ML17317B291

Amends 28 & 10 to Licenses DPR-58 & DPR-74,respectively, Authorizing Deletion of Installed part-length Rods & Eliminating All Ref to Rods from Tech Specs

ML17317B291
Person / Time
Site:	Cook
Issue date:	05/02/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML17317B292	List: ML17317B291 ML17317B293 ML17317B295
References
NUDOCS 7906290088
Download: ML17317B291 (54)

Text

t UNITED STATES t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY INDIANA AND MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Wo. 28 License No., DPR-58

].

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Indiana and Michigan Electric Company and Indiana 8 Michigan Power Company (the licensees) dated April 4, 1979 and April 23,

1979, comply 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.

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

There is reasonable assurance (i) that the activities author-ized 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; D.

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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51'f the Commission'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-58 is hereby amdnde'd to read as follows:

(2) Technical S ecification The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

28, are hereby incorporated in the license.

The licensees shall operate the facility in accordance 'with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuanc'e.

FOR THE NUCLEAR REGULATORY COh1NISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

@iMc.488~

A. Schwencer, Chief Operating Reactors Branch 81 Division of Operating Reactors

ATTACHMENT TO LICENSE'AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO.

DPR-58 DOCKET NO.

50-315 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided for document completeness.

~Pa es I I I 1-3 3/4 1-18 3/4 1-20 3/4 1-26 3/4 2-3 3/4 2-7 3/4 2-11 3/4 2-12 3/4 10-1 3/4 10-2 3/4 10-5 B 3/4 1-4 8 3/4 2-1 B 3/4 2-4 5-4

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHEHTS SEC'tI ON 3 4.0 APPLICABILITY................................

3/4.1 REACTIVITY CONTROL SYSTEMS

~Pa e

3/4 0-1 3/4.1.1 BORATION CONTROL Shutdown Margin - T

> 200'F.....

avg Shutdown Margin - T

< 200'F

~....

avg-Boron Dilution.....................

Moderator Temperature Coefficient..

Minimum Temperature for Criticality~

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3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-6 Charging Pumps - Operating.............

Boric Acid Transfer Pumps - Shutdown...

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~

1

~

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~ 1,t ~

Boric Acid Tran'sfer Pumps

- Operati Borated Water Sources

- Shutdown...

I Borated Water Sources

- Operating..

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3/4.1.3 MOYABLE CONTROL ASSEMBLIES Group Height..................

Position Indicator Channels...

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od Drop Time........:.................................

R Shutdown Rod Insertion Limit,....,,....................

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

3/4.1. 2 BORATION S YS TEMS Flow Paths

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

Flow Paths - Operating.......;...............,.........

Charging Pump - Shutdown...............................

3/4 1-7 3/4 1-9

'/4 1-1'1 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 1-16 3/4 1-18 3/4 1-20 3/4 1-21 3/4 1-22 3/4 1-23 D.

C.

COOY. - UNIT 1

V Amendment No.

28 C

C INDEX IMITIHG COHO!TIONS FOR OPERATION AND SURVEILLANCE RE UIREMEHTS ECTION

~Pa e

/4. 2 POWER DISTRIBUTION LIMITS

/4.2.1 Axial Flux Difference..................................

/4.2.2 Heat Flux Hot Channel Factor...........................

/4.2.3

/4.2.4

/4.2.5 Nuclear Enthalpy Hot Channel Factor..

quadrant Power Tilt Ratio............

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NB Parameters.........................................

0

/4.2.6 Axial Power Distribution...............................

3/4 2-1 3/4 2-5 3/4 2-.9 3/4 2-11 3/4 2-13 3/4 2-15

/4.3 INSTRUMENTATION

/4.3.1

/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION....................

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IHSTRUMENTATION.........-.........--....------

3/4 3-1 3/4 3-15

/4.3.3 MONITORING INSTRUMENTATIOH Radiation Monitoring Instrumentation.......:...........

Movable Incore Detectors...............................

Seismic Instrumentation................................

Meteorological Instrumentation.....................;...

Remote Shutdown Instrumentation........................

Fire Detection Instrumentation.........................

3/4 3-35 3/4 3-39 3/4 3-40 3/4 3-43 3/4 3-46 3/4 3-51

/4.4.2

/4.4.3

/4 4,4 SAFETY VALVES - SHUTDOWN.........................;.....

SAFETY VALVES - OPERATING..............

PRESSUR I ZER o ~

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/4.4.5 STEAM GENERATORS.......................

/4.4 REACTOR COOLANT SYSTEM

/4.4.1 REACTOR COOLANT LOOPS Hormal Operation.......................................

3/4 4-1 3/4 4-4 3/4 4-5 3/4. 4'-.6 3/4 4-7 C.

COOK -.'iNIT 1

IV Amendment Ho. gg, 28

~

~

DEFINITIONS CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL'EST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

I CORE ALTERATION 1.12 CORE ALTERATION shall be the movement or manipulation of any com-ponent within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not pr eclude completion of movement of a component to a safe conservative position.

SHUTDOWN MARGIN 1..13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the-reactor is, or would be subcritical from its present condi-tion assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

IDENTIFIED LEAKAGE t

1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED lEAKAGE) into closed

systems, such as pump seal or valve packing leaks that are captured and'onducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a

steam generator to the secondary system.

