Text

Amends 168 & 151 to Licenses DPR-58 & DPR-74,respectively, Making Administrative Changes to TSs
	ML17331A038
Person / Time
Site:	Cook
Issue date:	11/13/1992
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17331A039	List: ML17331A038; ML17331A040;
References
	NUDOCS 9302220305
	Download: ML17331A038 (34)
	v • d • e

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UNITED STATES t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 C

INDIANA IC IGAN OWER COMPANY 0 GETTY. 5-3 3

DONALD C.

COOK UCLEAR PLANT UN T NO.

1 M NDMENT TO CIL Y OPERA ING L C

NSE Amendment No.

168 License No. DPR-58 l.

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

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated February 15, 1991 as supplemented September 13,

1991, 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.

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 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; 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 of the Commission's regulations and all applicable requirements have been satisfied.

9aoamoaoS 9a~>S3

~

PDR ADOCK 050003l5, PDR

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 amended to read as follows:

echnical S eci at o

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 16'8

, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION p'8 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 13, 1gg2

TTACHHENT TO L CENSE AHENDHENT NO.

TO FACILITY OP RATING LIC NSE 0

P -58 OCKET NO. 50-3 5

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

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

HOVE 2-1 2-2 2-6 3/4 3-29 3/4 3-37 3/4 3-53 3/4 3-55 3/4 4-36 3/4 6-15 3/4 6-21 3/4 7-5 5-1 NSERT 2-1 2-2 2-6 3/4 3-29 3/4 3-37 3/4 3-53 3/4 3-55 3/4 4-36 3/4 6-15 3/4 6-21 3/4 7-5 5-1

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAPETY LIMITS REACTOR CORE 2.1.1 The combination of THBQRL pOWER, pressuriser

pzessuze, and the r

highest operating loop coolant average temperature (T

) shall not exceed avg the limits shovn in Pigure 2.1-1 for 4 loop operation.

APPLICABILITY:

MODES 1 and 2.

ACTION:

Whenever the point defined by the combination of'he hfghest operating loop average temperature and THERMAL POWER has exceeded the approprfate pressurizer pzessure line, be fn HOT STANDBY vithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1 and 2

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be fn HOT STANDBY vith the Reactor Coolant System pressure vfthin its limit vithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

MODES 3, 4 and 5

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressuze to vfthin fts limit vf'thin 5 minutes.

COOK NUCLEAR PLANT - UNIT 1 2-1 AMENDMENT NO. X7P, 168

65a-

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UNACCEPTABLE OPERATION eia

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P4~ 618 1~<o Dsi<

S~e 588 ACCEPTABLE OPERATION S-.a e.

PRESSURE (PS IA)

.3

.4

.5

.6

.7

.e

.'1 1 ~

F 1 1.2 POYER ttrection ol reainol)

BREAK POINTS (FRACTION RATED THERNL POWER, T-AVG IN DEGREES F) 1840 2000 2100 2250 2400 (0.0, 622.1),

(1.13, 587.3),

(1.20, 577.5)

(0.0, 633.8),

(1.08, 601.4),

(1.20, 586.0)

(0.0, 640.8),

(1.06, 609.8), (1.20, 591.3)

{0.0, 650.7),

(1.02, 621.9), {1.20, 598.9)

(0.0, 660.1),

(0.98, 633.7),

(1.20, 606.2)

FIGURE 2.1-1 REACTOR CORE SAFETY LIMITS COOK liVC'"=QL PLAVZ - UNIT 1 2~2 A~<VDMEVT No. 7/t le@

Zgg, 168

TABLE 2.2-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 13.Steam Generator Veter Lcvcl-Lov-Lov 14.Steam/Feedvater Flow Mismatch and Lov Steam Generator Veter Level Greater than or equal to 17%

of narrov range instrument span - each steam generator Less than6or equal to 0.71 x 10 lb/hr of steam flov at RATED DERMAL POWER coincident vith steam generator vater level greater than or equal to 25%

