ML033140552
| ML033140552 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/10/2003 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML033140552 (133) | |
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2 PUBLIC MEETING 3 BETWEEN U.S. NUCLEAR REGULATORY COMMISSION O350 PANEL AND FIRST ENERGY NUCLEAR OPERATING COMPANY 4 OAK HARBOR, OHIO 5 ---
6 Meeting held on Wednesday, September 10, 2003, at 2:00 p.m. at the Oak Harbor High School, Oak Harbor, Ohio, 7 taken by me, Marie B. Fresch, Registered Merit Reporter, and Notary Public in and for the State of Ohio.
8 9
PANEL MEMBERS PRESENT:
10 U. S. NUCLEAR REGULATORY COMMISSION 11 John "Jack" Grobe, 12 Senior Manager, Region III Office
& Chairman, MC 0350 Panel 13 William Ruland, Senior Manager NRR
& Vice Chairman, MC 0350 Panel 14 David Passehl, Project Engineer Davis-Besse 15 Christopher Scott Thomas, Senior Resident Inspector 16 U.S. NRC Office - Davis-Besse Jon Hopkins, 17 NRR Project Manager - Davis-Besse Monica Salter-Williams, 18 NRC Resident Inspector - Davis Besse 19 FIRST ENERGY NUCLEAR OPERATING COMPANY 20 Lew Myers, FENOC Chief Operating Officer James J. Powers, III 21 Director - Nuclear Engineering Mark Bezilla, Vice President/Plant Manager 22 Steve Loehlein, Manager - Nuclear Quality Assessment 23 Rick Dame - Reliability Unit Supervisor 24 ---
25 MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
2 1 MR. PASSEHL: Welcome to 2 FirstEnergy and members of the public for accommodating our 3 meeting today. This is a public meeting between the NRC 4 Davis-Besse Oversight Panel and FirstEnergy Nuclear 5 Operating Company.
6 My name is David Passehl. Im a Project Engineer 7 and Assistant to the Branch Chief Christine Lipa.
8 Christine is unable to join us today, so I will be 9 discussing the agenda today.
10 Next slide, please.
11 The purpose of this meeting is to discuss the NRC 12 Oversight Panel activities, focusing on those activities 13 since our last public meeting, and to allow FirstEnergy to 14 present the status of activities in their Restart Plan.
15 Next slide, please.
16 Todays agenda will cover an introduction and 17 opening remarks, a brief summary of the August 12th public 18 meetings. Well be discussing significant NRC activities 19 since the August 12th public meeting. Well hear the 20 Licensees presentation on the status of their Return to 21 Service Plan. We will adjourn the NRC meeting with 22 FirstEnergy, have a short break, and then hear comments and 23 answer questions and finally well adjourn the meeting.
24 First, before we get started, I would like to make 25 some introductions. Jack Grobe to my left is the Senior MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
3 1 Manager in the Region III Office in Lisle, Illinois, and 2 hes the Chairman of the Davis-Besse Oversight Panel.
3 Bill Ruland to his left is the Senior Manager and is 4 the Vice Chairman of the Oversight Panel. Bills position 5 is Director, Project Directorate 3 in the Division of 6 Licensing Project Management at our headquarters office.
7 Jon Hopkins to Bills left is the Project Manager 8 for the Davis-Besse facility. He works in our headquarters 9 office.
10 Scott Thomas to my right is the Senior Resident 11 Inspector at Davis-Besse.
12 Jack Rutkowski who is not here is another Resident 13 Inspector; and we just hired a third Resident Inspector, 14 Monica Salter-Williams.
15 MR. GROBE: Why dont I 16 introduce Monica.
17 Would you stand up? There you are. Dont sit down 18 yet.
19 Monica has just joined us this week. Shes moved 20 her family here to the area, which is outstanding. Monica 21 comes to us from our Region 1 Office. Shes got a 22 Bachelors degree in Chemistry and Masters degree in 23 Nuclear Engineering from Penn State University, and worked 24 at the Three Mile Island Plant for a couple of years prior 25 to joining the Regulatory Commission.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
4 1 She joined as an Intern Engineer in Region 1 Office 2 in Philadelphia, Pennsylvania, and received her inspector 3 training in that office, and just recently was qualified as 4 a fully qualified inspector, which is quite a significant 5 accomplishment.
6 And were very glad to have Monica and her husband 7 and her five year old son here with us. Take a good luck 8 at Monica. Youre not going to see her very often, because 9 usually what youll see is her going by in a motorcycle.
10 And, that will probably be at a fairly high rate of speed.
11 So, Monica has joined us and shes going to be the 12 third member of the Davis-Besse team that will be at the 13 plant every day inspecting the facility.