UHIDEHTIFIED LEAKAGE l.l5 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

D. C.

COOK - UNIT 1

1-3 Amendment No. 28

DEFINITIONS PRESSURE BOUNDARY LEAKAGE l.l6 PRESSURE BOUNDARY LEAKAGE shall 6e leakage (except steam generator tube leakage) through.a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

CONTROLLED LEAKAGE 1.17 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

QUADRANT POWER TILT RATIO 1.18 QUADRANT POMER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

With one excore detector

-inoperable, the remaining three detectors shall be used for computing the average.

DOSE EQUIYALENT I-131 1.19

.DOSE EQUIYALENT I-131 shall be that concentration of I-131 (yCi/gram) which alone would produce the same thyroid dose as the quantity and iso-topic mixture of I-131, I-132, I-133, 1-134, and I-135 actually present:

The thyroid dose conversion factors used for this calculation shall.be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

STAGGERED TEST BASIS 1.20 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified

~

test interval into n equal subintervals, b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

D.

C.

COOK

-. UNIT 1

1-4

REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS Continued) a.

At least once per 7 days by:

l.

Verifying the boron concentration in each water source, 2.

Verifying the water level of each water source, and 3.

-Verifying the boric acid storage system solution temperature.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is

< 35 F.

D.

C.

COOK - UNIT 1

3/4 1-17

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT I

LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods which are inserted in the core, shall be OPERABLE and positioned within + 12 steps (indicated position) of their bank demand position.

APPLICABILITY:

MODES 1* and 2*

ACTION:

'a

~

With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With more than one full length rod inoperable or misaligned from the bank demand position by more than

+ 12 steps (indicated position),

be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c.

With one full length rod inoperable or misaligned from its group step counter demand height by.more than

+ 12 steps (indicated position),

POWER OPERATION may continue provided that within one hour either:

1.

The rod is restored to OPERABLE status within the above

~ alignment requirements, or 2.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

An analysis of the potential ejected rod worth is performed within 3 days and the rod worth is deter-mined to be

< 0.751 IAk at zero power and

< 0.38%

hk at RATED THERMAL POWER for the remainder of the fuel cycle, and b)

The SHUTDOWN MARGIN requirement of Specification 3,1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

<<See Special Test Exceptions 3.10.2 and 3.10,4.

D. C.

COOV. - UNIT 1

3/4 1-18 Amendment Ho. Ap,28

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION Continued c)

The THERMAL POWER level is reduced to < 75Ã of RATED THERMAL POWER within one hour and with7n the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to

< 85Ã of RATED THERMAL POWER, or d)

The remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod within one hour whTle maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification

3. 1.3.5 during subsequent, operation.

SURVEILLANCE RE UIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full length rod not fully inserted shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per 31 days.

D. C.

COOK - UNIT 1

3/4 1-19

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR, OPERATION 3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within + 12 steps.

APPLICABILITY:

MODES 1

and 2.

ACTION:

a

~

b.

With a maximum of one rod position indicator channel per group inoperable either:

1.

Determine the position of the non-indicating rod(s) in-directly by the movable incore detectors at l.east once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.

Reduce THERMAL POWER TO 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

With a maximum of one demand position indicator per.bank inoperable either:

2.

Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a 'maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or Reduce THERMAL POWER to

< 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within 12 steps at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

D:

C.

COOY.

UNIT 1 3/< 1-20 r

Amendment No. 28

i ~

(FULLYWITHDRAWN) 228...

~ r 200

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i Z0 o

150 0K 100 D0K BANK C' BANK D L

50 P

f P

0 L

0.0 0.2 0.4 Or6 0.8 (FULLY INSERTED)

FRACTION OF RATED THERMAL POWER FIGURE 3.1-1 ROD GROUP INSERTION LIMITSVERSUS THERMALPOWER THREE LOOP OPERATION D.

C.

COOK - UNIT 1

3/4 1-25

g

> I

~ ~

This page intentionally left blank.

D.

C.

COOY. - UNIT l 3/4 l-26 Amendment Vo.

28

POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS (Continued) 4.2.1.2 The indicated AFD shall be considered outside of its

+ 5X target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

POWER OPERATION outside of the

+ 5'4 target band shall be accumulated on a time basis of:

a.

One minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One-hal f minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels below 50% of RATED THERMAL POWER.

4.2.1.3 The target flux difference of each OPERABLE excore channel shall be determinhd by measurement at least once per 92 Effective Full Power Days.

The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4.2.1.3 above or by linear interpolation between the most recently measured value and 0 percent at the end of the cycle life.

The provisions of Specification 4.0.4 are not applicable.

D.

C.

COOY, - UNIT 1

3/4 2-3 Amendment No. 7g,28

100 80

(-9,7 UNACCEPTABLE OP E RATION Q

fC O

~O 5x T(E))

(9 75 xT(E)}

UNACCEPTABLE OPERATION I

I I

I I

ACCEPTABLE 2, 50)

OP ERATIO (22, 50 20 0

-50 '0

-30

-20

-10 0

10 20 30 40 50 FLUX DIFFERENCE (Dl) %

FIGURE 3.2-1 AXIALFLUX DIFFERENCE LIMITSAS A FUNCTION OF RATED THERMALPOWER D.

C.