of narrov range instrument span - each stcam generator Greater than or equal to 16% of narrov range instrument span - each steam generator Less than6or equal to 0.73 x 10 lbs/hr of steam flov at RATED THERMAL POWER coincident vith steam generator vater level greater than or equal to 24% of narrow range instrument span - each steam generator 15.Undervoltage-Reactor Coolant Pumps Greater than or equal to 2750 volts - each bus Greater than or equal to 2725 volts - each bus 16.Underfrequency-Reactor Coolant Pumps Greeter then or equal to 57.5 Hz - each bus Greater than or equal to 57.4 Hz - each bus 17.Turbine Trip A. Low Fluid Oil Pressure B. Turbine Stop Valve Closure Greeter than or equal to 800 psig Greeter than or equal to 1% open Greater than or equal to 750 psig Greater than or equal to lt open 18.Safety Injection Input from ESF Not Applicable Not Applicable 19.Reactor Coolant Pump Breaker Position Trip Not Applicable Not Applicable COOK NUCLEAR PLANT - UNIT 1 2-6 AMENDMENT NO.

$g, 168

TASLE 3.3 5

Continued ENCINZZRED SAFETY FEATURES RESPONSE TIMES NITIATINC SICNAL AND FUNCTION

RESPONSE

TIME IN SECONDS-6.

Steam Flov in Tvo Steam Lines Hi h Coincident Mith Steam Lfne Pressure Lov a.

Safety Injection (ECCS) b.

Reactor Trip (from SI) c.

Feedvater Isolation d.

Contafnment Isolation-Phase A

I e.

Containmcnt Purge and Exhaust Isolation f.

Auxiliary Feedvater Pumps g.

Essential Service Mater System h.

Steam Line Isolation 7.

Containment Pressure--Hf h.Hi h Less than or equal 27.088/3>.%

Less than oz equal Less than or equal Less than or equal

18. 0s/28. &we Not Applfcable Not Applfcable Less than or equal 14.0e/48.Owe Less than or equal to to 3.0 to 8.0 to to to 11.0 b.

C.

d.

Containment Spray Containment Isolation-Phase "b"

Steam Line Isolation Containment Air Recirculation Fan Less than or equal to 45.0 Not Applicable Less than or equal to 10.0 Less than or equal to 600.0 8.

5:earn Generator Rater Level--Hi h-Hi h a.

Turbine Trip b.

Feedvater Isolation Less than or equal to 2.5 Less than or equal to 11.0 9.

5=earn Cenerator Mater Levels

-Lov.Lov a.

Motor Driven Auxilfary Feedvater Pumps Less than or equal to 60.0 b.

Turbine Driven Auxiliary Feedvater Pumps Less than or equal to 60.0 10.

4160 volt Emer enc Sus Loss of Volta e a.

Motor Drfven Auxiliary Feedvater Pumps Less than or equal to 60.0 11.

Loss of Main Feedvatez Pum s

a.

Motor Driven Auxiliary Feedvater Pumps Less than or equal to 60.0

12. Reactor Coolant Pum Sus Undenrolta e

a.

Turbine Drfven Auxiliary Feedvater Pumps Less than or equal to 60.0 COOK NUCLEAR PLANT - UNIT 1 3/4 3 29 AMENDMENT No. N, Zll, XA7 g

168

I OJ 4

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 20 - Vith the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply vith the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - Vith the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area vith portable monitoring instrumentation at least once per day.

ACTION 22 - Vith the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply vith the ACTION requirements of Specification 3.9.9.

This ACTION is not required during the performance of containment integrated leak rate test.

ACTION 22A-Vith the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable Channel(s) to OPERABLE status vithin 7 days of the event, or

2. prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 vithin 14 days folloving the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3. Technical Specification Sections 3.0.3 and 3.0.4 Not Applicable.

ACTION 22B-Vith the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.

l. either restore the inoperable Channel(s) to OPERABLE status vithin 7 days of the event, or

2. prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 vithin 14 days folloving the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3. In the event of an accident involving radiological releases initiate the preplanned alternate method of monitoring the appropriate parameter(s) vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Technical Specification Sections 3.0.3 and 3.0.4 Not Applicable.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-37 AMENDMENT NO. N, XW, 168

TABLE 3.3-10 Unit 1 and Common Area Ffre Detection S stems IXtector S stem Location Total Number of Detectors Auxiliary Building a) Elevation 573 b) Elevation 581 c) Elevation 609 d) Elevation 633 e) Elevatfon 650 f) Nev Fuel STGE Area g)

RP Access Control & Chem Labs Ul East Main Steam Valve Enclosure Ul Main Steam Line Arcs El.

