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Category:E-Mail
MONTHYEARML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24156A1072024-06-0404 June 2024 NRR E-mail Capture - (External_Sender) Supplement for FitzPatrick TS 3.4.2-2 ML24131A0612024-05-10010 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24122B5072024-05-0101 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-591, Revision 0 ML24060A0512024-02-28028 February 2024 NRR E-mail Capture - FitzPatrick - Final Arcb RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24033A0542024-02-0101 February 2024 NRR E-mail Capture - FitzPatrick - Final HFE RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24017A1112024-01-17017 January 2024 NRR E-mail Capture - Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-529, Clarifyuse and Applicaion Rules, Revision 4 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23261C3982023-09-0808 September 2023 Acceptance Review of Amendment to Update the Fuel Handling Accident Analysis ML23244A2662023-09-0101 September 2023 Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirement 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML23237B3972023-08-24024 August 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Alternative Request to Use Updated BWRVIP Guidelines ML23194A1822023-08-0303 August 2023 Acceptance Review for LAR Re SRM 3.3.1.2 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML22063A4742021-11-29029 November 2021 Acceptance of Requested Licensing Action License Amendment Request to Eliminate Selected Response Time Testing ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21246A2112021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-505 ML21246A2072021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21246A2142021-06-23023 June 2021 Acceptance of Requested Licensing Action Regarding License Amendment Request to Adopt TSTF-264 ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21033A8552021-02-0202 February 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request to Expand the Use ASME Codes Cases N-878 and N-880 ML21014A5112021-01-12012 January 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-545 Revision 3 ML20352A2752020-12-17017 December 2020 Request for Additional Information Regarding FitzPatrick Primary Containment Isolation Valve Amendment Request ML20350B5582020-12-14014 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Alternative Request for Documentation of Replacement of Pressure Retaining Bolting ML20294A0372020-10-19019 October 2020 Request for Additional Information Primary Containment Isolation Valve License Amendment Request ML20266G3032020-09-22022 September 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI ML20217L3882020-08-0404 August 2020 Acceptance of Requested Licensing Action License Amendment Request to Modify Primary Containment Isolation Valve TS (EPID L-2020-LLA-0145) (E-Mail) ML20204A9692020-07-22022 July 2020 Acceptance of Requested Licensing Action License Amendment Request to Adopt-TSTF-478 Revision 2 ML20122A2302020-05-0101 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of Fleet License Amendment Request to Adopt TSTF-566 ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence 2024-07-12
[Table view] Category:Letter
MONTHYEARIR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 2024-08-09
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Text
Gray, Mel From: Knutson, Ed Sent: Monday, April 18, 2011 11:38 AM To: Gray, Mel
Subject:
FW: FitzPatrick Hardened Vent Attachments:
Fitz Hardened Vent.pdf From: Knutson, Ed Sent: Thursday, March 17, 2011 1:47 PM To: Vaidya, Bhalchandra
Subject:
FitzPatrick Hardened Vent Attached is from a 1995 inspection report concerning completion of the TI that looked at hardened vents.
UNITED STATES NUCLEAR REGULATORY COMMISStON REGION I~~ 475 ALLEN DALE ROAD KING OF PRUSSIA, PENNSYLVANIA 1W4(1.1415
'April 18,. 1995 Mr. Harry P., Salmon, Jr.Resi'dent, Manager New YorkPower Authority James A. FitzPatrick Nuclear Power Plant Post Office Box 41 Lycoming, New York 13093
SUBJECT:
.
NOTIC'E OF VIOLATION (NRC REGION I INSPECTION NO. 50-333/95-06)
Dear,
Mr., Salmoný.This refe~rs to -the results of, the routi'ne resident safety inspection conducted byjMessrs.
W.. C.o.ok and R. Fernandes from February 12, 1995 to March 25, 1995 at, the- ýJame's ,A. FitzPatrick Nuclear Power Plant, Scriba, New York. A summary of the inspiec ,tion findings was presented to you and members of your staff at ,an exit .-meeting on April 1?, 1995.Thisinspectioon was directed toward areas important to public health' and safety.. eas examined during the inspection are described in the NRC Region I inspection report, whichi is enclosed with this letter. Within these areas, the inspectioneconsisted of observation of activities, interviews with personneluand document reviews.Performance by the plant staff during this inspection period was mixed.NYPA's deliberate and cautious approach to verifying the extent of fuel assembly debris and potential fuel pin damage demonstrated a safety consc'ious philosophy.