COOK - UNIT l 3/4 2-4 Amendment Ho. M hagi 28

POWER DISTRIBUTION ITS SURYEILLANCE RE UIREMENTS Continued b)

At least once per 31 EFPD, whichever occurs first,.

2.

When the F

is less than or equal to the F

limit for C

RTP xy the appropriate measured core plane, additional. power distribution maps shall be taken and F

compared to C

xy F

and F

at least once per 31 EFPD.

xy xy e.

The F

limits for RATED THERMAL POWER within specific core xy planes shall be:

1.

F

< 1.71 for all core planes containing bank "D"

xy control rods, and 2.

F

< 1.55 for all unrodded core planes.

xy f.

The F

limits of e, above, are not applicable in. the fol-xy lowing core plane regions as measured in percent of core

'eight from the bottom of the fuel:

1.

Lower core region from 0 to 15Ã, inclusive.

2.

Upper core region from 85 to 100% inclusive.

Grid plane regions at 18.4

+ 2f, 36.6 + 25, 54.7

+ 2X and 72.9 + 2N, inclusive.

• 4.

.Core plane regions within + 2N of core height (+ 2.88 inches) about the bank demand position of the bank "D"

control rods, g.

With Fx exceeding Fx 1.

The F~(Z,a) limit shal'1 be reduced at least lX for each 1>

F exceeds Fx

, and xy 2.,The effects of F on F~(Z,R) shall be evaluated to determine xy if F~('Z, a) i s within its 1 imit.

4.2.2.3 When F~(Z,a) is measured pursuant to specification 4.10.2.2, an overall measured F~(Z,t) shall be obtained from a power distribution map and increased by 3~ to account for manufacturing tolerances and further increased. by 5X t'o account for measurement uncertainty.

D.

C.

COOK - UNIT 1

3/4 2-7 Amendment No. 2'2',

28

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sl 14 FIGURE 3.2-2 K(Z) NORMALIZEDF~(Z) AS A FUNCTION OF CORE HEIGHT

POWER DISTRIBUTION LIMITS UADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY:

NODE 1

ABOVE 50%

OF RATED THERMAL POWER*

ACTION:

a.

b.

Mith the QUADRANT POWER TILT RATIO determined to exceed 1.02 but

< 1.09:

1.

Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

a)

Either reduce the QUADRANT POWER TILT RATIO to within its limit, o' b)

Reduce THERMAL POWER at least 3f for each 1$ of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2, Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than,50% of RATED THERNAL'OWER

'ithin the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip setpoints to

< 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POMER; subsequent.

POMER OPERATION above.

50% of RATED THERMAL 'power may proceed provided that the QUADRANT POWER, TILT RATIO is verified within its limit at least once per hour until verified acceptable at 95K or greater RATED THERMAL POWER:

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1.

Reduce THERMAL POWER at 'least 3/ for each 1/ of indi-,

cated QUADRANT POWER TILT RATIO in excess of 1.0, within 30 minutes.

2.

Verify that the QUADRANT POWER TILT RATIO is within its limit withi n 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or

<<E pi D.

C.

COOY. - UNIT 1

3/4 2-11 Amendment No. 2B

POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION (Continued)

C ~

reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron F1 ux-High trip Setpoints to

< 55~ of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 505 of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour until verified acceptable at 95% or greater RATED THERMAL POWER.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shut-down or control rod:

1.

Reduce THERMAL POWER to less than 50K of RATED THERMAL

'POWER within 2'hours and reduce the Power Range Neutron Flux-High Trip Setpoints to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.

Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50$ of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour until verified at 95K or greater RATED THERMAL POWER.

SURVEILLANCE RE UIREMENTS 4.2.4 The (UADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a.

Calculating the ratio at:least once per 7 days when the alarm is OPERABLE.

b.

Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alarm is inoperable.

C.

Using the movable i ncore detectors to determine the QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when one Power Range Channel is inoperable and THERMAL POWER is

> 75 percent of RATED THERMAL POWER.

D.

C.

COOK - UNIT 1

3/4 2-12 Amendment No.

28

I

~

~

j 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN.

LIMITING CONDITION FOR-OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity equivalent to at*least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod(s).

APPLICABILITY:

MODE 2.

ACTION:

With the reactor critical (K

> 1.0)= and with less than the above reactivity equivalent availakff for tr ip insertion, immediately initiate and continue boration at

> 10 gpm of, 20,000 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1;1.1 is restored.

b.

With the reactor subcritical (K

< 1.0) by less than the above reactivity equivalent, immediat$ fy initiate and continue boration at

> 10 gpm'f'0;000'pm boric;acid,solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE RE UIREMENTS 4.10.1.1 The position of each full length rod either partially or fully withdrawn shall be, determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 Each full length rod not fully inserted shall be demonstrated OPERABLE by verifying its rod drop time to be

< 1.8 seconds within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the SHUTDOWN MARGIN to less than the.limits of Specification 3.1.1.1.

D. C.

COOK-UNIT 1 3/4 10-1 Amendment No.

28

SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is mai ntai ned

< 85%'f RATED THERMAL POWER, and b.

The 1 imits of Specifications 3.2. 2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY:

MODE 1

ACTION:

With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.4, 3.1.3.5, 3.2.1 and 3.2.4 are suspended, either:

a.

Reduce THERMAL POWER 'sufficient to satisfy, the ACTION require-ments of Specifications 3.2.2 and 3.2.3, or b.

'Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.10.2.1 The'HERMAL POWER shall be determined to be

< 85% of RATED THERMAL POWER at least once 'per hour during PHYSICS TESTS.

4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be performed at the following frequencies during PHYSICS TESTS:

a.

Specification

4. 2.2 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Specification 4.2.3 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"k THERMAL POWER 1 imit of 90'. of RATED THERMAL POWER is permissible during tests perforr,=d as part of the Augmented Startup Test Program.

D. C.

COOK-UNIT 1

3/4 10-2 Amendment No. 28

~

~

I SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.4 and 3.1.3.5 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 5f of RATED THERMAL POWER, and b.

The reactor trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels are set at

< 25>. of RATED THERMAL POWER.

APPLICABILITY:

MODE 2.

ACTION:

With the THERMAL POWER

> 5~ of RATED THERMAl POWER, immediately open the reactor trip breakers, SURVEILLANCE RE UIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be 5'5 of RATED THERMAL POWER at. least once per hour during PHYSICS TESTS.

If 4.10.4.2 Each Intermediate and Power Range Channel shall be subjected.

to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

D C

COOK Ut... T 1

3/4 10-5 Amendment No. 28

SPECIAL TEST EXCEPTION NATURAL CIRCULATION TESTS LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specification 3.4.1.1 may be suspended during the performance of PHYSICS TESTS and Thermal-Hydraulic Tests, provided:

a.

The THERMAL POWER does not exceed the P-7 Interlock Setpoint-,

and b.

The Reactor Trip Setpoints on the.OPERABLE Intermediate and Power Range Channels are set

< 25K of RATED THERMAL POWER APPLICABILITY: During operation below the P-7 Inter lock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE RE UIREMENTS 4.10.5.1 The THERMAL POWER shall, be determiried to be less than P-7 Interlock Setpoint at least once per hour during PHYSICS TESTS.

~4.10.5.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

D.

C.

COOK-UNIT 1

3/4 10-6

~

~

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATION SYSTEMS Continued)

With the RCS temperature below 200 F, one injection system is accept-able without single failyre consideration on the basis of the stable r eactivity condition of the reactor and the additional restrictions pro-hibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The boron capability required below 200 F is sufficient to provide a

SHUTDOWN'MARGIN of 1X Ak/k after xenon decay and cooldown from 200'F to 140'F.

This condition requires either 835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9690 gallons of 1950 ppm borated'water from the refueling water storage tank.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of. this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of a rod ejection accident.

, OPERABILITY.of the control rod position indicators is required to determine control rod positions and-thereby ensure compliance with the control rod alignment and insertion limits.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure, that the original criteria are met.

Misalignment of a rod requires measure-ment of peaking factors or a restriction in THERMAL POWER; either of'hese restrictions provide assurance of fuel rod integrity during continued operation.

The reactivity worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used in the accident analysis for a rod ejection accident.

The maximum rod drop time restriction is consistent with the assumed rod droo time used in the accident analyses.

Measurement with T

> 541 F

and with all reactor coolant pumps operating ensures that the meQlred drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

D.

C.

COOK-UNIT 1

B 3/4 1-3

This a

e intentiona11 left blank.,

D.

C.

COOK-UNIT 1

B 3/4 1-4 Amendment, t<o.

28

3 4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integ-r ity during Condition I (Normal Operation)= and II (Incidents of Moderate Frequency) events by:

(a) maintaining the minimum DNBR in the core 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design criteria.

In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200' is not exceeded.

The definitions of hot channel factors as used in these specifi-cations are as follows:

Fq(Z,a)

Heat Flux Hot Channel Factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation Z

divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods.

Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD Target flux difference is determined at equilibrium xenon conditions.

The full lengthrods may be positioned within the core in accordance.

with their respective insertion limits and should be inserted near their normal position for steady state operation at high power'levels.

The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Tar get. flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level.

The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

D.

C.

COOY-U>'IT 1

B 3/4 2-1 Amendment No. gp, 28

'POWER DISTRIBUTION L INITS BASES

!<<ded that the plant wi.ll,be operated wikh the AXIAL FLUX DIFFERENCE within )he

+ 5Ã target band about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion wil,lcause the AFD to deviate outside of the target band at re-duced THERMAL POWER levels., This deviation will not affect, the xenon redistribution sufficiently to change the envelope of peaking factors which may be, reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the devi-ati'on, is limited.

According1y, a

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-lative duping the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels between 50~ and 75K x T(E) of RATED THERMAL POWER.

For THERMAL POWER levels between 15% and 50Ã of RATED THERMAL POWER, devia-tions the AFD, outside of the target band are less significant.

The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

Provisions for monitoring the AFD on anautomatic basis are derived from the plant pr'ocess..computer through, the AFD Monitor Alarm., The computer determines the one minute av'erage of each of the 'OPERABLE excore detector outputs

'and provides an alarm message imnediately if the AFD for. at least 2 of 4 or 2.of 3 OPERABLE excore channels are outside the,target band and the THERMAL POWER is greater, than 75% x T(E) 'of RATED.THERMAL POWER.,During operation at THERMAL POWER levels between 5dX and 75K,x T{E) and between 15% and 50%

RATED THERMAL POWER,,the, computer outputs an alarm message when the. penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

. The upper bound limit (84~ x T{E) of RATED THERMAL POWER) on. AXIAL FLUX DIFFERENCE assures that '.he F~(Z,a) envelope of 2.32 times K(Z) x T(E) is not exce ded during either normal operati'on or in the event of xenon redistribution following 'power changes.

