Email - from Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; Nausdj@Ornl.Gov; Carrion, Robert Cc: Miller, Craig L Dated Tuesday, December 01, 2009 4:29 PM Subject: Draft Refute 8.2 for Review Attachments:ML102910627 |
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Crystal River ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
12/01/2009 |
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From: |
Williams C Progress Energy Co |
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To: |
Robert Carrion, Lake L, Naus D, George Thomas NRC/RGN-II, Oak Ridge |
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References |
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FOIA/PA-2010-0116 |
Download: ML102910627 (3) |
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Category:E-Mail
MONTHYEARML24025A0952024-01-24024 January 2024 Clarifications Related to the NRC Staff'S EA for Crystal River ML23180A0562023-06-13013 June 2023 ADP-CR3, Crystal River Unit 3 Email from J. Jernigan to Tim Barvitskie Confirmation That Enclosure 22 Radiological Groundwater Characterization Report ML21117A2902021-04-26026 April 2021 Acceptance of License Amendment Request Related to the ISFSI-Only Physical Securityplan ML21096A0432021-04-0505 April 2021 Acceptance of License Amendment Request Related to the ISFSI-Only Emergency Plan ML19344C8052019-11-12012 November 2019 Response from NEIMA Local Community Advisory Board Questionnaire 11-12-2019 H Danenhower ML19310D8602019-10-24024 October 2019 E-Mail Dated October 24, 2019, from Mark Vansicklen, Duke Energy Florida, to John Hickman, NRC, Providing Background Information for the Crystal River Partial Site Release Request ML19344C7872019-10-0303 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-03-2019 D Taylor ML19310D8212019-09-13013 September 2019 E-Mail Dated September 13, 2019, from John Hickman, NRC, to Mark Vansicklen, Duke Energy Florida, Requesting Background Information for the Crystal River Partial Site Release Request ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML19070A3112019-03-0606 March 2019 Document Title or Accession No. E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of Partial Site Release Request for Crystal River Unit 3 ML19071A0662019-03-0606 March 2019 E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of a Request to Revise the ISFSI Only Emergency Plan for Crystal River Unit 3 ML18263A1462018-09-11011 September 2018 NRR E-mail Capture - Logbook Entry: 09/11/2018 a Kemp'S Ridley Sea Turtle (Federal Endangered Species) Carcass Was Recovered from the Crystal River Energy Complex Unit 2 Fossil Unit ML16054A2402015-12-10010 December 2015 E-44108 Attachment 10 E-mail from Steven Edwards (Due Energy) to Don Shaw (Areva) for Brunswick Nuclear Plant, Oconee Nuclear Station, and Robinson Nuclear Plant ML15176A2692015-06-25025 June 2015 NRR E-mail Capture - NRC Acceptance Review for LAR #317 Regarding Changes in Managment Titles ML15043A1042015-02-0505 February 2015 NRR E-mail Capture - Mf Crystal River TAC ML15015A6722015-01-15015 January 2015 NRR E-mail Capture - NRC Acceptance Review for LAR - Application for Order Approving Transfer of License and for Conforming License Amendment ML14344A9992014-12-0909 December 2014 NRR E-mail Capture - Severe Weather Exemption ML14258A7432014-09-0505 September 2014 NRR E-mail Capture - FW: Comparison of Crystal River'S Exemption Secy Paper with Kewaunee'S ML14290A1992014-08-27027 August 2014 NRR E-mail Capture - Draft RAIs for Ep/Eal LAR ML14163A2512014-06-0303 June 2014 NRR E-mail Capture - Request for Additional Information - Exemption for Conducting Annual force-on-force Exercises ML14153A0842014-05-29029 May 2014 NRR E-mail Capture - Logbook Entry: 05/29/2014 ML14153A6912014-05-21021 May 2014 NRR E-mail Capture - Request for Additional Information - Decommissionign Trust Fund Exemption Request ML14132A2052014-05-0909 May 2014 NRR E-mail Capture - MF3089 - Defueled TS Amendment Request for Additrional Information ML14114A2792014-04-10010 April 2014 NRR E-mail Capture - MF3089 Defueled TS Request for Additional Information