ML17326A850

Amends 44 & 26 to Licenses DPR-58 & DPR-74,respectively, Revising Fire Protection Tech Specs to Reflect Mods to Facility & Revising Tech Spec Index to Add Environ Qualification

ML17326A850
Person / Time
Site:	Cook
Issue date:	01/30/1981
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17326A851	List: ML17326A850 ML17326A852
References
NUDOCS 8103020762
Download: ML17326A850 (24)

Text

Py8 RECy 0

Cy 0O C)

+~

~O

+***+

l UNITED STATES NUCLEAR REGULATORY COIVIMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Indiana and Michigan Electric Company (the licensee) dated December 22, 1978 and April 9, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations seg forth in 10 CFR Chapter I; B.

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

D.

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

H N

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:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised. through Amendment No. 44

, are hereby incorporated in the..license.

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

3.

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

OR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Dafe of Issuance:

January 30, 1981

'Steven A. Varga, C ie Operating Reactors Branch Pl Division of Licensing

ATTACHMENT TO LICENSE AMENDMENTS AMENDHENT $0. 4'4 TO FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-315 Revise Appendix A as follows:

Remove Pages XVII XVIII 3/4 3-51 3/4 3-52 3/4 3-53 3/4 7-45 3/4 7-46 Insert Pa es XVII XVIII 3/4 3-51 3/4 3-52 3/4 3-53 3/4 7-45 3/4 7-46

~ 1 INDEX ADMINISTRATIVE CONTROLS

'ECTION PAGE 6el RESPONSIBILITYe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

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

~

~ ~ ~

6-1 6 e 2 ORGANIZATION 0 f t J

ffs~te....................................................:

6-1 F

'I ea acslsty Staff...............,.:.............'...............

e 6-1 6e3 FACILITY STAFF QUALIFICATIONS...............................

6-5 6 ~ 4 TRAININGe

~ ~

~ ~ ~

~

~

~ ~ ~

~ ~ ~ e

~

~ ~ ~

~

~ ~

~

~

~

~

~

~ ~ ~

~

~

~

~

~ ~

~

~.~

~

'e

~

~

~

~ ~

~

~

~ "~

~

~

6-5 6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW 'COMMITTEE F

t Unctlane ~ ~ ~ ~ ~

, ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

e

~

~

~

~

~

~

~

6-5 CONpasi t10n

~

~

~

~

~ e

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~ '

~

~

~

~

~

~

~

~

6-6 1 ternates........,.............................,...........

A 6-6 M t eet>ng Frequency..............,..........'.................