612 (Around Containment)

Ul NESV Valve Area El.

612 Ul 4KV Svitchgear (AB)

Ul 4KV Svitchgear (CD)

Ul Engr. Safety System Svitchgear 6 XFMR. Rm.

Ul CRD, XFMR, & Svitchgear Rm.

Znverter

& Bttry. Rms.

Ul Pressurizer Heater XFMR. Rm.

Ul Diesel Fuel Oil Transfer Pump Rm.

Ul Diesel Generator Rm.

1AB Ul Diesel Generator Rm.

1CD Ul Diesel Generator Ramp Corr.

Ul&2 AFPP Vestibule Ul Control Room Ul Svitchgear Cable Vault Ul Control Room Cable Vault Ul Aux. Cable Vault Ul&2 ESV Basement Area Ul ESP Pump 6

MCC Rms.

Heat (x/y)*

0/1 0/2 0/2 P1&>>&

(&/r)>>

0/3 0/3 0/5 0/5 0/104%%

Smoke (x/y)*

23/OC 55/OC 41/OC 41/OC 34/OC 4/OC 25/0 28/O~

13/QA+

2/0 0/2 0/2 0/9 0/8 12/0 4/Q 2/OC 45/0 0/13 0/65~

0/6 4/OC 9/0 C System protects area common to both Units 1 and 2

+'(x/y) x is number of Function h (carly varning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early varning and notification) fnstruments.

circuit contains both smoke and flame detectors tvo cfrcuits of five detectors each tvo circuits of 32 and 33 detectors each COOK NUCLEAR PLANT - UNlT 1 3/4 3-53 AMENDMENT NO. 7gi ggg, 168

OST-CCIDE MONITORING INSTRUMENT ON

~NS RUMENQ MINIMUM CHANNELS QZK>$5IZc 1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

Containment Pressure Reactor Coolant Outlet Temperature-T~ (Vide Range)

Reactor Coolant Inlet Temperature-Tco~ (Wide Range)

Reactor Coolant Pressure-Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level-Narrow Range Refueling Vater Storage Tank Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator -- Limit Switches~

PORV Block Valve Position Indicator -- Limit Switches Safety Valve Position Indicator -- Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

Containment Sump Level Containment Water Level 2

2 2

2/Steam Generator 1/Steam Generator 2

1 1/Steam Generator+

1/Valve 1/Valve~

1/Valve 2/Core Quadrant One Train (3 Channels/Train) 2 Steam Generator Qatar Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.

PPC subcooling margin readout can be used as a substi,tute for the subcooling monitor instrument.

Acoustic monitoring of PORV position (1 channel per three valves - headered discharge) can be used as a substitute for the PORV Indicator - Limit Switches instruments.

The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.

The schedule for modification or replacement of the transmitters is described in the Bases.

~ Pressurizer safety valve (SV-45A) position indicator acoustic moni.tor QR-107A is exempted from the above requirements until the end of Cycle 12.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-55 Amendment }to. 404,- 444,

161, 168

REACTOR COOLANT SYSTEM LIMITING CONDITION POR OPERATION (Continued) 2.

Vith tvo or more block valves inoperable, vithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore a total of at least tvo block valves to OPERABLE status, or (2) close the block valves and remove pover from the block valves, or (3) close the associated PORVs and remove pover from their associated solenoid valves; and apply the portions of ACTION a.2 or a.3 above for inoperable PORVs, relating to OPERATIONAL MODE, as appropriate.

c.

Vith PORVs and block valves not in the same line inopcrablc,+

vithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore the valves to OPERABLE status or (2) close and de-energize the other valve in each line.

Apply the portions of ACTION a.2 or a.3 above, relating to OPERATIONAL MODE, as approprfate for tvo or three 1fnes unavailable.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE:

a.

At least once pcr 31 days by performance of CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.

At least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through onc complete cycle of full travel.

The block valve(s) do not have to be tested vhen ACTION 3.4.1l.a or 3.4.ll.c is applied.

