ML17332A578

Amends 189 & 175 to Licenses DPR-58 & DPR-74,respectively, Revising TS to Relocate Radiological Effluent TS to Other Documents,In Response to GL Requirement

ML17332A578
Person / Time
Site:	Cook
Issue date:	02/10/1995
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML17332A579	List: ML17332A578 ML17332A580
References
GL-89-01, GL-89-1, NUDOCS 9502270348
Download: ML17332A578 (91)

Text

gals RECII c<

0 Cy o

05 r...

0

~O

++*++

UNiTED STATES NUCLEAR REGULATORY COMMISSION.

WASHINGTON, D.C. 205554001 INDIANA HICHIGAN POWER COMPANY

~KKET lll.

DONALD C.

COOK NUCLEAR PLANT UNIT NO.

AHENDHENT TO FACILITY OPERATING LICENSE Amendment No.

I89 License No. DPR-58 1.

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

A.

The application for amendment by Indiana Hichigan Power Company (the licensee) dated August 3,

1994, 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 Commi.ssion; 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.

9502270348 9502i0'DR ADQCK 050003i5 P

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:

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

189, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 10, 1995 John N. Hannon, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

9 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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 III V

X XI XII XIII XIV XV XVI XVII XVIII 1-5 1-6 3/4 3-36 3/4 3-36a 3/4 3-36b 3/4 3-38 3/4 3-38a 3/4 3-38b 3/4 3-57 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 3-67 3/4 3-68 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-6 3/4 11-7 INSERT III V

X XI XII XIII XIV XV XVI XVII 1-5 1-6 3/4 3-36 3/4 3-36a 3/4 3-38 3/4 3-38a 3/4 3-57 3/4 3-58 3/4 3-59 3/4 11-1 3/4 11-2 3/4 11-3

j

3/4 1 1-8 3/4 1 1-9 3/4 1 1-1 0 3/4 1l-l1 3/4 1 1-1 2 3/4 1 1-1 3 3/4 1 1-1 4 3/4 1 1-15 3/4 1 1-I6 3/4 1 1-1 7 3/4 1 2-1 3/4 1 2-2 3/4 12-3 3/4 12-4 3/4 1 2-4a 3/4 12-5 3/4 1 2-6 3/4 1 2-7 3/4 1 2-8 3/4 1 2-9 3/4 12-1 0 8 3/4 3-4 8 3/4 3-7 8 3/4 1 1 -1 8 3/4 1 1-2 8 3/4 1 1 -3 8

, 3/4 1 1-4 8 3/4 1 1-5 8 3/4 1 2-1 6-1 2 6-1 3 6-14 6-15 6-16 6-17 6-18 6-19 6-20 6-21 6-22 6-23 8 3/4 3-4 8 3/4 3-7 8 3/4 11-1 6-12 6-13 6-13a 6-13b 6-13c 6-14 6-15 6-16 6-17 6-18 6-19 6-20 6-21 6-22

EFINI ONS efined Terms.................,.....................

D ermal Power................................................

1 1 Th Rated Thermal Power...........................

Operational Mode.........................

CtiOn,ooo

~ o ~ ~ oooooooo

~ ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~

~

~

~

~ ~

A

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~ ~

Operable

- Operability...............................

~

~

~

~

l-l Reportable Event..............................

~ ~

~

~

1 2 Containment Integrity........................................

1-2 Channel Calibration....................

~

~

~

~

~

~

~

~

~

~ ~ ~

~ ~

~

~ o

~

~

znnel Check..............

Ck 1-2 CkuLnnel Functional Test..................

Core Alteration..;.........

~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~

1~3 1-3 Shutdown Margino ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

~ ~

~ ~

~ ~ ~

~ o

~

~

~

~ ~

~ ~

~ ~

W Identified Leakage.........

1-3 Unidentified Leakage..

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Pressure Boundary Leakage.............

~

~

~

~ ~ ~ ~

~

~

~ ~

~

~

~

ontrolled Leakage.....................................

C 1-4 Quadrant Power Tilt Ratio................

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

1 4 Dose Equivalent I-131........................................

1-4 Staggered Test Basis.........................................

1-4 Frequency Notation..............................

1-5 Reactor Trip System Response Time...............

Engineered Safety Feature Response Time............

1-5

~

~ ~

~

1 5 Axial Flux Difference..............................

1-5 Physics Testsooo

~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~

E - Average Disintegration Energy......

o ~ o ~ ~

~ ~ ~

~ ~

~ ~ ~

~

~ ~ ~ ~ ~ ~ ~

~

1 5

~ ~

~ ~

~ ~

~ ~

~ ~

~

~ ~

~

~ ~

~

~

~ ~

1 5 ource Check.................................................

1-5 S

Process Control Program (PCP).......................

1-6 COOK NUCLEAR PIANT - UNIT 1 AMENDMENT NO. 420, 189

DEFINI ONS

~CT~IO 0

EFN Offsite Dose Calculation Manual (ODCM)

Gaseous Radwaste Treatment System......

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~

~

~

~

~

~ ~ ~

~

~ ~

~ ~ ~

1 6 Ventilation Exhaust Treatment System........................

1-6 Purge-Purging.......

~

~

~

~

~ ~

~ ~ ~ ~

enting

~ ~ ~ 0 ~ ~ ~ 0 ~ ~ ~ ~ \\ ~ ~ ~ ~ \\ ~ ~ 0 ~ ~ ~

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

~

~ ~ I 1 6 V

Member(s) of The Public

~

~

~

~ ~ t

~

~

~

~

~

~

S ate Boundary..............................................

1-7 Unrestricted Area Allowable Power Level................................

~

~

~

~

~

1 7

1-7 Core Operating Limits Report (COIL)

Operational Modes (Table 1.1) 1-7

~

~

~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

o 1 8 Frequency Notation (Table 1.2).............................

1-9 COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. 4QO, ~

189

IKtZ 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4'.2.5 3/4.2.6 S

0 AXIALFLUX DIFFERENCEo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~ ~

HEAT FLUX HOT QDiNNEL FACTOR...........................

NUCLEAR ENTHALPY HOT CHANNEL FACTOR....................

QUADRANT POWER TILT RATIO..............................

NB PARAMETERS ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~

~ ~

~ ~ ~

~

~ ~ ~ ~

D IAL POWER LEVELo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~

~

~ ~

~

~

~

~

~

~

~

~

~ ~

~ ~

~

~

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

NSTRUMENTAT 0

., 3/4.3.1 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION....................

3/4 3-1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM Meteorological Instrumentation Remote Shutdown Instrumentation......

Fire Detection Instrumentation......

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Post-Accident Instrumentation..........................

Explosive Gas Monitoring Instrumentation...............

INSTRUMENTATION......................................

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................

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

Seismic Instrumentation.....

3/4 3-15 3/4 3-35 3/4 3-39 3/4 3-40 3/4 3-43 3/4 3-46 3/4 3-51 3/4 3-54 3/4 3-57 3 4 4 REACTOR COOIANT SYSTEM

~

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................

3/4 4-1 COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. M, 4QO, 189

IMITING CONDIT ONS R 0 ERATION SURVEILLANC E UIREMENTS 4 9 REFU I G OPERAT ON (Continued) 3/4.9.6 3/4.9.7 3/4.9.8 3/4.9.9 3/4.9.10 3/4.9.11 3/4.9.12 3/4.9.13 3/4.9.14 3/4.9.15 MANIPULATOR CRANE OPERABILITY..................

~

~

~

~

~

~ -

~

%VINE TRAVEL - SPENT FUEL STORAGE POOL BUILDING........

RESIDUAL HEAT REMOVAL AND COOLANT CIRCUIATION..........

CONTAINMENT PURGE AND EKHAUST ISOLATION SYSTEM.........

WATER LEVEL - REACTOR VESSEL.......................,..

~

STORAGE POOL WATER LEVEL.......................

~.

~

~

~

~ ~ ~

STORAGE POOL VENTIIATIONSYSTEM.......

SPENT FUEL CASK MOVEMENT...............................

SPENT FUEL CASK DROP PROTECTION SYSTEM.................

STORAGE POOL BORON CONCENTRATION.......................

3/4 9-6 3/4 9-8 3/4 9-9 3/4 9-10 3/4 9-11 3/4 9-12 3/4 9-13 3/4 9-17 3/4 9-18 3/4 9-19 3 4 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 3/4.10.2 3/4.10.3 3/4.10.4 3/4.10.5 HUTDOWN MARGINo ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

S GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..

PRESSURE/TEMPERATURE LIMITATION-REACTORCRITICALITY....

PHYSICS TESTS NATURAL CIRCULATION TESTS 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-5 3/4 10-6 3 4 IOAC VE U

3/4.11.1 LIqUID HOLDUP TANKS..............

3/4 ll-l 3/4.11.2 GASEOUS EFFLUENTS Explosive Gas Mixture Gas Storage Tanks.....

3/4 11-2 3/4 11-3 COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. 420.,

189

(~AS ~S 4 0

~ ~ ~ ~

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

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~

~ ~ o

~ ~ ~ o

~ ~ ~ ~

B 3/4 0 1

4 REACT CO OL SYS S

3/4.1.1 BORATION CONTROL;..................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~ ~

~ ~ ~

~ ~

~ ~ ~

~

B 3/4 1 2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-3 4

POWER DISTRIBUTION LIMITS 3/4.2.1 APPAL FlIK DIFFERENCE..............................

~...

3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY RISE HOT B 3/4 2-1 3/4.2.4 3/4.2. 5 3/4.2. 6 CHANNEL FACTORS e

~

~ ~

~ ~ ~ ~ ~

~ ~

~ ~

~ ~ ~ ~

~

~

~

~

~ ~

~ ~

~

~

~

~

~

QUADRANT POWER TILT RATIO.................