UOruN e

~

~ ~ e ~ e

~

~

~

~

~ e

~ ~

~

~ ~

~

~ ~

~

~

~ e

~

~

~

~ ~ ~

~

~

~

~ ~ ~ ~

~

~ ~

~

~ ~

~

~

~

~

~

~

~

~

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

uth0ri ty e

~

~

~

~

~

~

~

~ ~ e

~

~

~

~

~ ~

~

~

~ ~

~

~

~

~

~

A

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

I

~

~ ~

~ ~

~

~

~

~ ~

~

~

~

~

~

~

~ ~

~

~

~

~

~

6-7 eCOrds

~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~ ~ ~ ~ ~ ~

~

~

e

~

~

~

~

~

~

~

~

~ e

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

R 6-8 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE F pc,'"

~~~4~

LfpC e IOn ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ e

~ ~

~ e e

~

~ ~ ~ ~

~

~

~ ~

~

e p

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

I COWPOS 1 Ie1 On ~

~ ~

~ ~

~

~

~

~

~ ~

~

~

~ ~

~ e

~

~

~

~

~ ~ ~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~ ~ ~

~

~

~

~

6-8 6 a lternates................................................

A 6-9 D.

C.

COOK - UNIT 1

XVII

ADMINISTRATIVE CONTROLS SECTION Consultants..

Meeting Frequency.

quorum..

Review.

Audits Authority..

Records PAGE 6-9 6-9 6-9 6-10 6-11 6-11 6-'12 6.6 REPORTABLE OCCURRENCE ACTION 6".12 6.7 SAFETY LIMIT VIOLATION.

6-13 6.8 PROCEDURES 6-13 6.9 REPORTING RE UIREMENTS

6. 9. 1 ROUTINE REPORTS AND REPORTABLE OCCURENCES

6. 9. 2 SPECIAL REPORTS 6-14 6" 18

6. 10 RECORD RETENTION..

6-19 6.11 RADIATION PROTECTION PROGRAM.

6-20

6. 12 HIGH RADIATION AREA.

6-20

6. 13 ENVIRONMENTAL VALI F ICATION.

6-21 D.

C.

COOK - UNIT 1

XVIII Amendment No.44

~ t;

~

l,t V

'I

I I

I I

~

I ~

~ I

~

I

~

I

~

~

~

~

~

~

~

~

~

~ I I

~

~

I

~

~

~

~

~

~

I

~

I ~

~ I '

~

~

~

I

~

~

~

~

~ I'

~

~ I

~

I ~

~

~

~

~

~

o I

~

~

~

~

I

~

I I

~

~

I

~

~

~

g

~

I I ~

~

~

~

I I

I

~

~

~

~

I I

~

~

~

~ I I I

~

1!4 ll l

I 1

1 I

I I

o t

II,I

TABLE

3. 3-10 FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE l.

Containment Zone 6, quadrant 1 Cable Tunnel Zone 7, quadrant 2 Cable Tunnel Zone 8, quadrant 3N Cable Tunnel Zone 9, quadrant 3M Cable Tunnel Zone 10, quadrant 3S Cable Tunnel Zone ll, quadrant 4 Cable Tunnel quadrant 1

quadrant 2

quadrant 3

quadrant 4

1-HV-CFT-1 Charcoal Filters 1-HV-CFT-2 Charcoal Filters 2.

Control Room Zone 22, Control Room 3.

Cable Spreading Room Zone 15, Switchgear Cable Vault Zone 16, Auxiliary Cable Vault Zone 17, Control Room Cable Vault Zone 18, Control Room Cable Vault 4.

Diesel Generator Diesel Generator Room lAB Diesel Generator Room lCD SMOKE IONIZATION) 24 10 5

24 25 HEAT (THERMISTOR) 143" 18ll 1

1 OPTICAL

~INFRARED 5.

Diesel Fuel Oil Room D.

C.

COOK - UNIT 1

3/4 3-52 A'mendment No. 44,

TABLE 3.3-10 (Cont'd)

FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE 6.

Auxi 1 iary Bui 1 ding SMOKE

( IONIZATION)

HEAT THERMISTOR)

OPTICAL

~(INFRARED Zone 1, Zone 2)

Zone 3, Zone 4, Zone 5, Elevation 573 ft.

Elevation 587 ft.

Elevation 609 ft.

Elevation 633 ft.

Elevation 650 ft.

5 42 22 31 26 Zone 12, 4 Kv Switchgear 3

Zone 13, Engineered Safety Switchgear 7

Zone 14, CRD Switchgear 6

1-HV-AES-1 Charcoal Filters 1-HV-AES-2 Charcoal Filters 12-HV-AFX Charcoal Filters 1-HV-CPR Charcoal Filters 1-HV-CIPX Charcoal Filters 1-HV-ACRF Charcoal Filters 7.

Fuel Storage Zone 19, New Fuql Storage Room D.

C.

COOK - UNIT 1

3/4 3-53 Amendment No. 44,

l V

4

~ ~

SURVEILLANCE RE UIREHENTS Continued c ~

2, By inspection of deluge and preaction type system spray headers to verify their integrity.

3.

By inspection of each open head deluge nozzle to verify no blockage.

