ML100320678
| ML100320678 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/29/2009 |
| From: | Schwarz C Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML100320678 (9) | |
Text
Entergy Nuclear Operations, Inc.
- Palisades Nuclear Plant 27780 Blue Star-Memorial Highway Covert, MI 49043 Tel 269 764 2000
/ Christopher J. Schwarz
/ Site Vice President October 29, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Final Safety Analysis Report Update - Revision 28 Palisades Nuclear Plant Docket 50-255 License No. DPR-20
Dear Sir or Madam:
In accordance with 10 CFR 50.4(b)(6), Entergy Nuclear Operations, Inc. (ENO) is providing the Palisades Nuclear Plant (PNP) Final Safety Analysis Report (FSAR) update, Revision 28. This FSAR update is provided in its entiretv(on the CD-ROM in . Revision 28 changes, with the exception of typographical corrections and format changes, are denoted by vertical lines in the outboard margins for all revisions to text. All changes, other than typographical cbrrections and format changes, were made under the provisions of 10 CFR 50 or in accordance with safety evaluations received from the Nuclear Regulatory Commission (NRC). to Enclosure 1 contains a list of changes made in the FSAR revision.
No changes were made under the provisions of 10 CFR 50.59 that were not previously submitted to the Commission. No information was removed from the FSAR per Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71 (e)." provides a CD-ROM containing the PNP Fire Protection Program documents revised since the last FSAR update submittal dated April 17, 2008.
These documents are provided in accordance with Renewed Facility Operating License Condition 2.C.(3)b.
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Document Control Desk Page 2 FSAR, Revision 28, incorporates changes made to the PNP or to the plant procedures described in the FSAR, and all other applicable information and analyses submitted to the NRC or prepared pursuant to NRC requirements up to six months prior to the date of this submittal.
Summary of Commitments This letter identifies no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 29, 2009.
Sincerely, cjs/jse Enclosures 1. CD-ROM Containing Final Safety Analysis Report - Revision 28
- 2. CD-ROM Containing Revised Fire Protection Program Documents CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades USNRC
ENCLOSURE 1 PALISADES NUCLEAR PLANT CD-ROM CONTAINING FINAL SAFETY ANALYSIS REPORT - REVISION 28 1 CD-ROM Enclosed
ATTACHMENT 1 PALISADES NUCLEAR PLANT PALISADES FSAR REVISION 28 LIST OF CHANGES 4 Pages Follow
Palisades FSAR Revision 28 List of Changes Log No. Affected FSAR Sections, Tables, Description of Change or Figures FSAR Sections 6.10.2, 9.8.1.4.a, and This change reflects License Amendment Number 230 (dated February 20, 2008), which revised control room 9.8.2.4.12.b.(3) habitability requirements.08-004 FSAR Table 4-16 This change revises FSAR Table 4-16 to align with the chemistry administrative limits of the primary coolant system described in Chemistry Operating Procedure 1, "Primary Coolant System Chemistry."
This updates the FSAR to reflect Engineering Change 5861, which modified the turbine generator control system to improve system reliability.
This change removes FSAR Figure 12-3 (Palisades Nuclear Plant Organization), which is outdated. The current plant organization is now depicted in Figures 12-1 and 12-2.08-008 FSAR Section 9.8.2 FSAR Section 9.8.2 is revised to clarify that the described 135°F engineered safeguards room design temperature is for post-accident conditions.08-009 FSAR Table 4-6 This revises Table 4-6 to reflect the material (ASTM A-351 Gr CF3) that was approved for the primary coolant pump P-50D hydrostatic bearing under Engineering Change 5000121326.
This updates the FSAR to reflect the use of the Transnuclear 24PTH-S125 dry fuel storage cask, which was08-011 FSAR Section 9.11.5.1.2 approved under Engineering Change EC5000122423.
This FSAR change adds a discussion of Palisades' twenty year license extension to Section 1.1.2 and Table 1-1.08-012 FSAR Section 1.1.2 and Table 1-1 This extension was approved by the NRC via issuance of a renewed facility operating license on January 17, 2007.
This change adds to the FSAR a brief discussion of the administrative controls implemented to minimize 08-013 FSAR Section 6.1 containment sump debris in response to Generic Safety Issue 191, "Assessment of Debris Accumulation on PWR Sump Performance."
Appendix 7C, "Regulatory Guide 1.97 Rev 3 Parameter Summary Table," is revised to correct errors and 08-014 FSAR Appendix 7C inconsistencies identified in Condition Report CR-PLP-2007-06321. This table compares Palisades' instrumentation with requirements in the Regulatory Guide.
This adds a description of the temporary modification to disable the 2400 VAC fast transfer from the safeguards08-016 FSAR Section 8.6.2. transformer 1-1 or the station power transformer 1-2 to the startup transformer 1-2, which was implemented under Engineering Change 10638.
FSAR Section 4.8 is revised to reflect that the primary coolant gas vent system piping contains both Type 304 and Type 316 stainless steel piping (ref: Condition Report CR-PLP-2008-03351).
This revises FSAR Section 4.3.7 to clarify the description of the primary coolant system nozzle welds to which the 08-018 FSAR Section 4.3.7 Mechanical Stress Improvement Process was applied. This process mitigates pressurized water stress corrosion cracking.
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Palisades FSAR Revision 28 List of Changes08-019 FSAR Section 12.1.1 This corrects the referenced figure in Section 12.1.1, which should be "Figure 12-2" rather than "Figure 2-2".
This FSAR change corrects the classification of the containment hydrogen monitors, which should be Category 3 rather than Category 1.
This updates diesel generator sequence start information in the FSAR tables to reflect revision of diesel generator 08-022 FSAR Tables 8-6 and 8-7 loading calculation EA-ELEC-LDTAB-05, "Emergency Diesel Generators 1-1 and 1-2 Steady State Loadings."
The nameplate horsepower for miscellaneous loads and references to the calculation are updated in the tables.08-023 FSAR Table 8-3 FSAR Table 8-3 is revised to list the correct 2400V system breaker MVA ratings. The breakers were previously installed under Functionally Equivalent Substitution 99-012.08-024 FSAR Section 5.5.1.1.6 This adds a discussion27of a tornado missile barrier installed to protect the condensate storage tank under EgneigCag Engineering Change 7237.
FSAR Sections 9.11 and 14.19.1 and The FSAR is revised to include a discussion of the spent fuel pool dilution analysis of record (EA-WJB-00-01,08-025 Section 9 and 14.19 references "Spent Fuel Pool Dilution Analysis") that was used in support of Technical Specification Amendment 207 (ref:
Condition Report CR-PLP-2008-03263).
FSAR Table 11-15, "Process Radiation Service and Equipment," is updated to reflect replacement of an analog radiation monitor with a digital radiation monitor under Engineering Change 5000122451.
Revise FSAR Sections 4.7.1 and This FSAR change reflects the permanent disabling of a containment sump level indicating alarm under 6.1.2.2 Engineering Change 6553.
This change revises FSAR to reflect that the fuel manufacturer provided recommendations on bounding allowable power escalation rates and that these recommendations have been incorporated into plant operating procedures, with some additional built-in conservatism. The FSAR previously said that the power escalation rates are determined for each individual fuel cycle.09-003 FSAR Table 5.2-1 FSAR Adna Table 5.2-1 is revised to correct the ASME Section Xl code year from 1989 to 2001 Edition with 2003 Addenda.09-005 FSAR Tables 9-1 and 10-3 The FSAR is revised to reflect replacement of the turbine generator seal oil skid under Engineering Change 8490.
FSAR Sections 9.4.1 and 9.11.3 are revised to reflect the portion of spent fuel pool cooling that extends above the spent fuel pool deck (649' elevation). Engineering analysis EA-PSA-TORNADO-08-02 determined that failure of 09-008 FSAR Sections 9.4. and 9.11.3 the piping due to a missile generated by high winds or a tornado would result in only a limited loss of spent fuel pool inventory and would not adversely impact cooling and shielding provided by the spent fuel pool cooling system.
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Palisades FSAR Revision 28 List of Changes This revises FSAR safety analysis and fuel assembly information due to the cycle 21 reactor core reload package 09-009 FSAR Chapters 3, 4, and 14 (Engineering Change 11420). Cycle 21 introduces M5 fuel assembly cladding, which was approved in Amendment No. 234 dated December 12, 2008.09-010 FSAR Section 1.2.5 and Figure 10-5 The FSAR is revised due to the replacement of the main generator under Engineering Change 8157.
This editorially revises FSAR Appendix 7A to reflect that surveillance test procedure RI-3, concerning the calibration of pressurizer pressure channels, was split into five separate procedures (RI-3A, B, C, D, and E).
FSAR 9.11 is being revised due to long term stability issues with carborundum in the Region 1 spent fuel pool storage racks, a revised criticality analysis, and Amendment No. 236 issued by the NRC on February 6, 2009.09-016 1SAR Section 14.18.3 and Tables The FSAR is updated to reflect a revision of the site containment compartment pressurization analysis.
14.18.3-1, 2, and 3 09-018 FSAR Table 1.9 This revises FSAR Table 1-9 due to a change in the commitment date to submit the Reactor Vessel Internals Program in NRC letter dated March 24, 2009.09-019 FSAR 12.2 This updates FSAR Section 12.2, "Plant Staff Training Program," to align with the current site training program.
The FSAR steam generator tube rupture analysis description is revised to include a discussion of the NRC review of the analysis under the Systematic Evaluation Program.
These changes incorporate additional references to Palisades' NUREG-0612 submittals and add a brief 09-021 FSAR Sections 1.8.11 and 9.11.4.3.11 discussion of Palisades' reactor vessel head drop analysis. These FSAR sections are revised per NEI 08-05, "Industry Initiative of Control of Heavy Loads."
This change revises FSAR Section 9.11.3.5.1 to state that the new fuel elevator override key shall not be issued when the movement of irradiated fuel is in progress. This FSAR section previously said that the keys are only 09-023 FSAR Section 9.11.3.5.1 issued when moving non-irradiated fuel, but there are other times when the keys need to be issued, such as during fuel elevator maintenance, that do not involve the movement of non-irradiated fuel. This FSAR revision reflects these other instances in which the override key needs to be issued.
This revises the number of steam generator tubes plugged in FSAR Table 4-4 to reflect the tubes that were plugged during the 2009 refueling outage.09-027 FSAR Table 8-5 FSAR Table 8-5 is revised to correct discrepancies concerning DC bus short circuit ratings and to add equipment identification numbers (Engineering Change 15265).
This FSAR change updates the revision number of calculation EA-ELEC-LDTAB-005, "Emergency Diesel Generators 1-2 & 1-2 Steady State Loadings," in FSAR Tables 8-6 and 8-7.
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Palisades FSAR Revision 28 List of Changes This revises FSAR Section 4.5.6 to clarify that NRC Order EA-03-09 (Issuance of First Revised NRC Order (EA-09-036 FSAR Section 4.5.6 03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors) has been superseded by the 2008 revision of 10 CFR 50.55a.
09-038FSAR Sections 1.3, 3.3.2.7, 4.3.7, and This makes miscellaneous minor editorial changes in various FSAR sections.
5.8.8.2.2 FSAR Section 9.8.2 and Chapter 9 The FSAR is updated to reflect the replacement of control room heating, ventilation, and air conditioning system References dampers with bubble-tight dampers per Engineering Change 8368.
This revises FSAR safety analyses to reflect adoption of the alternate source term methodology under Engineering 09-047 FSAR Chapters 2, 11, and 14 Change 8368. Use of this methodology was approved by the NRC in Amendment No. 226 dated September 28, 2007.
SAR Sections 1.88, 5.1.2.4, 56.7. 1, This FSAR change updates references to SR-6, "Special Report No. 6 - Analysis of Postulated High Energy Line 09-050 andSectione5.61References Breaks Outside of Containment." This calculation was revised to more accurately describe the response of the turbine building to a high energy line break.
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ENCLOSURE2 PALISADES NUCLEAR PLANT CD-ROM CONTAINING REVISED FIRE PROTECTION PROGRAM DOCUMENTS Documents on CD-ROM:
- 1) Fire Protection Implementing Procedure (FPIP)-1, Revision 15
- 2) FPIP-1, Revision 16
- 3) FPIP-4, Attachment 8, Revision 24
- 4) FPIP-4, Attachment 8, Revision 25
- 5) FPIP-4, Attachment 8, Revision 26 1 CD-ROM Enclosed