14 Thats unusual to have three Resident Inspectors.
15 Most of the nuclear power plants in the United States have 16 two, but because of the challenges faced by the Licensee, 17 the increased oversight that the NRC is providing, Monica 18 has been assigned as the third Resident at Davis-Besse.
19 So, welcome, Monica.
20 MR. PASSEHL: Thanks, Jack.
21 Also, Nancy Keller is the Davis-Besse Resident 22 Office Assistant and shes in the lobby, making sure 23 everybody gets slides and that.
24 Also, Jan Strasma, who is our Region III Public 25 Affairs Officer, hes here.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
5 1 And, we were expecting our State and Government 2 Affairs Officer to come here. He was delayed however, and 3 he had with him the monthly newsletter. So, when he gets 4 here, we can distribute copies of the monthly newsletter.
5 Also, I wanted to say, in the monthly newsletter, 6 there was, there may be an error. The next 0350 Public 7 Meeting for Davis-Besse will be at Camp Perry on 8 October 7.
9 I think thats all the NRC.
10 Lew, could you introduce FirstEnergy, please.
11 MR. MYERS: Sure.
12 At the end of the table is Rick Dame. Rick is from 13 our Perry plant. He spoke at our last meeting. Rick is 14 the Restart Test Manager. As you know, were in the mode 15 of heating up our plant. Well talk about that today and 16 taking it up for the 7-day Pressure/Temperature Test.
17 Ricks job was to prepare that test which we have 18 approved today; and then to step back and work directly for 19 me and Gary Leidich in an assessment role, and were going 20 to monitor our process and proceed through this new 21 performance area during the 7-day cycle. So, Rick today 22 will be discussing that.
23 Jim Powers is the Director of Engineering. He is 24 sitting next to me on my left.
25 Mark Bezilla will talk about the plan and status MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
6 1 today.
2 And then, Steve Loehlein, at the end of the table, 3 is Manager of Quality Assurance and hell discuss those 4 areas.
5 MR. PASSEHL: Thank you, Lew.
6 At this time, I would like to ask for introductions 7 of public officials or representatives of public officials.
8 MR. WITT: Jere Witt, County 9 Administrator.
10 MR. PASSEHL: Anyone else 11 besides Jere?
12 Okay. Thank you.
13 As I said, this meeting is open to public 14 observation. Please note that this is a meeting between 15 the Nuclear Regulatory Commission and FirstEnergy. At the 16 conclusion of the business portion of the meeting, but 17 before the meeting is adjourned, the NRC staff will be 18 available to receive comments from members of the public 19 and answer questions.
20 The newsletter, when it gets here, will provide 21 some background information and discuss the current plan of 22 NRC activities and its a good resource to learn about what 23 activities have been ongoing in the last month.
24 On the back page of the newsletter there is some 25 reference information on how to contact us if you have MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
7 1 questions or concerns, and weve included the email address 2 and phone number for our Public Affairs Officers, and there 3 also is a web page address where individuals can read and 4 have access to numerous public documents about 5 Davis-Besse.
6 In the foyer, we also have a Public Meeting Feedback 7 Form, which we use to solicit comments and on aspects of 8 the meeting that we can improve on.
9 Were having the meeting transcribed today by Marie 10 Fresch to maintain a record of this meeting. The 11 transcription will be available on our web page in about 3 12 to 4 weeks. And, please keep in mind, it is important that 13 speakers use the microphones to ensure that Marie and the 14 audience can hear.
15 Next, I would like to briefly describe the August 16 12th public meeting, which was our last public meeting, 17 during which we provided a status update on our Restart 18 Checklist and Inspection Activities.
19 In todays presentation, we plan to provide an 20 update on the Checklist and also on our recently completed 21 and ongoing NRC activities.
22 FirstEnergy provided an update on efforts toward 23 restart. They discussed the High Pressure Injection Pumps, 24 Debris Issue, and the new Electrical Distribution System 25 Software called ETAP.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
8 1 They discussed the Plants Readiness for Mode 3 2 Pressure and Temperature Test, which is about 2155 pounds 3 per square inch and 530 degrees. They also discussed what 4 this test is expected to accomplish.
5 They also provided a status on results from Safety 6 Culture Assessments and their readiness for entry into Mode 7 3. Lastly, they discussed observations and assessments by 8 the sites Quality Assurance Organization.
9 The transcripts from that meeting are available on 10 our website.
11 Next slide, please.
12 Since the August 12 meeting, we closed Restart 13 Checklist Item 2c1, which entailed the Emergency Core 14 Cooling System and Containment Spray System Sump. The 15 Davis-Besse Oversight Panel approved this checklist item 16 for closure on September 2nd. We inspected the new sump 17 and our, the results of that inspection can be found in our 18 Inspection Report 03-06, 2003-06.