The lower bound limit (505 of RATED THERMAL POWER) is based on the fact that at THERMAL POWER levels below 50$ of RATED THERMAL POWER, the average linear heat generation rate is half of its nominal operating value and below that value, perturbations in lccalized flux distributions cannot affect the results of, ECCS or DHBR analyses in a manner which would adversely affect the health and safety of the public.

Figure B 3/4 2-1 shows a typical monthly target band near the beginning of core, life.

D.

C.

COOK-UNIT 1 B 3/4 2-2 Amendment Ho. Jg,

glt, 28 V

r'oil clio ve

~ svovu Therm 100/

a 0

90/o 80%

I ~

70/o x Difference Ta rget Flu 60%

60%

40%

30%o 20%

10o/

~

~

~30%

~20%

~ 10'io 0

+10% '20o~

NDICATED AXIAL FI.UX DIFFERENCE Figure B 3/4 2 'I TYPICAL IhIDICATED AXIALFLUX DIFFERENCE VERSUS THERMAL POWER AT BOL

+30%

D.

C.

COOV,-UNIT 1

B 3/4 2-3

L I

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS-F (Z) and F>H The limits on heat flux and nuclear enthalpy hot channel factors ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2), in the event of a LOCA the peak fuel clad temperature will not exceed the 2200 F

ECCS acceptance criteria limit.

t Each of these hot channel factors are measurable but will normally only be determined periodically as s'pecified in Specifications 4.2.2 and

~.2.3.

This periodic surveillance is sufficient to insure that the hot channel factor limits are maintained provided:

a.

Control rod in a single, group move together withr no in'dividual rod insertion differing by more than

+ 12 steps from the group demand position.

n Control rod groups are sequenced, with overl'apping groups as described in Specification 3.1.3.5.

(

a c.

The control rod inser tion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.

r d.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE is maintained within the limits..

The relaxation in F

H as a function of THERMAL POWER allows chanIIes in the radial power shape for all permissible rod insertion limits.

F H

will be maintained within its limits provided conditions a thru d abo3e, are maintained.

When an F

measurement is taken, both experimental error and man-ufacturing tolerance must be allowed for.

5~ is the appropriate allowance for a full core map taken with the incore detector flux mappi ng system and 3% is the appropriate allowance for manufacturing tolerance.

When F

is measured, experimental error must be allowed for and 4'~

is the apprIIIIriate allowance for a full core>nap taken with the incore detection system.

The specified limit for F

H also con a-:ns.an 8

allo)ance for uncertainties which mean that Informal opera:ion will result in F

H < 1.51/1.08.

The 8i. allowance is based on the following considera-tio'nk":

D. C.

COOK-UNIT 1 I

B 3/4 2-4 Amendment No. 28

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.NUCLEAR PLANT LOW POPULATION ZONE FIG 5

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I D. C.

COOK-UNIT' 5-3

DESIGN FEATURES DESIGN PRESSURE AHD TEMPERATURE 5.2.2 The reactor containment building is designed and shall be main-.

tained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.

PEHETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 5.4 of the FSAR wi th allowance for normal de-gradation pursuant to the applicable Surveillance Requirements 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies gath each fuel assembly containi.ng 2O4 fuel rods clad with Zjrcolop ;4, Each fuel rod shall have a nominal active fuel length of 1)4 inches and contain a maximum total weight of 2236 grams uranium.

The injtial.core loading shall have a maximum enrichment, of 3.35 weight percent U.-235.

Rel'oad fuel shall be similar in physical design to the initjal core loading and shall.have a maximum enrichment of,3.4 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies The full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent ijidium and 5

percent cadmium.

All control rods shall be, clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DES IGH PRESSURE AHD TEMPERATURE 5.4.1 The reactor coolant system is.designed and shall be maintained:

D.

C.

COOK-UNIT 1

'5-4 Amendment No."28

~pP RK0g Cg Op

~

c a '.) ~, ( I' V'

L C7

<<>>*++

NUCLEAR REGULATORY COMMISSION

'LVASHINGTDN,D. C. 20555 INDIANA AND HICHIGAN ELECTRIC COf1PANY INDIANA AND MICHIGAN POWER COtlPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 At4ENDh1ENT TO FACILITY OPERATING LICENSE Amendment No. 10 License No.

DPR-74 1

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Indiana and 'Iichigan Electric Company and Indiana

& Michigan Power Company (the licensees) dated April 4,.1979 and April 23,

1979, comply 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.

The facility.will operate in conformity wi.th the. application, the provisions oI'he Act, and the rules and regulations of tIi~ Commi ssion; C.

There is reasonable assurance'(i) that the activities author-ized 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; D.

The issuance of this amendment"will not be inimical to the commbn defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance wi th 10 CFR Part 51 of the Commission's regulations and all'pplicable 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 ecification The Technical Specifications contained in Appendices A,and 8, as revised through Amendment No.

1O

, are hereby incorporated i n the license.

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

3.

