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Category:E-Mail
MONTHYEARML24215A2092024-08-0101 August 2024 NRR E-mail Capture - Final RAI - Point Beach 1 & 2 - License Amendment Request to Modify Containment Average Air Temperature Requirements ML24199A2142024-07-17017 July 2024 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Modify Containment Average Air Temperature Requirements ML24149A3532024-05-24024 May 2024 Change in Estimated Review Schedule for Nextera Common Emergency Plan Amendment ML24122C6922024-05-0101 May 2024 NextEra Fleet EP Amendment - Demonstration Drill ML24108A1022024-04-17017 April 2024 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Revision to Reactor Vessel Surveillance ML24053A0112024-02-21021 February 2024 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Relief Request CISI-03-01 for Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 3 ML23271A1542023-09-28028 September 2023 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23208A3072023-07-27027 July 2023 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Relief Requests Regarding I6-RR-1, I6-RR-2, and I6-RR-3 (EPIDs L-2023-LLR-0030, L-2023-LLR-0031, L-2023-LLR-0032) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23136A2782023-05-0505 May 2023 Email to R Coffey Point Beach SLRA Second Annual Update - Request for Additional Information Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22291A3692022-10-18018 October 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Use Beacon Power Distribution Monitoring System ML22249A0052022-09-0202 September 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment and Exemptions Regarding Risk-Informed Approach to Address GSI-191 ML22229A1052022-08-17017 August 2022 Response to Questions Regarding Point Beach Nuclear Power Plant with Attachment ML22229A1022022-07-18018 July 2022 Original Request - Questions Regarding Point Beach Nuclear Power Plant ML22196A0062022-07-15015 July 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4b ML22094A0802022-04-0404 April 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-366 ML22006A2762022-01-0606 January 2022 SLR - FW: Subsequent License Renewal of Point Beach Nuclear Plant Unit Numbers 1 and 2, Manitowoc County, Wisconsin ML22006A1952022-01-0606 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22006A2012022-01-0606 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22004A3212022-01-0404 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22004A1732022-01-0404 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22004A0012022-01-0404 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22004A1672022-01-0404 January 2022 SLR - Ref: Point Beach ML22004A3182022-01-0404 January 2022 SLR - FW: EPA Comment Letter - Point Beach SEIS ML22004A3192022-01-0404 January 2022 SLR - FW: Point Beach ML22004A3202022-01-0404 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22006A1942022-01-0404 January 2022 SLR - (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, Docke ML22006A1992022-01-0303 January 2022 SLR - (External_Sender) Comments of Michael J Keegan on Dseis Point Beach ML22004A3172021-12-21021 December 2021 SLR - (External_Sender) EPA Comment Letter - Point Beach SEIS ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML22006A2752021-12-0202 December 2021 SLR - (External_Sender) Subsequent License Renewal of Point Beach Nuclear Plant Unit Numbers 1 and 2, Manitowoc County, Wisconsin ML21341A6102021-11-16016 November 2021 SLRA Safety RAI Set 12 Final Email ML21314A4212021-11-10010 November 2021 Fws to NRC, Concurrence with ESA Determination for Point Beach Subsequent License Renewal ML21307A1522021-11-0909 November 2021 NRC to Fws, Request for Concurrence with Endangered Species Act Determinations for Point Beach Subsequent License Renewal ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21279A1202021-10-0505 October 2021 Email: Wi Shpo Review Point Beach Nuclear Plant SLR ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21273A0232021-09-0202 September 2021 SLRA Safety RAI Set 9 Final Email ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2462021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final Email ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email 2024-08-01
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IHarold Chernoff - Fwd: PB AFW Recirc AOV CAP Page 1 From: Patrick Louden (L To: Harold Chernoff Uplo Date: Tue, Jun 29, 2004 9:13 AM
Subject:
Fwd: PB AFW Recirc AOV CAP q
I Harold Chernoff - PB AFW Recirc AOV CAP Paqe 1 I From: "PGK1 @NRC.GOV" <pgkl @nrc.gov>
To: "PLL@ NRC.GOV" <p1l @nrc.gov>, mjlc@ nrc.gov" <jic @nrc.gov>
Date: Mon, Jun 28, 2004 4:32 PM
Subject:
PB AFW Recirc AOV CAP CC: MAK3@NRC.GOV" <mak3@nrc.gov>
E: State Change History Initiate AR Pre-Screen 0 6/28/2004 14:23:24 by CHAPMAN. ROB Owner (None)
E Section I Activity Request Id: CAP057635 Activity Type: CAP Submit Date: 6/28/2004 14:23:24
, One Line
Description:
AFW Recirculation AOVs 'n6t 'st udo in'6'onfo~rnce&With Calculations i) Detailed
Description:
612812004 14:23:24 - CHAPMAN, ROB:
During preparation of Revision 1 to Calculation 2002-0002 for the nitrogen backup system for the Motor-Driven AFW pump AOVs, It was discovered that the AFW recirculation AOVs are not set up in conformance With the calculation. This also applies to the AOVs for the Turbine-Driven AFW pump (and calculation 2001-0056). Both calculations require the AOVs to be set up such that there is a V/4 gap between the actuator frame and the diaphragm housing when in the shut position. This serves to minimize the dead volume of the actuator. This dead volume Is a'n Input to the calculations, and the value used for this actuator (Copes Vulcan D-100-160) dead volume plus stroke volume of 291 cubic inches is contingent on the valve being set up in this manner.