4.4.11.3 The emergency pover supply foz'he PORVs and block valves shall be demonstrated OPERABLE at least once per 1& months by operating the valves through a complete cycle of full travel vhile the emergency buses are energized by the onsite diesel generators and onsfte plant batteries.

This testing can be performed in con)unction vith the requirements of Specifications 4.8.2.3.2.d and 4.8.1.1.2.e.

PORVs isolated to limit RCS leakage through their seats and the block valves shut to isolate this leakage are not considered inoperable.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-36 AMENDMENT NO. WV, nP. ZH 165

C EN URV LLANCE R UIREME S

4.6.3.1.2 Each isolation valve'specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months a.

b.

Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

'Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

c.

Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

COOK NUCLEAR PIANT - UNIT 1 3/4 6-15 AMENDMENT NO. ~, 444, PyP, 168

TABLE 3. 6-1 Continued VALVE NUMBER FUNCTION ISOLATION TIME IN SECONDS C.

CONTAINMENT PURGE EXHAUS~

Continued 12.

VCR-205 13.

VCR-206

14. VCR-207*

UPPER COMP.

PURGE AIR INLET UPPER COMP.

PURGE AIR OUTLET CONT.

PRESS RELIEF FAN ISOLATION D. MANUAL ISOLATION VALVES 1.

ICM-111 2.

ICM-129 3.

ICM-250 4.

ICM-251 5.

ICM-260 6.

ICM-265 7.

ICM-305 8.

ICM-306 9.

ICM-311 10.

ICM-321 11.

HPX 151 VI 12; Ph 343

13. SF-151 14.

SF-153

15. SF-159

16. SF-160

17. SI-171

18. SI-172 RHR TO RC COLD LEGS RHR INLET TO PUMPS BORON INJECTION OUTLET BORON INJECTION OUTLET SAFETY INJECTION OUTLET SAFETY INJECTION OUTLET RHR/CTS SUCTION FROM SUMP RHR/CTS SUCTION FROM SUMP RHR TO RC HOT LEGS RHR TO RC HOT LEGS DEAD %EIGHT TESTER CONTAINMENT SERVICE AIR REFUELING VATER SUPPLY REFUELING VATER SUPPLY REFUELING CAVITY DRAIN TO PURIFICATION SYSTEM REFUELING CAVITY DRAIN TO PURIFICATION SYSTEM SAFETY INJECTION TEST LINE ACCUMULATOR TEST LINE Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh Nh COOK NUCLEAR PLANT - UNIT 1 3/4 6-21 AMENDMENT NO.

$fg~ 168

PLANT SYSTEMS AUXILIARYFEEDVATER SYSTEM MITING CONDITION FOR OPERATION 3.7.1.2 a.

At least three independent steam generator auxilfary feedwater pumps and associated flov paths shall be OPERABLE vith:

1.

Tvo motor-driven auxfliazy feedvater

pumps, each capable of being povered from separate emergency busses, and 2.

One steam turbine-driven auxiliary feedvater pump capable of being povcred from an OPERABLE steam supply system.

b, At least one auxiliary feedvatcr flovpath in suppozt of Unit 2 shutdovn functfons shall bc available.

APPLICABILITY:

Specification 3.7.1.2.a - MODES 1, 2, 3.

Specification 3.7.1.2.b - ht all times vhen Unit 2 is fn MODES 1, 2, or 3.

ACTIONS:

Vhen Specification 3.7.1.2.a fs applicable:

Vfth one auxfliazy fcedvater pump inoperable, restore the required auxiliary feedwatcr pumps to OPERABLE status vithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or bc fn at least HOT STANDBY vfthfn the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and fn HOT SHUTDOVN vithin the follovfng 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

Vith tvo auxiliary feedwatcr pumps inoperable, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOVN vithin the folloving 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

Vith three auxiliary fecdwater pumps inoperable, immediately fnitiate correctfve action to restore at least one auxiliary feedvatez pump to OPERABLE status as soon as possfble.

