ML18064A530
| ML18064A530 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/22/1994 |
| From: | Fenech R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18064A531 | List: |
| References | |
| NUDOCS 9501040187 | |
| Download: ML18064A530 (11) | |
Text
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MICHl&AN'S PRO&RESS Site Offices: 27780 Blue Star Memorial Highway, Covert Ml 49043 * (616) 764-8913, Ext 0210 December 22, 1994 Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT REVISION 17 TO THE FINAL SAFETY ANALYSIS REPORT (FSAR) UPDATE Robert A Fenech Vice President Nuclear Operations In accordance with 10 CFR 50.4, one original and ten copies of the Palisades Plant FSAR Update, Revision 17, are enclosed. This revision is submitted on a replacement page basis and includes a vertical line in the right margin and "Rev 17" in the lower right-hand corner. Additionally, some of the submitted pages will encompass large sections (primarily following pages) of chapters to maintain format throughout the section.
In accordance with 10 CFR 50.71, FSAR changes made under the provisions of 10 CFR 50.59, but not previously submitted to the NRC, are identified by the attached "FSAR Change Request Log."
There were no changes, other than typographical corrections, that were not made under the provisions of 10 CFR 50.59, or SERs received from the Nuclear Regulatory Commission.
Typographical corrections include corrections to equipment descriptors in Appendix 7C (e.g. the second FM1042B was changed to FM1043B), deletion of "accident" from term "fire accident" in 8.4.1.2, grammatical corrections, and minor revisions to plant P&IDs included in the FSAR as figures.
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 other applicable information contained in licensing submittals within six months prior to the date of this submittal.
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9501040187 941222 PDR ADOCK 05000255
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j
SUMMARY
OF COMMITMENTS This letter contains no commitments.
Robert A. Fenech Vice.President Nuclear* Operations*
CC Administrator, Region III, USNRC, w/o attachment NRC Resident Inspector, Palisades, w/o attachment Attachment 2
ATIACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 FSAR CHANGE REQUEST LOG December 13, 1994
- 1 J
Chapter/
Chapter Section 02 Chapter 2 03 04 04 04 04 04 04 04 04 04 04 05 3.3.2.6 4.3.3 4.5.2 4.5.3 Table 4-18 Table 4-19 Table 4-20 Table 4-23 4.3.4 4.3.7 4.5.6 4.8 Fig 4-1 Sh Chapter 4 2
Fig 4-1 Sh 1 Fig 4-9 Table 4-23 Table 4-4 5.1.2.2
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PALISADES NUCLEAR PLANT 41 FSAR CHANGE REQUESTS REVISION 17 Change Request Number 2-11-R17-920 3-23-R17-994 4-79-R17-995 4-80-R17-1014 4-73-R17-953 4-74-R17-967 4-68-R17-887 4-71-R17-930 4-78-R17-987 4-75-R17-969 4-76-R17-972 4-72-R17-933 5-117-R17-985 Description Corrects references and editorial omissions.
Incorporates the results from reactor vessel surveillance capsule W-110.
Incorporates the results from reactor vessel surveillance capsule W-110.
Change description of auxiliary f eedwater temperature of both hot standby and secondary side dry conditions from 70 degrees fahrenheit to 32 degrees fahrenheit.
Reflects the design basis of auxiliary f eedwater temperature under accident conditions.
Update on pressurizer surge line stratification.
Editorial change as required by A-AG-93-025.
Corrections to delete annunciator alarm associated with PIA-1066.
Correct ASME boiler and pressure vessel code addenda used for construction of the pressurizer.
Revised reference to P&ID drawings.
EA-SP-20034-01 Figure 4-9 update resulting from steam generator replacement, C-PAL 062.
Correct figure number referenced and ensure NRC approval is obtained per 10CFR50, Appendix H.
Correct steam generator blowdown flow.
Revise the FSAR discussion of the EDG Fuel Oil transfer system as
. 2 Chapter 05 05 05 05 05 06 06 06 06 06 06 06 Chapter/
Section 5.1.3.8 5.1.5.12 5.1.6.9.
