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Category:Letter
MONTHYEARIR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection 2024-09-24
[Table view] Category:Technical Specifications
MONTHYEARML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20325A0952021-03-19019 March 2021 Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary) ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology ML19238A1272019-09-12012 September 2019 Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19156A2072019-05-24024 May 2019 Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01 ML17187A1322017-06-28028 June 2017 Submittal of Topical Report VEP-NE-1, Revision 0.2-A, Relaxed Power Distribution Control Methodology and Associated Fq Surveillance Technical Specifications for Information Only ML16252A4782016-10-17017 October 2016 Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0 ML16013A4442016-02-22022 February 2016 (NAPS) - Issuance of Amendment for Changes to Technical Specification (TS) 3.8.1 - AC Sources, Operating Revised Surveillance Requirement ML15307A3002016-02-0202 February 2016 (NAPS) - Issuance of Amendments for Changes to the Emergency Action Level Revisions - Correction of Equipment Mark Number ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15133A3812015-06-16016 June 2015 Issuance of Amendments to Extended Type a Test Frequency to 15 Years ML15147A0292015-05-22022 May 2015 Proposed License Amendment Request (Lar), TS 3.8.1 - AC Sources - Operating, Revised Surveillance Requirement ML15083A4362015-05-14014 May 2015 Issuance of Amendments Regarding Alternate Control Rod Position Monitoring ML15041A6672015-02-0404 February 2015 Proposed License Amendment Request Re Alternate Control Rod Position Monitoring ML14188C4532014-08-27027 August 2014 Issuance of Amendments Regarding Modification of Control Bank Sequence and Overlap Technical Specifications ML14169A3592014-08-12012 August 2014 Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality ML14183B3182014-06-30030 June 2014 Proposed License Amendment Request Permanent Fifteen-Year Type a Test Interval ML13302B8922013-10-0202 October 2013 Technical Specification Bases ML12356A2982012-12-13013 December 2012 Supplemental Information for Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process. ML12219A0722012-07-30030 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12136A4512012-05-11011 May 2012 Proposed License Amendment Request - Temporary Change to Allow Two Inoperable Demand Position Indicators Per Control Bank PLA-6842, Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 2812012-04-0202 April 2012 Response to E-mail (Dated March 30, 2012), Request for Additional Information on Proposed Amendment Number 281 ML1111900932011-04-27027 April 2011 License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation. ML1029804472010-10-21021 October 2010 Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) ML0935004002010-03-0303 March 2010 Issuance of Amendments to Adopt TSTF-490, Revision 0, Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Using the Consolidated Line Item Improvement Process ML0920503812009-07-23023 July 2009 License Amendment Request, One Time Extension of the Completion Time for 1 J - 480 Volt AC Distribution Subsystem ML0909000552009-03-26026 March 2009 License Amendment Request, Measurement Uncertainty Recapture Power Uprate ML0904004652009-02-0606 February 2009 License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Work Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0815106502008-06-30030 June 2008 Technical Specifications, Issuance of Amendment Regarding One-Time 5-Year Extension to Type a Test Interval ML0735202472007-12-17017 December 2007 Proposed License Amendment Request, One-time Risk-Informed Extension to the Completion Time for EDG Fuel Oil Storage Tank Recoating ML0730604062007-10-31031 October 2007 Tech Spec Pages for Amendments 252 and 232 Control Room Habitability, Using the Technical Specification Task Force Traveler, TSTF-448, Revision 3 ML0730304002007-10-17017 October 2007 Tech Pages for Amendments 251 and 231 Technical Specification Change to Add Limiting Condition for Operation 3.0.8 on the Inoperability of Snubbers, Using the Consolidated Line Item Improvement Process, TSTF-372, Rev 4 ML0715001452007-05-29029 May 2007 Proposed License Amendment Request, Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0714104632007-05-21021 May 2007 Proposed License Amendment Request Addition of LCO 3.0.8 - Inoperability of Snubbers Using the Consolidated Line Item Improvement Process Technical Specification Improvement ML0702202192007-01-19019 January 2007 Technical Specifications Corrected Page for Amendment Nos. 249 and 229 ML0701003492007-01-0909 January 2007 Technical Specifications, Relocated the ASTM Standard Used to Test the Total Particulate Concentration of the Stored Fuel Oil from TS 5.5.12, Emergency Diesel Generator Fuel Oil Testing Program to a Licensee-controlled Program ML0634502592006-12-11011 December 2006 Tech Spec Pages for Amendments 249 and 229 Regarding Diesel Fuel Oil Testing Program ML0630000282006-10-16016 October 2006 Tech Spec Pages for Amendments 248 and 228 Regarding Consolidated Line Item Improvement Process for the Steam Generator Tube Integrity ML0627700182006-09-25025 September 2006 Technical Specification Bases Pages ML0620604672006-07-18018 July 2006 