Vhen Specification 3.7.1.2.b is applicable:

Vith no flow path to Unit 2 available, return at least one flov path to available status vithfn 7 days, or provide equivalent shutdovn capability in Unit 2 and return at least one flov path to avaflable status vithin the next 60 days, or have Unft 2 fn HOT STANDBY vithin thc next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOVN vithin the folloving 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The requizements of Specffication 3.0.4 are not applicable.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-5 AMENDMENT NO ~

Ple 27Pe ass 168

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.

LOV POPULATION ZONE 5.1.2

.The low populatfan xone shall be as shown in Ffgure 5.1-2.

Site Bounda Far Gaseous and Li uid Effluents 5.1.3 The SITE BOUNDARY for gaseous and lfqufd effluents shall be as shown in Figure 5.1-3.

5. 2 CONTAINMENT CONFIGURATION 5.2.l The reactor cantainmcnt building fs a steel lined, reinforced concrete building of cylfndrfcal shape, vfth a dome roof and having the followfng design features:

a.

b.

Ce e.

go Nominal inside diameter ~ 115 feet.

Nominal fns ide height ~ 160 feet.*

Minimum thickness of concrete veils ~ 3'6".

Minfmum thfckness of concrete roof ~ 2'6".

Minimum thickness of concrete floor pad ~ 10 feet.

Nominal thickness of steel liner, side and dome 3/8 inches.

Nominal thickness af steel liner, bottom 1/4 inch.

h.

Net free volume ~ 1.24 x 10 cubic feet.

6

From grade (Elev. 608') to inside of dome.

COOK NUCLEAR PLANT - UNIT 1 5-1 AMENDMENT NO. Af 168

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t UNITEDSTATES t

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY

\\

ILOCDo.

5 -3 DONALD C.

COOK UCLEAR PLANT UNIT O.

2 MENDMENT TO FACI TY OPERATING LICENS Amendment No. 151 License No. DPR-74 1.

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

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated February 15, 1991 as supplemented September 13,

1991, 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.

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 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; 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 of 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-74 is hereby amended to read as follows:

Technical S

e 'f'cat o s The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

151, are hereby incorporated in the license.

The licensee 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:

November 13, 1992 FOR THE NUCLEAR REGULATORY COMMISSION pe~~

Ledyard B. Harsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

TTACHHENT TO C

NSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO.

DPR-7 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages, identified below and inserting the attached pages.

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

REMOVE 1-7 2-1 2-6 3/4 2-1 3/4 3-36 3/4 3-46 3/4 3-52 3/4 4-33 3/4 6-27 3/4 7-5 3/4 8-20 3/4 9-9

" 5-1 INSERT 1-7 2-1 2-6 3/4 2-1 3/4 3-36 3/4 3-46 3/4 3-52 3/4 4-33 3/4 6-27 3/4 7-5 3/4 8-20 3/4 9-9 5-1

DEFINITIONS SOLIDIFICATION 1.29 'OLIDIFICATIONshall be the conversion of radioactive liquid, resin and sludge vastes from liquid systems into a form that meets shipping and burial site requirements.

OFFSITE DOSE CALCULATION MANUAL ODCM 1.30 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints and the conduct of environmental radiological monitoring program.

GASEOUS RADWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

PURGE-PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

COOK NUCLEAR PLANT - UNIT 2 1-7 AMENDMENT NO.

gg, 151

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressur'izer pressure, and the highest operating loop coolant average temperature (T

) shall not exceed the limits shown in Figure 2.1-1 for 4 loop operation.

APPLICABILITY:

MODES 1 and 2.

ACTION:

Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1 and 2

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

MODES 3, 4 and 5

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

COOK NUCLEAR PLANT - UNIT 2 2-1 AMENDMENT NO.

