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Category:Graphics incl Charts and Tables
MONTHYEARML23107A0162023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Tables ML23107A0322023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Tables ML23107A0372023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Tables ML23107A0512023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Tables ML23107A0522023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Tables ML23107A0552023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Tables ML21354A7552021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 10 of 18 ML21125A3352021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 12, Figures ML21125A3362021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 15, Figures ML21125A3382021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 14, Tables ML18354A4272018-12-20020 December 2018 Superseded by Table Received with Mail 15 CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports PNP 2015-042, One-Year Status Notification in Response to Confirmatory Order, EA-14-0132015-06-19019 June 2015 One-Year Status Notification in Response to Confirmatory Order, EA-14-013 ML15016A0912015-01-16016 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Palisades Nuclear Plant (Pnp) Fire PRA (Fpra) Facts and Observations (F&Os ML15016A0732015-01-16016 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Palisades Nuclear Plant (Pnp) Internal Events PRA (Iepra) Facts and Observations (F&Os) ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1104704522011-02-15015 February 2011 Response to Request for Additional Information (RAI) - Cyber Security Plan ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0806302532008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-Water Reactors ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0733310832007-09-21021 September 2007 SG Tube Inspection Discussion During 2007 Palisades Outage ML0530705612005-10-31031 October 2005 Supplementary Information for the Application for Renewal of the Palisades Plant Operating License ML0520002372005-06-0707 June 2005 Precedents for Section 3.2 Exceptions to GALL ML0520002342005-06-0606 June 2005 Precedents for Section 3.1 Exceptions to GALL ML0520002412005-04-16016 April 2005 Precedents for Section 3.3 Exceptions to GALL ML0520004402005-04-0101 April 2005 Precedents for Section 3.5 Exceptions to GALL ML0520004542005-04-0101 April 2005 Precedents for Section 3.6 Exceptions to GALL ML0513800992005-03-31031 March 2005 Precedent Table, Mech Section 3.4 ML0513800922005-03-31031 March 2005 Precedent Table, Civil Section 3.5 ML0513800952005-03-31031 March 2005 Precedent Table, Mech Section 3.2 ML0513800982005-03-31031 March 2005 Precedent Table, Mech Section 3.3 ML0513800942005-03-31031 March 2005 Precedent Table, Mech Section 3.1 ML0513800862005-03-31031 March 2005 Precedent Table, Elec. Section 3.6 ML0520002302005-03-0202 March 2005 Exceptions to GALL Program Elements ML0434501802003-12-11011 December 2003 NMC Program Health Status Fleet Program at a Glance ML18347B2911994-04-13013 April 1994 Notification of Submittal of Request for Renewal of the National Pollutant Discharge Elimination System (NPDES) Permit ML18347B2891991-06-0101 June 1991 Semiannual Radioactive Effluent Release Report ML18344A2461984-05-14014 May 1984 a Steam Generator General Listing of 4C4 ML18346A2461978-08-0808 August 1978 Furnishing Information Re Combustion Engineering Owners' Group Proposed Plan to Resolve the Asymmetric LOCA Loads Issue ML18348A7361978-05-23023 May 1978 Letter Results of Burnup Study ML18346A2441978-04-0505 April 1978 Revision of Steam Generator Tube Dent Data ML18348A7561977-02-14014 February 1977 Primary System Pressure Increase to 2, 100 Psia ML18347A5441976-11-0909 November 1976 Submits Revised Table 6 of Special Report No. 9, Palisades Cycle II Start-Up Report August 27, 1976, Which Makes Provision for Measurement Uncertainty Allowance of 10% of Net Rod Worth ML18347A5581976-09-27027 September 1976 Referring to Meeting of 7/30/1976 Regarding Appendix J Which Requires Air Locks Be Tested After Each Opening, Letter Providing Information for NRC Consideration to CPC Exemption Request ML18347A6711976-04-23023 April 1976 Referring to 4/5/1976 Report, Rod Bow Measurements and Analysis of Effects on DNB, Providing Additional Data from Core I ML18347A6801976-04-0505 April 1976 Information Submitted in Addition to That Provided in Consumers Power Company Submittals of March 26, 1976 and April 5, 1976 2023-03-31
[Table view] Category:Letter
MONTHYEARML24312A2262024-11-0606 November 2024 Letter from C. Nelson, Michigan SHPO Regarding Palisades Nuclear Plant Architectural Survey ML24292A1572024-11-0505 November 2024 Ape Notification to Burt Lake Band Palisades ML24310A0142024-11-0505 November 2024 Ape Notification to Mackinac Bands of Chippewa Palisades ML24310A0132024-11-0505 November 2024 Ape Notification to Grand River Bands of Ottawa Indians Palisades ML24309A2032024-11-0404 November 2024 Ape Notification to Ottawa Tribe of Oklahoma Palisades ML24309A1972024-11-0404 November 2024 Ape Notification to Little Traverse Bay Bands of Odawa Indians Palisades ML24309A1982024-11-0404 November 2024 Ape Notification to Match E Be Nash She Wish Band of Pottawatomi Indians Palisades ML24309A1872024-11-0404 November 2024 Ape Notification to Grand Portage