ML14113A3632014-04-10010 April 2014 NRR E-mail Capture - MF3415/MF2981 RAI on EP Exemptions, EAL Scheme Change and E Plan Amendment ML14118A2872014-02-20020 February 2014 NRR E-mail Capture - Request for Additional Information: Exemptions to the Radiological Emergency Plan Requirements ML14045A0012014-02-12012 February 2014 NRR E-mail Capture - RAI: Adminstrative Controls ML14031A1752014-01-27027 January 2014 NRR E-mail Capture - CR3 Certified Fuel Handler Training and Retraining Program Approval - RAI Request ML14017A0772014-01-16016 January 2014 NRR E-mail Capture - Brunswick 1 and 2, Crystal River Unit 3, Harris Unit 1, and Robinson Unit 2 - Acceptance for Review of License Amendment Request for Cyber Security Plan Implementaion Milestone 8 (TAC Nos. MF3263 - MF3267) ML14027A0332013-12-16016 December 2013 NRR E-mail Capture - Eplan and EAL Scheme Change Request for Additional Information (LAR #315) ML13336A9112013-12-0202 December 2013 NRR E-mail Capture - Periodic Update to the Crystal River 3 Containment Petition ML13198A1422013-07-17017 July 2013 NRR E-mail Capture - Draft RAI - Request to Amend Section 5.0 of the CR-3 Technical Specifications (MF1504) ML13157A2062013-05-31031 May 2013 NRR E-mail Capture - Logbook Entry: 5/31/2013 ML13155A2062013-05-29029 May 2013 NRR E-mail Capture - Petition Status Update - Containment for Crystal River ML13120A0412013-04-29029 April 2013 NRR E-mail Capture - Status Update for Petition on Crystal River 3 ML13095A4002013-04-0505 April 2013 E-mail - Acceptance of Requested Licensing Action Change of Licensee Name ML13052A2402013-02-0808 February 2013 LTR-13-0131 - E-mail Tom Gurdziel Concerns Crystal River, Unit 3 ML13015A2832013-01-14014 January 2013 NRR E-mail Capture - Status of 10 CFR 2.206 Petition Related to Crystal River 3 ML13011A1482013-01-10010 January 2013 NRR E-mail Capture - CR-3 EPU LAR - Additional RAI from Eeeb (ME6527) ML12304A0682012-10-26026 October 2012 NRR E-mail Capture - RAIs Regarding Crystal River 30-day Report for ECCS Model Changes Pursuant to 10 CFR 50.46 Requirements (ME8408) ML12297A3922012-10-23023 October 2012 NRR E-mail Capture - Draft Bypass Test Plan ML12268A3592012-09-24024 September 2012 NRR E-mail Capture - Acceptance Review for LAR Regarding Cyber Security Plan Implementation Schedule Milestones ML12208A0142012-07-25025 July 2012 NRR E-mail Capture - State Consultation ML12184A3442012-07-0202 July 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs ML12144A0102012-05-22022 May 2012 NRR E-mail Capture - Acceptance Review Determination: CR-3 - Relief Request #12-001-MX for Option to Use ASME Code Case N-791 for Containment Repair ML12107A0682012-04-0404 April 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb) ML12100A1022012-03-30030 March 2012 NRR E-mail Capture - Acceptance Review for CR3 - LAR 312- Departure from a Method of Evaluation for Aux Bldg Over Head Crane, Implementation Schedule Change ML12023A1272012-01-23023 January 2012 NRR E-mail Capture - Acceptance Review Determination for TAC ME7729: CR3 - Relief Request #11-001-MX, Containment Surveillance Schedule, Fourth 10-Year ISI Interval ML12019A2662012-01-17017 January 2012 NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206 ML12019A2672012-01-17017 January 2012 NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206 2024-01-24
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Text
Franke','Mark From: Williams, Charles R. [Charles.Williams@pgnmail.com]
Sent: Tuesday, December 01, 2009 4:29 PM To: Lake, Louis; Thomas, George; nausdj@ornl.gov; Carrion, Robert Cc: Miller, Craig L
Subject:
RE: Draft Refute 8.2 for Review Attachments: Pages from FSAR Section 05.pdf Exhibit 2 for Refute 8.2 would not open for reviewers. This file replaces the two previous Exhibit 2 FSAR files and will now open.
From: Williams, Charles R.
Sent: Tuesday, December 01, 2009 2:18 PM To: 'louis.lake@nrc.gov'; 'George.Thomas2@nrc.gov'; 'nausdj@ornl.gov'; 'rpcl@nrc.gov'
Subject:
Draft Refute 8.2 for Review Mr Lake and others, Attached for your review is draft of refute 8.2 with supporting exhibits. If you have any questions, please contact me.
