ML18054A156

Forwards Rev 3 to Updated FSAR for Palisades Plant, Reflecting Removal of Pressurizer Heater Load Ctrs from Safety Injection Sys,Revised Turbine Valve Test Frequency & Replacement of Heat Tracing on Iodine Removal Sys Piping

ML18054A156
Person / Time
Site:	Palisades
Issue date:	10/30/1987
From:	Buckman F CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18054A157	List: ML18054A156
References
NUDOCS 8711090278
Download: ML18054A156 (4)

Text

consumers Power company General Offices:

1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1217 October 30, 1987 Nuclear Regulatory Connnission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

REVISION 3 TO THE FINAL SAFETY ANALYSIS REPORT (FSAR) UPDATE Fre4erick W Buckman Vice President Nuclear Operations In accordance wtth 10CFR50.7l(e)(ii), one original and 12 copies to the Palisades Plant.FSAR Upd_ate Revision* 3 is enclosed.* This revision is*

submitted on a replacement-page basis and includes a list of effective pages of the FSAR Update. Replacement pages containing revisions include a line

• vertically drawn in the right margin and "Rev. 3", in the lower right-hand corner.

The enclosed revision does not include revisions to Figures 7-14, 7-24 and 7-30.

These revisions are currently in progress and will be submitted by the end of November, 1987.

To the best of my knowledge, this revision accurately incorporates all changes made to the *Palisades Plant or to the Palisades Plant procedures described in the FSAR, and all the other applicable information contained in licensing submittals made to the.NRC through April,*1987.

In accordance with 10CFR50.71, an identification of changes made under the provisions of 10CFR50.59, but not previously submitted to the NRC, are identified as follows:

Removed pressurizer heater load cent~rs from Safety Injection System.

Revised Turbine Valve Test frequency.

Replaced the existing heat tracing on the Iodine Removal System piping.

Turbine Generator Coastdown - Removed* the-V /Hz-cards* from the voltage regulator circuit due to equipment instability circuits.

Added Containment High Pressure pretrip setpoint change.

Added Primary Coolant Pump select switch for Reactor Protection System setpoints.

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Nuclear Regulatory Commission Palisades Plant Revision 3, Final Safety Analysis Report October 30, 1987 Added changes made to the Component Cooling System.

Modified controls of CV-0878 and CV-0825.

This revision also reflects FSAR clarifications and corrections that were identified during our System Functional Evaluation (SFE) Program which included a detailed review of the Palisades FSAR and are identified as follows:

Reactor Vessel Pressure/Temperature Limits - change in operator curves resulting from Technical Specifications Amendment 89.

Corrected PORV operation description.

Deleted Technical Specification test for Reactor Internals Vibration Monitoring.

2 Incorporates use of ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1, 2 and 3 Piping Systems, into FSAR.

Reflects correct as-built condition of the Containment Air Cooler Relief Panels.

Containment De-isolation -

FSAR corrected to reflect that CCW and MSIV valves may be opened under administrative controls.

Editorial change to clarify basis of containment spray pumps starting times.

Corrected inaccurate statement regarding the Containment Isolation System Testing.

Reflected the Engineering Manual Procedure (EM-09-02/04) revision, Updating the ISI Pump Program to the ASME Section XI, 1983 Edition.

Revised Regulato-ry Guide 1. 97 1ristrumentati6n information~

Changed description of Plant dataloggers, Plant Information Processor (PIP) and Secondary Position Indication (SPI).

Corrected description of the steam generator low pressure initiating features.

Corrected statement regarding Main Feedwater and Steam Auto closure override button.

FSAR Update changed to specify proper operator control of Auxiliary Feedwater System upon Steam Generator failure. Isolation.

OC1087-0196A-NL04

Nuclear Regulatory Commission Palisades Plant Revision 3, Final Safety Analysis Report October 30, 1987 Corrected explanation of testing of Containment High Radiation.

Eliminated requirement to perform l/M plots during refueling.

Revised Chemical and Volume Control System charging pump capacity.

Revised constant' speed charging pumps flow rate.

Revised boric acid pumps flow rate.

Shield Cooling System surge tank makeup supply - clarified inaccurate statement.

Shield.Cooling System surging tank vent - clarified inaccurate statement.

3 Corrected description of Auxiliary Feedwater Nitrogen (backup) System to as-built.

Revised service water flow requirement b.ased on 80°F.

Changed Chemical and Volume Control System make-up flow control to reflect actual process for adding make-up flow.

Documented reduced Auxiliary Feedwater System flow rate requirements.

Emergency Electric Power System - wording was misleading -

FSAR changed to reflect that buses are manually transferred during each startup/shutdown and not tested during normal operation.

Station Power System - FSAR corrected to reflect that Bus lA and lB (4160 volt) cannot be taken out of service during operation.

Containment Isolation -

FSAR corrected to reflect that Component Cooling Water valves from containment are air to close valves with accumulators

• to allow valve closure on loss of instrument ait; Updated FSAR maximum hypothetical accident dose consequence analysis.

Neutron Monitoring System - deleted information regarding the reactivity computer no longer used at Palisades.

Emergency Electric Power System - Reflected results of l*oad study of station inverters.

Station Power System - changed FSAR to reflect that diesel generators are only blocked by manual action.

Changed Instrument Air System backup nitrogen system to be maintained at 60 psig.

OC1087-0196A-NL04

Nuclear Regulatory Commission Palisades Plant Revision 3, Final Safety Analysis Report October 30, 1987 Main Steam Isolation Valves -

FSAR corrected to clarify automatic closure circuit can be manually blocked at a prescribed steam generator pressure range.

4 Radiation Monitoring -

changed FSAR to reflect that the stack monitor is now used as a backup system to the RGEMS.

Revised description of Chemical and Volume Control System boration capability.

Control.Room Heating and Ventilation - Revised FSAR to reflect proper control room pressure.

Shutdown Cooling System -

FSAR changed to reflect that service water flow is maintained to equipment on an as-needed basis.

Removed incorrect reference to a turbine generator control feature.

Frederick W Buckman Vice President Nuclear Operations CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC1087-0196A-NL04