On the other hand, a number of personnel performance errors that involved radiation protection requirements and surveillance testing procedural noncompliances indicated carelessness by members of your staff for ,administrative controls.
Several examples of procedural noncompliance were citediand are discussed in detail in the enclosed report. We note that these, events occurred during 'your 1994-95' refuel outage and that NYPA has expe~rienced similar performance declines during previous planned outages.Your continued strong management attention is warranted.
You are required to respond to this letter and, should' follow the instructions specified in the enclosed Notice of Violation (Notice) when preparing your response.
In your response, you s*iould document the specific actions taken and any additi'onal actions you plan to prevent recurrence.
After reviewing ,Your response to this Notice, including your proposed corrective actions and the results of future inspections, the NRC will determine whether further NRC e~nforcement-action is necessary to ensure compliance with NRC regulatory requiremen ts,.In'acco~rd'ance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will' beplaced in the NRC Public Document Room.Theresponhse directed by this, letter and the enclosed Notice are not subject"to the clearance procedures of the Office of Management and Budget 'as required by .the Paperwork Reduction Act of '1980, Pub. L. No. 96.511.
10 0 Two component hangers on the. A emepgency firl ter;7 train were6 not reflected' on plaant drawin"gs ,and pare .a different design. than those similarly:
depicted on '-the drawings.;
Thetiiensee iniftiated drawing chaniges tJo, reflect the supports and prdvided the inspector with calculations , to.,demonstrate the structural integrity of system supports,.::
The inspector reviewed the c aicUlationsiand hadno 6further questions.
- Two AODs, 701OD-114 and '70MOD-113, were disconnected and lock wired in the cl osed and, open position, respec tively. The inspector' subsequently l earned that the configuration Iwas the result of. a temporary modi~fication (No.ý93-152) pu-t into. place, to :addre~ss si~ngle fali~l~u reýconcerns previouslyy Identified, by, the licensee,.
The temporary modification placed the modulating .dampers' in failY-safei positions, to ,ensure that the control !room I.s provided a' maximum ýsupply of, fresh airf and to ensure positi~ve
ýcontrol room air pressure,,,:duri'ngg emebrgencqdfty conditions.
The inspector also learned a... minor modihficationi , wa jin, prgestocnetthis tlelmporar modification, into a perna'nent-syttem-moodif ic-a tion.The inpctor reviewe"'d, the mi nor modi f ,ictioakg n had no further' quedstions...
41 As. part of the system. wa1kdown "the e :to : te NYPA staff that ,two MODs, and' M0"-114, and flow element FE'-102 were omited frmis-bu~ilt drawing FB-3-5C, Re-v. 12, Equipment Room Heating, Vent and Air Conditioning.
However, the inspector noted that the tcomponents were identified on the control room flow diagram FB-45A and Identified in the FSAR. The inspector was concerned that despite a temporary modification and a minobr modification being processed for two safety-,related components,, this deficiency in the as-built drawin~g ws,,-not Identified by the, NYPA staff. The.:insipector identified his to NYPA. ' NYPAP's' evaluation
- was inotf:compliete' at the end, o6f. theý period.The issue will remaini unresolved pendinig
!of NYPA 'eval uation and subsequent NRC rfeview. (RF WG643) /-The. inspector-s cdonclluded: -that the: control room :emergency.
ventilatiton!, system was ope-rable,.
and': with the.
bf the observations noted abovehad, no6 further qetos 4.3' TI 2515/121 Verification of Mark IHardenedtVent Modificaions As part of a comprehensive plan for closiniigL:
severe accident i issuesi, the NRC.staff undertook a program to determine if any actions should be taken, on a generi c basis, to reduce the vul nerabilI ty, of BWR' Mark I containments .to:severe accideht challenges.
At the conclusion of the Mark I Containment Performance Improvement Program, the. staff identified a number of plant.-Mod ifi cat ions Ithat would substantiially,,, enhance the pl ants' capabil ity t bboth prevent! and mitigate the conseque'nce I s of severe accidents.
