(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Similar Documents at Hatch |
---|
Category:- No Document Type Applies
MONTHYEARML24018A0702023-11-30030 November 2023 Form 2.1-1 Examination Preparation Checklist ML17076A4322017-03-23023 March 2017 TSTF-542 Deviations Descriptions for Hatch Nuclear Plant ML16285A3282016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 14-05 ML15236A1202015-08-25025 August 2015 Order EA-13-109 (HCVS) Phase 1 and 2 OIP Rev 0H3A - August 25, 2015 ML15233A0742015-08-10010 August 2015 SPRA Relief - Information to Support Reconsideration of Hatch U1 for Inclusion in SPRA Relief Due to Seismic Robustness and Similarities to Hatch U2 ML14314A5122014-11-13013 November 2014 Enclosure 2 - Frequently Asked Questions (Faqs) Discussed During the October 22 2014 Reactor Oversight Process Public Meeting ML13143A3312013-06-0606 June 2013 Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML11313A1472011-09-30030 September 2011 CR New Summary - Southern Company ML11308A6682011-09-28028 September 2011 Georgia Power Company - Reactor Plant Event Notification Worksheet ML1020302702010-07-13013 July 2010 Current Issues, Edwin I Hatch Nuclear Plant ML1019303132010-06-0909 June 2010 Onsite Ground/Surface Water Monitoring Questionnaire for Hatch ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML1019402172009-05-14014 May 2009 South Nuclear Plant E.I. Hatch - Actions for Potential Groundwater Contamination Events ML0818503872008-06-0606 June 2008 Consent and Hearing Waiver Form - Anthony Fortuna ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0610703612006-04-12012 April 2006 Attendance List ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants ML0505402642003-10-22022 October 2003 Summary of EB1 Findings (07-09/03) ML0505402952003-09-30030 September 2003 Fire Protection Mc 0612 Appendix B Minor Questions Worksheet ML0403502122003-08-13013 August 2003 DRS Open Items Status ML0510100462003-07-21021 July 2003 NRC Audit Question 71 ML0510100542003-07-21021 July 2003 NRC Audit Question 72 ML0510100592003-07-21021 July 2003 NRC Audit Question 70 ML0510100562003-07-10010 July 2003 NRC Audit Question 51 ML0510100362003-07-0808 July 2003 NRC Audit Question 6 ML0505402572003-02-18018 February 2003 Note Regarding Local Operation of Valve 2E11-F015A ML0208102742002-02-28028 February 2002 Requested Permit Revisions - Edwin I. Hatch Nuclear Plant ML0208102722002-02-28028 February 2002 EPA Form 2C NPDES - Application for Permit to Discharge Wastewater Consolidated Permits Program - Edwin I. Hatch Nuclear Plant ML0208102712002-02-28028 February 2002 EPA Form 1 General - General Information Consolidated Permits Program - Edwin I. Hatch Nuclear Plant ML0208102792002-02-20020 February 2002 Certificate of Analysis from General Test Lab. to Georgia Power Co ML0208102762002-02-20020 February 2002 Certificate of Analysis from General Test Lab. to Georgia Power Co for Hatch Plant ML0208102782002-02-14014 February 2002 Florida Radiochemistry Services, Inc. - Lab Reports for Alabama Power Co ML0208102812002-02-0202 February 2002 Certificate of Analysis from General Test Lab. to Georgia Power Co 2023-11-30
[Table view] |
Text
Control Number:
ARurdft Question Processing Form (For Staf use only)
AQ-51 Question Initiated By: Schin, Bob Date: 7/10/2003 Regulatory Basis for Qucstion:
Question:
If al,,pven SRV's opened simultaneously while reactor power is at 100%, would all RCS pressure variables be maintained within those predictable for a loss of normal AC Power?
Response
As previously documented in the response to AQ-6, the plant is designed to withstand the containment loads that result from operation all 1 SRVs. As part of extended power uprate, additional containment loads analysis was performed that demonstrated that adequate design margins continued to exist for operation at current rated power, 2763 MWt. A copy of the GE Proprietary report documenting the containment
-evaluation (GE-NE-AI13-00402-04-RI) is attached for review (but Abe returned in view of its proprietary nature). ,
(Fc Staff use on:y) -
I Re ~ r ul 'o Reviewed by Luker, Ira Safmt
.cileb:_~er
-rritn-~ycTae~da>qe~ Staff init:
NRC si e§ir6oeieedom of Information ___\
Act, exemptions A4 -- _
FOJA- >74 oV-S7-
Control Number.
Andit Question Processing Form (For Stanf use only)
AQ-51 Cxy' It should be noted however, that SNC believes that this question falls into the category of associated circuits, inspection of which was temporarily suspended as of 11/29/2000 (ML0037733142). This inspection scope reduction is referenced in NRC Inspection Procedure 71111.05. This suspension recognizes the ongoing industry and NRC activities to complete NEI (NEI 00-01) and NRC guidance to address issues associated with associated circuits analysis. Once these activities are completed, currently scheduled for this fall, SNC wxill review the applicable guidance and detennine if any additional actions are appropriate. Given that the cu5rrengjkg.nisin2g basis of Plant Hatch does-not incrhie hot shorts in associated Y L
circuits, and given the NRC guidance provided by NRC Inspection Procedure 71111.05, SNC believes this topic most appropriately could be deferred pending further resolution of the NRC's generic actions to clarify the regulatory basis of multiple hot shorts.
1s4 M.
towi£.4 '7z-(For Staff use onty)
Response by: Tully, Cin4_ Reviewed by-Luker, Ira Staff init:
NRC Status: In Progress _ ____- _