NB PARAMETERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

~

~ e

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~ ~

~ ~

~ ~

D ALIOWABLE POWER LEVELe

~

~

~ ~

~ ~ ~

~

~ ~

~ ~

~ ~ ~

~

~

~

~ ~

~

~

~

~

~

~

~

~ ~

e

~

~

~

B 3/4 2-4 B 3/4 2-5 B 3/4 2-6 B 3/4 2-6 3 4 NS UMENT 0

3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION...................

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...

B 3/4 3-2 3 4 4 REACTOR COOLANT SYS 3/4.4.1 REACTOR COOLANT LOOPS...........................

3/4.4.2 and 3/4.4.3 SAFETY VALVES...........

3/4o4e4 PRESSURIZERe

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

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

3/4.4.5 STEAM GENERATOR TUBE INTEGRITY......

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.........................

3/4'o7 CHEMISTRYe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

3/4e4e8 SPECIFIC ACTIVITYe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~

~ ~

~

~ ~

~ ~

~ ~

~ ~

~

B 3/4 4-1 B 3/4 4-1 B 3/4 4-2 B 3/4 4-2a B 3/4 4-3 B 3/4 4-4 B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 1 XI AMENDMENT NO. M, 420, 458, 189 t

ASES 4 4 OR COO (Cont:inued) 3/4.4.9 PRESSURE/TEMPERATURE LIMITS...........................

B 3/4o4o10 STRUCTUEVLL INTEGRITYo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ o B

3/4.4.11 RELIEF VALVES.........................................

B 3/4 4-6 3/4 4-12 3/4 4-13 3/4.5.1 G

0 COO ACCUMULATORS

~ ~ ~

~ ~ ~

~

~

~

~ ~ ~ ~

~ ~ ~

~ ~

~ ~ ~ ~

~

~

~

~ ~

~

o'

~ ~ ~ ~ ~ ~

~ ~

~

~

~

B 3/4 5-1 3/4.5.2 3/4.5.4 and 3/4.5.3 ECCS SUBSYSTEMS..........

BORON INJECTION SYSTEM...............

~ ~

~

~ ~

~

~

~ ~ ~

~

~

~ ~

~ ~

~

B 3/4 5-1 5-2

~ ~

~

~

~ ~ ~

~

~ ~

~

~ ~

~

~

~

~

B~3/4 3/4.5.5 REFUELING WATER STORAGE TANK (RWST)..

~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~

B 3/4 5-3 4 6 CONTAINMENT S S

3/4.6.1 3/4.6.2 PRIMARY CONTAINMENT

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

~ ~ ~

~

~

~

~

~

~

~

DEPRESSURIZATION AND COOLING SYSTEMS..................

3/4.6.5 CE CONDENSERo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~

~

~

~

~

~

~ o

~

~

~

~

~

~

~

~

~

~

~

I 3/4.6.3 CONTAINMENT ISOIATION VALVES..........................

3/4.6.4 COMBUSTIBLE GAS CONTROL....................

~..

~

~

~

~

~

~

~

~

B 3/4 6-1 B 3/4 6-3 B 3/4 6-3 B 3/4 6-3 B 3/4 6-4 3/4.7.5 3/4'.6 CONTROL ROOM EMERGENCY VENTIIATIONSYSTEM.............

ESF VENTILATION SYSTEMo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~

~ ~

3/4.7.7 SEALED SOURCE CONTAMINATION...........................

/4o7ol TURBINE CYCLE

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

~

~

~

~ ~

~ ~

~ ~

~ ~ ~

~ ~ ~ ~

3 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION 3/4.7.3 COMPONENT COOLING WATER SYSTEM.....

3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM........................

B 3/4 7-1 B 3/4 7-4 B 3/4 7-4 B 3/4 7-4 B 3/4 7-5 B 3/4 7-5 B 3/4 7-5 COOK NUCLEAR PIANT - UNIT 1 AMENDMENT NO. 420,

>89

BASES SECTION PAGE 4 7 S

(continued) 3/4.7.8 HYDRAULIC SNUBBERS....................................

B 3/4 7-5a 3/4.7.9 FIRE SUPPRESSION SYSTEMS 3/4.7.10 FIRE RATED ASSEMBLIES B 3/4 7-7 B 3/4 7-9 3 4 8 ELECTRICAL POWER SYSTEMS.

B 3/4 8-1 3 4 9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION............

3/4. 9. 2 INSTRUMENTATION....

3/4.

3/4.

3/4.

3/4.

3/4.

3/4.

3/4.

3/4.

.3 DECAY TIME............................................

9 9.4 CONTAINMENT BUILDING PENETRATIONS 9.5 COMMUNICATIONS 9.6 MANIPULATOR CRANE OPERABILITY...........

9.7 CRANE TRAVEL -

SPENT FUEL STORAGE BUILDING............

9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.........

9.9 CONTAINMENT PURGE AND EXHAUST ISOIATION SYSTEM........

9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 3/4.

3/4.

3/4.

3/4.

OOL o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

P 9.12 STORAGE POOL VENTILATIONSYSTEM.......................

9.13 SPENT FUEL CASK MOVEMENT 9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM.............

9.15 STORAGE POOL BORON CONCENTRATION B 3/4 9-3 B 3/4 9-3 B 3/4 9-4 B 3/4 9-4 B 3/4 9-4

.3 4 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.....................

~

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.

B 3/4 10-1 COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. M, CRT, ~,

189

ASES

~c>ECTION 3 4 0

PECIAL ES C

(Continued) 3/4.10.3 PRESSURE/TEMPERATURE LIMITATIONS-REACTOR CRITICALITY'

~

~

~ ~

~ ~

~ ~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~ ~

~

~

~ ~ ~ ~

~

~

~

~

~

~

~

~

~

B 3/4 10 1

3/4.10.4 PHYSICS TESTS..........................

B 3/4 10-1 3/4.19.5 NATURAL CIRCUIATION TESTS B 3/4 10-1 3 4 ll RADIOACTIVE E UENT 3/4.11.1 LIQUID HOLDUP TANKS...................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.....................................

B 3/4 11-1 COOK NUCLEAR PIANT - UNIT 1 XIV AMENDMENT NO. M,

@RAN, 189 I

G Exelusion Area...............................................

Low Population Zone..........................................

5 1 Site Boundary for Gaseous and Liquid Effluents..............'.

5 1 onfiguration................................................

5 1 C

Design Pressure and Temperature................ ~.............

5-4 enetrations.........................................,.......

5 4 P

el Assemblies.............................................

5 4 Fu Control Rod"Assemblies.......................................

5-4 5 4 REACTOR COO S

Design Pressure and Temperature..............

5-4 VOlume o

~ o o o

~ ~ ~

~ ~

~

~ ~ ~

~ ~

~ ~

~

~

~

~

~

~

~

~

~ o ~ ~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

5 RGENCY CO E

COO ING SYST 5-5 0

G riticalityo

~

~

~

~ ~ ~ ~ ~

~ ~ o ~ ~ ~ ~ o ~ ~

~ ~ o ~ ~

~ ~

~ ~ ~ ~ ~

~

~ ~ ~ ~ ~

~

~ ~

~ ~ ~

~

~

~

C rainage o o ~ ~ ~ o o

~ o o ~ o ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~

~

~

D 5-7 apacity................

C

~

~

~

~

~

~ ~

~ ~

5 7 SMIC CLASSIF C

~ ~ ~ ~ ~ ~ o o ~ ~ o ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~ ~ ~ ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

8 ORO GICA 0

~

~ ~

~ ~ ~

~ o ~ o ~ ~

~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~ ~

~

~

C 9

ON

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ o ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~

~ ~

COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. 40, 4QO, 463, 189

)

MINISTRATIVE CONTROLS PONS B

~ ~ ~ ~ ~

~

~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~

~

~ ~ ~

~ ~

~ ~

~ ~ ~ ~ ~ ~ ~

ORG Onsite and Offsite Organization..............................

6-1 Facility Staffo ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

~

6 1 6 3 FACILITY STAFF UAL FIC ON................................

6-4

'I I

NG ~ ~ ~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

~

~ ~

~

~

~

~

~

~ ~

~

~ ~ ~ ~

~

~

o 6

6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE Function.

~

~ ~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~ ~

~ ~

~

~ ~

~

OmPOSitiono

~

~ oooo...

~

os

.o

~ ~ ~

~

~

~

~ ~ ~

~

o

~

~

~ o C

~

~

~

~

~

~

~

~ ~

~

~

~ ~

Alternates..............

~

~

~ ~

~

~

~ ~ ~

~ ~

~ ~ ~ ~

~

~

~

~

~

~

~

~

~

6 5 Meeting Frequency..................

~

~

~

~

~

~

~

~

~

~

~

Orumo o o o ~ ~

'o o ~ ~ ~

~

~

Qu

~

~

~

~

~ ~

~ ~ ~

~

~

~ \\ ~ ~ ~ ~ ~

~ ~ ~

~ ~

~

~

~

~

~

~

~ ~

~ ~

~ ~

Responsibilities.............

6-5 Authority

~

~

~

~

~

~

~ ~ ~

~

~

~ ~

~

~ \\ ~ ~

~ ~ o

~

~

~ ~

~

~

~

~

~

~

~ ~ ~

~

ecordS

~

o ~ ~

~ ~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~ ~ ~ ~

~

~

~

~ ~

~

~

~

~

~ ~

~ ~

~ ~

~

~

6 6

R 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE Functiono

~ ~ o

~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o o

~ o ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

OmPOSition ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ o 7

C Alternate Members...........,.............................

6 7 COOK NUCLEAR PLANT - UNIT 1 XVI AMENDMENT NO, 69, 4QO, 454, 189

CO 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE (Continued)

Coneultents

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

~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ o ~ o ~ ~ ~ ~

~

~

~

~ ~

~ ~ ~

~

~

~

~

~ ~

~

6 8

Meeting Frequency.........................................