HR, 151

LE 2-o t ued EACTOR TRIP S

STEM INSTRUME ATION TRIP SET OI S

C 0AL I

0 W

LEVLU 13.Steam Generator Water Level-Low-Low Greater than or equal to 21X of narrow range instrument span - each steam generator Greater than or equal to 19.2X of narrow range instrument span - each steam generator 14.Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level Less than or equal to 1.47 x 10 lbs/hr of steam flow at RATED THERMAL POWER coincident with steam generator water level greater than or equal to 25X of narrow range instrument span

- each steam generator Less than or equal to 1.56 x 10 lbs/hr of steam flow at RATED THERMAL POWER coincident with steam generator water level greater than or 'equal to 24X of narrow range instrument span

- each steam generator 15.Undervoltage-Reactor Coolant Pumps Greater than or equal to 2905 volts - each bus Greater than or equal to 2870 volts - each bus 16.Underfrequency-Reactor Coolant Pumps Greater than or equal to 57.5 Hz - each bus Greater than or equal to 57.4 Hz - each bus 17.Turbine Trip A. Low Fluid Oil Pressure B. Turbine Stop Valve Closure Greater than or equal to 58 psig Greater than or equal to 1X open Greater than or equal to 57 psig Greater than or equal to 1X open 18.Safety Injection Not Applicable Input from ESF Not Applicable 19.Reactor Coolant Pump Not Applicable Breaker Position Trip Not Applicable COOK NUCLEAR PLANT - UNIT 2 2-6 AMENDMENT NO. 4R, jlPP, ]5]

3.4.2 POWER DISTRIBUTION LIMITS AXIALFLUX DIFFERENCE AFD LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIALFLUX DIFFERENCE (AFD) shall be maintained within the target band about a targe flux difference.

The target band is specified in the COLR.

APPLICABILITY:

MODE 1 above 50% RATED THERMAL POWER+

ACTION:

a.

With the indicated AXIALFLUX DIFFERENCE outside of the target band about the target flux difference and vith THERMAL POWER:

1.

Above 90% or 0.9 x APL (whichever is less) of RATED THERMAL POWER, vithin 15 minutes:

a)

Either restore the indicated AFD to vithin the tazget bend limits, or b)

Reduce THERMAL POWER to less than 90% or 0.9 x APL (vhichevez is less) of RATED 'GKDiAL POWER.

2.

Betveen 50% and 90% or 0.9 x APL (whichever is less) of RATED TfKRMAL POWER:

a)

POWER OPERATION may continue pzovided:

1)

The indicated AFD has not been outside of the target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2)

The indicated AFD is within the limits specified in the COLR.

Otherwise, reduce THE29fAL POWER to less than 50% of RATED KKRMAL POWER within 30 minutes and reduce the Pover Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED Tki&QfALPOWER vithin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b)

Surveillance testing of the Pover Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained vithin the limit specified in the COLR.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated vith the AFD outside of the target band during this testing without penalty deviation.

+ See Special Test Exception 3.10.2 COOK NUCLEAR PLANT - UNIT 2 3/4 2-1 AMENDMENT NO, Xn, ZW, 151

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 20 - Vith the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - Vith the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.9.9.

This ACTION is not required during the performance of containment integrated leak rate test.

ACTION 22A-Vith the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2. prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3. Technical Specification Sections 3.0.3 and 3.0.4 Not Applicable.

ACTION 22B-Vith the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.

l. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2. prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.

Zn the event of an accident involving radiological releases initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Technical Specification Sections 3.0.3 and 3.0.4 Not Applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-36 AMENDMENT NO. gP, XZP ~ ]5(

TABLE 3 3-10 OST-ACCIDEN MONITORING INSTRUMENTATION STRUMENT MINIMUM CHANNELS OPERABLE 1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

Containment Pressure Reactor Coolant Outlet Temperature

- TH~ (Wide Range)

Reactor Coolant Inlet Temperature

- Tco~ (Wide Range)

Reactor Coolant Pressure

- Wide Range Pressurizer Water Level Steam Line Pressure Steam Generator Water Level - Narrow Range Refueling Water Storage Tank Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator - Limit Switches~*

PORV Block Valve Position Indicator - Limit Switches Safety Valve Position Indicator - Acoustic Monitor++++*

Incore Thermocouples (Core Exit Thermocouples)

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

Containment Sump Level Containment Water Level 2

2 2

2/Steam Generator 1/Steam Generator 2

1 1/Steam Generator+

1/Valve 1/Valve 1/Valve 2/Core Quadrant One Train (3 channels/Train)

]~*

2+4+*

Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.

PPC subcooling margin readout can be used as a substitute for the subcooling monitor instrument.

Acoustic monitoring of PORV position (1 channel per three valves

- headered discharge) can be used as a substitute for the PORV Indicator - Limit Switches instruments.

