABLE residual heit renova1 heat exchanger,

d. One OPERABLE residual heat renoval pump, and

e. An OPERABLE f1m path capable of taking suction from the refueling ~ater sto'rage tank on a safety injection signal and

'ransferring suction to the containment sump during 'the rec1r-culation phase of op'ation.

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APPLICABILITY: IDES 1, 2 and 3.

ACTION:

Hith one ECCS subsystem <noperable, restore the inoperable sub-system ta OPERABLE status %thin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTOQMN

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~ithin the next, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

In the event the. ECCS $ s actuated and inspects mter into the Rcac.or Coolant Systen, a Special Report shall be prepared and suhnitted to the Ccrrnission pursuant to Specification 6.9.2

-~~i-thm-90-days-de c~kbkng-th~9.cian~tances- af 'Niewctiatfon and the total accunalated,.actuation Cycles to dato.

I 0.C. COOK-'UNIT 1 3(4 5-3 Awen&ent Ho.

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CONTAINMENT SYSTEMS AIR RECIRCULATION SYSTEMS

'ONTAINIMENT LIMITING CONOITION FOR OPERATION 3.6.5.6 =

Two independent containment air recirculation 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REAUIREMENTS 4.6.5.6 Each containment air recirculation system shall be demonstrated OPERABLE at least once per 3 months on a STAGGERED TEST. BASIS by:

a. Verifying that the return air fan starts on an auto-start signal after a 9 + 1 minute delay and operates for at least '5 minutes,

b. Verifying that, with the return air fan discharge backdraft damper locked closed and the fan motor energi ed, the static pressure between the fan discharge and the backdraft damper is ~ 4.0 inches, water gauge.

C. Verifying that with the fan off, the return air fan damper when a force of < 11 lbs is applied to the counter- 'pens weight, and

d. Verifying that the motor operated valve in the suction line to the containment's lower compartment opens after a 9 + 1 minute delay.

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

INSTRUMENTATION Continued

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SURVE I LLANCE REOUIRENEI<TS R,. -F

a. If the absolute value of is greater than 2od, another K.

map shall be completed to verify the new II . If the second map shows the first to be in error, the first lap shall be dis-regarded. If the second map confirms the new II, four more maps (including rodded cohfigurations allowed by the irisertion limits) will be completed so that a new K~ and a~ can be defined from the six new maps.

4.3.3.6.2 The APOHS shall be demonstrated OPFRABLE:

a. 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).

b. At least once per 18 months, during shutdown or below 5 of RATED THERMAL POWER, by performance of a CHANNEL CALIBRATION.

D. C. COOK-UNIT 1 3/4 3-50

COtkTAIttNENT SYSTEMS FLOOR DRAINS L ll"il ~ I'tr. COttDITIO!( FOR OPERATION 3.6.5.7 The ice condenser floor drains shall be OPERABLE.

APPLICABILITY: NODES 1, 2, 3 and 4.

ACTIOII:

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

SUP V E I L LANC E REOU I REt<EttTS 4,6.5.7 Each ice condenser floor drain shall be demonstrated OPERABLE at least once per 18 months during shutdown by:

a. Verifying that valve gate opening is not impaired by ice, frost or debris,

b. Verifying that the valve seat is not damaged, c ~ 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.

D. C. COOK-UtlIT 1 3/4 6-36

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Percsnc ot Rated Thernisr Power 5% 5%

I i I i Terree Flux Ditteren e

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INDICATED 'AXIAL FLUX DIFFERENCE F1~re 8 3/4 2-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL PO'hER AT BOL

0. C. COOK-UNIT 1 S 3/4 2-3

AQH IN I STPAT IVE CONTROLS REVIEW 6.5; 2.7 The NSDRC shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or exoeriments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section

50. 59, 10 CFR.

c ~ Proposed tests or experiments which involve an unreviewed safety auestion as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or licenses,

e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g. REPORTABLE OCCURRENCES requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Comnission.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

Reports and meetings minutes of the PNSRC.

D. C. COOK - UNIT 1 6-10

Attachment No. 4 to AEP:NRC:0790 Donald C. Cook Nuclear Plant Unit No. 2 The Proposed Revisions to Unit No. 2 Technical Specifications

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CONTAIttNEHT SYST MS ICE COtlDEtlSER S LIMITING'ONDITION FOR OPERATION 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

>lith one or more ice condenser doors open'or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOHtt within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURYEILLAHCE REQUIREMEHTS 4'.6.5.3.1 Inlet Doors - Ice condenser inlet doors shall be:

a. Continuously monitored and determined closed by the inlet door position moni toring. system, and

b. Demonstrated OPERABLE during shutdown at least once per 3 months durinq the first year after the ice bed is fully loaded and at least once per 6 months thereafter by:

l. Verifying that the torque required to initially open each door is < 675 inch pounds.

