ML051430148

Preoperational Tests, Startup Tests, and Other Items Which Must Be Completed Prior to Proceeding to Succeeding Operational Modes

ML051430148
Person / Time
Site:	Farley
Issue date:	05/01/2005
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
Liu T, NRR, 415-1315
References
Download: ML051430148 (6)

Text

ATTACHMENT 2 TO LICENSE NPF-2 Preoperational Tests. Startup Tests, and Other Items Which Must be Completed Prior to Proceeding to Succeeding Operational Modes I

This attachment identifies certain preoperational tests, startup tests, and other items which must be completed to the Commission's satisfaction prior to proceeding to certain specified Operational Modes. Alabama Power Company shall not proceed beyond the authorized Operational Modes without prior written authorization from the Commission.

A. Alabama Power Company may at the license issue date proceed directly to Operational Mode 6 (initial fuel loading), and may subsequently proceed to Operational Mode 2 (startup), except as noted below.

B. The following items must be completed prior to proceeding to Operational Mode 2 (startup):

1. Satisfactory completion of the following tests:

a. 032-5-002 Heating and Ventilation (Radiation Areas)

b. 036-5-005 Turbine Driven Auxiliary Feedwater Pump

c. 037-4-005 Demineralizer Water System

d. 044-4-003 Condensate Systems

e. 045-5-003 Feedwater System

f. 052-5-012 Boron Injection System - Trace Heating

9. 060-5-008 Containment Purge and Exhaust

h. 061-5-005 Spray Additive Tank Flow Rate Verification I. 063-5-005 Steam Generator Blowdown

j. 066-5-002 Reactor Cavity Cooling

k. 068-5-003 Solid Radioactive Waste System

1. 068-5-004 Drumming Station Heat Tracing

m. 069-5-023 Waste Evaporator

n. 069-5-026. Floor Drain Tank

0. 072-5-004 Gaseous Radioactive Waste P. 094-4-003 Secondary System Chemical Addition System

q. 100-5-010 Pre-Critical Heatup Thermal Expansion Farley- Unit 1 June 25, 1977

2. Completion of modification Qf sample sink exhaust ventilation in the Auxiliary Building Sample Room.

3. Completion of installation of single point recorders for the six effluent radiation monitors.

4. Completion of installation of integrator and recorder for liquid effluent line and installation of integrator for dilution water line.

5. Completion of installation of flow rate measuring, recording and integrating instrumentation for the plant vent.

6. Resolution of the measures and modifications required to ensure the successful operation of the ITT Grinnel Hydraulic Shock Suppressors.

Farley - Unit I June 25, 1977

APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-2 Southern Nuclear Operating Company, Inc. (SNC), shall comply with the following conditions on the schedules noted below:

Amendment Condition Completion Number Additional Condition Date 137 SNC shall complete classroom and simulator training Prior to Unit 2 entering for operations crews as described in SNC's letter Mode 2 from the dated September 22, 1997, and evaluated in the staff's spring 1998 refueling Safety Evaluation dated April 29, 1998. outage.

137 SNC shall complete final simulator modifications in Two years after restart accordance with ANSI/ANS 3.5-1985 and review from the Unit 1 fall results of the Cycle 16 startup testing to determine 1998 refueling outage.

any potential effects on operator training as described in SNC's letter dated September 22,1997, and evaluated in the staff's Safety Evaluation dated April 29, 1998.

137 SNC shall provide a Steam Generator (SG) Tube Prior to the Unit 1 Rupture radiological consequences analysis that SG replacement outage incorporates a flashing fraction , which is in spring 2000.

appropriate for the Unit 1 design.

146 SNC shall relocate certain Technical Specification Concurrent with the requirements to SNC-controlled documents. implementation of Implementation of the Improved Technical Specifications the Improved shall include relocating these certain technical Technical specification requirements to the appropriate documents, Specifications.

as described in Table LA - Removal of Requirements from Retained Technical Specifications and Table R -

Relocation of Technical Specifications, that are attached to the NRC staff's Safety Evaluation enclosed with this amendment.

Amendment No. 146

APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-2 Amendment Condition Completion Number Additional Condition Date 146 The schedule for performing new and revised Surveillance Requirements (SRs) shall be as Concurrent with the follows: implementation of the Improved

1. For SlIs that are new in this amendment the Technical first performance is due at the end of the first Specifications.

surveillance interval that begins on the date of implementation of this amendment.

2. For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance Interval begins upon completion of the first surveillance performed after implementation of this amendment.

3. For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

4. For SRs that existed prior to this amendment whose Intervals of performance are being extended, the first extended surveillance Interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

Amendment No. 146

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-8 Southern Nuclear Operating Company, Inc. (SNC), shall comply with the following conditions on the schedules noted below:

Amendment Condition Completion Number Additional Condition Date 129 SNC shall complete classroom and simulator training Prior to Unit 2 for operations crews and temporary simulator entering Mode 2 from modifications as described In SNC's letter dated the spring 1998 September 22, 1997, and evaluated in the staff's refueling outage.

Safety Evaluation dated April 29,1998.

129 SNC shall review the results of the Cycle 13 startup Prior to Unit 1 startup testing to determine any potential effects on operator from the fall 1998 training and incorporate these changes into licensed refueling outage.

operator training as described In SNC's letter dated September 22, 1997, and evaluated In the staff's Safety Evaluation dated April 29, 1998.

129 SNC shall provide a Steam Generator (SG) Tube Prior to the Unit 2 SG Rupture radiological consequences analysis that replacement outage incorporates a flashing fraction , which is appropriate in spring 2001.

for the Unit 2 design.

137 SNC shall relocate certain Technical Specification Concurrent with the requirements to SNC-controlled documents. implementation of the Implementation of the Improved Technical Specifications Improved Technical shall include relocating these certain technical specification Specifications.

requirements to the appropriate documents, as described in Table LA - Removal of Requirements from Retained Technical Specifications and Table R - Relocation of Technical Specifications, that are attached to the NRC staff's Safety Evaluation enclosed with this amendment.

Amendment No. 137

APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-8 Amendment Condition Completion Number Additional Condition Date The schedule for performing new and revised Concurrent with the 137 Surveillance Requirements (SRs) shall be as Implementation of follows: the Improved Technical

1. For SRs that are new in this amendment the Specifications.

first performance is due at the end of the first surveillance Interval that begins on the date of implementation of this amendment.

2. For SRs that existed prior to this amendment whose Intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

3 For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance Is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

4. For SRs that existed prior to this amendment whose Intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

Amendment No. 137