++++ The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.

The schedule for modification or replacement of the transmitters is described in the Bases.

~Pressurizer safety valve (SV-45C) position indicator acoustic monitor QR-107C is exempted from the above requirements until the end of Cycle 8.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-46 Amendment No. OR, ~ lgg~

151

TABLE 3.3-11 Unit 2 and Common Area Fire Detection S stems Detec'tion S stem Location Total Number of Detectors Auxiliary Building a) Elevation 573 b) Elevation 587 c) Elevation 609 d) Elevation 633 e) Elevation 650 f) Nev Fuel STGE Area U2 East Main Steam Valve Enclosure U2 Main Steam Line Area El.

612 (Around Containment)

U2 NESV Valve Area El.

612 Heat (x/y)*

Flaae

(*/X)e Smoke (z/y)*

23/OC 55/OC 41/OC 41/OC 34/OC 4/OC 28/0~

13/P~

2/0 U2 4KV Svitchgear (AB)

U2 4KV Svitchgear (CD)

U2 Engr. Safety System Svi.tchgear 6

XFMR. Rm.

U2

CRD, XFMR 6 Svitchgear Rm.

Inverter 6 AB Bttry. Rms.

U2 Pressurizer Heater XFMR. Rm.

U2 Diesel Fuel Oil XFMR. Rm.

U2 Diesel Generator Rm.

2AB U2 Di.esel Generator Rm.

2CD U2 Diesel Generator Ramp Corr.

Ul&2 AFVP Vestibule U2 Control Room U2 Svitchgear Cable Vault U2 Control Rm. Cable Vault U2 Aux. Cable Vault 0/1 0/2 0/2 0/3 0/3 0/2 0/2 0/5 0/14 0/5 0/17 12/0 4/0 2/OC 42/0 P/10%%+

P/13 0/76~

0/6 Ul&2 ESV Basement brea U2 ESV Pump 6

MCC Rms.

4/OC 9/0 C System protects area common to both Units 1 and 2

(x/y) x is number of Function h (early varning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early varning and notification) instruments.

circuit contains both smoke and flame detectors tvo circuits of five detectors each tvo circuits of 38 detectors each COOK NUCLEAR PLANT - UNIT 2 3/4 3-52 AMENDMENT NO.

HZ. ZZ$

151

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued 2.

Vith two or more block valves inoperable,

%ithunn 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore a total of at least two block valves to OPERABLE status, or (2) close the block valves and remove power from the block valves, or (3) close the associated PORVs and remove power from their associated solenoid valves; and apply the portions of ACTZON a.2 or a.3 above for inoperable PORVs, relating to OPERATIONAL MODE, as appropriate.

c.

With PORVs and block valves not in the same line inoperable,*

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1) restore the valves to OPERABLE status or (2) close and de-energize the other valve in each line.

Apply the portions of ACTION a.2 or a.3 above, relating to OPERATIONAL MODE, as appropriate for tvo or three lines nnavailable.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE:

a.

At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.

At least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

The block valve(s) do not have to be tested when ACTION 3.4.11.a or 3.4.1l.c is applied.

4.4.11.3 The emergency power supply for 'the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries.

This testing can be performed in con5unction with the requirements of Specifications 4.8.1.1.2.e and 4.8.2.3.2.d.

PORVs isolated to limit RCS leakage through their seats and the block ~alves shut to isolate this leakage are not considered inoperable.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-33 AMENDMENT NO.

PR, 97, AS'51

TABLE 3.6-1 (Cont'd)

CONTAINMENT ISOLATION VALVES VALVE NUMBER D.

MANUAL ISOLATION VALVES (Cont'd)

(1)

FUNCTION ISOLATION TIME IN SECONDS 3.

ICM-250 4.

ICM<<251 5.

ICM-260 6.

ICM-265 7.

ICM-305 8.

ICM-306 9.

ICM-3110 10.

ICM-3210 BORON INJECTION OUTLET BORON INJECTION OUTLET SAFETY INJECTION OUTLET SAFETY INJECTION OUTLET RHR/CTS SUCTION FROM SUMP RHR/CTS SUCTION FROM SUMP RHR TO RC HOT LEGS RHR TO RC HOT LEGS NA Nh NA Nh Nh Nh E.