19 The only remaining item from that inspection was to 20 complete a review of the technical adequacy of certain 21 calculations, which we identified as a concern in that 22 Inspection Report. Weve completed that review and 23 determined that FirstEnergy addressed our concerns.
24 Closure of that item will be discussed in the NRC 25 Inspection Report 03-17, which is due to be out in the next MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
9 1 couple weeks.
2 We also closed Restart Checklist Item 6g, which was 3 a License Amendment Request by FirstEnergy to relocate 4 their high pressure and low pressure injection flow balance 5 testing from a Technical Specifications to the updated 6 Safety Analysis Report.
7 We are also in the process of updating our 8 Confirmatory Action Letter to address two items. The first 9 item concerned quarantine of material from the reactor 10 pressure vessel head and control rod drive mechanism nozzle 11 penetrations that were necessary to address the root cause 12 of the head degradation.
13 NRC has received nozzle specimens and those have 14 been sent to a laboratory at Northwest and they have been 15 inventoried and the reactor vessel head has been shipped to 16 a low level waste repository.
17 Also -- next slide, please.
18 MR. GROBE: Dave, before you 19 go on. There is one other item thats been accomplished 20 since the last meeting that was accomplished since these 21 slides were prepared, that has to do with a license 22 amendment that was issued last Friday.
23 FirstEnergy requested a license amendment to conduct 24 the Mode 3 Normal Operating Pressure and Temperature Test, 25 with the existing high pressure injection pumps prior to MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
10 1 the modification to address the concern that was identified 2 regarding some internal components in the pump. That 3 license amendment was approved and issued Friday.
4 From the NRCs perspective, all of the checklist 5 items that need to be addressed prior to Licensee 6 commencing this test have been accomplished.
7 MR. PASSEHL: Okay. I wanted to 8 discuss some continuing NRC activities. First, being the 9 System Health Reviews and Design Issues. This is an 10 inspection that we conducted that evaluated the safety 11 function of various systems and topical issues, such as 12 high energy line breaks, equipment qualification, seismic 13 flooding and Intensive 10CFR50, Appendix R, which deals with 14 fire protection.
15 This inspection was conducted by several inspectors 16 and we held an Exit Meeting with FirstEnergy to discuss 17 their results. The report should be available in a few 18 weeks.
19 We also performed an inspection of the sites 20 Corrective Action Process to ensure that this process is 21 being effectively implemented and appropriate corrective 22 actions are being taken to prevent recurrence of problems.
23 This inspection included a review of Restart 24 Corrective Action items to determine if items required to 25 be accomplished prior to startup of the plant had been MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
11 1 correctly characterized and actions had been completed in 2 accordance with the Licensee and NRC requirements.
3 We also held an Exit Meeting with the Utility 4 yesterday and discussed the results of the inspection, and 5 that report should be available in a few weeks.
6 We continue to perform an inspection of the site 7 Safety Culture and Safety Conscious Work Environment area, 8 where were evaluating the Licensees process and tools for 9 monitoring improvement in Safety Culture and Safety 10 Conscious Work Environment and the effectiveness of the 11 Employee Concerns Program.
12 That inspection, as I mentioned, is in progress.
13 And on April 7th of this year, we issued a press release 14 that has biographical information on the members of the 15 team.
16 Also, we continue to perform inspections by our 17 Resident Inspectors. As we introduce the three, they are 18 stationed permanently at the site and they inspect a broad 19 range of activities covering in the areas of Operations, 20 Maintenance and Testing. The Resident Inspectors issue an 21 inspection report every six to seven weeks.
22 MR. GROBE: Let me just 23 comment on the first two inspections that Dave identified; 24 that is, the System Health Inspection and Corrective Action 25 Team Inspection. Those two inspections are very important MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
12 1 activities. They were conducted by quite a number of staff 2 over a long period of time.
3 The Corrective Action Inspection began in March and 4 the System Health Inspection began earlier this year. The 5 number of inspectors, for example, on the Corrective Action 6 Team Inspection, is that inspection has involved ten 7 inspectors with well over two hundred years of experience 8 in nuclear power operation.
9 The results that were presented during the Exit 10 Meeting yesterday by those inspection teams are preliminary 11 results. Those need to be reviewed by regional management 12 and then presented to the panel by the teams. And the 13 panel will evaluate the results of those inspections and 14 make a final determination on whether they are sufficient 15 to address the checklist items.
16 Consequently, its not appropriate at this point in 17 time to discuss the preliminary results of those 18 inspections; however, we are planning and expect a specific 19 meeting to discuss the results of those inspections, 20 because those two areas are very important to the closure 21 of the Restart Checklist.