Band of Lake Superior Chippewa Palisades ML24309A2072024-11-0404 November 2024 Ape Notification to Quechan Tribe of the Fort Yuma Indian Reservation Palisades ML24309A1832024-11-0404 November 2024 Ape Notification to Bois Forte Band of the Minnesota Chippewa Tribe Palisades ML24309A2122024-11-0404 November 2024 Ape Notification to Sault Ste. Marie Tribe of Chippewa Indians Palisades ML24309A2042024-11-0404 November 2024 Ape Notification to Pokagon Band of Potawatomi Indians Palisades ML24292A0492024-11-0404 November 2024 Ape Notification to Bad River Band of the Lake Superior Tribe of Chippewa Indians Palisades ML24309A1932024-11-0404 November 2024 Ape Notification to Leech Lake Band of Ojibwe Palisades ML24309A2012024-11-0404 November 2024 Ape Notification to Mille Lacs Band of Ojibwe Palisades ML24309A1922024-11-0404 November 2024 Ape Notification to Lac Vieux Desert Band of Lk Superior Chippewa Indians Palisades ML24309A1892024-11-0404 November 2024 Ape Notification to Hannahville Indian Community Palisades ML24309A2002024-11-0404 November 2024 Ape Notification to Miami Tribe of Oklahoma Palisades ML24309A1952024-11-0404 November 2024 Ape Notification to Little River Band of Ottawa Indians Palisades ML24309A2112024-11-0404 November 2024 Ape Notification to Saint Croix Chippewa Indians of Wisconsin Palisades ML24309A1902024-11-0404 November 2024 Ape Notification to Lac Courte Oreilles Band of Lake Superior Chippewa Palisades ML24309A2022024-11-0404 November 2024 Ape Notification to Nottawaseppi Huron Band of the Potawatomi Palisades ML24309A1852024-11-0404 November 2024 Ape Notification to Citizen Potawatomi Nation Palisades ML24309A2142024-11-0404 November 2024 Ape Notification to White Earth Band of Minnesota Chippewa Tribe Palisades ML24309A2092024-11-0404 November 2024 Ape Notification to Red Lake Band of Chippewa Indians Palisades ML24309A1862024-11-0404 November 2024 Ape Notification to Forest County Potawatomi Community Palisades ML24309A1822024-11-0404 November 2024 Ape Notification to Bay Mills Indian Community Palisades ML24309A2052024-11-0404 November 2024 Ape Notification to Prairie Band Potawatomi Nation Palisades ML24309A2102024-11-0404 November 2024 Ape Notification to Saginaw Chippewa Indian Tribe of Michigan Palisades ML24309A2082024-11-0404 November 2024 Ape Notification to Red Cliff Band of Lake Superior Chippewa Indians Palisades ML24309A1992024-11-0404 November 2024 Ape Notification to Menominee Indian Tribe of Wisconsin Palisades ML24292A0072024-11-0404 November 2024 Ape Notification to Achp Palisades ML24309A1882024-11-0404 November 2024 Ape Notification to Grand Traverse Band of Ottawa and Chippewa Indians Palisades ML24309A1842024-11-0404 November 2024 Ape Notification to Chippewa Cree Indians of the Rocky Boys Reservation of Montana Palisades ML24309A1912024-11-0404 November 2024 Ape Notification to Lac Du Flambeau Band of Lake Superior Chippewa Indians Palisades ML24309A2132024-11-0404 November 2024 Ape Notification to Turtle Mountain Band of Chippewa Indians Palisades ML24309A2062024-11-0404 November 2024 Ape Notification to Prairie Island Indian Community Palisades PNP 2024-014, Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances2024-10-0909 October 2024 Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances PNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024 Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020 ML24267A2962024-10-0101 October 2024 Summary of Conference Call Regarding Steam Generator Tube Inspections ML24263A1712024-09-20020 September 2024 Environmental Request for Additional Information ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24219A4202024-09-12012 September 2024 Change in Estimated Hours and Review Schedule for Licensing Actions Submitted to Support Resumption of Power Operations (Epids L-2023-LLE-0025, L-2023-LLM-0005, L-2023-LLA-0174, L-2024-LLA-0013, L-2024-LLA-0060, L-2024-LLA-0071) IR 05000255/20244022024-09-0606 September 2024 Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402 PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024 Notice of Payroll Transition at Palisades Nuclear Plant IR 05000255/20240022024-08-0909 August 2024 NRC Inspection Report No. 05000255/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024 Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations ML24206A0572024-07-25025 July 2024 PRM-50-125 - Letter to Alan Blind; Docketing of Petition for Rulemaking and Sufficiency Review Status (10 CFR Part 50) PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024 Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations 2024-09-06
[Table view] |
Text
{{#Wiki_filter:consumers
General Offices: 212 West Michigan' Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 March 23, 1976 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT, ANSWER TO QUESTION ON LOcA*(4.A.7)
By letter dated March 20, 1976, we transmitted answers to questions contained in your letter of March 10, 1976. In answer to Question 4.A.7, we indicated that a response would be provided at a later date. This letter provides that
- response. Please note that the question responded to is somewhat different from that contained in your March 10, 1976 letter. This response is based on discussion with the regulatory staff which took place prior to receipt of the letter. We believe our response will provide the information required.