6-8 0D1I o

~ ~ o ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~

~ ~

~

~ ~

~

~

~ ~

~ ~

~

o

~

~

~

~

~ ~

~ \\

~

~

~

~

ReViewo

~ ~ oo

~ ~ ~ ~ ~ ~ ~ ~

6-8 Audits

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~ ~

~

~ ~ ~ o ~

~

~

~ ~

~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

~ ~

~

~ ~

~ ~ ~ ~ ~ ~

~

6 9 uthority o ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o

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

~ ~ o ~ o ~ ~ ~ ~ o ~

~

1 A

Records o ~ ~ ~

~

~

~ ~ ~ ~

~

~

~ o ~

~

~

~ ~

~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ o 6 10 6.5. 3 TECHNICAL REVIEV AND CONTROL..............................

6-10 POR

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o

~ ~

~ ~

~

~ ~

~ ~

~ ~ ~ ~ ~ \\ ~

~ ~

~

~

6 7 SAFETY LIMITVIOLATION......

6-12 8

ROCEDUR S

OC

~

~ ~

~

~

~

~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~

~

~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~

6 9

POR C

E U 6 ~ 9 ~ 1 ROUTINE REPORTS

~

~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~

6 13c 6.9.2 SPECIAL REPORTS...........................................

6-18 6

0 RECORD R

~

~

~

~

~ ~

~

~

~

~ ~ ~

~

~

~

~

~

~ ~

~

~ ~ ~ ~ ~ ~

~ ~

~

~

~

~

~

~

~

~

~

~ ~

~

~

0 RAD ION ROTECTION PRO 6-20 IAT ON o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ oooooo ~ ~ o ~

~ o

~ o ~ ~ ~ ~ ~

0 o ~ ~ ~ ~ ~ o ~ ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ o 6 14 OFFS TE DOSE CALCULATION MANUAL OD 6-22

,COOK NUCLEAR PUTZ - UNIT 1 XVII AMENDMENT NO. 4Q, 4RO, 454, 189

E N TION UENCY NOTATION 1.21 The FREQUENCY NOTATION specified for the performance of Surveillance, Requirements shall correspond to the intervals defined in Table 1.2.

OR S

0 S

1.22 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

GINEERED AFETY TURE RESPONSE ME 1.23 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays where applicable.

1.24 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.

HYSICS TESTS 1.25 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

VERAGE DISINTEG TION ENERGY 1.26 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for

isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95X of the total non-iodine activity in the coolant.

OURC C

1.27 A SOURCE CHECK shall be the qualitative assessment of Channel response when the Channel sensor is exposed to a radioactive source.

COOK NUCLEAR PIANT - UNIT 1 1-5 AMENDMENT NO. 189

EFINITIONS ROCES CONTROL PRO CP 1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,

sampling, analyses,

tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, state regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

1.29 Deleted.

OFFSITE DOSE CALCULATION MANUAL ODCM 1.30 The OFFSITE DOSE CALCUIATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM shall contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

G S

OU W

TE TR S

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.

VENT LA 0

EXHAUS E

SYST 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-G NG 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.

VENT NG 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 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 1 1-6 AMENDMENT NO. 40, 189

0 I

IAT ON MON NG S

E ASES SCUSS D

SES SECT ON 3 4 3

3 ION 0

S

1. Modes 1, 2, 3 6 4 A. Area Monitors

i. Upper Containment+

(VRS 1101/1201)

MINIMUM CHANNELS QZE3MLK N/A TRIP

~~/~

~CQ~N S 54 mR/hr 21 ii. Containment High Range 2

(VRA 1310/1410)

B. Process Monitors

i. Particulate Channel+

(ERS 1301/1401) ii. Noble Gas Channel+

(ERS 1305/1405)

C. Noble Gas Effluent Monitors 6 10R/hr N/A N/A N/A C 2.52 pCi 20 c 4.4xl0 ~~

20

i. Unit Vent Effluent Monitors a.

Low Range (VRS 1505)

---

(see the ODCM)------------

b. Mid Range (VRS 1507) 1 N/A N/A 22B

c. High Range (VRS 1509) 1 N/A N/A 22B ii. Steam Generator PORV a.

MRA 1601 (Loop 1) 1 b.

MRA 1602 (Loop 4) 1 c.

MRA 1701 (Loop 2) 1 d.

MRA 1702 (Loop 3) 1 iii. Gland Steam Condenser Vent Monitor N/A N/A N/A N/A N/A N/A N/A N/A 22B 22B 22B 22B a.

Low Range (SRA 1805)

---

(see the ODCM)------------

iv. Steam Jet Air Ejector Vent Monitors a.

Low Range (SRA 1905)

---

(see the ODCM)------------

b. Mid Range (SRA 1907) 1 N/A N/A 22B

c. High Range (SRA 1909) 1 N/A N/A 22B COOK NUCLEAR PIfÃZ - UNIT 1 3/4 3-36 AMENDMENT NO 04e 434 i 189

LE 3

-6 Co t ued ION ON ORING NSTRUMENTAT ON OPERABILITY BASES DISCUSSED IN BASES SECTION 3 4 3

3 0

TO OD

2. Mode 6

MINIMUM CHANNELS ALARM 'RIP mXSRLZ IXX>oIm ZKP~O haXXQE A. Train A

i. Containment Area+

Radiation Channel (VRS 1101) ii. Particulate Channel+

(ERS 1301) iii. Noble Gas Channel+

(ERS 1305)

B. Train B

i. Containment Area+

Radiation Channel (VRS 1201) ii. Particulate Channel+

(ERS 1401) iii. Noble Gas Channel+

(ERS 1405)

3. Mode ~

any 2/3 channels any 2/3 channels N/A N/A N/A N/A N/A N/A 6 54 mR/hr N2.52 pCi c 4.4x10-3NCC, CC 4 54 mR/hr N 2.52 pCi c 4.4xl0 3~C cc 22 22 A. Spent Fuel Storage (RRC-330) 6 15 mR/hr c 15 mR/hr 21

+

This specification only applies during purge

~ With fuel in storage pool or building COOK NUCLEAR PIANT - UNIT 1 3/4 3-36a AMENDMENT NO 04

434, 189

TION ON TORI G

S UM ON UR CE RE U R 0

ODE N

1. Modes 1, 2, 3 6 4 A. Area Monitors CHANNEL CHANNEL

%CANNEL FUNCTIONAL APPLICABLE MHKIL~ ~ ~M

i. Upper Containment (VRS 1101/1201) ii. Containment High Range (VRS 1310/1410)

B. Process Monitors

i. Particulate Channel (ERS 1301/1401)

C. Noble Gas Effluent Monitors s>>

S*

R 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4

i. Unit Vent.Effluent Monitors a.

Low Range (VRS 1505)

b. Mid Range (VRS 1507)

c. High Range (VRS 1509) ii. Steam Generator PORV

---

(see the ODCM)--------------

S R

N/A 1, 2, 3, 4 S*

R N/A 1, 2, 3, 4

a.

MBA 1601 (Loop 1) b.

MRA 1602 (Loop 4) c.

MRA 1701 (Loop 2) d.

MRA 1702 (Loop 3) s' S>>

S R

R R

R Q

Q Q

Q 1, 2, 3, 4 1, 2, 3, 4 1,.2, 3, 4 1, 2, 3, 4 iii. Gland Steam Condenser Vent Monitor a.

Low Range (SRA 1S05)

---

(see the ODCM)--------------

iv. Steam Jet Air Effector Vent Monitors a.

Low Range (SRA 1905)

b. Mid Range (SRA 1907)

c. High Range (SRA 1909)

---

(see the S

R S

R ODCM)--------------

1, 2, 3, 4 N/A 1, 2, 3, 4 COOK NUCLEAR PLANT - UNIT 1 3/4 3-38 AMENDMENT NO. 04, 43+, fgg; 189

4 Cont ue A

ON ONI ORI G I S

E A

0 V

C U R S

2.

Mode 6

CHANNEL lRANNEL CHANNEL FUNCTIONAL APPLICABLE MIEK. 'IRIJJPII ~IM.~ODEI A. Train A

i. Containment Area Radiation Channel (VRS 1101) ii. Particulate Channel (ERS 1301) iii. Noble Gas Channel (ERS 1305)

B. Train B

i. Containment Area Radiation. Channel (VRS 1201)

Particulate Channel (ERS 1401) iii. Noble Gas Channel (ERS 1405) 3.

Mode **

S'o Se So S'e R

Q A. Spent Fuel Storage (RRC-330)

Q To include SOURCE CHECK per T/S Section 1.27

++ With fuel in storage pool or building COOK NUCLEAR PIANT - UNIT 1 3/4 3-38a AMENDMENT NO. 04o 434e N8, 189

S UMENT 0

S V GAS ON G

S 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

~CTION:

a.

With an explosive gas monitoring instrumentation channel alarm/trip'etpoint less conservative than the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.

b.

With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days. If unsuccessful, prepare and submit a SPECIAL REPORT to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREHENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and analog CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-S.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-57 AMENDMENT NO. 60, 454, 189

LE 3-los ve Gas Monitorin Instrumentatio s

e s

e Minimum Channels QRHEKK 1.

Waste Gas Holdup System Explosive Gas Monitoring System~

a.

Hydrogen Monitor (QC-1400) 23 b.

Oxygen Monitor (QC-1400, QC-370) 24 ON Stateme ts Action 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days, provided grab samples are taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Action 24 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 30 days.

With 2 channels inoperable, operation of this system may continue for up to 30 days,-provided grab samples are taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

During waste gas holdup system operation.

The waste gas holdup system explosive gas monitoring system may be inoperable for up to 160 days on a one-time basis for the purpose of replacing one oxygen monitor.

During this time, grab samples for oxygen are to be taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-58 AMENDMENT NO 04 420 470,.189

Ex losive Gas Monitorin Instrumentat on Surveillance Re ui erne ts nstrument Instrument CHANNEL CANNEL FUNCTIONAL CHANNEL licabi it 1.

