Text

Corrections to Proposed Amendment 184, Editorial Errors Corrected
	ML022600676
Person / Time
Site:	Kewaunee
Issue date:	08/29/2002
From:	Webb T; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NRC-02-087
	Download: ML022600676 (7)
	v • d • e

NMC Committed to Nuclear Excellence Kewaunee Nuclear Power Plant N490 Highway 42 Kewaunee, WI 54216-9511 920 388.2560 Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241 9207552321 Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-087 August 29, 2002 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Corrections to Proposed Amendment 184 for the Kewaunee Nuclear Power Plant Technical Specifications

Reference:

Letter from Mark E. Warner (NMC) to Document Control Desk (NRC), "Proposed Amendment 184 to the Kewaunee Nuclear Power Plant Technical Specifications,"

dated June 7, 2002 In the referenced letter, several editorial errors were discovered in the submittal pages. Attachment 1 contains these strikeout pages while attachment 2 contains the corrected pages. These changes do not affect the significant hazards consideration determination or the environmental evaluation of the referenced letter.

We apologize for any inconvenience this may have caused.

Thomas Webb Regulatory Affairs Manager Kewaunee Nuclear Power Plant GOR Attach.

cc -

US NRC, Region III US NRC Senior Resident Inspector Electric Division, PSCW Letter from T. Webb (NMC)

To Document Control Desk (NRC)

Dated August 29, 2002 Corrected Strikeout Pages TS iii TS iv

Section 4.4 Containment Tests 4.4-1 4.4.a Integrated Leak Rate Tests (Type A)........................................

4.4-1 4.4.b Local Leak Rate Tests (Type B and C).....................................

4.4-1 4.4.c Shield Building Ventilation System............................................

4.4-1 4.4.d Auxiliary Building Special Ventilation System............................ 4.4-3 4.4.e Containment Vacuum Breaker System.....................................

4.4-3 4.4.f Containment Isolation Device Position Verification...............................................................................

4.4-3 4.5 Emergency Core Cooling System and Containment Air Cooling System Tests................................................................................

4.5-1 4.5.a System Tests...........................................................................

4.5-1 4.5.a.1 Safety Injection System......................................

4.5-1 4.5.a.2 Containment Vessel Internal Spray System...............................................................

4.5-1 4.5.a.3 Containment Fan Coil Units................................

4.5-2 4.5.b Component Tests.....................................................................

4.5-2 4.5.b.1 Pumps................................................................

4.5-2 4.5.b.2 Valves.................................................................

4.5-2 4.6 Periodic Testing of Emergency Power System...........................................

4.6-1 4.6.a Diesel Generators.....................................................................

4.6-1 4.6.b Station Batteries.......................................................................

4.6-2 4.7 Main Steam Isolation Valves.......................................................................

4.7-1 4.8 Auxiliary Feedwater System.......................................................................

4.8-1 4.9 Reactivity Anomalies..................................................................................

4.9-1 4.10 Deleted 4.11 Deleted 4.12 Spent Fuel Pool Sweep System................................................................

4.12-1 4.13 Radioactive Materials Sources..................................................................

4.13-1 4.14 Testing and Surveillance of Shock Suppressors (Snubbers)..................... 4.14-1 4.15 Deleted 4.16 Reactor Coolant Vent System Tests.........................................................

4.16-1 4.17 Control Room Postaccident Recirculation System....................................

4.17-1 5.0 Design 5.1 5.2 5.3 5.4 Features.....................................................................................................

5.1-1 Site...........................................................................................................

5.1-1 Containment..............................................................................................

5.2-1 5.2.a Containment System................................................................

5.2-1 5.2.b Reactor Containment Vessel...................................................

5.2-2 5.2.c Shield Building..........................................................................

5.2-2 5.2.d Shield Building Ventilation System............................................

5.2-2 5.2.e Auxiliary Building Special Ventilation Zone and Special Ventilation System.....................................................

5.2-32 Reactor Core.............................................................................................

5.3-1 5.3.a Fuel Assemblies.......................................................................

5.3-1 5.3.b Control Rod Assemblies...........................................................

5.3-1 Fuel Storage..............................................................................................

5.4-1 5.4.a Criticality..................................................................................

5.4-1 5.4.b Capacity..................................................................................

5.4-1 5.4.c Canal Rack Storage................................................................

5.4-21 Proposed Amendment 184 TS iii 06/10/2002 Pgge Title

Section Title Page 6.0 Administrative Controls............................................................................................

6.1-1 6.1 Responsibility.............................................................................................

6.1-1 6.2 Organization..............................................................................................

6.2-1 6.2.a Off-Site Staff............................................................................

6.2-1 6.2.b Facility Staff.............................................................................

6.2-1 6.2.c Organizational Changes.........................................................

6.2-21 6.3 Plant Staff Qualifications............................................................................

6.3-1 6.4 Training.....................................................................................................

6.4-1 6.5 Deleted.........................................................................................

6.5 6.5-6 6.6 Deleted.....................................................................................................

6.6-1 6.7 Safety Limit Violation.................................................................................

6.7-1 6.8 Procedures................................................................................................