R icommended
'improvements, included imprved hardened" etwe-0 vent capabilitj!.y:.
On Septembe0r" 1', 19809,, Ithe? NRC: i'ss~ue'dGeneric Ldetter (-GL) 89-1l6,, "Installatin o.a Hardened Wetwell Vent ," r,,equesting liten'see~s wi.th MNark- I ctinai~nments "to-, cons~ider instal ation of' hardened, wetwei i vent systemsunder the provisi,ons of 10* CFR 50.59. Using guidance provided in Temporaryiinnstction
('I)2515/,"Vrfcato of~ Mark& I Hardened 'ent. Modfctos.G
- 91) the.flRC'
~is in al the process of ,conduct ing inspections ,to verify iicensees" impl ementationof commitments made in response to, GL 89-16. , Byltes a7 ctbr2, 18,,and July 2u5, 1990, NYPA not fified:the
ýýNRC, staff ,that it' would defer it s decision on harden ed wetwel 1 vent i on until the Fitzpatrick Indiv'idual Plant, Examinati:n (IP'E) as completed.
The NRC reviewed the information provided 4n tihose letters and also, inspected the,-existing wetwell vent path at, FitzPatricL,..
As a result -o f these activiti~es, the, NRC identified weaknesses:
in procedures and operations trai;ning al'Sdo, determined that all Boil ing, Water Reactor Owners Group (,BWRO) Fy crifteri a were not met by the licensee's current design. However, because the design was expected to achieVe the desired reduction in coe damage frequency, the NRC approved NYPA's request toi defer its decision 'o Ifully implement the BWROGýhardened vent general destgn criteria until completion of their IE. This aproa adIntal safety- eval uati on, is documented in an NRC letter dat~d January. 24,1 1991.The January 19911 letter talo approved the dferai of improvemets in Ioperator tranin ad po'dus u Il IPE comlto .After the~ FitzPatr'ick,'
WEl` was completed, the NRC eed the ýchang t6o the and pr6o6edures
- propoqsed' by the l-icnse Th subseqen NRC s~afetyhts
`6h NIf evaluation, of t"he Vent-related proced6res and propqosed wag trns mitted by NRC' ltte'r April 27, 1992.In a September.280, 1992 le tter, the NRCdetermined that the current ve' path fet the, intent of the BW'IaROG design criteria,,, based on additionalt infor.ati'oh provided, by, NYPA and results of the previous NRC inspection' of thee vent path.Thits letter forwvarded the NRC staff',s safety evaluation for the harde~ned vent.n, -addition, the NCfound that the plant ,Procedures and training Wver~e adeq~ua'te toprovide'-the"Information and g.Ujdanqce necessary for ope~rators to.effectively
'use. the 'FitzPatric~k, hardened.
wtwe~ll- vent.The, inspector reviewed the referenced reports: and determi-ned ithat all T appl icabl.e portiidons of TI -2501,1121 for, the hardened vent at rt zPa trihk have been effectively addrietsd.
The FitzPatrick wetwell 'vent, met, th:e intent of the NRC approved BWROG cy'Qpeati Procd....were avalbet direct, the ini t iat ion -nd, termnat ion of vent ing,, ':oppe~rator training on the was ýacceptable, and operators were found to beý " .knowledgeable of-the design and funct iion. .of, t heý system. TI 2515/121 is closed.4;4 Previously 1ýIdentofi:d Iýtems S dd..U.. ...rol v.I1tem.(92-14-01): -Rel a Room. CO System Testing As noted in inspection report, 0-3331/95-02', Section 4.C;2_.1,, NY0A, conducted, special' test procedure, STP-76AU, Relay Room Enclosure i-ntegrity T:estf,-, to! ..cq lect data "for an' engi neering anal ysiis perfOre' In li ieu ofa full discharge test of the relay room CO 2 fire suppression system. The engineering analys"'is was performed.
for WYPA: by Yankee Engineerinhg Seryvices via a February 1995~EngineePrilng ,Report to, NYPA and captured under a memorandum (JAF-RPT-FPS-02009o).
teda ted:March 2, "1995. Based, uponl satisfactory completion of th i s eng ng