Waste Gas Holdup System Explosive Gas Monitoring System a.

Hydrogen Monitor (QC-1400)

Q(1) b.

Oxygen Monitor (QC-1400, QC-370 )

Q(2) able Nota io (1)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a.

One volume percent hydrogen, balance nitrogen, and b'.

Four volume percent hydrogen, balance nitrogen.

(2)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a.

One volume percent oxygen, balance nitrogen, and b.

Four volume percent oxygen, balance nitrogen.

During waste gas holdup system operation.

These surveillances are not required during the 160-day period in which this monitor is being replaced.

COOK NUCLEAR PIANT - UNIT 1 3/4 3-59 AMENDMENT NO. 04, 4RQ, ~,

189

U HO G

CO ON 3.11.1 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a.

Outside temporary tanks.

P IC At all times.

!EXXON a.

Qith the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

4.11.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

COOK NUCLEAR PLANT - UNIT 1 3/4 11-1 AMENDMENT NO. 69, 454, 189

GASEOU G

C 3.11.2.1 The concentration of oxygen in.the waste gas holdup system shall be limited to less than or equal to 3X by volume if the hydrogen in the system is greater than or equal to 4X by volume.

IZRLMZX:

a.

Vith the concentration of oxygen in the waste gas holdup system greater than 3X by volume but less than or equal to 4X by volume and containing greater than or equal to 4X hydrogen, restore the concentration of oxygen to less than or equal to 3X or reduce the hydrogen concentration to less than 4X within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

b.

Vith the concentration of oxygen in the waste gas holdup system or tank greater than 4X by volume and greater than 4X hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to less than or equal to 3X or the concentration of hydrogen to less than or equal to 4X within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> in the system or tank.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVETLLANCE RE UTR~NTS 4.11.2.1 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

COOK NUCLEAR PLANT - UNIT 1 3/4 11-2 AMENDMENT NO. M, 444, 189

IOACT VE F

U S

GAS STORAGE TANKS G COND 0

3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

At all times.

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVE LLA CE R 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days whenever radioactive materials are added to the tank and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during primary coolant system degassing operations, by analysis of the Reactor Coolant System noble gases.

COOK NUCLEAR PLANT - UNIT 1 3/4 11-3 ANENDMENT NO. 4s. 454

108, 189

INSTRUMENTATION ASES adiation Monito in nst e ta on Co t ued ALARM/TRIP

6) Noble Gas Unit Vent Monitors a) Low Range (VRS 1505) b) Mid Range (VRS 1507) c) High Range (VRS 1509)

7) Gland Steam Condenser Vent Noble Gas Monitor a)

Low Range (SRA 1805)

See the ODCM Not Applicable~

Not Applicable~

See the ODCM 5.8x10 ~pCi/cc to

2. 7x10 ~pCi/cc.

1.3x10 ~pCi/cc to

7. Sx10+~pCi/cc.

2.9x10 ipCi/cc to

1. 6x10+ipCi/cc.

5.8x10 ~pCi/cc to

2. 7x10 ipCi/cc.

8) Steam Jet Air Ejector Vent Noble Gas Monitor a)

Low Range (SRA 1905) b) Mid Range (SRA 1907) c) High Range (SRA 1909)

See the ODCM Not applicable.++

Not Applicable.~

5.8xlO ~pCi/cc to 2.7x10 2pCi/cc.

1.3x10 3pCi/cc to

7. 5xl0+~pCi/cc.

2.9x10 ~pCi/cc to

1. 6x10+ipCi/cc.

9) Spent Fuel Storage (RRC-330)

The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a)

(2) lx10 mR/hr to lxlO+'mR/hr

• This is the minimum sensitivity of the instrument for normal operation, to follow the course of an accident, and/or take protective actions.

Values of the instrument above or below this minimum sensitivity range are acceptable.

~ These monitors are used to provide data to assist in post-accident off-site dose assessment.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-4 AMENDMENT NO. 04, 434, 45$

189

34UiM 4

9 P

S G

S NON 0

NG NS UME This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the vaste gas holdup system.

The OPERABILITY and use of this instrumentation is consistent vith the requirement of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-7 AMENDMENT NO. 40, 458, 189

OA V

ASKS UI Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR part 20, Appendix B, Table II, Column 2, at the nearest potab1e water supply and the nearest surface water supply in an UNRESTRICTED AREA.

This specification, being applicable to outside temporary tanks, does not apply to the refueling water storage tank, primary water storage tank, or the condensate storage tank, since they are a part of the permanent plant design.

3 4 11 2

GASEOUS EFFLU S

3 4 1

.1 EXPLOS VE GAS I This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen and oxygen mixtures.

Haintaining the concentration of hydrogen or oxygen below their flannnability limits provides that the releases of radioactive materials willbe controlled in conformance with the requirements of the General Design Criterion specified in Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3 4 11.2 2

GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest site boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Paste Gas System Failure."

COOK NUCLEAR PLANT <<UNIT 1 B 3/4 11-1 AMENDMEHT NO. m, a

~

l

N (continued) plan and implementing procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Plant Manager.

NRC approval shall be obtained as appropriate.

Recommended changes to the Security Plan and implementing procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Plant Manager.

NRC approval shall be obtained as appropriate.

6.5:3.2 Records of the above activities shall be provided to the Plant

Manager, PNSRC and/or the NSDRC as necessary for required reviews.

6 6

REPORTAB 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73, and b.

Each REPORTABLE EVENT shall be reviewed by the

PNSRC, and the results of this review shall be submitted to the NSDRC and the Vice President

- Nuclear Operations.

6 7 SAFETY LIM T VIO ON 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PNSRC.

This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.

C ~

The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Vice President Nuclear Operations within 14 days of the violation.

d.

Operation of the unit shall not be resumed until authorized by the Commission.

COOK NUCLEAR PLANT - UNIT 1 6-12 AMENDMENT NO. M,

@SAN, 189

8 ROC D

S G

6.8.1 Vritten procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appends A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Security Plan implementation.

c.

Emergency Plan implementation.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CALQJLATION MANUAL implementation.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, Junc 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

I 6.8.2 Each procedure and administrative policy of Specification 6.8.1

above, and changes thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.

The program will include the following:

a."

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PIANT - UNIT 1 6-13 AMENDMENT NO. M, 444 189

S T V C

8 OCEDURE (continued)

'6.8.4 The following programs shall be established, implemented, and maintained:

a.

ad pact v ue A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the

ODCM, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2 ~

3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the

ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming, to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I.to 10 CFR Part 50, COOK NUCLEAR PLANT - UNIT 1 6-13a AMENDMENT NO. 189

8 OC D

ES P

OG (continued) 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10CFR Part 50, and 10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

b.

adiolo ca nviro en a o

to 0

A program shall be provided to monitor the radiation and radionuclides in the'nvirons of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure

pathways, and (2) verification of the accuracy of'he effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratozy Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in emrironmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

COOK NUCLEAR PIANT - UNIT 1 6-13b AMENDMENT NO. 189

MINISTRATIVE CONTRO S

9 EP N

E 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

ARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT - UNIT 1 6-13c AMENDMENT NO. M, 454, 189

MIN STRA IVE CONTRO (continued) 6.9.1.3 Startup reports shall be submitted within (1) 90 days following, completion of the startup test program, (2) 90 days following resumption or commencement of commexcial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Repox't does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of

.each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other pex'sonnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functionsx, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20X of the individual total dose need not be accounted for.

In the aggregate, at least SOX of the total whole body dose received from external sources shall be assigned to specific major work functions.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

C, Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the I-131 specific activity limit was exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units st the station.

This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NJCLEAR PLANT - UNIT 1 6-14 AMENDMENT NO. M, 434, 454, 189

6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

AL RADIOACTIVE E UE RE EASE R PO 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operations shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PIANT - UNIT 1 6-15 AMENDMENT NO. M, 44K, 454, 474 189

This page intentionally left blank.

COOK NUCLEAR PIANT - UNIT 1 6-16 AMENDMENT NO. 60, 454, 474 189

V 0

0 C 0 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

0 0

T G I TS 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. "'oderator Temperature Coefficient Limits for"Specification 3/4.1.1.4, b.

Rod Drop Time Limits for Specification 3/4.1.3.3, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.

Control Rod Insertion Limits for Specification 3/4.1.3.5, e.

Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a.

b.

Ci d.

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),

WCAP-8385, "Power Distribution Control and Load Following Procedures

- Topical Report," September 1974 (Westinghouse Proprietary),

WCAP-10216-P-A, Part B, "Relaxation of Constant Axial Offset Control/F Surveillance Technical Specification," June 1983 (Westingh9use Proprietary),

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PIANT - UNIT 1 6-17 AMENDMENT NO. 6Q, 454, 474 189

MINIS T V CO 0

CO E

OP RAT NG I TS REPORT (Continued) 6.9.1.9.3 The core operating limits shall be determined so'hat all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document control desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPOR 6.9.2 Special reports shall be submitted to the attention of the document control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555) ~

with copies to the Region IIIAdministrator and the Resident Inspector at the Cook Nucleax'lant within the time period specified for each report.

These xeports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

c.

Inopexable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activity in RCS Coolant, Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.

f.

Moderator Temperature Coefficient, Specification 3.1.1.4.

g.

Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

i.

Violation of Safety Limit, Specification 6.7.1.

COOK NUCLEAR PIANT - UNIT 1 6-18 AMENDMENT NO. 4Q, 454 189

MINISTRATIVE 0

0 6 10 RECORD R 6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of unit operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c ~

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1.

Records of sealed source and fission detection leak tests and results.

Records of annual physical inventory of all sealed source material on record.

COOK NUCLEAR PLANT - UNIT 1 6-19 AMENDMENT NO. W, 430, 444, 454 189

CO 6.10.2 The following records shall be retained for the duration of the Facili~ Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histori.es.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environment.

e.

Records of transient or operational cycles for those facility components identified in Table 5.9-1.