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

3. Testing a sample of at least 25 . of the doors and verifying that the torque required to open each door is less than 195 inch-pounds when the door is 40 degrees open. This torque is defined as the "door opening 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 ensure that all doors are tested at least once during four test intervals.

i3,. 'C.. COOK -" UNIT 2 3/4 6-39 Amendment tlo.

COhaAQI'.~i PURGE P'i3 =a~RUST T.SOLA:IGH SYST~i LPETI'.tC CQ'. DI 0Ã:OR OP POTION 3.9. 9 The Containment Purge ar 6 Exhaust 'ol ation sys t em shal3. be OP ~~L"-.

APPLICA3V:5: During Core Alterations or movement of irradiated fue3.

within the containment.

ACiIOH:

Mich the Contai."=ent ?u ge and Exhaust isolation system* inoperable close each oi the Purge and Exhaust penet"ations prov'd'ng direct access from the conta.'"-ent at=osphcre to the outs'de a=osphere. The f

provisions o Spec' ication 3.0.3 a" e no appl'able.t SUKV-,ILr ;;CE REQUI3~~i a S 4.9.9 The Containment P rge and ~.chaust isolation system shal'e demon-strated OP"=%Mt . ~~thin l00 hours pr.'or to the start oi and at least once per 7 days during CQHZ ALTWQIONS by verifying that, containment Purge and Exhaust isolation occurs on manual 'nitiation and on a high rad"at"on test signal from each oi the containment radiat on monitoring inst=mentation channels.

D. C. COOK - UN:T 2 3/4 '9-9 Amendment 'to.

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/<.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment sp~ay system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

3 4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH volume and concentration ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanica1 systems and components.

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

The contained water volume limit includes an allowance for water not usable because of tank discharge location or other physical cnaracteristics.

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the o'utside environment in the event of a release of radioactive material to the containment atmos-phere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material the environment will be consistent with the assumptions used in the

'o analyses for a LOCA.

D. C~ COOK - UNIT 2 B 3/4 6-3 Amendment No.

INDEX LIMITING CONOITIONS FOR OPERATION l ANO SURVEILLANCE REQUIREMENTS SECT ION Paae 3/4,0 APPLICABILITY.......,, 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T avg 200'F.......................... 3/4 1-1'/4 Shutdown Margin - T < 200'F................ ... ., . 1-3 avg ~ ~ ~ ~

B oron Oilut>on ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-4 Moderator Temperature Coefficient...................... 3/4 1-5 Minimum Temperature for Criticality................... ~ 3/4 1-7 3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown................... 3/4 1-8 Flow Paths - Operating.......... 3/4 1-9 Charging Pump - Shutdown....................... 3/4 1-11 Charging Pumps - Operating....'......................... 3/4 1-12 Boric Acid Transfer Pumps - Shutdown. 3/4 1-13 Boric Acid Transfer Pumps - Operating.................. 3/4 1-14 Borated Water Sources - Shutdown.......... ~ ... ..,.. ..~ ~ 3/4 1-15 Borated Water Sources - Operating...................... 3/4 1-16 3/<.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.................. ~ 3/4 1-18 Position Indicator Channels - Operating. ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-21 Position Indicator Channels - Shutdown.. 3/4 1-22 Rod Dropop Time

--- eo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-23 Shutdown Rod Insertion Limit............ 3/4 1-24 Control Rod- Insertion Limits............ 3/4 1-25

0. C. COOK - UNIT 2

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TABLr 3. 3-1 (Continued)

RFACTOR TR1l'YSTCt1 IIISTRUHf,tlTATIOtl I'l H I H! IH TOTAl tlO. CIIAttttCLS CIIAtitIELS APPL ICABLF FUIICT IOIIAL util 1 Ol'INtttIELS TO TRIP OPFRAbkf. ten". AC T lntt

16. Undervol tape-Reactor Coolant Pumps 4-1/hus 6l l

17.'lnderfrequency-Reactor Coolant I'umps 4-1/bus 6

18. Turbine Trip '

A. Low Fluid Oil Pressure 3 2 B. Turbine Stop Valve Closure 4

19. Safety Injection Input 6'0.

from ESF 1, 2 Reactor Coolant Pump Breaker Position Trip

'0 A. Above P-8 1/breaker 1/breaker 1 B. Ahove P-7 I/breaker 1/breaker 1 11 per oper-ating loop

21. React. or Trip l)reakers 1, 2 and

22. Automatic Trip Logic 2 and

I:,'STRU,'.ENTAT I ON Rf'l10TE SHUTDO'hN INSTRUMENTATION L IHIT It/i) CONDITION FOR OPERATION 3.3.3.5 The remOte ShutdOWn mOnitOring inStrumentatiOn ChannI:le ShOwn .iri Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

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APPLICABILITY: HODES 1, 2 and 3.