22 Sometime in the near future well be identifying a 23 public meeting time and place to discuss the results of 24 those inspections.
25 Thanks, Dave.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
13 1 MR. PASSEHL: Okay, next slide, 2 please.
3 Okay, I wanted to cover some upcoming activities 4 that the NRC is undertaking.
5 We are preparing to conduct an inspection of the 6 lower reactor vessel head area. This inspection will 7 review procedures and related ASME code requirements 8 relative to the leak test of the Reactor Coolant System.
9 The NRC will also observe conduct of the tests and verify 10 proper implementation of procedures. There is a fuller 11 description of this in the monthly newsletter.
12 The NRC is planning to conduct a meeting to discuss 13 the Licensees Assessment of Safety Culture, once the 14 Licensee has fully integrated their independent and 15 internal assessments. The meeting is currently scheduled 16 to be held in the Region III Office on October 1st.
17 The NRC is preparing to conduct an assessment of the 18 Licensees efforts to address Restart Checklist item 3i, 19 which is the process for ensuring completeness and accuracy 20 of required records and submittals to the NRC. The results 21 of this inspection will enable the NRC to gain confidence 22 in the quality of the Licensees submittals, such that the 23 NRC can have reasonable assurance in the completeness and 24 accuracy of the Licensee basis and other important 25 communications to the NRC.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
14 1 The NRC is also performing follow-up reviews of 2 potentially risk significant issues regarding the 3 Containment Emergency Sump and the High Pressure Injection 4 Pumps. In the NRC Inspection Report 03-15, we discuss a 5 finding associated with ineffective Corrective Actions 6 related to unacceptable Containment coatings, fibrous 7 material, and other debris. This resulted in the inability 8 of the Emergency Core Cooling System Sump to perform its 9 safety function under certain postulated accident scenarios 10 due to clogging of the sump screen.
11 We are also following up a finding that was 12 discussed in Licensee Event Report 2003-02 associated with 13 their high pressure injection pumps being incapable of 14 maintaining suction from the Containment Emergency Sump via 15 the Low Pressure Injection Pumps during high pressure 16 recirculation. As I mentioned, that is discussed in the 17 OER LER. Oh, also is discussed in Report 03-15 as well, 18 2003-15.
19 And also, the last thing I wanted to mention, is the 20 NRC is preparing to conduct a Restart Assessment Team 21 Inspection when the Utility nears the point where it will 22 seek NRC authorization for restart. The inspection will 23 review the readiness of the plant and the plant staff to 24 resume plant operations safely and in compliance with NRC 25 requirements. The inspection findings will be considered MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
15 1 by the NRC Oversight Panel in making its recommendation to 2 the Regional Administrator on possible restart.
3 MR. GROBE: Thanks, Dave.
4 Just a couple more observations. We dont like to 5 conduct meetings outside of this local area, because we 6 know that there is a large amount of interest in the local 7 population regarding the activities going on at 8 Davis-Besse. Occasionally, we found it necessary to 9 conduct the meeting either in our headquarters office in 10 Rockville or the Region III Office in Chicago.
11 The upcoming Safety Culture Meeting will be 12 conducted in Chicago because of the need to have additional 13 staff management at that meeting. Instead of bringing them 14 all out to here, we need to conduct the meeting, its more 15 effective to conduct the meeting in Chicago. As weve done 16 in the past, we will have both audio and video 17 teleconferencing of that meeting.
18 So, if youre here in the local area and youre 19 interested in that meeting, you can participate both by 20 listening to the meeting via telephones, free 1-800 number; 21 and also participate in the question and answer period 22 after the conclusion of the business portion of the meeting 23 through the telephone lines.
24 In addition to that, the meeting will be available 25 to the public in our headquarters office in Rockville MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
16 1 through video teleconferencing. We felt it was important 2 to make those opportunities since were taking this meeting 3 out of the local community here.
4 The other thing I wanted to mention, and Dave was 5 too humble to mention this. He is leading the Restart 6 Assessment Team Inspection; and that will be a team of 7 operation experts and engineering experts that will do the 8 final evaluation of the readiness of the Davis-Besse Plant 9 to move from a shutdown mode of operations to a restart 10 operations, mode of operations.
11 And that inspection is not currently scheduled, 12 because we dont know when restart might be, but we just 13 put it on the slide here to make you aware that thats an 14 upcoming inspection.
15 It will be a fairly large team inspection. They 16 will be observing plant operations around the clock for 17 several days to gather a sense of the readiness of the 18 plant to return to an operational configuration.
19 Thanks, Dave.
20 MR. PASSEHL: Thank you. And 21 that completes our portion of the presentation. So, with 22 that, I would like to turn it over to FirstEnergy.