At least once per 3 years by performing an air flow test through each open head deluge header and verifying each open head deluge nozzle is unobstructed.

0.

C.

COOK - UNIT 1

3/4 7-4b Amendment No, 44

~

I

TABLE 3.7-5 SRRAY AND/OR SPRINKLER SYSTEMS A.

OPEN HEAD DELUGE TYPE WATER SYSTEMS LOCATION 1-HV-AES-1 Charcoal Filters 1-HV-AES-2 Charcoal Filters 12-HV-AFX Charcoal Filters 1-HV-CPR-1 Charcoal Fi-lters 1-HV-CIPX-1 Charcoal Filters 1-HV-ACRF-1 Charcoal Filters ACTUATION Electri c-heat Electric-heat Electric-heat Electric-heat Electric-heat Electric-heat LOCATION B.

CLOSED HEAD SPRINKLER TYPE WATER SYSTEMS TYPE SYSTEM ACTUATION Preaction Sprinkler Auxiliary Bldg. Elev, 587* & 609" Preaction Sprinkler (Corridors, charging, safety Inj.

pump rooms, laundry area)

Auxiliary Bldg.

Cask Handling Area" Auxiliary Bldg.

Drumming Area" Preaction Sprinkler Dry Pilot Dry Pilot Dry Pilot Reactor Coolant Pumps (4)'reaction Sprinkler Manual Shared system with D.

C.

COOK - UNIT 2.

D.

C..

COOK - UNIT 1

3/4 7-46 Amendment No. ~4,

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

26 License, No. DPR-74 1.

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

A.

The applications for amendment by Indiana and Michigan Electric Company (the licensee) dated February 13, 1979 and April 9, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applicatio'ns, 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, atId (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 (FR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes

.o the Technical Specifications as indicated in the attachment to this license amendment, and paragraph Z.C.(2) of Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2)

Techni ca 1 S eci ficat ions The Technical Specifications contained in Appendices A and B, as revised through'Amendment No. 26

, are hereby incorporated in the li,cense.

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

3.

This license amendment is effective as of the da.e of its issuance.

OR TKE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 30, 1981 Steven A~Varga, Chi~

Operating Reactors Branch Pl Division of 'censing

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.

26 TO FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:

Remove Pages XVII 3/4 3-51 3/4 3-52 3/4 7-41 3/4 7-42 Insert Pages XYII 3/4 3-51 3/4 3-52 3/4 7-41 3/4 7-4P

ADMINISTRATIVE CONTROLS SECTION PAGE onsultantst

~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t

~ ~ ~ ~ ~ ott ~ ~ ~ t ~ tt ~ ~ ~ ~ t ~ ~ ~ t ~ ~

~ os ~

C 6-9 Meeting Frequency...........................................

6-9 Uol Umt

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ o

~

~

~

~

~

~

~

~

~

~

Q 6-9 evl ew ~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ t

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

R 6-10 AUdlts

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ t

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ o

~

~

~

~

~

~

~

~

~

~

6-11 Uthor1 ty t

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ t

~

~

~

~

~ t

~

~

~

~

~

~

~

~

~

~

A 6-11 eCOrdS

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~

~ ~ o ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~

~

~

~

~

~

~

~

~

R 6-12 6.6 REPORTABLE OCCURRENCE ACTION................................

6-12 6.7 SAFETY LIMIT VIOLATION......................................

6-13

,8 PROCEDURES...,.......,......................................

6 6-13 6.9 REPORTING RE UIREMENTS 6.F 1 ROUTINE REPORTS AND REPORTABLE OCCURENCES................

6-14 6.9.2 SPECIAL REPORTS....................,.........,......,......

6-18 6.10 RECORD RETENTION...........................................