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

Attachment:

Changes to the Technical Specifications Date of Issuance:

FOR THE NUCLEAR REGULATORY COtlNISSION

~

~

/

dd~M~c4~

A. Schwencer, Chief Operating Reactors Branch

".1 Division of Operating Reactors

ATTACHMENT TO LICENSE NIENDt<ENT NO. 10 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO. 50-316 Replace the following pages of the Appendix "A" Technical Specifications with the ericlosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

~Pe es 1-3 3/4 1-18 3/4 1-19 3/4 1-20 3/4 1-21 3/4 1-22 3/4 2-3 3/4 2-7 3/4 2-13 3/4 2-14 3/4 10-1.

3/4 10-2 3/4 10-3 8 3/4 2-1

DEFINITIONS 0

CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog channels

- the injection of a simulated signal'into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions, b.

Bistable channels

- the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functi ons.

CORE ALTERATION 1,12 CORE ALTERATIOH shall be the movement or manipulation, of any com-ponent within the reactor pressure vessel with the vessel head removed and fuel in the v'esse].

" Suspension of CORE. ALTERATION shall not preclude cmpletion of movement of a component to a safe conservative

position,

'\\

SHUTDOWN HARGIN

, 1,13 SHUTDOWH NARGIN shall be the instantaneous amount of reactivity by wh'ich'he reactor is subcrjtica1 or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown. and control ) are fully inserted except f'r the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn, I'DENTIFIED LEAKAGE" 1.14 IDENTIFIED LEAKAGE shall be:

a, Leakage.(except CONTROLLED LEAKAGE) into closed

systems, such as pump seal or valve packing leaks that are captured and conducted to a

sump or collecting tank, or Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c,

Reactor coolant system leakage through a steam generator to the secondary system.

D. C, COOK - UNIT 2 1-3 Amendment No.

10

DEFINITIONS UHIDENTIFI ED LEAKAGE 1.15 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

PRESSURE BOUNDARY LEAKAGE 1.16 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

'ONTROLLED LEAKAGE 1.17 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

QUADRANT POWER TILT RATIO 1.18 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lowor excore detector

'calibrated outputs, whichever'is greater.

With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (pCi/gram) which alone would produce the same thyroid dose as the.quantity and iso-topic mixture of I-131, I-132, I-133, I-134, and I-135 actually present; The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

D. C.

COOK - UNIT 2

~

'EACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) a.

At least once per 7 days by:

V l.

Verifying the boron concentration in each water source, 2.

Verifying the contained borated water volume of each water

source, and b.

3.

Verifying the boric acid storage system solution temperature.

y t

I At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the'WST temperature when the outsi'de air temperature is

< 80'F.-

D, C.

COOK - UNIT 2 3/4 1-17

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TABLE 3.1-1 ACCIDENT ANALYSES RENDU.IRING REEVALUATION III~IIE EVE OF AN NQPEINBL N T DD Rod Cluster Control Assembly Insertion Characteristics I

Rod Cluster Control Assembly Misalignment Loss Of Reactor Coolant From Small Ruptured Pipes Or From Cracks In Large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor'Coolant System Ptpe Ruptures (Loss Of Coolant Accident).

Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Kfection)

D. C.

COOI' UNIT 2 3/4 1-2O, Amendment No, lp

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REACT I V ITY CONTROL S Y STEMS POSITION INDICATOR CHANNELS SHUTDOWN LINITING CONDITION FOR OPERATION 1,

d 3.1.3. 3 At 1 eas t one rod'os iti on indicator channel (excluding demand position indication} shall be OPERABLE for each shutdown or control rod not fully inserted, APPL'ICABILITY:

NODES 3*~, 4*8 and 5"0 ACTION:

With less than the above required position indicator channel(s)

OPERABLE, immediately open th'e reactor trip system breakers.

SURVE IL'LANCE REQUIRENENTS d

4.'1,'3,3 Each of the above required rod position indicator channel(s)

~ shhl]

b'e determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at ')east.once per 18 months, "d~did<<d 1

1 dd "See Special Test Exception 3.10.5.

D. C.

COOK - UNIT 2 3/4 1-22 Amendment 'No. 10

POWER DISTR IBUT.ION LIMITS SURVEILLANCE RE(g IRENENTS (Continued) 4.2.1.2 The indicated AFD shall be considered outside of its

+5% target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target'band, Penalty deviation outside of the

+5% target band shall be accumulated on a time basis of:

a, One minute penalty deviati on for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50K of RATED THERMAL POWER, and b,

Gne-.ha1f mi nute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15Ã and 50X of RATED THEINAL POWER.

4,2,1.3 The target flux difference of each OPERABLE excore channel shall be determi'ned by measurement at least once per 92 Effective Full Power Days.

The provisions of Specification 4.0.4 are not applicable.

4.2,1,4 The target flux difference shall be updated. at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4,2,1,3 above or by linear interpolation between th'e most. recently measured value and 0 percent at the end of the cycle

'Itive, The proyjsions of Specification 4,0,4 are not applicable, D.

C.

C00}w -. UNIT 2 3/4 2-3 Amendment No.. 10

100 u0

>o O

Z QC LlJ.xI-80

(-10, 84)

(10, 84)

'NACCEPTABLE OP E RATION UNACCEPTABLE OPERATION 60 ACCEPTABL OPERATION

(-27, 50)

(27, 50)

J 40 20 0-60

-40

-30

-20

-10 0

10 20 30 40 50 FLUX DIFFERENCE {b I) %

FIGURE 3.2-1 AXIALFLUX DIFFERENCE LIMITSAS A FUNCTION OF RATED THERMAL POWER 0.