OTHER 1.

CS-442-1 2.

CS-442-2 3.

Cs-442-3 4.

CS-442-4 SEAL QTR.

TO RCP $1 SEAL QTR.

TO RCP 52 SEAL QTR.

TO RCP 83 SEAL QTR.

TO RCP iP4 Nh Nh COOK NUCLEAR PLANT - UNIT 2 3/4 6-27 AMENDMENT NO.

151

PLANT SYSTEMS AUXILIARYFEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 a.

At least three independent steam generator auxfliary feedvater pumps and assocfated flov paths shall be OPERABLE vith:

1.

Two motor-drfven auxiliary feedvater

pumps, each capable of being povered from separate emergency busses, and 2.

One steam turbine-driven auxilfary feedwater pump capable of being povered from an OPERABLE steam supply system.

b.

At least one auxiliary feedwater flov path in support of Unit 1 shutdovn function shall be available.

APPLICABILITY:

Specificatfon 3.7.1.2.a

- MODES 1, 2, 3.

Specification 3.7.1.2.b - At all times vhen Unit 1 is fn MODES 1, 2, or 3.

ACTIONS:

When Specification 3.7.1.2.a is applicable:

a.

With one auxiliary feedvater pump inoperable, restore the required auxiliary feedvater pumps to OPERABLE status vithin 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 HOT SHUTDOWN within the folloving 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With tvo auxiliary feedwater pumps inoperable, be in at least HOT STANDBY wfthin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT Shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedvater pumps fnoperable, immediately initiate corrective action to restore at least one auxiliary feedvater pump to OPERABLE status as soon as possible.

When Specification 3.7.1.2.b is applicable:

With no flow path to Unit 1 available, return at least one flow path to available status vithfn 7 days, or provide equivalent shutdown capability in Unit 1 and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN vithin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The requfrements of Specificatfon 3.0.4 are not applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-5 AMENDMENT NO.

HS le, 151

ELECTRICAL POWER SYSTEMS 3 4.8.3 Alternative A.C. Po~er Sources LIMITING CONDITION FOR OPERATION 3.8.3.1 The steady state bus voltage for the manual alternate reserve source*

shall be greater than or equal to 90% of the nominal bus voltage.

APPLICABILITY: Whenever the manual alternate reserve source (69 RV) is connected to more than two buses.

ACTION:

With bus voltage less than 90% nominal, adjust load on the remaining buses to maintain steady state bus voltage gteatet than ot equal to 90 t'imit.

SURVEILLANCE RE UIREMENTS 4.8.3.1 No additional surveillance requirements other than those required by Specifications 4.8.1.1.1 and 4.8.1.2.

Shared vith Cook Nuclear Plant Unit 1.

COOK NUCLEAR PLANT - UNIT 2 3/4 8-20 AMENDMENT NO.

ging, 151

REFUELING OPERATIONS CONTAINMENT PURGE AND 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:

Vith 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 provisions of Specification 3.0.3 are not, applicable.

SURVEILLANCE RE UIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment Purge and Exhaust isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels.

COOK NUCLEAR PLANT - UNIT 2 3/4 9-9 AMENDMENT NO. p7 pp

5. 0 DESIGN FEATURES

5. 1 SITE Exclusion Area 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.

Low Po ulation Zone 5.1.2 The low population xone shall be as shown in Figure 5.1-2.

Site Bounda For Gaseous and Li id Effluents 5.1.3 The SITE BOUNDARY for gaseous and liquid effluents shall be as shown in Figure 5.1-3.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:

a.

Nominal inside diameter 115 feet.

b.

Nominal inside height 160 feet.

c.

Minimum thickness of concrete walls ~ 3'6".

d.

Minimum thickness of concrete roof ~ 2'6".

e.

Minimum thickness of concrete floor pad 10 feet.

f.

Nominal thickness of steel liner 3/8 inches.

g.

Net free volume 1.24 x 10 cubic feet.

6 DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.2 of the FSAR.

COOK NUCLEAR PLANT - UNIT 2 5-1 AMENDMENT NO ~ gl,

ML17331A038

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