23 MR. MYERS: Thank you.
24 There are a couple people in the audience. We have, 25 from our corporate organization, we have Mary OReilly with MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
17 1 us today. Mary is our corporate legal group.
2 And, Fred von Ahn, the VP of Quality Assurance, is 3 also in the audience.
4 And Bob Schrauder is here, and hes supervising the 5 HPI Project, so thats on the schedule today. So, you know 6 Bob is here too, if there is any questions in that area.
7 If youre ready to get started, our Desired Outcome 8 today, we have an agenda where I thought I would take a few 9 moments and discuss the, the loss of transmission that we 10 experienced since the last meeting. That ought to be 11 interesting. And the response of Davis-Besse and our other 12 plants during that time.
13 Mark Bezilla will discuss the plant status today.
14 Jim Powers will talk about some of the technical 15 issues that are still ongoing and theyre coming to 16 closure.
17 And then Operational Readiness Assessment Plan, 18 Rick Dame will discuss that. And as we said, that is 19 underway as we speak.
20 Then Steve Loehlein will finally give a prospective 21 from the Quality Assurance Program; and then I will come 22 back and summarize.
23 Our Desired Outcomes today -- next slide. The plant 24 systems are being inspected and tested for restart. Weve 25 already completed the Containment Pressure Test, which is MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
18 1 part of our Restart Test Plan. Containment Pressure Test 2 was done very successfully and the leakage rate was 3 probably one of the lowest weve seen in the history of the 4 plant.
5 Weve also completed 250 pound pressure test of our 6 nuclear reactor, when we pressurized the reactor up to 250 7 pounds run on reactor coolant pump. At this time, plant 8 systems are being inspected and the net next plateau is 2155 9 pound pressure test, which is our normal pressure. And 10 well heat the reactor up to about 532 degrees and maintain 11 it there for about 7 days. And, well discuss that more in 12 our presentation today.
13 Once again, we want to discuss our technical issues 14 that weve addressed at the plant; and most, if not all of 15 the technical issues are coming to closure. Theres still 16 a couple of outstanding things, like the API HPI pump that we 17 have to go install and Bob is working hard on that on the 18 test that we have going on.
19 Then we have the ongoing assessments that we will be 20 performing during this Pressure Temperature Test, along 21 with some other tests that we have to monitor our people, 22 our plant, and our processes, and ensure that nuclear 23 safety is maintained and we operate the plant event-free.
24 We think that sets us up to develop a rapport that 25 we will provide to our Restart Oversight Panel, Gary MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
19 1 Leidich, and myself; and then if, with corrective actions 2 after that, we would be ready to turn to the NRC to ask for 3 restart.
4 With that, were prepare to get started. If you 5 would like, Ill start out talking about the plant response 6 on the loss of grid.
7 Shortly after 4 p.m. on August 14th, the electric 8 power at our switchyard was lost. We had the opportunity 9 to implement our emergency plan procedures as part of that 10 process, and this type drill meant physically implement the 11 procedures.
12 Our overall conclusions were that our equipment at 13 the plant performed as designed. In fact, it performed 14 very well. The Davis-Besse plant was in Mode 5. The fuel 15 was in the reactor, with the reactor head installed during 16 that time.
17 The decay heat train too two was in service providing 18 core coolant. At the time, we issued both emergency 19 diesels start, started as desired; load to your bus, and 20 ran throughout the time of the event. All of our systems 21 at our plant performed as designed. And, once again, we 22 were pleased with the overall performance of our system.
23 The initial response to the event was in accordance 24 with our Emergency Preparedness Program. We have that in 25 place and that we drill all the time. We classified the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
20 1 event as an unusual event, as at 1621. Our offsite 2 notifications were made in a timely manner.
3 The Emergency Response Organizations consisting of 4 what we call our Technical Support Center was manned, our 5 Operator Support Center was manned, and the Emergency 6 Control Center was manned. We went beyond the requirements 7 to man those centers and those centers were manned to 8 provide station support.
9 The Perry Station was also operating at that time at 10 a hundred percent power, and trip power tripped when power was lost, and 11 performed similar.
12 Our Beaver Valley Plant was operating, had to reduce 13 power for a short length of time, and then, then returned 14 to a hundred percent power until after the event was over 15 with.
16 At 1621, I think, on the 15th, we decided, we 17 declared the event over with. We returned -- the diesel 18 performed its action well. We returned, once we decided 19 both plants were stable and the grid was stable; thats 20 what we were watching voltage preparations variations of the grid for 21 a couple days before we returned to our normal power, per 22 power source was the grid; and we did that at 1621 on 23 8-15.