6-19 6.11 RADIATION PROTECTION PROGRAM...............................

6-20 6.12 HIGH RADIATIONAREA.........................,..............

6-20

6. 13 ENVIRONMENTAL UALI F I CAT I ON.

6-21 D.

C.

COOK -

UN IT 2 XVI I Amendment No.

26

TABLE 3. 3-11 FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE 1.

Containment Zone I, quadrant 1 Cable Tunnel Zone 2, quadrant 2 Cable Tunnel Zone 3, quadrant 3N Cable Tunnel Zone 4, quadrant 3M Cable Tunnel Zone 5, quadrant 3S Cable Tunnel Zone 6, quadrant 4 Cable Tunnel quadrant 1

quadrant 2

quadrant 3

quadrant 4

2-HV-CFT-1 Charcoal Filters 2-HV-CFT-2 Charcoal Filters 2.

Control Room Zone 16, Control Room 3.

Cable Spreading Room SMOKE IONIZATION) 22 HEAT OPTICAL (THERMISTOR)

(INFRARED) 12 5

23 11 1

1 Zone 10, Switchgear Cable Vault Zone ll, Auxiliary Cable Vault Zone 12, Control Room Cable Vault Zone 13, Control Room Cable Vault 4.

Diesel Generator Diesel Generator Room 2AB Diesel Generator Room 2CD 5.

Diesel Fuel Oil Room 8

5 24 25 D.

C.

COOK - UNIT 2 3/4 3-51 Amendment No. 22

0 TABLE 3.3-11 (Cont'd)

FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE 6.

Auxiliary Building Elevation 573 ft."

Elevation 587 ft."

Elevation 609 ft."

Elevation 633 ft."

Elevation 650 ft.*

SMOKE (IONIZATION) 5 42 22 31 26 HEAT OPTICAL (THERMISTOR)

(INFRARED Zone 7, 4 Kv Switchgear Zone 8, Engineered Safety Switchgear Zone 9, CRD Switchgear 2-HV-AES-1 Charcoal Filters 2-HV-AES-2 Charcoal Filters

'2-HV-AFX Charcoal Filters 2-HV-CPR Charcoal Filters 2-HY-CIPX Charcoal Filters 2-HV-ACRF Charcoal Filters 7.

Fuel Stor age New Fuel Storage Room" 37' 1

1 1

1 1

5 4

4 Shared system with D.

C.

COOK - UNIT 1 D ~

C.

COOK - UNIT 2 3/4 3-,52 Ame'ndment No. 26

TABLE 3.7-5 SRRAY AND/OR SPRINKLER SYSTEMS A.

OPEN HEAD DELUGE TYPE MATER SYSTEMS LOCATION 2-HV-AES-1 Charcoal Fi 1 ters 2-HV-AES-2. Charcoal Fi 1 ters 12-HV-AFX Charcoal Filters 2-HV-CPR-1 Charcoal Fi1 ters 2-HV-CIPX-1 Charcoal Filters 2-HV-ACRF-1 Charcoal Filters ACTUATION Electric-heat Electric-heat Electric-heat Electric-heat Electric-heat Electric-heat B.

CLOSED HEAD SPRINKLER TYPE MATER SYSTEMS LOCATION Auxiliary Bldg.

Cask Handling Area" Auxiliary Bldg; Drumming Area~

Auxiliary Bldg. Elev 587*

8; 609~

(Corridors, charging, safety Inj. pump rooms, laundry area)

Reactor Coolant Pumps (4)

TYPE SYSTEM Preaction Sprinkler Preaction Sprinkl er Preaction Sprinkler.

Preaction Sprinkler ACTUATION Dry Pilot Dry Pilot Dry Pilot.

Manual Shared system with D.

C.

COOK - UNIT l.

0.

C.

COOK - UNIT 2, 3/4 7-41 Amendment No. 26

PLANT SYSTEt1S LOW PRESSURE C02 SYSTEMS I INITING CONDITION FOR OPERATIOiN 3.7.9.3 The low pressure CO systems located in the areas shown in

'f ble 3.7 0-shall be OPERRBLi wit ha minimum level of 50/ and a minimum pressure of 285 psig in the associated storage tank.

APPLICABILIl'Y: Whenever equipment in the low pressure C02 protected areas is required to be OPERABLE.

ACTION:

With one or more of the above required low pressure C02 systems inoperable, establish a continuous fire watch ivith backup fire suppression equipment for the unprotected area(s),

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit a Special Report to the Com-missionn pur uant to Specification

6. 9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMEHTS N

4.7.9.3 Each of the above required low pressure C02 systems shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying the C02 storaqe tank

'level and pressure.

b.

At least once per 18 months by verifying:

l.

The systeni v<ilvos and associ ited ventilatioi> dampei s

<<ctu,ite manuilly and automatically, upo;i recoipL'f a simulated actu&.ion sigiial, and 2.

Flow from each nozzle during a "Puff Test."

D.

C.

COOK - UNIT 2 3/4,7-42