Thank you, Charles Williams 919-516-7417 1
Y/J?8
FM 8.2 Exhibit 2 Page 1 of 2 FINAL SAFETY ANALYSIS REPORT Revision: 31.3 0- Florida Power A Progress Energy Cnrmpany CONTAINMENT SYSTEM & OTHER Chapter: 5 SPECIAL STRUCTURES Page: 82 of 93 5.5 VENTILATION AND PURGE SYSTEMS 5.5.1 DESIGN BASES 5.5.1.1 SYSTEM FUNCTIONS The Reactor Building (RB) Ventilation and Purge Systems consist of the RB recirculation subsystem (AH-XA), RB area fans and coolers subsystem (AH-XB) and RB purge subsystem (AH-XC). These three subsystems were designed to perform the following functions:
- a. Remove or add sensible heat under normal conditions of operation to maintain average RB air temperature below the Improved Technical Specification limit (130'F), and above a pre-determined minimum temperature (60'F). (AH-XA, AH-XB)
- b. Remove sensible and latent heat under emergency conditions to reduce the building temperature and pressure from predetermined maximum values (281'F, 55 psig). This is an Engineered Safeguards (ES) function and therefore, is also described in Chapter 6. (AH-XA)
- c. Recirculate air through demisters and throughout the reactor building. (AH-XA and AH-XB)
- d. Supply filtered and tempered outside air to, and exhausts air from, the building when required, during Operational Modes 5 and 6. (AH-XC)
- e. Filter air exhausted from the building through roughing, High Efficiency Particulate Air (HEPA) filters, and charcoal filters and then discharge it to the atmosphere through the plant vent, during Operational Modes 5 and 6. (AH-XC)
- f. Maintain uniform temperature throughout the building during the integrated leak rate test.
(AH-XA and AH-XB)
- g. Reactor Building atmosphere can be purged or pressure equalized using the containment minipurge valves. (AH-XC and LR)
Additional information on the Reactor Building Cooling Systems is provided in Section 9.7.
5.5.1.2 SYSTEM SIZING The system is sized to support the following operating modes:
- a. Normal cooling load, ranging from approximately 6.0 x 106 Btu/hr (500 tons) during the winter months, to 12.0 x 106 Btu/hr (1000 tons) during the summer months. Available Cl System cooling capacity exceeds 16.8 x 106 Btulhr (1400 tons).
- b. Outage cooling load, ranging from approximately 1.2 x 106 Btu/hr (100 tons) to 2.4 x 106 Btuthr (200 tons). Maintaining an RB air temperature of 65'F (+/-5°F) during outages improves productivity while reducing the incidence of personal contamination.
- c. Emergency cooling load, Loss-of-Coolant Accident (LOCA): Each RB Cooler shall have the capability to remove a minimum of 80 x 106 BTUs/hr from the RB atmosphere via condensate to
FM 8.2 Exhibit 2 Page 2 of 2 FINAL SAFETY ANALYSIS REPORT Revision: 31.3 2Florida Power 4,Progress Energy ;,',i' COTIMN CONTAINMENT SYSTEM & OTHER YTM&OHR Chapter: 5 SPECIAL STRUCTURES Page: 83 of 93 the RB sump and heat transfer to the SW system. No more than one (1) RB cooling fan will operate following receipt of an ES signal.
- d. Normal heating load (outside design air temperature of 257F, inside design air temperature of 60'F, full shutdown of plant): 615,000 Btu/hr.
- e. Ventilation and exhaust rate (1.5 air changes per hour): 50,000 cfm. At this rate, the system reduces the activity level in the building to doses defined by 10 CFR 20 for a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> occupational work week which will allow accessibility, within two hours after initiation of the purge systems, after establishing a Plant Operational Mode 5.
- f. Reactor Building minipurge flow rates up to 1000 SCFM can be obtained using redundant control valves. Minipurge flow joins the normal Reactor Building Purge Exhaust System downstream of the redundant leak rate throttle valves.
5.
5.2 DESCRIPTION
The Reactor Building Cooling Systems are subdivided into three major sets of components - Group A, Group B, and Group C. These are shown in the flow diagram Figure 5-27.
- a. Group A Group A components are those which filter (demister only) and recirculate air throughout the building under both normal and emergency conditions. Sensible and latent heat are removed as required. Included in this group are the reactor building fan assemblies and the auxiliary fan systems which deliver air to the operating floor, the reactor compartment, the service structure and the steam generator compartments. This group also includes the normal duty Industrial Cooling (CI) system, featuring a water cooled chiller, two evaporative cooling towers, and miscellaneous supporting equipment. The Cl System supplies cooling water to the RB Fan Assemblies and Cavity Coolers during normal plant operation.
- b. Group B Group B components are those which supply filtered (85% efficiency) and electrically heated (tempering only) outside air to the building whenever required for purging, during Operational Modes 5 and 6.
Included in this group are the two 48 inch diameter butterfly valves which seal the building air supply port.
- c. Group C Group C components are those which exhaust air from the building during Operational Modes 5 and 6 purging, pass it through roughing, HEPA, and charcoal filters, and then discharge it to the atmosphere through the unit vent. Included in this group are the two 48 inch diameter butterfly valves which seal the building air exhaust port.
- d. General Duct work is used with Group A components to return air to the main reactor building fan assemblies located in the lower part of the building. A portion of this supply air from these assemblies is picked up by auxiliary fan-duct systems for delivery to the steam generator compartment, the reactor compartment, and the operating floor area. The CRDM Shroud Exhaust Fans draw air from above the service structure and discharge out through the lower service structure area. The remainder of the air circulates due to the