Technical Specifications, Issuance of Amendments on Changes to Analytical Methodology and Core Operating Limits Report, MC7526 and MC7527 ML0615101992006-05-30030 May 2006 Proposed Technical Specifications Change Diesel Fuel Oil Testing Program ML0533502792005-11-21021 November 2005 10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency ML0529900852005-10-25025 October 2005 Enclosure, Technical Specifications, Amd MC7612, Equation for Over-Temperature Delta T Function Allowable Value ML0529900152005-10-24024 October 2005 Technical Specifications, Revised Test Frequency of P-4 Interlock Function ML0526301042005-09-15015 September 2005 Tech Spec Pages for Amendment Nos. 243 and 224, Revise the Administrative Controls Section ML0519604352005-07-14014 July 2005 Proposed Technical Specification Changes Correction to Equation for Overtemperature T Function Allowable Value ML0518900342005-07-0505 July 2005 Proposed Technical Specification Changes Addition of Analytical Methodology to COLR 2023-05-01
[Table view] |
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I VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 21, 2005 U.S. Nuclear Regulatory Commission Serial No.05-742 Attention: Document Control Desk NL&OS/ETS RD Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 10 CFR 50.9 CORRECTION OF INFORMATION PROVIDED TO SUPPORT TECHNICAL SPECIFICATION CHANGE FOR QUENCH SPRAY AND RECIRCULATION SPRAY NOZZLES SURVEILLANCE FREQUENCY In a February 26, 2002 letter (Serial No.02-124), Virginia Electric and Power Company (Dominion) requested amendments, in the form. of changes to the Technical Specifications to Facility Operating Licenses Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively. The proposed changes revised the surveillance frequency of the Quench Spray and Recirculation Spray System spray header nozzles from a periodic surveillance to a performance-based surveillance. The NRC approved the proposed amendments on October 1, 2002, as amendments 233 and 215 for Units 1 and 2, respectively.
During the review of the proposed changes, the NRC staff requested additional information to complete their review of the proposed amendments. This included information on pre-operational testing performed on the spray headers. Dominion provided the requested information in a July 15, 2002 letter (Serial No.02-452). During a recent review of the pre-operational testing, which was completed to support ongoing maintenance activities on Unit 2, it was identified that each recirculation spray header was not completely full-flow tested on Unit 2 as identified in the July 15, 2002 response.
The attachment to this letter provides the corrected pre-operational test information and details of the recent inspection and testing activities performed by Dominion to ensure the spray headers were free of any significant debris. These inspection activities support the initial conclusion provided in the Dominion amendment request that the recirculation spray headers were free of debris that could have significantly reduced their capability to perform their intended safety function. Mr. D. A. Sommers of Dominion discussed this issue with Mr. K. D. Landis of Region II on October 21, 2005 and Mr. S. R. Monarque of NRR on October 24, 2005.
The results of the inspection activities for the spray system headers are included in the attachment to this letter. If you have any further questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.
Very truly yours, Leslie N. Hartz Vice President - Nuclear Engineering Attachment Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center Suite 23T85 61 Forsyth Street, SW Atlanta, Georgia 30303 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, VA 23218 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8-H12 Rockville, Maryland 20852
r
Subject:
10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz who is Vice President - Nuclear Engineering of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.
Acknowledged before me this ;1 day of 22z " 4-., 2005.
My Commission Expires: Z 3f O8.
e Notary fublic
Attachment 10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency North Anna Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion)
10 CFR 50.9 Correction of Information Provided to Support Technical Specification Change for Quench Spray and Recirculation Spray Nozzles Surveillance Frequency NRC Question 2 from July 15, 2002 letter:
"Experience at D. C. Cook, Units 1 and 2 (LER 98-027-02) indicates that the typical test for blockage in the containment spray lines and nozzles may not be effective in detecting debris in the spray lines at the amounts reported in this LER.
Please indicate if your testing records show any evidence that the containment spray flow blockage test may have a sensitivity to debris in the lines or nozzles, which cannot be detected by this test. For example, has construction debris or other debris been found in the containment spray system from later inspections, tests or repair work that was not discovered by the containment spray system blockage test required by your technical specifications?"
Dominion July 17, 2002 Response to Question 2:
UFSAR Sections 6.2.2.4.1 and 6.2.2.4.2 describe testing and inspections performed on the Quench Spray (QS) and Recirculation Spray (RS) subsystems. A partial description of the testing performed on each system is provided below.
