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Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, 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 ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A2062023-11-21021 November 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23313A0432023-11-13013 November 2023 Summary of Regulatory Audit in Support of Amendment Request for Control Room Air Conditioning Technical Specifications RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 2024-02-02
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STANDARD DISTRIBUTION FO. COMING MATERIAL RELATING TO 1 II CONTAINMENT UAo NUCI,EAR REGULATORY COMMISSI N OCKET NUM8ER NRC FORM 196 (2 TSI
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NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TOP ICAL REPORT TO: FROM: DATE OF OOCUMENT Mr. Victor Stello General Electric 10 24 77 San Jose, Ca. 95125 OATE RECEIVEO Glenn G. Sherwood ER C3NOTORIZEO PROP INPUT FORM NUM8ER OF COPIES RECEIVEO JOE ORIGINAL HGNCLASSIFIEO QCOP Y I 5(CoQM ENCLOSURE Ref. Amendment 3 to NED0-20566, Effe t of Steam Environment on Core Spray Distr bu tion. ~ ~
Furnishing information regarding NRC's p oposal to perform some additional test in a cor spray facility owned by ConsuIIIers Power Corp. ~ ~
3p LETTERS OF INCORPORATION WILL BE PLACED DOCKET LISTED BELOW+
IN'ACH iVOTE: .CYS WILL BE PLACED IN THE LPDR FOR THE FOLLOWDIG ZEKKR 50-358 NINE MILE P T 50-410 LIMERICK 50-352/353 WPPS-2 50-397 BAILLY 50-367 SHOREI+m .40-3%2 LA SALLE 50 3/3/374 gem 11/02/77 FOR ACTION/INFORMATION INTERNAL 0 IST RI BUTION CENTRAL FILES 2 W 9 s o eac LETTER OiVLY NRC PDR Re DEYOUNG LPDRIS 7 S e Note Do VASSALLO TIC Ko KNIEL NSIC 0+ PARR ACRS 6 J~ T L Ie S IHWELL 2 R TEDESCO Ge LAINAS (7 Mo RUSHBROOK Ja KNIGHT 2 Wo P IKE Co ANDERSON S ~ VARGA Io PEL'ZIER TALI 0 Re B~L LYNCH MD Jo SNELL Ao BOURNIA We ~K S~ MINER EXTERNAL OISTRI BUTION CONTROL NUMBF1
6 E ItI E R A l ' E I. E C T II I C NUCLEAR ENERGY SYSTEMS DIVISION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 676, (408) 925-5040 BWR PROJECTS DEPARTMENT gjguIggp gggg F([f glglt -'403-77 CO October 24, 1977
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h/Oyg 18 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation .~gag, 8?ClIII Washington, D. C. 20555 ~>acr~"
Attention: Mr. Victor Stello, Jr., Director Division of Operating Reactors Gentlemen:
SUBJECT:
AMENDMENT 3 TO NED0-20566, EFFECT OF STEAM ENVIRONMENT ON CORE SPRAY DISTRIBUTION
Reference:
- 1) Letter, V. Stello (NRC) to G. G. Sherwood (GE) dated August 5, 1977, same subject
- 2) Letter, 0. D. Parr (NRC) to G. G. Sherwood (GE) dated September 6, 1977, same subject Reference 1 states that the NRC staff is reviewing the subject Amendment and notes a concern with regards to an apparent lack of experimental spray distribution data in a steam environment for multi-nozzle, sparger spray systems. The letter also notes the testing performed by GE with single nozzles in a steam environment and the full scale multiple nozzle tests performed in air, and proposes that it would be useful for GE to perform some additional tests in a core spray facility owned by Consumers Power Corporation (CPC). GE has reviewed this request and offers the following:
- 1. The CPC test facility was designed and built to provide data on a core spray configuration of the Big Rock Point station.
This configuration is not representative of the later, larger BWR plants. Although Reference 1 indicated that it may be feasible to design a more representative sparger, our review indicates that there would be a significant technical effort required and based on the present test schedule it would not be possible to accomplish such a change in the time frame requested in Reference 1. Such an effort would significantly dilute our efforts to complete the new larger test facility described in the next paragraph in an appropriate time frame.
GENERAL " ELECTRIC U. S. Nuclear Regulatory Commission Attn: Mr. Victor Stello, Jr.
October 24, 1977 Page 2
- 2. Since the submittal of the subject Amendment, GE has put in place a program to build a full scale test facility which is representative of the design of larger BMR plants. This facility will consist of a 30 sector of the reactor with core spray spargers and non-heated bundles. The facility will have the capability to provide a steam environment and will be constructed at a GE site in Lynn, Massachusetts where a sufficient steam source is available. This facility will provide the information to resolve item 3 of Table 1-2 of the NRC Staff Safety Evaluation Report (SER) for the 251 and 238 NSSS GESSAR, and item VII of Table 1-2 of the 238 NI GESSAR SER. The results of the tests from this facility will.be much more applicable to the core spray configuration of the larger, later design BMR.
Therefore, it would be more efficient and productive to direct the resources of GE and the staff toward the completion of testing in the new full scale facility. Toward this end, GE has been discussing the test facility and test programs with the Oivision of Reactor Safety Research (RSR) of the Office of Nuclear Regulatory Research (NRR) and the Electrical Power Research Institute (EPRI) to determine the extent of their participation in this program. As presently foreseen, the facility will be started up in late 1978 with significant results expected by the middle of 1979. This effort is also supported by other programs presently underway and planned on single and multiple nozzle tests in smaller scale facilities. Single full scale heated bundle tests will also be performed which will provide supportive information for the full scale test program.
GE agrees that it is appropriate to acquire additional experimental information about this phenomenon. However, there should be no urgency associated with any such effort. It is important to note that the presently approved Loss Of Coolant Accident (LOCA) Evaluation Model requires that the Counter Current Flow Limiting (CCFL) phenomenon be accounted for. Our current approved model shows that subsequent to actuation of the Emergency Core Cooling Systems (ECCS) the flow to the top of the fuel bundles is limited by CCFL resulting in a buildup of water inventory above the top of the core and any concerns about the effects of core spray distribution become moot. If in consideration of this concern, one were to assume that CCFL does not occur, or breaks down shortly after the ECCS are actuated, the spray water then rapidly passes through the core to the lower plenum. For the case where calculated peak cladding temperature is. limited by reflooding, the criteria of 10CFR50.46 are satisfied even without taking credit for any core spray heat transfer during that time. Again, any concerns about the effects of core spray distribution become moot.
GER ERAL O ELECTRIC U. S. Nuclear Regulatory Commission Attn: Mr. Victor Stello, Jr.
October 24, 1977 Page 3 Based on the information presented herein, there should be no immediate safety concern with regard to core spray distribution. It would also .
appear that as a result of the test programs described herein, that more directly applicable data can be expected in the near future. To keep the staff continually apprised on this subject, it is proposed that a series of meetings be scheduled with GE personnel on an appropriate schedule. Formal reports to the staff would be provided as soon as the data from the new facility are available. Progress reports would be made in routine fashion as a result ot RSR and EPRI participation in the operation of the new facility. Therefore, it is more appropriate and significant to respond to Reference 2 at a later date when data from the new facility is available. A schedule for response is to be at some mutually agreeable time.
If you require any further information, please contact A. J. Levine, (408) 925-3217 of my staff.
Sincerely, saA~<
Safety and Licensing Operation GGS:csc/1C cc: L. S. Gifford (GE-Bethesda)
- 0. D. Parr (NRC)
R. Moods (NRC)