24 With that, thats all I have.
25 MR. GROBE: I have one MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
21 1 question for you, Lew.
2 MR. MYERS: Sure.
3 MR. GROBE: There is a lot of 4 effort to, there is a lot of effort right now focused on 5 trying to understand what caused an unprecedented power 6 outage in the northeast and southern part of Canada. What 7 are your plans on evaluating the information thats gained 8 and learned from the evaluation of the cause of this event, 9 and incorporating that into the probabilities of loss of 10 outside power included in your Probabilistic Risk 11 Assessment for the plant?
12 MR. MYERS: You know, Jack, 13 thats, as part of our ETAP program, we have to look at 14 grid stability and look at the probabilities of loss of 15 power like this. We wont know anything until all the 16 facts are gathered, what caused this loss of power, and 17 where the actions of companies, our company as well as 18 other companies, will be taken. And once we look at all 19 that, well go back and redetermine where our stability 20 factors of our grid are at the time.
21 And so, well look at the, the actions that our 22 company would take, because it was a combination of many 23 events that caused this situation.
24 MR. GROBE: Okay, thank you.
25 MR. BEZILLA: Thank you. Our MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
22 1 next slide, please.
2 My Desired Outcome for today is to demonstrate to 3 you that our preparations for this Normal Operating 4 Pressure Test is thorough, well planned, and 5 comprehensive.
6 Next slide, please.
7 (mike problem) 8 MR. BEZILLA: Okay, Ill start 9 over. My Desired Outcome for today is to demonstrate to 10 you that our preparations for this Normal Operating 11 Pressure Test is thorough, well planned, and 12 comprehensive.
13 Next slide, please.
14 The plant is currently in Mode 5. Reactor Coolant 15 System is around 110 degrees and were heating it up and 16 were about two hundred pounds per square inch in the 17 Reactor Coolant System.
18 Were in the progression through the remaining 19 activities required to be completed for entry into Mode 4; 20 and Mode 4 is Reactor Coolant System greater than 200 21 degrees; and we anticipate making that mode change late 22 tonight or early tomorrow.
23 What we have in front of us is final venting of the 24 Reactor Coolant System, making sure all our testing and 25 paperwork is in place. One final check, to make sure were MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
23 1 in accordance with our tech specs and license amendment 2 requests; and then well start the first two reactor 3 coolant pumps and start heating up and pressurizing the 4 Reactor Coolant System.
5 Next slide, please.
6 During the Normal Operating Pressure Test, our focus 7 will be on the following:
8 Nuclear Safety, our ability to ensure that the 9 reactor core remains covered and cool.
10 Our People, their attitudes and behaviors.
11 Our Plant, how well the systems, structures and 12 components perform.
13 And our Processes, how they enable our, how they 14 enable and guide our people in their performance of their 15 tasks and assignments.
16 Next slide, please.
17 Our expectations of our people during this Normal 18 Operating Pressure Test are as follows:
19 First, that Nuclear Safety is first and foremost in 20 their thoughts and that they ensure issues receive the 21 attention warranted by their significance.
22 That they be prepared. For example, they preview 23 each task and assignment. They verify that they have the 24 tools and materials needed to do their tasks. They conduct 25 preevolution briefs. They know what success looks like.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
24 1 And that they can recognize issues and problems. And that 2 they know what to do if faced with adversity.
3 Another expectation of our people is that they 4 communicate. For example, that they use three-way 5 communication to ensure that they have been understood or 6 that they understand. That they report any issues 7 immediately to their supervisor; and if its a plant 8 equipment issue, immediately to the control room. That 9 they provide complete and accurate information. And 10 finally, that they be accountable. For example, they 11 self-check their work. They peer check others work. They 12 make sure that each tasking job is completed. The 13 paperwork is completed. They exhibit a questioning 14 attitude. They identify mistakes and errors and use our 15 Corrective Action Process. That theyre reliable and that 16 they own the outcome of their efforts.
17 Next slide, please.
18 This next slide just depicts, Ill say, the 19 Management Team. Ill say a piece of the Management Team, 20 but a focused piece of the Management Team that will be in 21 place for this Normal Operating Pressure Test.
22 As you see, Lew will be filling the Site 23 Vice-President role. Ill be Director of Operations. Mike 24 Roder is Manager of Operations. And we have a Normal 25 Operating Pressure Test Team, and Ill get to that in a MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
25 1 minute on the next slide.
2 We have Jim Powers, Engineering Organization, 3 providing support as needed through the evolution. And, 4 then we have Mike Stevens, our Director of Maintenance; and 5 Greg Dunn, our Manager of Work Control. Gregs working day 6 shift; Mikes working night shift; and we have our Outage 7 Control Center manned up to be able to support Mike and his 8 team if there are any anomalies or issues that are 9 encountered on the heatup and pressurization, the stable 10 period, and then the cooldown and depressurization of the 11 plant.