5.1.6.7 Table 5.8-4 5.2-5 Chapter 6.1.2.1 6.4 Fig 6-2 6.4.1 6.4.2 6.7-2 6.8 Fig 6-7 6.9.1 5
Sh lB Fig 6-6 Sh 1 Fig 6-6 Sh 3
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PALISADES NUCLEAR PLANT ~
FSAR CHANGE REQUESTS REVISION 17 Change Request Number 5-116-R17-983 5-111-R17-919 5-114-R17-964 5-112-R17-926 5-118-R17-997 6-93-R17-931 6-92-R17-918 6-74-R17-736 6-95-R17-965 6-98-R17-1002 6-94-R17-951 6-77-R17-768 Description required by E-PAL-94-0lOM.
EA-ELEC-LDTAB-009 shows the results of the battery sizing for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with load shed.
T-102 Hydrazine Addition Tank retired in place per Tech Spec Amendment 158; manual discharge valves have been closed.
Add to the FSAR descriptions how penetration 65 meets general design criteria 56 and is classified as a class C2 penetration.
Change the "safety class" of containment temperature to "No".
Newer LOCA containment analysis of record has been completed.
Revised to correct in accordance with the MSLB analysis.
T-102 Hydrazine Addition Tank retired in place per Tech Spec Amendment 158.
The manual discharge valves have been closed.
Amendment 158 to Palisades Technical Specifications deleted the requirement for hydrazine addition to containment spray solution.
Add to the FSAR descriptions how penetration 65 meets general design criteria 56 and is classified as a cla~s C2 penetration.
Enhance the description of the Reactor Cavity Flooding System and correct Figure 6-7.
Non-standard code repair of sump check valves.
NRC SER dated 4/6/94.
Adds "C-1" to Penetrations 6 and 73," reflects the as built condition.
3 Chapter/
Chapter Section 07 7.2.3.2 07 7.2.9.2 07 7.4.2 07 7.6 07 7.6.1.4 07 7.7.2 07 07 07 07 07 07 07 08 Appendix 7A Appendix 7C Appendix 7C Appendix 7C Appendix 7C Chapter 7 Fig 7-42 Fig 7-39 Fig 7-38 8.1. 3 Chapter 8 Ref e PALISADES NUCLEAR PLANT -
FSAR CHANGE REQUESTS REVISION 17 Change Request Number Description 7-148-R17-971 Modification to install Annunciator Time Delays.
7-146-R17-960 Corrects information on RPS outputs to datalogger.
7-150-R17-992 Correct TS section referenced in FSAR.
7-147-R17-968 Correct description of incore instrumentation.
7-141-R17-925 Revised to indicate that 4 CETs per quadrant are required.
7-145-R17-956 Correction of control room fire zone.
7-140-R17-912 Delete acceptance criteria for safety injection system surveillance tests.
7-142-R17-927 Incorporates information in NRC SER on RG 1.97 instrumentation.
7-143-17-932 Correct equipment identification numbers per Incore Project, reference WBS 43373.
7-144-R17-938 SC-92-128 "Replace Various Primary System Transmitters" revised various instrument loops.
7-149-R17-984. Update Appendix 7C references to refer to latest NRC SER on RG.
1.97 and incorporate change implemented by SC 92-128.
7-151-R17-1013 Incorporates Technical Specifications Amendment 161.
Amendment changed requirement for AFW operability to 320 degrees fahrenheit to greater than or equal to 300 degrees fahrenheit.
7-145-R17-940 Revise logic diagrams to reflect AFW instrument and power supply upgrade FC-842.
8-103-R17-1019 Change containment flood level.
Shows effect of completely draining the SIRW tank on the current flood analysis (EA-PAH 02).
- 4 Chapter/
Chapter Section 08 8.3.5.2 08 8.3.5.2 8.7.3.1 08 8.4 08 8.4.1 08 8.4.1.2 8.4.1.3 08 8.4.1.2 8.4.1.3 08 8.4.1.2 and Figures 08 8.4.1.3 08 8.4.1.3 08 8.4.2.3 Table 8-8 08 8.5.3.2 08 8.6.2 8.6.3.2 08 8.8 08 Fig 8-1 Sh 1 Fig 8-8 It PALISADES NUCLEAR PLANT ~
FSAR CHANGE REQUESTS REVISION 17 Change Request Number Description 8-94-R17-961 Added to FSAR discussion of AC buses on the bypass regulator.