Following installation of the QS subsystems, temporary drain lines were connected to blind flanges and pipe plugs were placed in the spray nozzle sockets. The QS pumps were started and water was circulated through the spray header supply lines to the spray headers and out the temporary drain connections. This pre-operational testing provided a full system capability test and provided a complete system flush to remove all particulate matter prior to installation of the spray nozzles. At the completion of this testing, the temporary drain lines were removed, blind flanges were replaced, pipe plugs removed, and the spray nozzles were installed. After installation of the nozzles, a nozzle air test was conducted and verified that the spray nozzles remained unobstructed after the full-flow testing. The QS system pre-operational flow and air/smoke tests established that the QS spray headers and spray nozzles were free of debris.
A pre-operational, full-flow system test was performed with water on the RS subsystems. With the spray nozzle sockets plugged, permanently installed spray header drain lines running between the spray nozzle headers and the containment sump were temporarily connected. Water was then added to the containment sump, surrounded by a portable dike so that each RS pump could circulate water up through its respective heat exchanger and spray nozzle headers. The full flow test through the shell side of each RS heat exchanger ensured that the required flow and head for effective spray nozzle operation and system operation was achieved. This testing also Page 1 of 5
provided a complete system flush to remove all particulate matter prior to installation of the spray nozzles. Upon completion of the system test, water was drained, temporary connections were removed and the spray nozzles were installed. A nozzle air test was conducted and verified that the spray nozzles remained unobstructed after the full-flow testing. The RS system pre-operational flow and air/smoke tests established that the RS spray headers and spray nozzles were free of debris.
Based on this pre-operational testing, it is assumed that construction debris was removed from the QS and RS systems prior to declaring them operable. Subsequent 10-year air/smoke tests performed to date have not identified any nozzle blockage caused by debris in the spray ring headers. These air tests are performed with station service air, which provides air at approximately 100 psig, to verify the nozzles are unobstructed.
Since the original pre-operational testing, the QS and RS spray ring headers have not been opened for maintenance, inspection, or testing. Therefore, we have not identified any additional construction debris in the spray headers during maintenance or testing of the spray system headers and nozzles.
Corrected information:
During a recent review of the pre-operational testing completed for the spray systems to support ongoing maintenance activities, it was identified that not each recirculation spray header in Unit 2 was completely full-flow tested as identified in our July 15, 2002 response. Since only one of the two downcomers was aligned on each spray header, only half of each spray header was flowed during pre-operational testing. When this inconsistency was identified, actions were taken to ensure that the spray headers were free of debris that could potentially cause nozzle blockage that would reduce the spray systems' ability to reduce containment pressure and temperature. The inspection activities included:
- A boroscope inspection of the portions of the Unit 2 RS spray headers that were not full flow tested. This included the spray headers - pipe segment 8"-RS-420-153A-Q2, 8"-RS-421-1 53A-Q2, 8"-RS-422-1 53A-Q2, and 8"-RS-423-1 53A-Q2 (see attached drawings). Experienced engineering, operations, and project management personnel performed the inspections. There was not significant debris identified in the spray array piping. See attached pictures.
- A portion of the pipe that was inspected was also vacuumed to obtain a sample of the dust observed in the spray headers. The dust would not have affected the operation of the spray arrays.
- An air flow test of RS spray headers was successfully performed with no indications of any obstructed spray nozzles.
- Unit 1 RS pre-operational testing was reviewed to re-verify that the entire spray headers were flow tested. They had been completely flow tested.
Page 2 of 5
- Unit 1 and 2 pre-operational testing of the QS System was reviewed to re-verify that the entire spray headers were flow tested.
None of the original records indicated debris in the containment spray system nor did any of the pre-operational test results indicate any reduced system flow; however, foreign material was discovered on the top of the inlet tube sheets in the recirculation spray heat exchangers (RSHXs) of Units 1 and 2 during last refueling outages in October 2004 and 2005, respectively. The debris found was assessed to be construction related. The foreign material was removed from the shells of all RSHXs to the extent practical due to limited access into and within the RSHXs. Assessments of the "as found" and "as left" condition of the RSHXs was performed for Units land 2. It was determined that the RSHXs remained capable of performing the Design Basis functions of the NAPS Units 1 and 2 Recirculation Spray Systems.
Although a portion of the Unit 2 RS spray headers were not flow tested during pre-operational testing, the RS spray headers were confirmed to be free of significant debris and capable of performing their intended safety function based on the inspection results. The inspection results continue to support the NRC's SER conclusion that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation (revised surveillance frequency of the spray headers) in the proposed manner, and (2) the activities continue to be conducted in accordance with the commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Page 3 of 5
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