12 Off to the left here, youll see that we have Rick 13 Dame, as we talked about Independent Assessor, and Steve 14 Loehlein, Manager of Quality Assurance and his team. What 15 these individuals will be doing will be taking a look at 16 the, us, our people, and our behaviors, and Ill say 17 attitudes and approach to solving problems, as well as our 18 processes and how well those processes enable our people to 19 work through solutions and issues. And both Rick and Steve 20 will talk a little bit later in the presentation about what 21 theyre going to be doing during this Normal Operating 22 Pressure Test.
23 Next slide, please.
24 Okay, this is a little finer look at the Normal 25 Operating Pressure Test Team. Again, we have our Manager MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
26 1 of Operations, Mike Roder, in charge of the plant.
2 We have Test Directors on day shift and night shift 3 and those are the conductors, the orchestrators of the 4 evolution.
5 We have a couple of assistants. Those guys will 6 back up, spell the Test Directors, as well as take care of 7 all the Post Maintenance Tests that were going to be doing 8 during this Normal Operating Pressure Test.
9 You can see we have three specific teams. First 10 team is Boric Acid Inspection, part of our Restart Test 11 Plan, has us go back at 2155 pounds, which is normal 12 pressure in the system and theyll inspect over a thousand 13 pieces, parts, if you will; checking flanges, checking 14 bolted connections, checking valves, and other type 15 equipment.
16 We got teams set up. Again, we have day shift, 17 night shift. We have a number of inspectors that have been 18 trained and are ready to perform the tasks. Theyve 19 reviewed what components and things they need to look at.
20 What we plan on doing is when we get to 2155 pounds, 21 well have them go out and take an initial look; and in 22 about three days into the stabilization period, well have 23 them go back out and Ill say do the four score inspections 24 of the system. Okay.
25 Again, those guys, we have a couple of the system MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
27 1 managers, again, to spell them and provide additional 2 management focus for those teams.
3 Middle group here, Reactor Coolant System 4 Sensitivity Leakage. We have again Test Managers and Test 5 Support Groups, which consist of chemistry personnel and 6 radiological protection personnel.
7 What we will do during this test period is a couple 8 different things. First off, well do a long-duration 9 Reactor Coolant System Leak Rate Test. And part of that 10 test puts in known leakage. Then we run our program and 11 see if that program can identify the known leakage and how 12 accurate it can get to measure that quantity of Reactor 13 Coolant System leakage.
14 And then, the additional activity well perform 15 during this test is weve installed a new reactor coolant 16 leakage monitor device known as a FLUS Monitor. And that 17 item is, the detector is physically located underneath the 18 vessel, and then the monitoring equipment is located in the 19 basement of the building over underneath one of the 20 stairwells.
21 What well do is put in some, well increase the 22 humidity at the detector and then well be able to analyze 23 to see how sensitive that monitor is and how low humidity 24 change it can detect underneath the vessel. It will give 25 us an indication of potential leakage in the vicinity of MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
28 1 the bottom part of the reactor vessel.
2 Lastly, as part of our team, we realize there is 3 going to be some opportunities and challenges on the way 4 up. Were going to have some valves that leak. We may 5 have some flanges that leak. There may be some other 6 equipment issues that arise as we heat up and pressurize 7 the system and as were stable and then as we cool down and 8 depressurize.
9 What weve done is set up some immediate response 10 teams. Weve got engineering support, we have maintenance 11 support, we have radiologic protection support. So, if 12 there are any immediate issues, at these individuals 13 disposal are teams that are prepared to go out and assess 14 those problems, use our Problem-Solving Decision-Making 15 Process, if required, and then hopefully be able to 16 remediate and address whatever those issues may be.
17 So, thats our Normal Operating Pressure Testing.
18 And most of those functions are in place. The remainder 19 will be in place today and/or tomorrow.
20 Okay, next slide.
21 MR. RULAND: Mark, could you 22 clarify for me, when you say youre establishing a known 23 leakage rate, how you actually do that?
24 MR. BEZILLA: Well establish a 25 Reactor Coolant System sample and well be able to monitor MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
29 1 that and be able to determine what that sample flow rate is 2 and go ahead and run our program and it will be able to, it 3 will say half a gallon a minute or a tenth of a gallon per 4 minute and it will compare that to the known leak rate that 5 we established. So, it will be through the samples is how 6 well establish that.
