|
---|
Category:Inspection Plan
MONTHYEARIR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) IR 05000387/20220052022-08-31031 August 2022 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2022005 and 05000388/2022005) IR 05000387/20210062022-03-0202 March 2022 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2021006 and 05000388/2021006) ML22041A1562022-02-10010 February 2022 Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000387/2022013 and 05000388/2022013 ML21312A1012021-11-0808 November 2021 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000387/2022011 ML21236A2662021-11-0808 November 2021 Ti 2515/194 Inspection Documentation Request IR 05000387/20210052021-09-0101 September 2021 Updated Inspection Plan for the Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2021005 and 05000388/2021005) ML21210A2232021-07-29029 July 2021 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000387/2021010 and 05000388/2021010 IR 05000387/20200062021-03-0303 March 2021 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2020006 and 05000388/2020006) IR 05000387/20200052020-08-31031 August 2020 Updated Inspection Plan (Inspection Reports 05000387/2020005 and 05000388/2020005) ML20149K4492020-05-28028 May 2020 Notification of Conduct of a Fire Protection Team Inspection IR 05000387/20190062020-03-0303 March 2020 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2019006 and 05000388/2019006) ML20056E4392020-02-21021 February 2020 Ti 2515/194 Inspection Documentation Request IR 05000387/20190052019-08-28028 August 2019 Updated Inspection Plan (Inspection Reports 05000387/2019005 and 05000388/2019005) ML19191A0652019-07-10010 July 2019 Information Request for Triennial Baseline Design Bases Assurance Inspection (Team); Notification to Perform Inspection 05000387/2019011 and 05000388/2019011 IR 05000387/20180062019-03-0404 March 2019 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2018006 and 05000388/2018006) IR 05000387/20180052018-08-28028 August 2018 Updated Inspection Plan (Inspection Report 05000387/2018005 and 05000388/2018005) IR 05000387/20170062018-02-28028 February 2018 Annual Assessment Letter for Susquehanna Units 1 and 2 (Report 05000387-2017006 and 05000388-2017006 Report 05000387-2017402 and 05000388-2017402 Report 05000387-2017501 and 05000388-2017501) IR 05000387/20170052017-08-28028 August 2017 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 Letter with Report 22 (Report 05000387/2017005 and 05000388/2017005) IR 05000387/20160062017-03-0101 March 2017 Annual Assessment Letter for Susquehanna Units 1 and 2 Report Nos. 05000387/2016006 and 05000388/2016006 IR 05000387/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2, (Report 05000387/2016005 and 05000388/2016005) IR 05000387/20150062016-03-0202 March 2016 ROP 16 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Inspection Report 05000387/2015006 and 05000388/2015006) IR 05000387/20150052015-09-0101 September 2015 ROP-16 Mid-Cycle Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2015005 and 05000388/2015005) IR 05000387/20140012015-03-0404 March 2015 ROP 15 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2014001 and 05000388/2014001) IR 05000387/20140062014-09-0202 September 2014 ROP-15 Mid-Cycle Performance Review and Inspection Plan Report 05000387-14-006 and 0500388-14-006 IR 05000387/20130012014-03-0404 March 2014 ROP-14 2013 Susquehanna Steam Electric Station, Units 1 & 2, Annual Assessment Letter for Report 05000387/2013001 and 05000388/2013001 and Inspection Plan IR 05000387/20130062013-09-0303 September 2013 Mid-cycle Performance Review and Inspection Plan Report 05000387-13-006 and 05000388-13-006 IR 05000387/20120012013-03-0404 March 2013 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2012001 and 05000388-12-001) IR 05000387/20120062012-09-0404 September 2012 Mid-Cycle Performance Review and Inspection Plan 2012 - Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2012006 and 05000388/2012006) IR 05000387/20110012012-03-0101 March 2012 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2011001 and 05000388/2011001) ML1124304692011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plan 2011 - Susquehanna Steam Electric Station, Units 1 and 2 IR 05000387/20100012011-03-0404 March 2011 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2, EOC-11 (Report 05000387/2010001 and 05000388/2010001) ML1024404622010-09-0101 September 2010 IR 05000387-10-001 and 05000388-10-001 on 08/11/2010 for Susquehanna Steam Electric Station, Units 1 & 2, Mid-Cycle Assessment Letter 2010 ML1006210392010-03-0303 March 2010 Annual Assessment Letter - Susquehanna Steam Electric Station, Units 1 and 2 (05000387-10-001 and 05000388-10-001) ML0924402702009-09-0101 September 2009 Mid-Cycle Performance Assessment Letter - Susquehanna Steam Electric Station IR 05000387/20090012009-03-0404 March 2009 Annual Assessment Letter - Susquehanna Steam Electric Station (05000387-09-001 and 05000388-09-001) ML0824704642008-09-0202 September 2008 2008 Mid-Cycle Performance Assessment Letter - Susquehanna ML0734707322007-12-13013 December 2007 ROP 8 - Susquehanna - Change to Inspection Plan, 12/13/07 ML0724306552007-08-31031 August 2007 Mid-Cycle Performance Review and Inspection Plan, for 07/01/2007 - 12/31/2008 IR 05000387/20070012007-03-0202 March 2007 Annual Assessment Letter - Susquehanna Steam Electric Station (Report 05000387/2007001 and 05000388/2007001) ML0624305252006-08-31031 August 2006 Mid-cycle Performance Review and Inspection Plan - Susquehanna Steam Electric Station ML0606204502006-03-0202 March 2006 2006-001 - Annual Assessment Letter - Susquehanna Steam Electric Station (Report 05-387/2006001 and 05-388/2006001) ML0524207002005-08-30030 August 2005 2005 Mid-Cycle Review and Inspection Plan - Susquehanna ML0718301432005-03-14014 March 2005 CH-ER-314, Rev 1, SSES Environmental Inspection Plan Procedure. IR 05000387/20050012005-03-0202 March 2005 Annual Assessment Letter for 05000387-05-001 and 05000388-05-001 2024-08-29
[Table view] Category:Letter
MONTHYEARPLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) 2024-09-04
[Table view] |
See also: IR 05000387/2021010
Text
July 29, 2021
Mr. Brad Berryman
President and Chief Nuclear Officer
Susquehanna Nuclear, LLC
769 Salem Blvd., NUCSB3
Berwick, PA 18603
SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
INFORMATION REQUEST TO SUPPORT TRIENNIAL BASELINE DESIGN-
BASIS CAPABILITY OF POWER-OPERATED VALVES INSPECTION;
INSPECTION REPORT 05000387/2021010 AND 05000388/2021010
Dear Mr. Berryman:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a team inspection at Susquehanna Steam Electric Station, Units 1
and 2. David Kern, a Senior Reactor Inspector from the NRCs Region I Office, will lead the
inspection team. The inspection will be conducted in accordance with Inspection Procedure
71111.21N.02, Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a
Requirements, dated October 9, 2020 (ADAMS Accession No. ML 20220A667).
The inspection will assess the reliability, functional capability, and design bases of risk-important
power-operated valves (POVs) as required by Title 10 of the Code of Federal Regulations
(10 CFR) 50.55a, and Appendix A and B requirements. The inspectors will select a sample of
POVs based on risk insights, safety significance, and operating margin.
During a telephone conversation on July 30, 2020, with Mr. Shane Jurek, Senior Licensing
Engineer, we confirmed arrangements for an information gathering visit and the two-week onsite
inspection. Depending on site access conditions, the information gathering visit may be onsite
or may be performed remotely. The schedule is as follows:
- Information gathering visit: Week of August 16
- Onsite weeks: Weeks of November 1 and November 15
The purpose of the information gathering visit is to meet with members of your staff and to
become familiar with your programs and procedures intended to ensure compliance with 10
CFR 50.55a for POVs. The lead inspector will discuss aspects of the programs including any
specific applicable regulatory commitments made by your facility and your use of NRC
Regulatory Guides or industry standards. Frank Arner, a Region I Senior Risk Analyst, will
support David Kern during the information-gathering visit to review probabilistic risk assessment
data and identify the final POV samples to be examined during the inspection.
B. Berryman 2
Experience with previous design basis team inspections of similar depth and length has shown
this type of inspection is resource intensive, both for NRC inspectors and licensee staff. In
order to minimize the inspection impact on the site and to ensure a productive inspection for
both parties, we have enclosed a request for information needed for the inspection.
It is important that all of these documents are up-to-date and complete in order to minimize the
number of additional documents requested during the preparation and onsite portions of the
inspection. Insofar as possible, this information should be provided electronically to the lead
inspector at the NRC Region I Office by August 16, 2021. Recognizing the timeframe, my staff
will work with your staff to prioritize our document requests so these activities can be
accomplished, as much as possible, in the normal course of your activities. Additional
documents may be requested during the information gathering visit and/or during team
preparation week (the week prior to the first onsite inspection week). The inspectors will
minimize your administrative burden by specifically identifying only those documents required
for the inspection.
If there are any questions about the inspection or the material requested in the enclosure,
please contact the lead inspector at 610-337-6931 or via e-mail at David.Kern@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, Control Number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget Control Number.
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
Digitally signed by
Melvin K. Melvin K. Gray
Date: 2021.07.29
Gray 13:03:23 -04'00'
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
Docket Nos. 05000387 and 05000388
License Nos. NPF-14 and NPF-22
Enclosure:
Document Request for Design Bases
Assurance Inspection
cc: Distribution via ListServ
ML21210A223
X Non-Sensitive X Publicly Available
X SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DORS RI/DORS
NAME DKern MGray
DATE 7/28/21 7/29/21
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
Inspection Report: 05000387/2021010 and 05000388/2021010
Onsite Inspection Dates: November 1 through November 5, 2021; and
November 15 through November 19, 2021
Inspection Procedure: Inspection Procedure 71111.21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a Requirements
Lead Inspector: David Kern, Senior Reactor Inspector
610-337-6931
David.Kern@nrc.gov
I. Information Gathering Visit
During this visit, we plan to obtain sufficient insights to finalize power-operated valve (POV)
samples for this inspection. We would like to meet with POV specialists to discuss the
upcoming inspection and our sample selection process. The primary valve types to be
reviewed for this inspection include motor-operated valves (MOVs) and air-operated valves
(AOVs); and additional valve types include hydraulic-operated valves (HOVs), solenoid-
operated valves (SOVs), and pyrotechnic-actuated (squib) valves. During this visit, the lead
inspector will: (a) discuss the scope of the planned inspection; (b) identify additional
information needed to review in preparation for the inspection; (c) ensure that the
information to be reviewed is available at the beginning of the inspection; and (d) verify that
logistical issues will be identified and addressed prior to the teams arrival. Depending on
the local COVID environment and potential travel restrictions, this visit may be either onsite
or performed remotely through a series of skype video calls. If performed onsite, please
reserve a room during the site visit with a telephone, wireless internet access, and a
licensee computer with access to procedures, corrective action program documents, and a
printer.
II. Information Requested for Selection of Power-Operated Valves
The following information is requested by August 16, 2021, to facilitate inspection
preparation. Feel free to contact the lead inspector if you have any questions regarding this
information request. Please provide the information electronically in pdf files, Excel, or
other searchable formats, preferably on some portable electronic media (e.g., CD-ROM,
DVD). The files should contain descriptive names, and be indexed and hyperlinked to
facilitate ease of use. Information in lists should contain enough information to be easily
understood by someone who has knowledge of light water reactor technology and POVs.
1. A word-searchable Updated Final Safety Analysis Report. If not available in a single file
for each unit, please ensure a collective table of contents is provided.
2. Site (and corporate if applicable) procedures associated with implementation of the MOV
program required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory
Appendix III; and site (corporate) procedure for AOV program.
Enclosure
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
3. Site response(s) to NRC Generic Letter (GL) 95-07, Pressure Locking and Thermal
Binding of Safety-Related Power-Operated Gate Valves.
4. Site response(s) to NRC GL 96-05, Periodic Verification of Design-Basis Capability of
Safety-Related Motor-Operated Valves.
5. Site evaluation of NRC Information Notice 2012-14, MOV Inoperable due to Stem-Disc
Separation.
6. List of corrective action documents related to the MOV and AOV programs since
November 1, 2016 (include document No., title/short description, date).
7. List of corrective action documents related to each of the 30 POVs listed below since
November 1, 2016 (include document No., title/short description, date).
8. List of significant modifications, repairs, or replacement of safety-related POVs
completed since November 1, 2016, including date completed (include document No.,
title, date completed).
9. List of POVs removed from the In-Service Test program since January 1, 1990.
10. Any self-assessments or quality assurance type assessments of the MOV/AOV
programs (performed since November 1, 2016).
11. Most recent POV (e.g., MOV, AOV, SOV) program health report(s).
12. List and electronic copy of all Emergency Operating Procedures.
13. List of Abnormal Operating Procedures.
14. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
(OM Code) that is the Code of Record for the current 10-year Inservice Test Program
interval, as well as any standards to which the station has committed with respect to
POV capability and testing.
15. For each of the following MOVs, provide the information listed in the table below.
HV01222B Residual Heat Removal Service Water - UHS Spray Bypass Isolation
Valve
HV112F073A Residual Heat Removal Service Water - RHR/RHRSW Loop A
Crosstie Valve
HV149F007 RCIC Turbine Pump - RCIS Turbine Steam Supply Inboard Isolation
Valve
HV151F004A Residual Heat Removal - RHR Pump A Suppression Pool Suction
Valve
HV151F016B Residual Heat Removal - RHR Loop B Drywell Spray Outboard
Isolation Valve
HV151F028A Residual Heat Removal - RHR Loop A Suppression Pool Spray Test
Shutoff Valve
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
HV155F003 High Pressure Core Spray - HPCI Turb Steam Supply Outboard
Isolation Valve
HV155F003 High Pressure Core Spray - HPCI Turb Steam Supply Outboard
Isolation Valve
HV155F079 High Pressure Core Spray - HPCI Turb Exhaust Inboard Vac Breaker
Valve
HV21210A Residual Heat Removal Service Water - RHR HX A SW Supply
Isolation Valve
HV249F013 RCIC Turbine Pump - RCIC Injection Valve
HV250F045 RCIC Turbine Pump - RCIC Turbine Steam Supply Valve
HV250F046 RCIC Turbine Pump - RCIC Lube Oil Cooler Water Supply Valve
HV251F015B Residual Heat Removal - RHR Loop B Injection Outboard Isolation
Valve
HV251F021A Residual Heat Removal - RHR Loop A Drywell Spray Inboard
Isolation Valve
HV251F024B Residual Heat Removal - RHR Loop B Supp Pool Cooling/Test
Control Valve
HV251F048B Residual Heat Removal - RHR HX B Shell Side Bypass Valve
HV255F001 Residual Heat Removal - HPCI Turb Steam Supply Valve
HV255F006 High Pressure Core Spray - HPCI Injection Valve
HV255F042 High Pressure Core Spray - HPCI Pump Suction Suppression Pool
Supply Valve
Item Parameter/Information*
1 MOV Identification
2 Safety Function
3 Valve manufacturer, type, and size
4 Actuator manufacturer, type, and size
5 Motor manufacturer, type (AC/DC), and size
6 Valve ASME Class
7 Risk Significance
8 Control Switch Trip (CST) Application (Close/Open)
9 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)
10 Rising-Stem Valve: Assumed Valve Factor (VF)
11 Quarter-Turn Valve: Assumed bearing torque coefficient
12 Assumed Stem Friction Coefficient (SFC)
13 Assumed Load Sensitive Behavior (LSB) (%)
14 % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)
15 Calculated Required Thrust/Torque (Close/Open)
16 Least Available Output (e.g., actuator, CST, rating, spring pack, weak link)
17 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,
and temperature; ambient temperature; and motor voltage) (Close/Open)
18 Thrust and torque required to overcome dynamic conditions (Close/Open)
19 Rising-Stem Valve: Measured VF (Close/Open)
20 Rising-Stem Valve: Available VF (Close/Open)
21 Measured SFC (Close/Open)
22 Measured LSB (%)
23 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)
24 Determined % Margin (Close/Open)
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
25 Basis for Design-Basis Capability:
25.a Dynamic test performed at design-basis DP/flow conditions
25.b Extrapolation of dynamic test data
25.c Justification from normal operation at or above design-basis conditions
25.d Industry dynamic test methodology (such as EPRI MOV PPM)
25.e Grouped with similar valves dynamically tested at plant
25.f Grouped with similar valves dynamically tested at other plants
25.g Valve qualification testing (such as ASME QME-1-2007)
25.h Other (such as large calculated margin)
- Specify Not Applicable (NA) as appropriate
16. For each of the following AOVs/SOVs/HOVs, provide the information listed in the table
below.
HV141F022A Main Steam - "A" Main Steam Line Inboard Isolation Valve
HV141F028D Main Steam - "D" Main Steam Line Outboard Isolation Valve
HV16108A1 Liquid Rad Waste - Drywell Floor Drain Sump Pump Discharge
Isolation Valve
HV16116A2 Liquid Rad Waste - Drywell Equipment Drain Tank Discharge Isolation
Valve
HV18792B2 Reactor Building Chill Water - RRP A Cooling Water Inboard Isolation
Reactor Building Chilled Water Return
HV25703 Liquid Rad Waste - Suppression Chamber Purge Exhaust Upstream
Isolation Valve
HV25723 Containment Atmosphere Control - Drywell Air Purge Isolation Valve
SV12654A Containment Instrument Gas - I-G to Main Steam PSV1F013 GJM
TV01124E Emergency Service Water - DG E ESW Loop B Return Temperature
Control Valve
XV247F010A Control Rod Drive Hydraulic - CRD SDV Vent Valve
XV247F010B Control Rod Drive Hydraulic - CRD SDV Vent Valve
Item Parameter/Information*
1 AOV Identification
2 Safety Function
3 Fail safe position (open/close)
4 Valve manufacturer, type, and size
5 Actuator manufacturer, type, and size
6 Valve ASME Class
7 Risk Significance
8 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)
9 Rising-Stem Valve: Assumed Valve Factor (VF)
10 Quarter-Turn Valve: Assumed bearing torque coefficient
11 % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)
12 Calculated Required Thrust/Torque (Close/Open)
13 Minimum allowable air pressure (Beginning/End Stroke)
14 Maximum allowable air pressure (Beginning/End Stroke)
15 Minimum allowable spring preload (Beginning/End Stroke)
16 Maximum allowable spring preload (Beginning/End Stroke)
DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION
17 Least Available Actuator Output (e.g., actuator capability, actuator limit, valve
weak link limitation)
18 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,
and temperature; and ambient temperature) (Close/Open)
19 Thrust and torque required to overcome dynamic conditions (Close/Open)
20 Rising-Stem Valve: Measured VF (Close/Open)
21 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)
22 Determined Margin (%) (Least margin for air stroke operation, spring stroke
operation, maximum spring load, and structural capability)
23 Basis for Design-Basis Capability:
24.a Dynamic test performed at design-basis DP/flow conditions
24.b Extrapolation of dynamic test data
24.c Justification from normal operation at or above design-basis conditions
24.d Industry dynamic test methodology
24.e Grouped with similar valves dynamically tested at plant
24.f Grouped with similar valves dynamically tested at other plants
24.g Valve qualification testing (such as ASME QME-1-2007)
24.h Other (such as large calculated margin)
- Specify Not Applicable (NA) as appropriate