C.

COOK - UNIT 2 3/4 2-4

0'OWER DISTRIBUTION LIMITS SURVEILLANCE RE(}UIRENENTS (Continued)-

2.

When the F

i's less than or equal to the F

limit for C

RTP xy the appropriate measured core plane, additional power distribution maps shall be taken and Fx compared to C

F and F

at least once per 31 EFPD.

L xy xy e.

The F

limits for RATED THERt)AL POWER within specific core Y,y planes shall be:

1, F

~ 1.71 for all core planes containing bank "D"

wy contxol rods, and 2.

F

< 1.55 for all unrodded core planes.

f.

The F

limits of e, above, are not applicable in the following core planes regions as measured in percent of core height from the b'ottom of. the fuel.

1, Lower core region from 0 to 15>, inclusive.,

2.

Upper core region from 85 to 100Ã, inclusive.

3, Gr id plane regions at 17.8

+ 2/, 32.1

+ 2%, 46.4

+ 25, 60,6

+ 2A and 74,9 + 2'X inc)usive.

4, Core plane regions within + 2X of core height

(+2,88'nches) about the bank demand position of the bank "P" contro'1 rods, g,

With F exceeding F

C L=.

'j.

The 'F~(Z) limit shall be reduced at least lX for each ll f

exceeds F, and C

zy Xy',

The effects of Fzy on Fq(Z). shall be evaluated to determine i:f Fq(Z) is within its limits,

,2.2.3 When F~(Z) is measured for other than F

deteminati overall measured F~(Z) shall be obtained from a power distribution map

't and increased by 3~ to account for manufacturing tolerances and further i.ncreased by 5/ to account for measurement uncertainty.

D. C.

COOV. - UNIT Z 3/4 2-7 Amendment No. 10

1.2

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(12 0, 0 0.2 0

6 CORE HElGHT (FT) 10 12 FlGURE 3.2-2 K(Z) NORMALlZEDFQ(Z) AS A FUNCTION OF CORE HElGHT

j POWER DISTRIBUTION 1TS QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2,4 THE QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPL'ICABILITY:

NODE 1 above 50% of RATED THERMAL POWER*

ACTION.',

Ni.th the QUADRANT POWER TILT RATIO determined to exceed 1.02 but

< 1.09.

1.

Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

4 a)

Either reduce the QUADRANT POWER TILT RATIO to withi n it s 1 imit, or b)

Reduce THERMAL.POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1,0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2, 3,

$erify that the (UADRANT POWER TILT RATIO is within its

'I i%it within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER withiv the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-Hi'gh Trip setpoints to

.'55% nf RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Identify and correct the cause of the out of limit con-di tion prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the qUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.

b.

With the QUADRANT POWER TILT RATIO determined to exceed 1,09 due to misalignment of either a shutdown or control rod:

1.

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1,. of indicated QUADRANT.POWER TILT RATIO in excess of 1.0, within 30 minutes.

2.

Verify tha; the QUADRANT POWER TILT RATIO is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or See Special Test Exception 3.,10.2.

D. C.

COOK - UNIT 2 3/4 2-13 Amendment No.

10

POWER DISTRIBUTION ACT1ON:

(Gontinued) reduce THERMAL POWER to less than 50 ~ of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Fl ux -Hi g h tri p Se tpo ints to

< 55," of RATED THERt~1AL POWER withi n the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3, Identify and correct the cause of the out of limit con-dition prior to increasing THERMAL POMER; subsequent POWER OPERA7ION above 50K of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until weri'fied acceptable at 95Ã or greater RATED THERMAL

POWER, c,

With the QUADRANT POWER TILT RATIO. determined to exceed 1,09 due to causes other than the misalignment of either a shut-down or control rod:

1, Reduce THERMAL POWER to less than 50~ of RATED THERMAL POMER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and,reduce the Power Pange Neutron

'F') ux-.High Tr ip Setpoints to

~ 55K of RATED THERMAL POWER wit5in the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2, Identify and correct the cause of the out of limit con-dition prior to increasing DERMAL POWER; subsequent POWER OPERATION above 50K of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified wi.thin its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or

-until verified at 95% or greater RATED THERMAL POWER, SURVE ILLAHCE RE gUIREMENTS.

4,2.4 The QUADRANT POWER TILT RATIO shall be determined to 'be within the limit ab'ove 50> of RATED THERMAL POWER 5y:

a, Calculating the ratio at least once per 7 days when the alarm i's OPERABLE, b.

Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady

- state operation when the alarm is inoperable.

c, Using the movable incore detectors to'onfirm that the power distribution i's consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when one Power Range Channel is inoperable and THERMAL POWER is

> 75 percent of

=- RATED THERMAL POWER, D. C.

COOK - UNIT 2 3/4 2-14 amendment No. 10

3/4.10 SPECIAL TEST EXCEPTIONS SHUTDORH MARG IN L IMITIHG CONDITION FOR OPERATION 3,10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth.and shutdown margin provided the reactivity equivalent to at least the highest estimated

'ontrol rod worth is available for trip insertion from OPERABLE control rod(s),

APPLICABILITY:

MODE 2.

ACTION:

a.

b.

Mi'th any full length control rod not fully inserted and with less than the ab'ove reactivity equivalent available'or trip insertion, tmmediately'ini'tiate and continue boration at

~ 10 gpm of 20,000 ppm

'oric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3. 1,1.1 is restored.

Wtth a')1 full length control rods inserted and the reactor subcritical 5'y less th'an the above reactivity equivalent, imnediately initiate

- and continue b'oration at. ~'10 gpm of 20,000 ppm boric aci'd solution or i.ts equivalent until tVe'HUTDOWN MARGIN required by Specification 3,'),l,l is restored, SURVE IL'LANCE REQUIREMENTS 4,10;1,1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1,2 Each fu'll length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn

'position'with'in 24 b'ours prior to reducing the SHUTDOWN YARGIN'to less th'an the limits of Specification 3,1.1,1.

D. C.

COOK - UNIT 2 3/4 10-]

Amendment Ho,10

SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2

.The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3,5, 3.1.3.6, 3.2.1, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is maintained 85'~ of PATED THERMAL POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3., are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY:

MODE 1

ACTION:

With any of the limits of Specifications 3.2.2 or. 3.2.3 being exceeded while. the requirements df Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2,1 and 3.2.4 are suspended, either:

a.

Reduce THERMAL POWER sufficient to satisfy the ACTION require-ments of Specifications 3.2.2 and 3.2.3, or b.

Be in HOT, STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RE UIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be

< 855 of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be performed at the following frequencies during PHYSICS TESTS:

a.

Specification 4.2.2 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Specification 4.2. 3 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D.

C. 'OOt: - UNIT 2 3/4 10-2 Amendment No. )0

SPECIAL TEST EXCEPTIONS PHYSICS 'TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed 55 of RATED THERMAL POWER, and b.

The reactor. trip setpoints on the OPERABLE Intermediate and Power Range Nuclear Channels are set at

< 25/ of RATED THERMAL POWER.

APPLICABILITY:

MODE 2.

ACTION:

With the. THERMAL POWER 5% of RATED THERMAL. POWER, immediately open the reactor trip breakers.

SURVEILLANCE RE UIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be 5% of RATED THERMAL POWER at least once per hour, during PHYSICS TESTS.

4.10.3.2 Each Intermediate and Power Range Channel shall be subjected to a

CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS.

D.

C.

COOK - UNIT 2 3/4 10-3 Amendment No.

10

SPECIAL TEST EXCEPTION REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of start up and PHYSICS TESTS provided:

a.

The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and b.

The Reactor Trip Setpoints on the OPERABLE Intermediate and Power Range Channels are set ( 25K of RATED THERMAL POWER.

APPLICABILITY: During operation below the P-7 Interlock Setpoint.

ACTION:

With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.

SURVEILLANCE RE UIREMENTS 4.'10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setpoint at least once per hour during start up and PHYSICS TESTS.

4.10.4.2

= Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a

CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating start up or PHYSICS TESTS.

D. C.

COO);

UNIT 2 3/4 10-4

~

3/4.'2 POWER DIST UTION LIMITS BASES The specifications of this section provide assurance of fuel integ-rity during Condition I (Normal Operation) and II (Incidents of Hoderate Frequency) events by:

(a) maintaining the calculated DNBR in the core-at or above design during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature and cladding mechanical properties to within assumed design criteria.

In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA ahalyses are met and the ECCS acceptance'riteria limit of 2200'F is not exceeded.

The definit>ons of certain hot channel and p'eaksng factors as used in these specifications are as follows:

Fq{Z)

FN aH Fx (Z)

Meat Flux Hot Channel Factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation Z

divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods.-

Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.

Radial Peaking Factor, is.defined as the ratio of peak

, power density to average power density in the horizontal plane at core elevation Z.

3/4:2.1 AXIAL FLUX DIFFERENCE AFD The limits on AXIAL FLUX DIFFERENCE assure that the F (Z) upper bound envelope of 2.32 times'he normalized axial peaking %actor is not exceeded during either normal operation or in the event of xenon redis-tribution following power changes.

Target flux differenpe is determined at equilibrium xenon 'conditions.

The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady state operation at high power levels.

The value of the target f1ux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup con-ditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERHAL POWER level.

The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

D.C.

COOYi - UNIT 2 B 3/4 2-1 Amendment No.

1O

POWER DrSTRIBUTION LIMITS BASES Although it is intended that the plant will be operated with the AXIAL FLUX DIFFERENCE within the

+5% target band about the target flux difference, during rapid plant THERHAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at re-duced THERMAL POWER levels.

This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERYiAL POWER (with the AFD within the target band) provided the time duration of the devi-ation is limited.

Accordingly, a

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-lative during the pr evious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target band but within the limits of Figure, 3.2-1 while at THERMAL POWER levels between 50% and 84% of RATED THERMAL POWER.

For THERNL POWER levels between 15% and 50",.- of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant.

The penalty of 2 'hours actual time reflects this reduced significance.

Provisions for monitoring the AFD on an automatic basis are derived from the'lant process computers through the AFD Honitor Alarm.

The computer determin'es the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 84~ of RATED THERNL POMER.

During operation at THERNL POMER levels between 50% and 84% and between 15% and 50%

RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1

hour and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

Figure B 3/4 2-1 shows a typical monthly'arget band.

D.C.

COOK - UNIT 2 B 3/4 2-2