Records of reactor tests and experiments.

g.

Recoi'ds of training and qualification for current members of the Plant Staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or equipment or review of tests and experiments pursuant to 10 CFR 50.59.

Records of meetings of the PNSRC and the NSDRC.

l.

Records of radioactive shipments.

m.

Records of the service lives of hydraulic snubbers including the date at which service life commences and associated installation and maintenance records.

n.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

IATION PRO ON 0

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

COOK NUCLEAR PLANT - UNIT 1 6-20 AMENDMENT NO. 8&, 454, ~

189

MINISTRATIV CO 0

6 2

HIGH RAD ATION 6.12.1 In lieu of the control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.

Any individual-or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.

C.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000mrem/hr.

When

possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.

In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT - UNIT 1 6-21 AMENDMENT NO. 04, 450, 454 189

MINISTRATIVE CO 0

6 13 PROCESS CONTRO PROG 6.13.1 Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal,

State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.

6 14 OFFSITE DOSE CALCULATION MANUAL ODCM 6.14.1 Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.

c ~

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected

pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

COOK NUCLEAR PMT - UNIT 1 6~22 AMENDMENT NO. 87., 454 189

~g8 REGII l,

Cq 7 +a**+

UNITED STATES NUCLEAR REGULATORY COMMISSlON.

WASHINGTON, D.C. 205554001 INDIANA MICHIGAN POWER COMPANY KcCKET N

S -3 6

DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

175 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 August 3,

1994, 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 ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

175 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 10, 1995 (g

i John N. Hannon, Dire tor Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO ICENSE AMENDMENT NO. 175.

FACILITY OPERAT NG LICENSE NO. DPR-74 DOCK T NO. 50-16 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 II V

X XI XII XIII XIV XV XVI XVII XVIII 1-6 1-7 3/4 3-35 3/4 3-35a 3/4 3-35b 3/4 3-37 3/4 3-37a 3/4 3-37b 3/4 3-53 3/4 3-54 3/4 3-55 3/4 3-56 3/4 3-57 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 3/4 11-5 3/4 11-6

~NSERT II V

X XI XII XIII XIV XV XVI XVII 1-6 1-7 3/4 3-35 3/4 3-35a 3/4 3-37 3/4 3-37a 3/4 3-53 3/4 3-54 3/4 3-55 3/4 3-56 3/4 3-57 3/4 11-1 3/4 11-2 3/4 11-3

3/4 11-7 3/4 11-8 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-17 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-4a 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 B 3/4 3-lc B 3/4 3-3 B 3/4 3-4 B 3/4 11-1 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 B. 3/4 11-5 B 3/4 12-1 6-12 6-13 6-14 6-15 6-16 6-17 6-18 6-19 6-20 6-21 6-22 6-23 B 3/4 3-lc B 3/4 3-3 B 3/4 11-1 6-12 6-13 6-13a 6-13b 6-13c 6-14 6-15 6-16 6-17 6-18 6-19 6-20 6-21 6-22

N Offsite Dose Calculation Manual (ODCM)......................

1-7 Gaseous Radwaste Treatmeht System...........................

1-7 Ventilation Exhaust Treatment System..........

1-7 ge-Purging...............................................

Pur 1-7 Venting.............................

~

~

~ ~ ~

~

~

~

~

~ ~ ~

~ ~

1-7 Member(s)

Of The Public.....................................

1-8 Si te Soundary o ~ ~ ~ ~ ~

~ ~ ~ ~ e

~

~ ~ ~ ~

~

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

~ ~ ~ ~ ~ ~

~ ~

~

~

~

~

~ ~ ~ ~

~ ~

1-8 nrestricted Area...........................................

U 1-8 Allowable Power Level..................

~

~ ~

~

~ ~ ~

~ ~

~ ~

1-8 Core Operating Limits Report (COLR)..................,......

Operational Modes (Table 1.1)...............................

1-8 1-9 Frequency Notation (Table 1.2).............

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO.

4OTV, @SR 175

MITING CO I ONS OR 0 I N URV ILLANCE R R

3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 3/4.2.6 OWER D STR 0

AXIALFLUX DIFFRNCE

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ o HEAT FLUX HOT CHANNEL FACTOR NUCLEAR EKQfALPY HOT CHANNEL FACTOR QUADRANT POWER TILT RATIO.

DNB PARAMETERS ODE 1 o

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

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

~

M MODES 2, 3, 4 and 5

~

~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~

ALLOWABLE POWER LEVEL

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oo

~ o ~

~

~

~

~ ~ ~

3/4 2-1 3/4 2-5 3/4 2-9 3/4 2-13 3/4 2-15 3/4 2-17 3/4 2-19 4

3 NSTRUMENT T 0 3/4.3.1 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-1 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation Movable Incore Detectors Seismic Instrumentation........

Meteorological Instrumentation........................

Remote Shutdown Instrumentation..

Post-Accident Instrumentation.........................

Fire Detection Instrumentation...

Explosive Gas Monitoring Instrumentation...............

3/4.3.4 TURBINE OVERSPEED PROTECTION.

3/4 3-34 3/4 3-38 3/4 3-38a 3/4 3-39 3/4 3-42 3/4 3-45 3/4 3-50 3/4 3-53 3/4 3-56 3 4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOIANT CIRCUIATION Startup and Power Operation...........................

3/4 4-1 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. 4Q, 408 175

G CO NS C

U REM S

~~~ON 4

9 3/4.9.6 3/4.9.7 3/4.9.8 3/4.9.9 3/4.9.10 3/4.9.11 3/4.9.12 3/4.9.13 3/4.9.14 3/4.9.15 G 0 (Continued)

MANIPUIATOR CRANE OPERASILITY

~

~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

CRANE TRAVEL - SPENT HJEL STORAGE POOL BUILDING RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM........

WATER LEVEL-REACTOR VESSEL............................

STORAGE POOL WATER LEVEL............

STORAGE POOL VENTILATION SYSTEM.......................

SPENT FUEL CASK MOVEMENT

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

~ ~

~

~

~

~

SPENT FUEL CASK DROP PROTECTION SYSTEM................

STORAGE POOL BORON CONCENTRATION 3/4 9-6 3/4 9-7 3/4 9-8 3/4 9-9 3/4 9-10

~ 3/4 9-11 3/4 9-12 3/4 9-16 3/4 9-17 3/4 9-18 4

0 3/4.10.1 3/4.10.2 3/4.10.3 3/4.10.4 3/4.10.5 C

E S HUTDOWN MARGIN

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~ ~

~

~

~

~

GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..

PHYSICS TESTS

~

~ ~

~

~

~ ~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~ ~ e

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

REACTOR COOMT LOOPS POSITION INDICATOR CHANNELS -

SHUTDOWN 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 3/4 10-5 3 4 1

RADIOACT VE 3/4. 11. 1 LIQUID HOLDUP TANKS 3/4.11.2 GASEOUS EFFLUENTS Explosive Gas Mixture......

~

~

~ ~

~ ~ ~ ~ ~ ~

~ ~

~

~ ~

~ ~

~ o ~ ~

~ ~

~

3/4 11 1

~

~

~

~ ~ ~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

3/4 11 2

Gas Storage Tanks......................................

3/4 11-3 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. 407.

175

&RED ZlEEZ 4 0 PP CABI B 3/4 0 1 3/4.1.1 3/4.1.2 3/4.1.3 V

0 0

BORATION CONTROL...................................:

B 3/4 1-1 BORATION SYSTEMS....................................

B.3/4 1-2 MOVABLE CONTROL ASSEMBLIES..........................

B 3/4 1-4 3/4.2.1 3/4.2.2 3/4.2.4 3/4.2. 5 3/4.2. 6 0

AXIALFLUX DIFFERENCE

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

~ ~

~

~

~

~

~

and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTEQZY HOT CHANNEL FACTOR QUADRANT POWER TILT RATIO NB PARAMETR o ~ ~

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

o

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

D ALLOWABLE P OWER LEVEL

~ ~

~

~ ~

~ ~

~

~

~ ~ ~

~ ~ ~

~

~

~

~

~ ~

~

~

~ ~ ~ ~

~

~

~ ~

B 3/4 2-1 B 3/4 2-4 B 3/4 2-5 B 3/4 2-5 B 3/4 2-5 4

S E

0 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION..'.........................

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION.......

B 3/4 3-la 3/4.3.4 TURBINE OVERSPEED PROTECTION.................-.......

B 3/4 3-3 3.4.4.4 RES SURIZER

~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~

P 3/4.4.5 STEAM GENERATOR TUBE INTEGRITY.......................

3/4.4.6 3.4.4.7 REACTOR COOLANT SYSTEM UM(AGE EMISTRY

~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~

~ ~

~ ~ ~ ~

~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

CH 3/4.4.8 SPECIFIC ACTIVITY..............................,....

4 4 R

CTOR COO 3/4 ~ 4 ~ 1 REACTOR COOLANT LOOPS

~ ~ ~ ~ ~ ~

~

~ ~ ~

~ ~

~

~

o'

~

~

~ ~

~ ~

~ ~

~ ~

~

~

~

~

~

3/4.4.2 and 3/4.4.3 SAFETY VALVES B 3/4 4-1 B 3/4 4-2 B 3/4 4-2 B 3/4 4-2a B 3/4 4-3 B 3/4 4-4 B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO.

4Q, ~, 444 175

~A~S

~~~0 4 4 COO (Continued) 3/4.4.9 3/4.4.10 3.4.4.11 RELIEF VALVES

~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~

~

~

~

~

~

~

B 3/4 4-11 PRESSURE/TEMPERATURE LIMITS...............,..........

B 3/4 4-6 STRUCTURAL INTEGRITY.................................

B 3/4 4-10 3/$.4.12 REACTOR COOIANT VENT SYSTEM..........................