8-92-R17-955 Add description of battery charger and inverter cooling fans, and delete reference to cooling fans in AFW junction boxes.
8-89-R17-942 Add alarms for local DG panels.
8-95-R17-963 Reanalysis of the EDG Day Tank and Belly Tank fuel oil capacity.
8-96-R17-976 Clarify the intent and description of the EDG start circuits.
8-98-R17-980 Revise the FSAR discussion of the EDG Fuel Oil Transfer System as required by E-PAL-94-0lOM.
8-99-R17-981 The diesel generator fuel oil system is now considered to be a safety related system from the storage tank (T-10) to the diesel generator.
8-88-R17-936 Provide reference to T-926 tie-in with T-10 for additional onsite fuel oil supply to the EDGs.
8-97-R17-977 Describe the "as-licensed" electrical design of the fuel oil transfer system, as required by E-PAL 0lON.
8-100-R17-982 EA-ELEC-LDTAB-009 shows the results of battery sizing for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with load shedding.
8-86-R17-923 Correct an inaccurate statement concerning the protection of power cables.
8-92-R17-959 Provided updated startup transformer 1-2 and safeguards transformer 1-1 reserve capacity, due to load shed.
8-101-R17-993 The MOV PM intervals are changed per revision of EM-28-01 to Rev 2.
8-81-R17-859 SC-92-124 provides permanent 480Vac power feed to steam generator temporary storage building.
- 5 Chapter/
Chapter Section 08 Table 8-6 08 Table 8-6 Table 8-7 09 9.1.2.1 09 9.10-2 09 9.10.2.6.12 9.10.3.1 Table 9-10 Fig 9-25 Sh 1 09 9.10.5 09 9.11.3.5.1 9.11. 3. 5. 5 09 9.11.4.3 Table 9-24 09 9.11.5.1.5 09 9.2.2.3 09 9.2.2.3.1 09 9.3.2.1 e PALISADES NUCLEAR PLANT e FSAR CHANGE REQUESTS REVISION 17 Change Request Number Description 8-91-R17-949 Insertion of new information due to SC-92-099.
Addition of time delay on CHP start for P-54C 8-87-R17-929 Update load and reserve capacity margins for the EDGs.
EA-ELEC-LDTAB-005 Rev 1 "Emergency Diesel Generator Steady State Loadings First Two Hours."
9-173-R17-934 Corrects erroneous information in FSAR regarding cooling for air compressor C-2B.
9-183-R17-970 Changed referenced figure to Figure 4-9.
9-161-R17-841 Removal of nonfunctional boronometer AE203 and associated electrical instruments, FC-946.
9-185-R17-978 To resolve CCP discrepancy report F-CG-91-152, clarify text regarding testing of eve system.
9-171-R17-917 Change to address handling a single fuel rod.
9-178-R17-948 Existing 100 ton fuel building crane L3 has been modified to install a new main hoist motor, main hoist motor controls and new Control Chief radio control system for the entire crane controls.
9-189-R17-1003 Changes the spent fuel pool temperature limit to at or below 100 degrees fahrenheit during fuel loading of the MSB.
9-182-R17-958 Corrected shield cooling coil flow requirements to match design.
9-188-R17-1000 Change the flow rates through the shield cooling system cooling coils to 38-43 gpm per wall coil and 20-25 gpm per floor coil.
This changes the total system flow rate to 134-154 gpm.
9-184-R17-974 Corrects erroneous information in FSAR which indicated CCW surge tank normally vents to gas
6 Chapter/
Chapter Section 09 09 09 09 09 09 09 09 09 09 09 10 10 9.3.2.3.1 9.6.7.2.2.2.B
.1 9.7 9.8.5.2 Chapter 9 Fig 9-1 Sh 2 Fig 9-11 Fig 9-21 Sh lC Fig 9-9 Sh 1 Table 9-10 Table 9-5 Fig 10-6 Sh 3 Fig 10.6 Sh 3
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PALISADES NUCLEAR PLANT ~
FSAR CHANGE REQUESTS REVISION 17 Change Request Number 9-179-R17-950 Description collection header.