ACTION:

lilith the number of OPERABLE rem'ote shutdown monitoring channels less than required by Table 3.3-9, either restore the inop~rable channel to OPERABLE status within 30 days, or be in HOT SHU D01I'I within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. The provisions of Specification 3. 0. 4 are not applicahle.

SUR".E ILLANCE REOUIREtlENTS 4.3.3.5 Each remote shutdown monitoring instrumentation chanr el shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBPATION operations at the frequencies shown in Table ~.3-6.

D. C. COOK - UNIT 2 3/4 3-42

REACTOR Ci30'NT SYSTEM ACTIu.'l Continued) b) Place the following reactor trip system and ESF instrumentation channels, associated with the loop not in operation, i>> their tripped conditions.

1) Overpower aT channel.

2) Overtempet.ature hT channel.

3) T -- Low-Low channel used in the coinci-d$ 8Pe circuit with Steam Flow - High for Safety Injection.

4) Steam Line Pressure - Low channel used in the coincidence circuit with Steam Flow - Hign for Safety Injection.

5) Steam Flow-High channel used for Safety Injection.

6) Differential Pressure Between Steam Lines - Higr channel used for Safety Injection (trip all bistables which indicate low active loop steam pressure with respect to the idle loop s:earn pressure).

c) Change the P-8 interlock setpoint from the value specified in Table 3.3-1 to < 76:l of RATED TVERr'1AL POWER.

2. THERMAL POWER is restricted to < 71".. of RATED THERtAL POWER.

Below P-7:

a. With > 1.0, operation may proceed provided at least two reactor fcoolant loops and associated pumps are in operation.

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b. With < 1.0, operation may proceed provided at least one reactor fcoolant loop is in operation with an associateo reactor K

coolant or residual heat removal pump."

c ~ The provisions of Specification 3.0.3 and 3.0.4 are not app1 i cab1e.

" All reactor coolant pumps and residual heat removal pumps may be de-energi:ed for up to hour, provided no operations are permitted 1

which could cause dilution of the reactor coolant system boron concentra tion.

D.C. COOK - UNIT 2 3/4 4-2 Amendment No. 39

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'ATER 2000 :i BASE METAL Cl)

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INITIALRTNPT ~ 580F D 1800 5.0 EFPY RTNDT I/eT) ~ 129

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REACTOR COOLANT SYSTEM COOLDOWN Llh1ITATIONS APPLICABLE FOR FIRST 5.0 EFFECTIVE FULL POWFR YEARS. IMARGINS OF 60 PSIG AND 10"F ARE INCLUDED FOR POSSIBLE 'INSTfIUhlENT ERROR.) I PROPERTY BASIS I

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COOI DOWN O 600 RATE F/IIR. = i:ii i-"

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0 100 200 300 400 AVERAGE REACTOR COOLANT SYSTEM TEMPERATURE {"F)

FIGURE 34 3 REACTOR COOLANT SYSTEM PRESSURE TEMPEIIATURE Llh1ITS VERSUS COOLDOWN RATES

CMERhE'ICY CORE COOLING SYSTEMS

.URVE ILLANCE REQUIREMENTS (Continued)

d. At least once per 18 months by:

l. Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 ps'g.

2. A visual inspection of the contairment sump ana verifyino that the subsystem suction inlets are not restricted Cy 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, hy:

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

2. Verifying that each of the following pumps start automaticall,.

upon receipt of a safety injection test signaI:.

a ) Centri fuga 1 cha rg ing pump b) Safety injection pump c) Residual heat removal pump

f. By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when test",d pur suant to Soecif ication 4.0. 5: I

1. Centr i fvga I cha rg ing pump ) 2<05 ps i g

2. Sa fety Inj ection pump 1445 psig

3. Residual heat removal pump ) 195 psig By verifying the correct position of each mechanical stop foi tne the following Emergency Core Cooling System throttle valves:

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroNing operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

D. C. COOK - UNIT 2 3/4 5-5

CONTAINMIENT 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 additive tank to a containment spray system pump flow.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTIOII:

With the spray additive system inoperable, restore the sistern to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the spray additive system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 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

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REFUEL It(G OPERATIOttS WATER LEVEL - REACTOR VESSEL LIMITlhG COttDITION FOR OPERATIOtt 3.9.10 At least, 23 feet of water shall be maintained over the top of irradiated fuel asse,,blies seated within the reactor pressure vessel.

APPLICABILITY: During movement of fuel assemblies or control rods within ttie reactor pressure vessel while in MODE 6.

ACT roti:

With the reauirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel. The provisions of Specification 3.0.3 are not applicabl~

SURVE I LLAt(CE. RE UIREMENTS 1

4.9.10 The Water level shall be determined,to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of uel assemblies or control rods.

D. C. COOK - UNIT 2 3/4 9-10

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