SECTION 4.0, ACCIDENT AND TRANSIENT ANALYSES Question 4.A.7 Provide the following information for the calculated worst break case for Palisades.
- 1. Reactor coolant temperature versus time at the hot spot.
- 2. Average fuel temperature at the hot spot .
- 3. Hot assembly flow rate.
4~ Quality at*. the hot spot.
- 5'. Gap conductance versus tinie at hot spot.
- 6. Hot rod internal pressure.
- 7. Rupture time.
- Response The attached information is for the 1.0 DES/PD case with ENC fuel. For this case, the blowdown maximum temperature node is heat transfer Node 22 f32'g . .
5
r---
2
- Figure 3.2 of XN-75-64. Node 22 is also the maximl11Il power node and corresponds to* Node 17 of the TOODEE2 calculation. The hot spot during reflood moves up the rod to TOODEE2 Node 19 (hot channel Node 24). All these heat transfer nodes are bounded by fluid Volume 6 of the hot channel model as shown by Fig-lire 3.l of XN-75-64.
The following information is supplied:
- l. The average fluid temperature in Volume 6 of the hot channel model.
(Figure 1).
- 2. The. volumetric average fuel rod temperature for heat transfer Node 22 of the hot channel model (Figure 2).
3 . . Hot assembly flows at inlet Junction 10 and outlet Junctions ll and 12 for the hot channel model (Figures 3, 4 and 5).
- 4. Average quality of Volume 6 of the hot channel model (Figure 6).
- 5. Gap conductance for the maximum power node for both blowdown and reflood and gap conductance for the PCT node during refill and reflood (Figures
- 7. and 8).
- 6. The hot rod pin pressure during the entire transient *(Figure 9) .
- 7. Rupture time for the 1.0 DES/PD was calculated to occur at 49.82 seconds after the break.
The transient gap conductance during blowdown is not an available quantity from the RELAP4-EM runs and was approximated from the fuel rod surface heat flux and the calculated outer fuel surface and inner cladding surface temper-atures. This procedure is valid when pseudo steady state conditions exist across the gap and cladding but may be in error when energy storage terms in the cladding are significant compared to the surface heat flux, as at CHF.
During refill and reflood, the gap conductance is available directly from TOODEE2 results.
Pressure Distribution Overall system irrecoverable pressure losses were adjusted equal to the pl11Ilp head as given by pump performance data. Loss coefficients through the core were based on experimental data from full scale single assembly flow experi-ments which included modeling of the upper and lower core support structure.
Line losses were estimated from standard correlations for expansions and con-tractions. Because of the conservatively low flow rate assUliled, system balancing, particularly across the steam generator, required artifically aug-menting the pressure loss. This was accomplished conservatively by reducing the steam generator effective flow area until a balance was achieved .
- Flow Distribution The distribution of flow between the two steam generators and four pump flow paths was taken from plant flow measurements made in April 1975.
Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC
* - - * - *. ~ ****..* -- ***~-~-:*--***~"":**-*~*--.. ...................... , .......h
- Pl=lLISRDES SLOWDOWN WREM/ENC.S/PO CD=lJeO F* RLP4EM/O. 12/05
. 00 ,-- 1 *------------.--~~*~.----
O')
to a: i FIGURE l RELAP4-Ef.1 HOT CHANflEL HOT SPOT FLUID TEMPERATURE 0 1. 0 DES/PD 0
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a Q_*
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~ t i! !
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- 0 fill i
L_ **---L---~*,___ L-~-~-~-*---.l _____,_.