A walkdown confirmed the following dimensions:
1AF-4002 1.718" AF-40071 18"'
AF-4014 7/8" 2AF-4002 1 1/4" The calculations contain a large amount of margin In that very conservative leakage is assumed, as well as conservatively large number of valve strokes. A review of the effects on the calculations (current revisions on record) using 'the worst case stroke volume (dead volume plus stroke volume) of 600 cubic indhes'follows:
Calculation 2001-0056 Rev 2 (TDAFP): If the worst case value of 600 cubic inches is used, it results in a required tank volume of approximately 211 gallons (the '112T-212 tanks are actually 150 gallons). 'If a realistic value of leakage is used (from recent performance of IT 8C), the required tank volume is 154 gallons.- The net result of this condition is that less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of backup air may be available, If the recirculation valves are stroked 10 times per hour.
Calculation 2002-0002 Rev 0 (MDAFP): If the worst case value of 600 cubic inches is used, it results in a bottle changeout pressure of approximately 1927 psig to ensure a minimum of 90 minutes of operation.- Note that this review has also considered CAP057630 was issued earlier that has resulted in a required increase'in the changeout pressdreto 1950 osig.
Initiator: CHAPMAN, ROB Initiator Department: EXD Engineening Safety 8 EU Design Review PB DateMme of Discovery: 6/28/2004 14:19:00 DateMme of Occurrence: 6128/2004 14:19:00 Identified By: -Site-Identified System: AF PB Equipment# (I1st): (None) Equipment Name (1st): (None)
Equipment # (2nd): (None) Equipment Name (2nd): (None)
Equipment # (3rd): (None) Equipment Name (3rd): (None)
Site/Unit: Point Beach -
Cornmon Why did this occur?: 6128/2004 14:23:24 - CHAPMAN, ROB:
Requirements from calculations were not transferred to the field for setup of the AOVs.
Immediate Action Taken: 6/2812004 14:23:24 - CHAPMAN, ROB:
Reviewed calculations for the effects of this condition.
Recommendations: 6/28/2004 14:23:24 - CHAPMAN,'ROB:
http://enwsO2/tmtrack/lmtrack.dll?lssuePage&Tcmplate=viewvbody&rccordid=726888&ta ... 6/2S/2004
The recirculaiton AOVs should be set up such that the gap between the actuator frame and the diaphragm housing is less than 1/4". This will bring the actuators into conformance with the calculations.
' SRO Review Required?: Y E Section 2 Operability Status: (None) 0 Compensatory Actions: N Basis for Operability:
- Unplanned TSAC Entry: N @External Notification: N 8 Section 3 Screened?: N I Significance Level: (None)
INPO OE Reqd?: N Potential MRFF?: N 0 QA/Nuclear Oversight?: N 0 LUcensing Review?: N Good Catch/Weil Doc'd?: NA 8 Section 4 Inappropriate Action:
Process: :(None) Activity: (None)
Human Error Type: (None) Human Perf Fail Mode: (None)
Equip Failure Mode: (None) Process Fall Mode: (None)
OrgfMgt Failure Mode: (None) 6 Group Causing Prob: (None)
Hot Buttons: (None)
Iittp://cnws02/tmtrack/tmtrack.dll?lssitePage&Tcmplate=vicwbody&recordid=726888&ta ... 6/28/2004
I -
CALC 2001-0056 Rev 02 RCC IO4I42003 Page 10 of 13 Using the difference in SCFA volumes in the tank as equal to the total required demand:
Vsr,- VSTf= VSCFA = 35.4 SCFA (6.1.9)
Inserting Eq 6.1.9 into Eq 6.1.7 and 6.1.8 and solving yiclds:
VTANK= 0.142(35.4 + Vs-r) = 0.195 Vs7
- 0. 142(35.4) =48sF VS=f =(19( 1)2--9-4.8' SCFA Vs,-(0. 195 -0.142)
Vs,= 35A + 94.8 = 130.2'.SCFA VTANK= 0.195(94.8) = 18.5f' *(748 galfi3)= 138 gal 6.2 Calculation of Modification PMT Acceptance Criteria V, = 291 in3 Swept volume of diaphragm including dead band (Input 5.2)
,d,= 0.245 in Tubing diameter (Input 5.9, Section 6.1)
L, = 1000 in Maximum length of tubing pressurized (Input 5.9) t = 5 minutes Test duration (Input 5.10)
- Calculation of filled volume of tubing and valve:
V =-X d,2Lt = Z (.245tin])2(1000[in]) = 47.1[in3 ] (62.1) 4:T 4 VT-FST= Vt+ VP = 47.1 +-291=.338 in3 VTES= 338 in 3 *(1 ft'/1728 in)--0.196 ft3
- Pressure dron in system during testinz-The pressure drop can be calculated for standard conditions assuming any value of leakage in SCFM. The equation for the change in standard volume of air is:
=(1-V,)
Vi1. (622) t where Vi and VWare the initial and final volumes of air in the pressurized section of tubing in SCFA. Using Equations 6.1.5 and 6.1.6, the pressures and volume have the following relationship: