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| {{Adams | | {{Adams |
| | number = ML13351A508 | | | number = ML13142A344 |
| | issue date = 12/17/2013 | | | issue date = 05/21/2013 |
| | title = Er 05000528/2013301; 05000529/2013301; 05000530/2013301; October 1 - November 20, 2013; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report | | | title = Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Notification of NRC Initial Operator Licensing Examination 05000528/13-301; 05000529/13-301; 05000530/13-301 |
| | author name = Gaddy V G | | | author name = Gaddy V G |
| | author affiliation = NRC/RGN-IV/DRS/OB | | | author affiliation = NRC/RGN-IV/DRS |
| | addressee name = Edington R K | | | addressee name = Edington R K |
| | addressee affiliation = Arizona Public Service Co | | | addressee affiliation = Arizona Public Service Co |
| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| | license number = NPF-041, NPF-051, NPF-074 | | | license number = NPF-041, NPF-051, NPF-074 |
| | contact person = Gaddy V G | | | contact person = |
| | document report number = 50-528/13-301, 50-529/13-301, 50-530/13-301 | | | document report number = 50-528/13-301, 50-529/13-301, 50-530/13-301 |
| | document type = Letter, License-Operator Examination Report | | | document type = Inspection Plan, Letter |
| | page count = 13 | | | page count = 3 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter: |
| [[Issue date::December 17, 2013]] | | [[Issue date::May 21, 2013]] |
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| Randall K. Edington, Executive Vice President, Nuclear/CNO | | Randall K. Edington, Executive Vice President, Nuclear/CNO |
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| Arizona Public Service Company P.O. Box 52034, Mail Stop 7602 Phoenix, AZ 85072-2034 | | Arizona Public Service Company P.O. Box 52034, Mail Stop 7602 Phoenix, AZ 85072-2034 |
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| SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NRC EXAMINATION REPORT 05000528/2013301; 05000529/2013301; | | SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NOTIFICATION OF NRC INITIAL OPERATOR LICENSING EXAMINATION 05000528/2013301; 05000529/2013301; 05000530/2013301 |
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| 05000530/2013301 | |
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| ==Dear Mr. Edington:== | | ==Dear Mr. Edington:== |
| On November 9, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on November 9, 2013, with Mr. B. Bement, Senior Vice President for Nuclear Operations, and other members of your staff. A telephonic exit meeting was conducted on November 20, 2013, with Mr. W. Potter, Simulator Support Section Leader, who was provided the NRC licensing decisions.
| | In a telephone conversation on April 11, 2013, between Messrs. W. Potter, Simulator Support Section Leader, and C. Steely, Chief Examiner, arrangements were made for the administration of licensing examinations at Palo Verde Nuclear Generating Station, Units 1, 2 and 3 during the week of November 4, 2013. |
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| The examination included the evaluation of eleven applicants for reactor operator licenses, eight applicants for instant senior reactor operator licenses, and six applicants for upgrade senior reactor operator licenses. The license examiners determined that all twenty five of the applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued. There was one post examination comment submitted by your staff. Enclosure 1 contains details of this report and Enclosure 2 summarizes post examination comment resolution. No findings were identified during this examination.
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
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| enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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| Sincerely,/RA/ Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74
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| ===Enclosures:===
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| 1. NRC Examination Report 05000528;05000529; 05000530/2013301, w/Attachment 2. NRC Review of PVNGS Written Post-Examination Comments
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| Electronic Distribution for Palo Verde Nuclear Generating Station Electronic distribution by RIV
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| : Regional Administrator (Marc.Dapas@nrc.gov)
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| Deputy Regional Administrator (Steven.Reynolds@nrc.gov) DRP Director (Kriss.Kennedy@nrc.gov) DRP Deputy Director (Troy.Pruett@nrc.gov)
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| DRS Director (Tom.Blount@nrc.gov)
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| DRS Deputy Director (Jeff.Clark@nrc.gov)
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| Senior Resident Inspector (Tony.Brown@nrc.gov)
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| Resident Inspector (John.Reynoso@nrc.gov)
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| Resident Inspector (Mica.Baquera@nrc.gov) Resident Inspector (Dustin.Reinert@nrc.gov)
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| Administrative Assistant (Revonna.Stuart@nrc.gov)
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| Branch Chief, DRP/A (Ryan.Lantz@nrc.gov)
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| Senior Project Engineer, DRP/A (Bob.Hagar@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov)
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| Project Manager (Balwant.Singal@nrc.gov)
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| Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov)
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| RITS Coordinator (Marisa.Herrera@nrc.gov)
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| ACES (R4Enforcement.Resource@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov)
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| Technical Support Assistant (Loretta.Williams@nrc.gov)
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| Congressional Affairs Officer (Jenny.Weil@nrc.gov)
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| RIV/ETA: OEDO (Brett.Rini@nrc.gov)
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| R:\_REACTORS\_PV\2013\PV 2013301 RP kdc.docx ML ML13351A508 SUNSI Review Completed: __KDC__ ADAMS: Yes No Initials: __KDC__
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| Publicly Available Non-Publicly Available Sensitive Non-Sensitive OE:OB OE:OB SOE:OB OE:OB OE:OB SPE: PB SHedger CSteely BLarson DStrickland CCowdrey MBloodgood /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ 12/16/13 12/16/13 12/13/13 12/16/13 12/16/13 12/16/13 OE:OB (R3) SOE:OB C: PBA C:OB CMoore KClayton WWalker TFarnholts for VGaddy TBlount for
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| /RA/telecom
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| /RA/ /RA/ /RA/ 12/13/13 12/13/13 12/17/13 12/17/13 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION IV Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74 Report: 05000528/2013301; 05000529/2013301; 05000530/2013301 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Location: 5951 S. Wintersburg Road Tonopah, Arizona Dates: October 1 - November 20, 2013 Inspectors: K. Clayton, Senior Operations Engineer B. Larson, Senior Operations Engineer C. Steely, Operations Engineer
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| S. Hedger, Operations Engineer D. Strickland, Operations Engineer C. Cowdrey, Operations Engineer M. Bloodgood, Senior Project Engineer (DRP)
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| C Moore, Operations Engineer (RIII) Approved by: Vincent Gaddy, Chief Operations Branch
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| Division of Reactor Safety
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| =SUMMARY OF FINDINGS=
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| ER 05000528/2013301; 05000529/2013301; 05000530/2013301; October 1 - November 20, 2013; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report.
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| NRC examiners evaluated the competency of el even applicants for reactor operator licenses, eight applicants for instant senior reactor operator licenses, and six applicants for upgrade senior reactor operator licenses at Palo Verde Nuclear Generating Station, Units 1, 2, and 3.
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| The licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the licensee on November 1, 2013. NRC examiners administered the operating tests the week of November 4, 2013.
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| The examiners determined that all 25 of the applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued.
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| ===A. NRC-Identified and Self-Revealing Findings===
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| None.
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| ===B. Licensee-Identified Violations===
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| None.
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| =REPORT DETAILS=
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| ==OTHER ACTIVITIES (OA)==
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| {{a|4OA5}}
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| ==4OA5 Other Activities (Initial Operator License Examination)==
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| ===.1 License Applications===
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| ====a. Scope====
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| NRC examiners reviewed all license applications submitted to ensure each applicant satisfied relevant license eligibility requirements. The examiners also audited four of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and on-the-job training, including control manipulations that provided significant reactivity changes. For the reactivity credits, the licensee had several credits (which were not used on the final applications) that did not meet the intent of the regulation for positive control of the reactor as evidenced with parameter changes and accurate logs for one and only one individual. There were several credits where numerous applicants were logged into the control room at the same time, which clearly does not meet the spirit of having one person signed in to the logs as an under-instruction watch-stander and that person performing the manipulation credit. The chief examiner asked the licensee to remove these credits from the final applications and use other control manipulation credits from the qualification cards that met the spirit of the regulation for this activity. The licensee completed these changes prior to final application submittal and wrote Condition Report PVAR 4477615 to capture this issue.
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| ====b. Findings====
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| No findings were identified.
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| ===.2 Examination Development===
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| ====a. Scope====
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| NRC examiners reviewed integrated examination outlines and draft examinations submitted by the licensee against the requirements of NUREG-1021. The NRC examination team conducted an onsite validation of the operating tests.
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| ====b. Findings====
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| No findings were identified.
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| NRC examiners provided outline, draft examination and post-validation comments to the licensee. The licensee satisfactorily completed comment resolution prior to examination administration.
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| NRC examiners determined that the written ex aminations initially submitted by the licensee were within the range of acceptability expected for a proposed examination.
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| The draft scenarios submitted required numerous changes due to overlap issues with the previous two NRC examinations. The licensee wrote Condition Report PVAR 4476184 to address this issue. Several critical tasks were not tied to physical parameters (not just procedure transitions) as required to meet the NUREG-1021 guidance. The licensee wrote Condition Report PVAR 4476152 to address this issue. There were several other examination development/administration issues that required condition reports and were rolled up in the previous two conditions reports listed above.
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| During examination validation, the NRC and licensee examination teams identified six procedure enhancement opportunities that were captured by Condition
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| Report PVAR 4480931.
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| ===.3 Operator Knowledge and Performance===
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| ====a. Scope====
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| On November 1, 2013, the licensee proctored the administration of the written examination for all 25 applicants, analyzed the results, and presented their analysis and post-examination comments to the NRC with a letter postmarked on November 14, 2013. These items were reviewed on November 18, 2013.
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| The NRC examination team administered the various portions of the operating tests to
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| all 25 applicants the week of November 4, 2013.
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| ====b. Findings====
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| No findings were identified.
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| All 25 of the applicants passed the written examination and all 25 passed all parts of the operating test. The final written examinations, final operating test, and post-examination analysis may be accessed in the ADAMS system under the accession numbers noted in the attachment, which includes one post-examination comment. There was one post-examination comment that requested a change to the answer key, Question 80, to which the NRC regional office accepted the recommended change and the answer key was changed accordingly. (See Enclosure 2 for a brief synopsis of the question, the comments, and the NRC resolution of these comments. The complete submittal can be found in the ADAMS system using accession number ML13343A136.)
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| The examination team noted the following generic weaknesses:
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| There were two questions missed by 50 percent or more of the applicants, with each question analyzed by the licensee as required by NUREG-1021. Both question weaknesses were determined to be knowledge weaknesses. The licensee wrote Condition Report PVAR 4479704 to address these weaknesses and the operating test
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| weaknesses.
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| Additionally, the licensee wrote Condition Report PVAR 4481035 to address the problem of general content issues with the examination. Specifically, the applicants
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| appeared to study old examination materials (such as events on previous scenarios and JPMs from the bank) and then tried to predict the direction or outcome of the task being administered. The licensee was informed that this methodology is not in accordance with the NRC standards or a systems approach to training and should be avoided.
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| Additionally, NUREG-1021 specifically limits the use of bank materials on the NRC examination because of the predictability of this practice. On page 1 of APPENDIX A, "OVERVIEW OF GENERIC EXAMINATION CONCEPTS," it states that:
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| "The internal attributes of the examination, such as its level of knowledge, level of difficulty, and use of item banks, also impact the operational and discriminatory validity of the examination, which, in turn, can affect its consistency and reliability. If the internal and external attributes of examinations are allowed to vary significantly, the uniform conditions that are required by Section 107 of the Atomic Energy Act of 1954, as amended, and the basis upon which the NRC's licensing decisions rest are challenged.
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| The NRC must reasonably control and structure the examination processes to ensure the integrity of the licenses it issues."
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| Furthermore, it states on page 10 of this same appendix in section C.3.e for "Use of
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| Item Banks" that:
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| "Test item banks are a valuable resource for learning and represent one fundamental basis for training and testing. However, it would be inappropriate to copy all or a significant portion of the items for an examination directly from the bank if the same items were previously used for testing or training. Test item banks must be used properly to maintain the validity, reliability, and consistency of the examinations.
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| Previously administered test items reduce examination integrity because examination discrimination is reduced." It also states below that paragraph that:
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| "Furthermore, when the bank of items from which the examination is drawn is known to the examinees prior to the examination, the examination is said to be highly predictable. Predictable examinations tend not to discriminate because what is being tested is simple recognition of the answer. Although studying past examinations can have a positive learning value, total predictability of examination coverage through over-reliance upon examination banks reduces examination integrity. When the examinees know the precise and limited pool from which test items will be drawn, they will tend only to study from that pool (i.e., studying to the test) and may likely exclude from study the larger domain of job knowledge. When this occurs, it decreases the confidence in the validity inferences that are made from performance on the test to that of the larger realm of knowledge or skill to be mastered."
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| ===.4 Simulation Facility Performance===
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| ====a. Scope====
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| The NRC examiners observed simulator performanc e with regard to plant fidelity during examination validation and administration. There were several minor simulator fidelity observations that did not impact scenario administration and are documented below as required by NUREG-1021. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with IP 71111.11, are not indicative of non-compliance with 10 CFR 55.46. The licensee wrote condition reports, listed with PVAR numbers, in the table below:
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| Item Description Condition Report #
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| Condensate pump "C" upper thrust bearing temp This temp exceeded the alarm setpoint of 194 degrees F during some scenarios. This was unplanned but did not impact the scenario administration PVAR 4476190 Containment temp and NCW outlet temp Simulator temperatures for Containment and NCW outlet for the running and idle CEDM ACUs need to be adjusted for better fidelity to Unit 1. This did not impact the scenario
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| administration. PVAR 4476190 SG Blowdown constants Blowdown constants on the simulator are different than Unit 1. This does not align
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| with Operator Information Aid for Appendix F of 40DP-9OP14. This did not impact the scenario administration.
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| Simulator discrepancy DRC 2013-3612 has been created. ERFDADS RCS leak rate The simulator ERFDADS RCS leak rate for a SGTL event appeared to change between morning and afternoon runs of the same scenario (8 gpm in the AM;
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| 5-6 gpm in the PM). This did not impact the scenario
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| administration.
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| PVAR 4476190 Multiple TCW alarms There were multiple B06 and B07 alarms that came fairly quickly after inserting the TCW sheared shaft malfunction. Need to verify that the timing of the alarms is appropriate for the condition. Need to verify amperage indication was appropriate on affected
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| pump motor.
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| PVAR 4477166 The NIS Control Channel gain adjustment
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| potentiometer The NIS Control Channel gain adjustment
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| potentiometer in Unit 1 is different than the simulators (One PVAR for simulator fidelity; one for Palo Verde's PVAR 4476283 PVAR 4476289 like-for-like component replacement process).
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| 2B SIT Tank Hi-Hi and Lo-Lo Pressure Alarm setpoints not correct This issue was found and fixed after validation week but prior to examination
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| administration week.
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| Simulator discrepancy DRC 2013-3591 was created
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| and fixed prior to examination administration
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| week.
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| ====b. Findings====
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| No findings were identified.
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| ===.5 Examination Security===
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| ====a. Scope====
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| The NRC examiners reviewed examination security during both the onsite preparation week and examination administration week for compliance with 10 CFR 55.49 and NUREG-1021. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
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| ====b. Findings====
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| No findings were identified.
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| {{a|4OA6}}
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| ==4OA6 Meetings, Including Exit==
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| The chief examiner presented the preliminary examination results to Mr. B. Bement, Site Vice President of Nuclear Operations, and other members of the staff on November 9, 2013. A telephonic exit was conducted on November 20, 2013, between Messrs. Kelly Clayton, Chief Examiner, and W. Potter, Simulator Support Section Leader.
| | As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1, and NUREG-1122, "Knowledge and Abilities Catalog for Nuclear Power Plant Operators," Revision 2, Supplement 1. The NRC's regional office will discuss with your staff any changes that might be necessary before the examinations are |
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| The licensee did not identify any information or materials used during the examination as proprietary.
| | administered. |
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| ATTACHMENT:
| | To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by August 16, 2013. The written examinations, operating tests, and supporting reference materials identified in Attachment 3 to ES-201 will be due by September 6, 2013. |
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| =SUPPLEMENTAL INFORMATION=
| | Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (10 CFR 55.40(b)(3)), an authorized representative of the facility licensee shall approve the outlines, examinations, and tests before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use. We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Any delay in receiving the required examinations and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled. In addition, your support for on-site validation of the examinations is required during the week of September 30, 2013. |
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| ==KEY POINTS OF CONTACT==
| | In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final. |
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| ===Licensee Personnel===
| | Appendix E to NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered. |
| : [[contact::B. Bement]], Vice President of Nuclear Operations
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| : [[contact::D. Mims]], Vice President of Nuclear Regulatory Assurance
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| : [[contact::W. Potter]], Simulator Support Section Leader
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| : [[contact::L. Burton]], Operations Training / Written Examination Author
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| : [[contact::A. Rasmussen]], Operating Test Author
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| ===NRC Personnel===
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| : [[contact::T. Brown]], Senior Resident Inspector
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|
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| ==ADAMS DOCUMENTS REFERENCED==
| | To permit timely NRC review and evaluation, your staff should submit preliminary operator and senior operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024), and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date. |
| Accession No. ML13343A132 - FINAL WRITTEN EXAMINATION (delayed release until Dec. 15, 2015)
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| : Accession No. ML13343A135 - FINAL OPERATING TEST
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| : Accession No. ML13343A136 - POST EXAMINATION ANALYSIS AND COMMENTS
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| : Enclosure 2 NRC Review of PVNGS Written Post-Examination Comments Note:
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| : A complete text of the licensee's post examination analysis and comments can be found in ADAMS under Accession Number ML13343A136.
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| : Question 80
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| : With regards to the (EW) Essential Cooling Water system in mode 1, which of the following is the correct application of Tech Specs?
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| (1) When cross connected to the Nuclear Cooling Water (NCW) system, EW is
| | This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by OMB, under approval number 3150-0018, which expires on April 30, 2016. The public reporting burden for this collection of information is estimated to average 50 hours per response, including the time for reviewing instructions, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of these information collections, including suggestions for reducing the burden, to the Records and FOIA/Privacy Services Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail to INFOCOLLECTS@NRC.GOV. |
| : INOPERABLE...
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|
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|
| (2) When cross connected to the Fuel Pool Cooling, EW is INOPERABLE...
| | The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection, unless it displays a currently valid OMB control number. |
| : A. (1) and remains inoperable while cross connected. (2) and remains inoperable while cross connected.
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| : B. (1) and remains inoperable while cross connected. (2) but operability can be restored if a flow balance is performed because the
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| : EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
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| : C. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat
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| exchanger.
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the electronic Reading Room page of the NRC's public Web site at http://www.nrc.gov/reading-rm/adams.html. Thank you for your cooperation in this matter. Mr. Potter has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Steely at 817-200-1432, or myself at |
| (2) and remains inoperable while cross connected. | |
| : D. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat
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|
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| exchanger.
| | 817-200-1159. |
| (2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
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| : Proposed Answers: A & B
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| : Licensee Comments for Question 80:
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| : In the justification section for this question, the licensee wrote the following:
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|
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| "Originally B was identified as the only correct answer but after review it has been determined that A is also correct.
| | Sincerely,/RA/ |
| : Given only conditions stated in the stem, 'A' and 'B' are correct answers.
| | Vincent Gaddy, Chief Operations Branch Division of Reactor Safety |
| : EW is
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| : INOPERABLE when cross connected to either the NC or SFP cooling systems. EW may be restored to OPERABLE when connected to SFP cooling if a flow balance is performed. The
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|
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| stem makes no reference to a flow balance being performed. 'A' would have been wrong if the statement read (1) and remains inoperable when cross connected regardless of performing a flow balance.
| | Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74 |
|
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| 'B' is still correct (1) is correct and (2) is correct in stating that operability is restored if a flow balance is performed. 'C & D' are both still wrong because (1) is a wrong statement for both.
| | ML13142A344 ADAMS: No Yes SUNSI Review Complete Reviewer Initials: VGG Publicly Available Non-Sensitive Non-publicly Available Sensitive OE:OB C:OB CSteely VGaddy /RA/ /RA/ 5/21/2013 5/21/2013 |
| : Operability is not restored for EW when cross tied to NC even if a flow balance is completed. EW is not sized to supply both NC priority loads and the SDC heat exchanger. EW is sized to carry the SFP heat exchanger, Essential chiller and the SDC heat exchanger. Operability is restored if a flow balance is completed after the cross-tie to Fuel Pool Cooling. | |
| : Distracters D are plausible because one part of the answer is correct.
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| : Distracter C is plausible because the answers are true for the opposite condition." | |
| : NRC Resolution of Question 80:
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| : The NRC reviewed the licensee's submittal and concluded that the licensee was correct, that both "A" and "B" are correct.
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| : Any time two safety systems are cross-connected they are typically INOPERABLE as defined in the Technical Specifications.
| |
| : The new question and subsequent validation by several licensed operators was flawed and a Condition Report
| |
| : PVAR 4476152 was written to address this issue. | |
| : The NRC changed the key and re-graded the written examinations with the correct answer as "A" or "B" for question 80 as recommended.
| |
| }} | | }} |
|
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Category:Inspection Plan
MONTHYEARML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI IR 05000528/20220062023-03-0101 March 2023 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Report 05000528/2022006, 05000529/2022006, and 05000530/2022006) ML22252A0352022-09-12012 September 2022 PVNGS Units 1, 2, and 3 - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000528/2022401; 05000529/2022401; 05000530/2022401 IR 05000528/20210062022-03-0202 March 2022 Annual Assessment Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021006, 05000529/2021006, and 05000530/2021006) ML22067A2292022-03-0202 March 2022 Inservice Inspection Inspection PWR Request for Information ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information IR 05000528/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021005, 05000529/2021005, and 05000530/2021005) ML21245A2222021-09-0101 September 2021 Request for Information ML21237A5172021-08-10010 August 2021 Email to PV Licensee and Palo Verde Nuclear Generating Station, Units 1, 2 and 3 - Notification of Inspection of the Licensees Implementation Industry Initiative Associated with the Open Phase Condition (NRC Bulletin 2012-01) and Request Fo IR 07200044/20214012021-07-21021 July 2021 ISFSI, Information Request, Security Inspection Report 07200044/2021401 ML21200A2392021-07-20020 July 2021 Docs Request AC - AA August 2021 ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21061A3382021-02-25025 February 2021 Request for Information: Palo Verde Nuclear Generating Station, Dated December 4, 2020, Inspection Report 05000528/529/5302021001 Public Radiation Safety Inspection-5.8 ML21042B9692021-02-18018 February 2021 Notification of NRC Design Bases Assurance Inspection and Initial Request for Information ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML21011A1972021-01-12012 January 2021 Unit 2, and Unit 3 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012) and Request for Information IR 05000528/20200052020-09-0101 September 2020 Updated Inspection Plan for Palo Verde Nuclear Generating Station Units 1, 2, and 3 (Reports 05000528/2020005, 05000529/2020005, and 05000530/2020005) ML20238B9552020-08-25025 August 2020 Request for Information ML20213C7002020-07-31031 July 2020 PVNGS Security Team Inspection Docs Request 2020411 ML20183A1902020-07-0101 July 2020 Notification of Inspection (NRC Inspection Report 05000528/2020004, 05000529/2020004, 05000530/2020004) and Request for Information ML20099G1002020-04-0808 April 2020 Notification of NRC Triennial Heat Sink Performance Inspection (05000528/2020002, 05000529/2020002, and 05000530/2020002) and Request for Information ML20055E1092020-03-0303 March 2020 PV2019006 Annual Assessment Letter ML19347D1062019-12-10010 December 2019 PVNGS Security Inspection Information Request 2020412 ML19331A5582019-11-27027 November 2019 Request for Information Draft ML19312A1312019-11-0808 November 2019 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000528/2020001, 05000529/2020001, and 05000530/2020001) and Request for Information IR 05000528/20190052019-08-30030 August 2019 Updated Inspection Plan for Palo Verde, Units 1, 2, and 3 Report 05000528/2019005, 05000529/2019005, and 05000530/2019005 IR 05000528/20180062019-03-0404 March 2019 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2018006, 05000529/2018006, and 05000530/2018006) ML18274A1922018-10-0101 October 2018 Notification of NRC Triennial Heat Sink Performance Inspection (05000528/2018004, 05000529/2018004 and 05000530/2018004) and Request for Information IR 05000528/20180052018-08-31031 August 2018 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2018005, 05000529/2018005, and 05000530/2018005) IR 05000528/20170062018-03-0101 March 2018 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Report 05000528/2017006, 05000529/2017006, and 05000530/2017006) ML17298B5612017-10-25025 October 2017 Notification of NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2018007; 05000529/2018007; 05000530/2018007) and Request for Information IR 05000528/20180072017-10-25025 October 2017 Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Notification Of NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2018007; 05000529/2018007; 05000530/2018007) And Request For Information IR 05000528/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000528/2017005, 05000529/2017005, and 05000530/2017005) ML17243A3552017-08-28028 August 2017 Updated Non-Public Security Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 IR 05000528/20160062017-03-0101 March 2017 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Report 05000528/2016006, 05000529/2016006, and 05000530/2016006) ML16336A8322016-12-0101 December 2016 Notification of Evaluations of Changes, Tests, and Experiments, & Permanent Plant Modifications Inspection (05000528/2017007; 05000529/2017007; and 05000530/2017007) & Request for Information ML16258A0312016-09-14014 September 2016 PVNGS Units 1-3 - Notif of NRC Insp of the Implementation of Mitigation Strategies and Spent Fuel Pool Instr. Orders and Emer. Prep. Comm./Staffing/Multi-Unit Dose Assessment Plns(05000528/ 2016009;05000529/2016009;and 05000530/2016009) and IR 05000528/20160052016-09-12012 September 2016 Errata for Mid-Cycle Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2016005, 05000529/2016005 and 05000530/2016005) IR 05000528/20164012016-08-31031 August 2016 Non-Public Security Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (NRC Physical Security Inspection Report Numbers 05000528/2016401, 05000529/2016401, and 05000530/2016401) ML16237A0572016-08-31031 August 2016 Mid-Cycle Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2, and 3(report 05000528/2016005, 05000529/2016005 and 05000530/2016005) IR 05000528/20150062016-03-0202 March 2016 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (05000528/2015006, 05000529/2015006, and 05000530/2015006) ML15264B1522015-09-21021 September 2015 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000528; 05000529; and 05000530/2015008) and Request for Information IR 05000528/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Palo Verde Nuclear Generating Station, Units 1,2,and 3 (Report 05000528/2015005, 05000529/2015005 and 05000530/2015005) IR 05000528/20144022014-09-0202 September 2014 Non-Public Security Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (NRC Physical Security Inspection Report Numbers 05000528/2014402, 05000529/2014402, and 05000530/2014402) IR 05000528/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2014006, 05000529,2014006 and 05000530/2014006) IR 05000528/20130012014-03-0404 March 2014 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2, and 3 (Report 05000528/2013001; 05000529/2013001; 05000530/2013001) 2024-01-18
[Table view] Category:Letter
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection 2024-08-08
[Table view] |
Text
May 21, 2013
Randall K. Edington, Executive Vice President, Nuclear/CNO
Arizona Public Service Company P.O. Box 52034, Mail Stop 7602 Phoenix, AZ 85072-2034
SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NOTIFICATION OF NRC INITIAL OPERATOR LICENSING EXAMINATION 05000528/2013301; 05000529/2013301; 05000530/2013301
Dear Mr. Edington:
In a telephone conversation on April 11, 2013, between Messrs. W. Potter, Simulator Support Section Leader, and C. Steely, Chief Examiner, arrangements were made for the administration of licensing examinations at Palo Verde Nuclear Generating Station, Units 1, 2 and 3 during the week of November 4, 2013.
As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1, and NUREG-1122, "Knowledge and Abilities Catalog for Nuclear Power Plant Operators," Revision 2, Supplement 1. The NRC's regional office will discuss with your staff any changes that might be necessary before the examinations are
administered.
To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by August 16, 2013. The written examinations, operating tests, and supporting reference materials identified in Attachment 3 to ES-201 will be due by September 6, 2013.
Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (10 CFR 55.40(b)(3)), an authorized representative of the facility licensee shall approve the outlines, examinations, and tests before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use. We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Any delay in receiving the required examinations and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled. In addition, your support for on-site validation of the examinations is required during the week of September 30, 2013.
In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.
Appendix E to NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.
To permit timely NRC review and evaluation, your staff should submit preliminary operator and senior operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024), and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.
This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by OMB, under approval number 3150-0018, which expires on April 30, 2016. The public reporting burden for this collection of information is estimated to average 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> per response, including the time for reviewing instructions, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of these information collections, including suggestions for reducing the burden, to the Records and FOIA/Privacy Services Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail to INFOCOLLECTS@NRC.GOV.
The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection, unless it displays a currently valid OMB control number.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the electronic Reading Room page of the NRC's public Web site at http://www.nrc.gov/reading-rm/adams.html. Thank you for your cooperation in this matter. Mr. Potter has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Steely at 817-200-1432, or myself at
817-200-1159.
Sincerely,/RA/
Vincent Gaddy, Chief Operations Branch Division of Reactor Safety
Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74
ML13142A344 ADAMS: No Yes SUNSI Review Complete Reviewer Initials: VGG Publicly Available Non-Sensitive Non-publicly Available Sensitive OE:OB C:OB CSteely VGaddy /RA/ /RA/ 5/21/2013 5/21/2013