B 3/4 4-11 345 3/4. 5 3/4.5 3/4.5 3/4.5 3 4 6 G N 0 E 00 NG SYSTEMS CCS

~ 1 ACCUMULATORS

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~

o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

.2 and 3/4.5.3 ECCS SUBSYSTEMS

.4 BORON INJECTION SYSTEM

.5 REFUELING WATER STORAGE TANK (RWST)

CO NMENT SYST B 3/4 5-1 B 3/4 5-1 B 3/4 5-2 B 3/4 5-3 3/4.6 3/4.6 3/4.6 3/4.6 3/4.6

. 1 PRIMARY CONTAINMENT

~ 2 DEPRESSURIZATION AND COOLING SYSTEMS

.3 CONTAINMENT ISOLATION VALVES

.4 COMBUSTIBLE GAS CONTROL

~ 5 ICE CONDENSER o

~ ~

~

~

~ ~ ~ ~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~ ~

~ ~

~

~

~

~

~ ~

B 3/4 6-1 B 3/4 6-3 B 3/4 6-3 B 3/4 6-3 B 3/4 6-4 3 4.7 PLANT SYSTEMS 3/4.7.1 3/4.7.2 3/4.7.3 3/4.7.4 3/4.7.5 3/4.7.6 3/4.7.7 INE CYCLE

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

~

~

~

~

~ ~ ~

~ ~

~ ~ ~

~ t ~ ~

TURB STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION COMPONENT COOLING WATER SYSTEM ESSENTIAL SERVICE WATER SYSTEM CONTROL ROOM EMERGENCY VENTIIATION SYSTEM ESF VENTILATION SYSTEM HYDRAULIC SNUBBERS B 3/4 7-1 B 3/4 7-4 B 3/4 7-4 B 3/4 7-4 B 3/4 7-4a B 3/4 7-5 B 3/4 7-5 COOK NUCLEAR PIANT - UNIT 2 AMP')MENT NO. uu, ~

175

4 S

S (Continued) 3/4.7.8 SEALED SOURCE CONTAMINATION..........................

B 3/4.7.9 FIRE SUPPRESSION SYSTEMS...................

B 3/4.7.10 FIRE-RATED ASSEMBLIES..............................

B 3/4 7-6 3/4 7-6 3/4 7-9 4 '8

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

~ ~ ~ ~

~ ~

~

B 3/4 8-1 4

EFUE G OP ONS 3/4.9.1 3/4.9.2 3/4.9.3 3/4.9.4 3/4.9.5 3/4.9.6 3/4.9.7 3/4.9.8 3/4.9.9 3/4.9.10 3/4.9.12 3/4.9.13 3/4.9.14 3/4.9.15 BORON CONCENTRATION INSTRUMENTATION......................................

ECAY TIME

~ ~ ~ ~ ~ o ~

~

~ ~

~

~ ~

~ ~ ~

~

~

~ ~ ~

~ ~ ~ ~ ~

~

~

~ ~

~

~

~

~

~ ~

~ ~ ~

~

~

o' D

CONTAINMENT BUILDING PENETRATIONS COMMUNICATIONS

~

~ ~ ~

~ ~ ~

~ ~ ~

~ ~

~

~ ~ ~ ~ ~ ~ ~ ~

~

~

~ ~

~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~

MANIPUIATOR CRANE OPERABILITY CRANE TRAVEL - SPENT FUEL STORAGE BUILDING RESIDUAL HEAT REMOVAL AND COOIANT CIRCULATION CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL STORAGE POOL VENTILATION SYSTEM......................

SPENT FUEL CASK MOVEMENT

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

~

~

~

~ ~ ~ ~

~

~ ~

~ ~

~

~

SPENT FUEL CASK DROP PROTECTION SYSTEM STORAGE POOL BORON CONCENTRATION..................;...

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 B 3/4 9-3 B 3/4 9-3 B 3/4 9-4 B 3/4 9-4 B 3/4 9-4 4

0 SPECIA ES EXCEPT 0 3/4o10ol SHUTDOWN MARGIN o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ o ~ o

~ ~

~

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.

B 3/4 10-1 COOK NUCLEAR PLANT - UNIT 2 XIII AMENDMENT NO.

175

~A'.S SECTION PAGE 3 4 10 SPECIAL TEST EXCEPTIONS (Continued) 3/4.10.3 PHYSICS TESTS.......

B 3/4 10-1 3/4.10.4 REACTOR COOIANT LOOPS

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

B 3/4 10 1 3/4.10.5 POSITION INDICATOR CHANNELS - SHUTDOWN...............

B 3/4 10-1 3 4.11 RAD OACTIVE EFFLUENTS 3/4.11.1 LIQUID HOLDUP TANKS........

~...................,.....

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS B 3/4 11-1 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. 4k, 175

N ES Q~C'.~ON

~AG elusion Area............................

Ex Low Population Zone Site Boundary for Gaseous and Liquid Effluents

~

~

~

~

~

~

~

~

~ * ~

~

~

~

~

~

~

~

~

5 1

~

~

~

~

~

~

~

~

~

~

~

~

~

5 2

CONTAINMENT Configuratlon iowa

.so

~.oo ~ ~ ~

~

~ oooooeoo.

~

~

Design Pressure and Temperature

~

~

~

~

~

~

~

~

~

~

~

~

~

5-1 5

3 REACTOR CORE Fuel Assemblies

~

~

~ at

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Control Rod Assemblies.......,.......................

5-4 5 4 REACTOR COOLANT SYSTEM Design Pressure and Temperature Volume

~

~

~

~

t

~

~

~

~

~

~

~

~

~

~

~

~

~

~

5-4 5

5 METEOROLOGICAL TOWER LOCATION 5-5 5

6 FUEL STORAGE Criticality - Spent Fuel 5-5 Criticality - New Fuel...................

5-6 rainage................,..................................

5 7 D

Capacity........

~

~

~

~

~

~

~

~

~

~

~

~

~

7 5

7 COMPONENT CYCLIC OR TRANSIENT LIMIT

~

5 7

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO.

175

IHDEK NS V

CO SPO S

~ ~ ~ ~ ~

~

~ ~ ~ ~ e

~ ~ e ~ ~ ~ ~

~ ~ ~ ~ ~ ~

~

~

~ ~ ~ ~ e

~ ~

~

~

~

~ ~ ~

~ ~ ~ ~

~

RG Onsite and Offsite Organization.........................

6-1 acility Staff.............................................

6-1 F

~ e

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~

~

~

~ ~

~

~ ~ ~

~ ~

6 4 6 4 NG

~ ~ ~ ~ e

~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ o ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~ ~

~ ~ ~ ~ ~

~

~ ~

~

~

~

~

~

~

~

~

6 4 6

EVIEW 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE CtiOn.

e ~ eoee

~ ~ ~ ~ e

~ ~ eoo

~

~

Fun

~

~ ~

~

~

~

~

~

~

Composition...

~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~

~ ~

~ ~ ~

~

~

6 4 Alternates 6-5 Meeting Frequency...

~

~

~

~

6 5

0 rum

~ ~ ~ ~

~

~ ~

~ ~ ~

~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ e

~

~

~ ~

~

~

~

~

~

~

~

~ ~ ~

~

~

~

6o5 Responsibilities.......................

6-5 1

Authority ~....

~ ~ ~ ~ ~ ~ ~ ~ e

~ ~ ~ e

~ ~ ~

~ ~

~

~

~

~ ~

~

~

~ ~

~ ~

6o6 ecords

~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ e e e ~ e

~

~ e

~

~ ~

~ ~ ~

~

~

~ ~ ~

~

~ ~

~

~ ~

~

~

~

~ ~ ~

~

~

~

~

~

~

~

6 6 R

6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE ction e ~ e ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eee

~ ~ ~

~ ~ ~ ~ ~ ~ eoeee

~

~

~ ~

~ ~ ~ ~ ~ ~ ~

~ ~

6 6 Fun OmpOSitiOn ee ~ ~ ~ ~ e ~ e ~ ee ~ ee ~ ~ ~ ~ ~ ~ e ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~

C

~ ~ ~

~ ~ ~

~ e 6 7 lternate Members................'........................

6-Z A

COOK NUCLEAR PIANT - UNIT 2 AMENDMENT NO. M', 440, 438 175

INDEX MINISTRATIVE CONTROLS

~GE 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE (continued)

Consultants.........

6 8

Meeting Frequency..

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Qllorum

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

eview R

~

~

~

~

~ t ~

~

~

~

~

~

Audits

~

~

~

~ o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

A 10 uthority

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

Records

~

~

~

~

~

~

~

~ I ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

6.5.3 TECHNICAL REVIEW AND CONTROL...

~.........................

6-10 6

6 REPORTABLE EVENT ACTION

~

~

~

~

~

~

~

~

~

~

6 12 6 7 SAFETY LIMIT VIOLATION..................':......,...........

6-12 6

8 PROCEDURES A%) PROGRAMS 6-13 6.9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS 6-13c 6.9.2 SPECIAL REPORTS

~

~

~

~

~

~

~

~

~

~

~

6 1 8 6 10 RECORD RETENTION..........................................

6-19 6 11 RADIATION PROTECTION PROGRAM..............................

6-20 6 12 HIGH RADIATION AREA 6-21 6 13 PROCESS CONTROL PROGRAM PCP.............................

6-22 6 14 OFFSITE DOSE CALCULATION MANUAL ODCM...................

6-22 COOK NUCLEAR PLANT - UNIT 2 XVII AMENDMENT NO. 407., 438 175.

FIN TIONS SIC S

1.25 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the PSAR,

2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

E - AVERAGE ISINTEGRATION ENERGY 1.26 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for

isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95X of the total non-iodine activity in the coolant.

1.27 A SOURCE CHECK shall be the qualitative assessment of Channel response when the Channel. sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM PCP 1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,

sampling, analyses,

tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulate'd wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

COOK NUCLEAR PLANT - UNIT 2 1-6 AMENDMENT NO. 4k 175

FINI ONS 1.29 Deleted.