6.8-1 6.9 Reporting Requirements............................................................................

6.9-1 6.9.a Routine Reports........................................................................

6.9-1 6.9.a.1 Startup Report....................................................

6.9-1 6.9.a.2 Annual Reporting Requirements......................... 6.9-1 6.9.a.3 Monthly Operating Report...................................

6.9-3 6.9.b Unique Reporting Requirements...............................................

6.9-3 6.9.b.1 Annual Radiological Environmental Monitoring Report...............................................

6.9-3 6.9.b.2 Radioactive Effluent Release Report.................. 6.9-3 6.9.b.3 Special Reports..................................................

6.9-3 6.10 Record Retention.....................................................................................

6.10-1 6.11 Radiation Protection Program...................................................................

6.11-1 6.12 System Integrity.......................................................................................

6.12-1 6.13 High Radiation Area.................................................................................

6.13-1 6.14 Post A^ *ident S

,mplig aRnd M* nit*rFin*

eletedd.......................................

6.14-1 6.15 Secondary W ater Chemistry.....................................................................

6.15-1 6.16 Radiological Effl uents..............................................................................

6.16-1 6.17 Process Control Program (PCP)...............................................................

6.17-1 6.18 Offsite Dose Calculation Manual (ODCM).................................................

6.18-1 6.19 Major Changes to Radioactive Liquid, Gaseous and Solid W aste Treatment Systems........................................................

6.19-1 6.20 Containment Leakage Rate Testing Program...........................................

6.20-1 7/8.0 Deleted Proposed Amendment 184 TS iv 06/10/2002

I, Letter from T. Webb (NMC)

To Document Control Desk (NRC)

Dated August 29, 2002 Affected Pages TS iii TS iv

4.4 Containment Tests 4.4-1 4.4.a Integrated Leak Rate Tests (Type A)........................................

4.4-1 4.4.b Local Leak Rate Tests (Type B and C).....................................

4.4-1 4.4.c Shield Building Ventilation System............................................

4.4-1 4.4.d Auxiliary Building Special Ventilation System............................ 4.4-3 4.4.e Containm ent Vacuum Breaker System.....................................

4.4-3 4.4.f Containment Isolation Device Position Verification...............................................................................

4.4-3 4.5 Emergency Core Cooling System and Containment Air Cooling System Tests................................................................................

4.5-1 4.5.a System Tests...........................................................................

4.5-1 4.5.a.1 Safety Injection System......................................

4.5-1 4.5.a.2 Containment Vessel Internal Spray System...............................................................

4.5-1 4.5.a.3 Containm ent Fan Coil Units................................

4.5-2 4.5.b Com ponent Tests.....................................................................

4.5-2 4.5.b.1 Pum ps................................................................

4.5-2 4.5.b.2 Valves.................................................................

4.5-2 4.6 Periodic Testing of Emergency Power System...........................................

4.6-1 4.6.a Diesel Generators.....................................................................

4.6-1 4.6.b Station Batteries.......................................................................

4.6-2 4.7 M ain Steam Isolation Valves.......................................................................

4.7-1 4.8 Auxiliary Feedwater System.......................................................................

4.8-1 4.9 Reactivity Anom alies..................................................................................

4.9-1 4.10 Deleted 4.11 Deleted 4.12 Spent Fuel Pool Sweep System................................................................

4.12-1 4.13 Radioactive Materials Sources..................................................................

4.13-1 4.14 Testing and Surveillance of Shock Suppressors (Snubbers)..................... 4.14-1 4.15 Deleted 4.16 Reactor Coolant Vent System Tests.........................................................

4.16-1 4.17 Control Room Postaccident Recirculation System....................................

4.17-1 5.0 Design Features.....................................................................................................

5.1-1 E. 1 Site...........................................................................................................

5.1-1 5.2 Containment..............................................................................................

5.2-1 5.2.a Containment System................................................................

5.2-1 5.2.b Reactor Containment Vessel...................................................

5.2-2 5.2.c Shield Building..........................................................................

5.2-2 5.2.d Shield Building Ventilation System............................................

5.2-2 5.2.e Auxiliary Building Special Ventilation Zone and Special Ventilation System.......................................................

5.2-2 5.3 Reactor Core.............................................................................................

5.3-1 5.3.a Fuel Assem blies.......................................................................

5.3-1 5.3.b Control Rod Assem blies...........................................................

5.3-1 5.4 Fuel Storage..............................................................................................

5.4-1 5.4.a Criticality..................................................................................

5.4-1 5.4.b Capacity.................................................................................. 5.4-1 5.4.c Canal Rack Storage..................................................................

5.4-1 TS iii Page Title I

-17 Section

Section Title Page 6.0 Administrative Controls............................................................................................

6.1-1 6.1 Responsibility.............................................................................................

6.1-1 6.2 Organization..............................................................................................

6.2-1 6.2.a Off-Site Staff............................................................................

6.2-1 6.2.b Facility Staff.............................................................................

6.2-1 6.2.c Organizational Changes...........................................................

6.2-1 6.3 Plant Staff Qualifications............................................................................