TIME 16
~-__J*~--~-*~'---\---------~--------------------j
~o
~PTER*BRE~K
~4 IN SECONDS is 32. 36 40
~--------------------------
N I
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- . PRLIS~DES
- SLOWDOWN WREM/ENC DES/PO CD=l.O F RLP4EM/003 * *12/05
~-----....,,..----.-.F-I-GU_R_E_2__,,,~-EL-AP-4--E-M_H_O....-~-C-HA_N_riE--L---.1, 0
~ - - - - - - --*--.--* r*
.~ HOT SPOT AVERAGE FUEL
; ROD TEMPERATURE 1.
l
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. (
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~ 4 s lf. 16 w 2.4 2.8 32. 40 TIME ~FTER GRERK IN SECONDS
.. -- *-"' . '.'... '-'*'~ . . * . . . * . * -.*: **.*--:.-... -:-*~.::"":":".!~*-** *~**""!~ . . ..
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PRLISROES -----r-*---
BLOWOOWN WREM/ENC~S/PO CD=l.O F 12/05
;. FiGURE 3 RELAP4-EM HOT CHANNEL
{Jur~cnm~ 10) 1 .0 DES/PD I
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g L. ___......_1_ ~-*---*- _ _J ___ .__ ,___ _J _ _ _ _ _ _ ...J__._~--- i - __..-1~. - - " - ' - - -_ ____.,____,_ ____.._ _ ____.
~ 4 ! 8 tt Y M ~ H 36
! TIME AFTER BRERK IN SECONDS
419-PRLISRDES
*-, I .
SLOWDOWN WREM/ENC Its/PD co~1.o F RLP4EM/OO' 12/0~/
~-I FIGURE 4 RELAP4-EM HOT CHANNEL HOT ASSEMBLY OUTLET FLOW
( JUflCTION 11 )
l .0 DES/PD i
i I
~
r
.I 1
I I
i I
-{
*I
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8 re m w ~ ~ 32. 36 40 TIME RFT~R BR~~K IN StCONDS
. --. ... - .. .. ... **- --*--~*** -*-**~*~*
- PALTSr:lDES SLOWDOWN WREM/ENC,S/PD CD=l.O F RLP4EM/01 12/0.5
--*- I
.FIGURE 5 RELAP4-EM HOT CHANUEL HOT ASSEMBLY OUT FLOW (JUNCTION 12)
- 1. 0 DES/PD l1
_J
- )
>-:\ ~ ,.
r .
~ ~ .[l1 ! I
- ~ '*![)~
.I 0 11!~w- - - - - - - - -* *- -
L.1;,l~,:\yJ~'I i~
I lf .* .
i,r :!
- 0 ------~--'----~-----~----~--------------_._-----------1*~~~__,_~~~~~~~-'-~~~--~~~
)l> t.._ . .-* - s 16 io e4 ~s . 3~ 36 TIME RFTER BRERK IN SECONDS
RLP4EM/ 12/05 w : FIGURE 6 RELAP4-EM HOT CHANNEL x HOT SPOT FLUID QUALITY a:"-' 1. 0 DES/PD
-I*
t-o n...
(f)o
-I*
t-o I
CI <n II 0
t~ >-
H
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- > tO CJ *
. 0
(.!)
a:
0 0
- plL-~~---'-~~~--'-~----~-'-~~~...1-~~*----"--~~--l~..;.._~--..J..~~~-'-~~~-'-~~__._J J) 4. 8 1s ~o ~4 ~s ~6 40 TIME RFTER BRERK IN SECONDS
l'
0 I :.**-;.**
(\J
.µ
..s...
LI-
. 600
..c:
- s
-+->
co Cl) u c:
'500 It:!
+->
*~ u 0
0.
400 It:!
t!:I 300 Rupture at 49.82 200 lOO 0 l-~-1.~~-L-~--1~~...J-~~L-.~-1-~--1~---l-~~.i.-~--&..~---
- 4 8 12 Bl owdown FIGURE 7 16 30 60 lOO 140 180 220 Refi 11 + Re flood Time After Break (Sec)
PEAK POWER NODE GAP CONDUCTANCE VS TIME 1.0 DES/PD ENC FUEL
* . 700
.600 N
u.
0 I
500
.µ
'+-
S-
.c: '
- I
.µ co 400 I QJ u
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300 c..
rel
(,!)
200 100 O._.....,__.___,__iL-.,.__.._._.....,___.......,_.....,_...1-__..---1......,_-.--'-~-1--.-~i.--:---L..~--'
o 20 40 60 ao 1oo 120 140 160 mo . 200 Time After Break (Sec)
FIGURE 8 HOT SPOT GAP CONDUCTANCE
- VS TIME 1.0 DES/PD ENC FUEL
T---
1~-- ...
l1* .
l \
I '
i:
j:
j; 900 l.
~i t*
800 200 100 8 12 Slowdown --1--*--
20 60 l 00 Refill +
140 180 Ref~ood 220
~
Time After Break (Sec)
FIGURE 9 MAX. POWER FUEL ROD PRESSURE VS TIME 1.0 DES/PD ENC FUEL}}