0 C L 0

C 1.30 The OFFSITE DOSE CALClJLATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM shall contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the, Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

G S

OUS RADWASTE TREATMENT SYST 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.

V TION UST 1.32 A VENTIIATION 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.

VEN'+NG 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. ~, 454 175

TABLE 3 3-6 RADIATION MONITORING INSTRUMENTATION OPERABILITY BASES DISCUSSED IN BASES SECTION 3 4 3 3.1 OPERATION MODE NSTR MINIMUM CHANNELS ALARM TRIP

~OPERAB

/ETIO

$ ETP~OQ

/~~ON

1. Modes 1, 2, 3 & 4 A. Area Monitors

i. Upper Containment+

(VRS 2101/2201) ii. Containment High Range 2

(VRA 2310/2410)

B. Process Monitors

i. Particulate Channel+

(ERS 2301/2401)

N/A

~ 10R/hr N/A 6 54 mR/hr N/A N2.52 pCi 21 22A 20 ii. Noble Gas Channel+

(ERS.2305/2405)

C. Noble Gas Effluent Monitors N/A c 4.4x10

~ ~C 20 CC

i. Unit Vent Effluent Monitors a.

Low Range (VRS 2505)

---

(see the ODCM)-------------

b. Mid Range (VRS 2507) 1 N/A N/A 22B

c. High Range (VRS 2509) 1 N/A N/A 22B ii. Steam Generator PORV a.

MRA 2601 (Loop 1) 1 b.

MRA 2602 (Loop 4) 1 c.

MRA 2701 (Loop 2) 1 d.

MRA 2702 (Loop 3) 1 iii. Gland Steam Condenser Vent Monitor N/A N/A N/A N/A N/A N/A N/A N/A 22B 22B 22B 22B a.

Low Range (SRA, 2805)

---

(see the iv. Steam Jet Air Ejector Vent Monitors ODCM)------------"

a.

Low Range (SRA 2905)

---

(see the ODCM)-------------

b. Mid Range (SRA 2907) 1 N/A N/A 22B

c. High Range (SRA 2909) 1 N/A N/A 22B COOK NUCLEAR PLANT - UNIT 2 3/4 3-35 AMENDMENT NO. 80, 4k'75

-6 Co t u

A ON ON TORING S

UMENT ON S

S D

N SES E

ON 3 4

2. Mode 6 A. Train h any 2/3 channels ALARM TRIP

$XXZQZHX XEXZQZK dQXXQK 22

i. Containment Area+

Radiation Channel (VRS 2101) ii. Particulate Channel+

(ERS 2301) iii. Noble Gas Channel+

(ERS 2305)

B. Train B

i. Containment Area+

Radiation Channel (VRS 2201) ii. Particulate Channel+

(ERS 2401) iii. Noble Gas Channel+

(ERS 2405)

3. Mode ~

any 2/3 channels N/A N/A N/A N/A N/A N/A 6 54 mR/hr C 2.52 pCi N 4.4x10 3~C CC 5 54 mR/hr 52.52 pCi c 4.4x10 '~

CC 22 A. Spent Fuel Storage (RRC-330)

C 15 mR/hr c 15 mR/hr 21 Pith fuel in storage pool or building

+

This specification only applies during purge COOK NUCLEAR PLANT - UNIT 2 3/4 3-35a AMENDMENT NO. 80, 440 175

2 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERAT ON ODE INS UM

1. Modes 1, 2, 3 & 4 A. Area Monitors CHANNEL CHANNEL CHANNEL FUNCTIONAL APPLICABLE

i. Upper Containment (VRS 2101/2201) ii. Containment High Range (VRA 2310/2410)

B. Process Monitors S

Q 1, 2, 3,

4 1, 2, 3, 4

i. Particulate Channel (ERS 2301/2401)

C. Noble Gas Effluent Monitors 1, 2, 3, 4

i. Unit Vent.,Effluent Monitors a.

Low Range (VRS 2505)

b. Mid Range (VRS 2507)

c. High Range (VRS 2509) ii. Steam Generator PORV S

S*

R R

(see the ODCM)--------------

N/A 1, 2, 3, 4

N/A "1, 2, 3, 4

a.

MRA 2601 (Loop 1) b.

MRA 2602 (Loop 4) c.

MRA 2701 (Loop 2) d.

MRA 2702 (Loop 3)

S S'*

S R

R R

R Q

Q Q

Q 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4 iii. Gland Steam Condenser Vent Monitor a.

Low Range (SRA 2805) iv, Steam Jet Air Ejector Vent Monitors (see the ODCM) a.

Low Range (SRA 2905)

b. Mid Range (SRA 2907)

c. High Range (SRA 2909)

S S

(see the ODCM)

R Q

1, 2, 3, 4

R N/A 1, 2, 3, 4

COOK NUCLEAR PLANT - UNIT 2 3/4 3-37 AMENDMENT NO. 80, 440>

NH~

175

LE 4 3-3 Cont ued RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS OP T ON MODE INSTRUM CHANNEL CHANNEL CHANNEL

'FUNCTIONAL APPLICABLE CHECK CALIBRATION TEST

~MODE 2.

Mode 6

A. Train A

i. Containment Area Radiation Channel (VRS 2101) ii. Particulate Channel (ERS 2301) iii. Noble Gas Channel (ERS 2305)

B. Train B

i. Containment Area Radiation.,Channel (VRS 2201) ii. Particulate Channel (ERS 2401) iii. Noble Gas Channel (ERS 2405) 3.

Mode **

s*

S S*

s*

S S*

R A. Spent Fuel Storage (RRC-330)

To include SOURCE CHECK per T/S Section 1.27

~ Pith fuel in storage pool or building COOK NUCLEAR PLANT - UNIT 2 3/4 3-37a AMENDMENT NO. 80, 440,

165, 175

PLOS GAS MONITORING INSTRUMENTAT ON IM TING CONDITION FOR OPERAT ON 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specifications 3.11.2.1 are not exceeded.

IJRHIJZQ

~AOT ON:

a.

With an explosive gas monitoring instrumentation channel alarm/trip setpoint less conservative than the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.

b.

With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days. If unsuccessful, prepare and submit a SPECIAL REPORT to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

S VE LANCE RE U REM S

4.3.3.9.1 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and analog CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-53 AMENDMENT NO. 4k, 488 175

TABLE 3 3-12 Ex losive Gas Monitorin Instrumentatio Instrument Instrument Minimum Channels OPERABLE ACTION 1.

Waste Gas Holdup System Explosive Gas Monitoring System~

a.

Hydrogen Monitor (QC-1400) 23 b.

Oxygen Monitor (QC-1400, QC-370) 2 24 ACTION STATEMENTS Action 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days, provided grab samples are taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Action 24 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 30 days.

With 2 channels inoperable, operation of this system may continue for up to 30

days, provided grab samples are taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

During waste gas holdup system operation.

The waste gas holdup system explosive gas monitoring system may be inoperable for up to 160 days on a one-time basis for the purpose of replacing one oxygen monitor.

During this time, grab samples for oxygen are to be taken and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-54 AMENDMENT NO. 80, 414, 443 175

4 losive Gas Monito t

entat o

urve la ce Re ui erne ts st ent CHANNEL

%CANNEL FUNCTIONAL CHANNEL MHEHL ~E81 LUEetZB 1.

Waste Gas Holdup System Explosive Gas Monitoring System a.

Hydrogen Monitor (QC-1400)

Q(1) b.

Oxygen Monitor (QC-1400, QC-370 )

Q(2) b e a

o (1)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a.

One volume percent hydrogen, balance nitrogen, and b.

Four volume percent hydrogen, balance nitrogen.

(2)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

a.

One volume percent oxygen, balance nitrogen, and b.

Four volume percent oxygen, balance nitrogen.

During waste gas holdup system operation.

These surveillances are not required during the 160-day period in which this monitor is being replaced.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-55 AMENDMENT NO. 80, 444, 46k 175

434 3.3.4.1 At least one turbine overspeed protection system shall be OPERABLE.

MODES 1, 2 and 3

a.

Vith one stop valve or one control valve per high pressure turbine steam lead inoperable or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, operation may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the inoperable valve(s) is restored to OPERABLE status or at least one valve in the affected steam lead is closed; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

Qith the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.

SURVEI LANCE E UIREME 4.3.4.1.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.1.2 The above pequired turbine overspeed protection system shall be demonstrated OPERABLE:

a.

At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running position.'.

Four high pressure turbine stop valves.

2.

Four high pressure turbine control valves.

3.

Six low pressure turbine reheat stop valves.

4.

Six low pressure turbine reheat intercept valves.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-56 AMEMDMEHT NO 41, 17.5

INSTRUMENT TION SURVEILLANCE RE UIREMENTS Continued b.

C.

At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position.

At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.

d.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-57 AMENDMENT NO. 44, 175

4 RADIOAC IVE VENT LDUP TANK

• LIMITING CONDITION FOR OPERAT 0 3.11.1 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equaI to 10 curies, excluding tritium and dissolved or entrained noble gases.

a.

Outside temporary tanks.

At all times.

~C~ION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SUR IL CE RE UIREM S

4.11.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Tanks included in this Specifications are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank over flows and surrounding area drains connected to the liquid radwaste treatment system.

COOK NUCLEAR PLANT - UNIT 2 3/4 11-1 AMENDMENT NO. 44, 4SL 175

RADIOACTIVE EFFLUENTS 3 4 11 2

GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 3X by volume if the hydrogen in the system is greater than or equal to 4X by volume.

APPLICABILITY: At all times.

ACTION a

~

With the concentration of oxygen in the waste gas holdup system greater than 3X by volume but less than or equal to 4X by volume and containing greater than or equal to 4X hydrogen, restore the concentration of oxygen to less than or equal to 3X or reduce the hydrogen concentration to less than 4X within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

b.

With the concentration of oxygen in the waste gas holdup system or tank greater than 4X by volume and greater than 4X hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to less than or equal to 3X or the concentration of hydrogen to less than or equal to 4X within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> in the system or tank.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.1 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

COOK NUCLEAR PIANT - UNIT 2 3/4 11-2 AMENDMENT NO. 54, 438 175

IOAC V 'FFLU GAS STORAGE TANKS LIMITING CONDITION OR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

ACTION'.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIR E

S 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days whenever radioactive materials are added to the tank and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during primary coolant system degassing operations, by analysis of the Reactor Coolant System noble gases.

COOK NUCLEAR PLANT - UNIT 2 3/4 11-3

NSTRUMENTATION ASES adiat on o ito ns e ta o

C t ued ALARM/TRIP M~MQIKK

6) Noble Gas Unit Vent Monitors a) Low Range (VRS 2505) b) Mid Range (VRS 2507) c) High Range (VRS 2509)

See the ODCM Not Applicable~

Not Applicable~

5.8x10 ~pCi/cc to

2. 7xl0 ~pCi/cc.

1.3xlO pCi/cc to

7. 5xlO+~pCi/cc.

2.9xlO ~pCi/cc to

1. 6xlO+ipCi/cc.

7) Gland Steam Condenser Vent Noble Gas Monitor a) Low Range (SRA 2805).

8) Steam Jet Air Ejector Vent Noble Gas Monitor a)

Low Range (SRA 2905)

See the ODCM See the ODCM 5.8x10 ~pCi/cc to

2. 7x10 ipCi/cc.

5.8x10 ~pCi/cc to 2.7x10 ~pCi/cc.

b) Mid Range (SRA 2907) c) High Range (SRA 2909)

9) Spent Fuel Storage (RRC-330)

Not applicable.~

Not Applicable.~

The monitor setpoint is selected to alarm and trip consistent with 10 CFR 70.24(a)

(2) 1.3x10 ~pCi/cc to

7. 5x10+~pCi/cc.

2.9x10 ~pCi/cc to l.6xlO+ipCi/cc.

lx10 mR/hr to lxlO+~mR/hr

• This is the minimum sensitivity of the instrument for normal operation, to follow the course of an accident, and/or take protective actions.

Values of the instrument above or below this minimum sensitivity range are acceptable.

~ These monitors are used to provide data to assist in post-accident off-site dose assessment.

COOK NUCUDLR PLANT - UNIT 2 B 3/4 3-lc AMENDMENT NO. 80, XX', 442 175

INSTRUMENTAT ON BASES 3 4 3

3 6

POST-ACCIDENT NSTRUMENT ION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.

3 4.3.3.7 Deleted 3 4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

Use of containment temperature monitoring is allowed once per hour if containment fire detection is inoperable.

3 4 3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the Waste Gas Holdup System.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C.

Cook Nuclear Plant.

3 4.3 4

TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-3 AMENDMENT NO. M, 445, 175

3 4 1

RADIOACTIVE FFLUE S

/USES 4

1 I UID 0

UP Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an, uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the n'earest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

This specification, being applicable to outside temporary tanks, does not apply to the refueling water storage tank, primary water storage tank, or the condensate storage tank, since they are a part of the permanent plant design.

3 4 ll 2 GASEOUS EFFLUENTS 3 4 2

P S

G S

XTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen and oxygen mixtures.

Maintaining the concentration of hydrogen or oxygen below their flammability limits provides that the releases of radioactive materials will be co'ntrolled in conformance with the requirements of the General Design Criterion specified in Section 11.1 of the Final Safety Analysis Report for the Donald C.

Cook Nuclear Plant.

3 4 1 2

2 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest site boundary willnot exceed 0.5 rem.

This is consistent with Standard Review Plan 15.7.1, "Paste Gas System Failure."

COOK NUCLEAR PLANT - UNIT 2 B 3/4 11-1 AMENDMENT NO. $k, 8Q 175

M N S

VE CO (continued) plan and implementing procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Plant Manager.

NRC approval shall be obtained as appropriate.

g.

Recommended changes to the Security Plan and implementing procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Plant Manager.

NRC approval shall be obtained as appropriate.

6.5:3.2 Records of the above activities shall be provided to the Plant

Manager, PNSRC and/or the NSDRC as necessary for required reviews.

6 0 TAB 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73, and b.

Each REPORTABLE EVENT shall be reviewed by the

PNSRC, and the results of this review shall be submitted to the NSDRC and the Vice President

- Nuclear Operations.

6.7 SAFEr Y LIMITV OLAT 0 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PNSRC.

This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.

C ~

The Safety Limit Violation Report. shall be submitted to 'the Commission, the Chairman of the NSDRC and the Vice President-Nuclear Operations within 14 days of the violation.

d.

Operation of the unit shall not be resumed until authorized by the Commission.

COOK NUCLEAR PLANT - UNIT 2 6-12 AMENDMENT NO. M, 438 175

MINI T VE CONTRO 6

8 PROCE URES AND OG 6.8.1 Vritten procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.

b.

Security Plan implementation.

c.

Emergency Plan implementation.

d.

PROCESS CONTROL PROGRAM implementation.

e.

OFFSITE DOSE CALCULATION MANUAL implementation.

f.

Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June

1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

6.8.2 Each procedure and administrative policy of Specification 6.8.1

above, and changes

thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.

The program will include the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

COOK NUCLEAR PIANT - UNIT 2 6-13 AMENDMENT NO. 44, 438 175

ADMINISTRATIVECONTROLS ROC DURE AND ROG

{continued) 6.8.4 The following programs shall be established, implemented, and maintained:

a.

adioac uet ot s

o A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the

ODCM, 2)

.Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2

3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the

ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to'0 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, COOK NUCLEAR PLANT - UNIT 2 6-13a AMENDMENT NO.

175

ADMINISTRATIVE CONTROLS PROCEDURES AND ROGRAMS (continued) 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10CFR Part 50, and 10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to

.radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

b.

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure

pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

Y 1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

COOK NUCLEAR PLANT - UNIT 2 6-13b AMENDMENT NO.

475

6 9

REPORTING RE U REM S

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

TUP EPO 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT - UNIT 2 6-13c AMENDMENT NO. M, 438 175

V CO 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functionsz, e.g.,

reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),

waste processing and refueling.

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20X of the individual total dose need not be accounted for.

In the aggregate, at least SOX of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

c ~

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the I-131 specific activity limit was exceeded.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

1 This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NUCLEAR PLANT - UNIT 2 6-14 AMENDMENT NO.

175

MINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT3 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitorieg Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operations shall be submitted within 90 days after January 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous

'effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste

systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT - UNIT 2 6-15 AMENDMENT NO. 48, kRQ, 438, 175

This page intentionally left blank.

COOK NUCL1RR PLANT - UNIT 2 6-16 AHENDMENT NO. 44, 43S, 175

MIN STRATIVE CO 0

ONTHL REACTOR OP T NG REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

0 E 0 ERAT NG 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a.

Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.

Rod Drop Time Limits for Specification 3/4.1.3.4, c.

Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, d.

Control Rod Insertion Limits for Specification 3/4.1.3.6, e.

Axial Flux Difference for Specification 3/4.2.1, f.

Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985 (Westinghouse Proprietary),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures

- Topical Report," September 1974 (Westinghouse Proprietary),

c ~

WCAP-10216-P-A, Part B, "Relaxation of Constant Axial Offset Control/F Surveillance Technical Specification," June 1983 (Westingh9use Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

COOK NUCLEAR PlANT - UNIT 2 6-17 AMENDMENT NO. $k, 438, 175

MINISTRATIVE CONTROLS OR 0

ERA NG ITS P R (Continued) 6.9.1.9.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC document control desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the attention of the document control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555),

with copies to the Region IIIAdministrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report.

These reports shall be submitted covering, the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.

C.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

High Specific Activity in RCS Coolant, Specification 3.4.8.

e.

RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.

Moderator Temperature Coefficient, Specification 3.1.1.4.

Sealed Source Leakage in Excess of Limits, Specification 4.7.F 1.3:

h.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

Violation of Safety Limit, Specification 6.7.1.

COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. M, 438 175

6.10.1 The following records shall be retained for at least five years:

Records and logs of unit.operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1.

Records of sealed source and fission detection leak tests and results.

g.

Records of annual physical inventory of all sealed source material on record.

COOK NUCLEAR FIANT - UNIT 2 6-19 ANENDMENT NO. M, 440, 445, 488 175

M S

0 0

CORD RET 0

(Continued) 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environment.

e.

Records of transient or operational cycles for those facility components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the Plant Staff.

h, Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or equipment or review of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PNSRC and the NSDRC.

1.

Records of radioactive shipments.

m.

Records of the service lives of hydraulic snubbers including the date at which service life commences and associated installation and maintenance records.

n.

Records of reviews performed for changes made to the OFFSITE DOSE CALCUIATION MANUAL and the PROCESS CONTROL PROGRAM.

6 RADIA ION PROTECTIO PROG Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

COOK NUCLEAR PIANT - UNIT 2 6-20 AMENDMENT NO. M, 438, 454 175

MINISTRATIVE CONTROLS ICH RADIA ION 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radi,ation area and'ntrance thereto shall be controlled by requiring issuance of a Radiation Work Permit Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.

C ~

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiati.on is greater than 1000mrem/hr.

When

possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.

In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assi,gned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT - UNIT 2 6-21 AMENDMENT NO. 80, 436, 438 175

rn DMINISTRATIUE CO 0

S 6 13 PROC SS CO 0

P OQ 6.13.1 Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal,

State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.

6 14 OFFS TE DOSE CALCULATION MANUAL ODCM 6.14.1 Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6 '0.2.n.

This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.

A determination that the change will maintain the level of radioactive effluent control zequired by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuzacy or zeliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.

c ~

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected

pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

COOK NUCLEAR PLANT - UNIT 2 6-22 AMENDMENT NO. M, 438 175