It vents to the auxiliary building.
FSAR change will correct an inaccurate statement regarding CCW pump(s) and CCW heat exchanger configurations.
9-190-R17-1005 Change to reflect the diesel fuel oil analyses as performed by the Chemistry Department to verify the operability of the diesel fire pumps.
9-180-R17-952 Condensate storage tank T-2 low level alarm set point change. (SC-94-038) 9-172-R17-924 Corrects FSAR description of ESF room cooling.
9-187-R17-996 Enhances FSAR discussion of condensate inventory and adds two references.
9-181-R17-957 SC-94-052 Upgrade and revise set points on high differential pressure switches.
9-129-R17-685 Update P&ID per SC-92-009 "Replacement of Jayco Fig 149 relief vales with Lonergan Model FBF. II 9-154-R17-824 9-112-R17-598 9-176-R17-945 9-177-R17-947 10-35-R17-833 10-41-R17-990 Addition of a suction line accumul~tor to compressor C-17.
Change high pressure air compressor C-6A.
Correct to as built for four Auxiliary Feedwater System valves.
New LOCA containment analysis of record incorporated.
EA-D-PAL 207-01 Removal of control scheme IF51.
FC-898 Revised referenced to P&ID drawings.
EA-SP-20034-01
7 Chapter/
Chapter Section 11
- 11. 2. 5 11 11.6.6.7 11 Chapter 11 11 Chapter 11 11 Table 11-4 12 12.2.1.2 12 Chapter 12 14 14.11-1 14.11.3.1.2
- 14. 11. 3. 2. 2 14.11.3.3.2 Table 14.11-1 14 14.11.2.2.1 14 14.14.3.1 14 14.18.1 14 14.22 14 14.22.3.1 14 14.22.3.2 Table 14.22-1 e PALISADES NUCLEAR PLANT e FSAR CHANGE REQUESTS REVISION 17 Change Request Number Description ll-51-R17-1018 Incorrect description of dilution flow for radwaste effluents.
11-47-R17-954 Revise a FSAR facility contamination control requirement for portal monitor use upon exit from the restricted area in the Security Building during SEP activations and drills involving accountability actions.
11-46-R17-921 Corrects references and editorial omissions.
11-48-R17-962 Major rewrite of Chapter 11.
11-49-R17-979 Changed because of FES-94-102, Gould pump upgrades.
12-19-R17-937 Basic Radiation Worker (BRW)
Requalification/Challenge Training Courses have been changed to not require completion of Practical Factors.
12-23-R17-1031 Change to reflect corporate and site reorganization.
14-59-R17-1015 Dry Storage of Spent Nuclear Fuel (FC-864).
Update information on MTC/LDS drop.
14-56-R17-1004 Changes the spent fuel pool temperature limit to at or below 100 degrees fahrenheit during fuel loading of MSB.
14-55-R17-999 Minor editorial change.
14-53-R17-946 New LOCA containment analysis of record incorporated.
EA-D-PAL 207-01 14-58-R17-1011 Hydrogen concentration analysis revision.
Makes corrections to FSAR - original revision missed a change.
14-52-R17-935 Incorrect section of Chapter 2 of FSAR reference in Chapter 14.
14-37-R17-738 Amendment 158 to Palisades Technical Specifications to delete
. 8. '
Chapter 14 14 Chapter/
Section e PALISADES NUCLEAR PLANT e FSAR CHANGE REQUESTS REVISION 17 Change Request Number Description Table 14.22-2 Table 14.16-2 Chapter 14 Chapter 14 14-49-R17-904 14-54-R17-998 requirement for hydrazine addition to containment spray solution.
Incorporates new change to Licensing Basis - Technical Specifications Amendment 158 New LOCA containment analysis.