7 MR. RULAND: Okay, great.
8 MR. BEZILLA: Okay. Another 9 question?
10 MR. RULAND: Well, I wanted to 11 make sure --
12 MR. BEZILLA: Im not going to 13 go --
14 MR. RULAND: I just wanted to 15 make sure you were. Good. Thank you.
16 MR. BEZILLA: Normal Operating 17 Pressure Test; already talked a little about the conditions 18 right at, around 532 degrees, which is normal, normal 19 no-load temperature. And then the Reactor Coolant System 20 pressure around 2155 pounds per square inch.
21 And, as I said, we initially get up at 2155. Well 22 perform a walkdown. And there is over a thousand 23 components and pieces and parts that well go look at to 24 make sure we know the status of those components. If there 25 is any issues, well address those at the time.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
30 1 And, then, about three days into it, well go ahead 2 and repeat those inspections and that will give us a little 3 bit of soak time on the plant and well be able to identify 4 if there is any minor web page weepage or anything like that from 5 those specific components that were looking at. Okay.
6 Then, also, during this 7-day test, well be able to 7 perform Post Maintenance and Modification Testing. Weve 8 done as much testing as we can do in the current state, but 9 we need pressure and temperature to be able to complete 10 some of those inspections and tests.
11 All right, last thing, is during this timeframe, it 12 will give us a chance to see how we respond in more of a 13 normal mode of operation. And if the plant behaves and 14 doesnt provide some of those opportunities as were 15 heating up, as were stabling, as were cooling down, Rick 16 and Steves groups will run some exercises on us and see 17 how we perform. Theyll talk a little more about that 18 shortly.
19 Next slide, please.
20 So, whats this Normal Operating Pressure Test going 21 to do for us? I believe its going to help demonstrate 22 confidence in our plant systems and equipment. In 23 preparation for this test, weve done a lot of work. Ill 24 get to that. I have a slide that just rolls that up. Ill 25 get to that.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
31 1 Weve done a lot of work. And from a safety 2 equipment standpoint, to enter Mode 4, we have to have 3 proven to ourselves that all that equipment will function 4 if needed, and so were in the final stages of completing 5 that testing, as I said, completing the paperwork, so we 6 can appropriately raise temperature above 200 degrees and 7 enter Mode 4.
8 So, well have check down on Safety Features 9 Actuation System, which is a lot of the safety equipment 10 designed to protect the fuel if we have an accident or some 11 condition where it would require it to work.
12 Our Reactor Protection System, which essentially 13 monitors the number of parameters within the plant and will 14 cause automatic shutdowns of the reactor. In this Normal 15 Operating Pressure Test, we wont be using the fuel in the 16 reactor. Well have lots of shutdown margin, if you will, 17 but nonetheless, we want to make sure that system is ready 18 to go. And pieces of it are required in Mode 4 and Mode 3, 19 some of it is not required until Mode 1 and 2, but well 20 have it thoroughly checked out.
21 Then, also, our Feedwater Line Rupture Control 22 System -- Steam and Feedwater Line Control Rupture System; 23 this helps mitigate any kind of steam like leak on the secondary 24 plant to again ensure that the fuel remains covered and 25 cool.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
32 1 So, well check those all out and have done the 2 required testing. So, well have good confidence in those 3 systems prior to changing modes.
4 From our Primary Systems standpoint, Lew talked 5 about in his opening remarks having conducted the 250 6 pound -- the 250 pound test on the Reactor Coolant System.
7 That gave us some confidence that our systems will be okay, 8 but this, I will say, is the dress rehearsal for actual 9 restart. It will bring the plant up to normal pressure and 10 close to normal temperature and that will give us a much 11 better feel of the equipment and the things we worked on, 12 if we have any additional component problems or equipment 13 problems.
14 Ive already talked about validating our Integrated 15 Leakage, Reactor Coolant System Leakage capabilities, as 16 well as the FLUS monitoring. And, from a secondary systems 17 standpoint, we have put steam on the main turbine seals, 18 weve drawn vacuum, weve exercised a number of those 19 components, but its been awhile since we had the main 20 steam pipe hot and weve had that system pressurized. And 21 by doing this Normal Operating Pressure Test, well be able 22 to check out a lot of the fluid systems on the secondary 23 plant and look for any component deficiencies or 24 deficiencies that we might have in the secondary plant 25 also.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
33 1 Okay, next slide.
2 Some of the inspections that well be doing on the 3 primary side, once we get up, actually were going to watch 4 it as we come up, but when we get up to full pressure and 5 near normal temperature, well be checking out Reactor 6 Vessel flange and the O-rings and between the O-rings on 7 that connection.
8 Reactor Head Control Rod Drive Mechanism, checking 9 the nozzle penetrations. Weve installed view ports on the 10 head, so we can get a pretty good look at those nozzle 11 penetrations even when the reactor is up and hot. Of 12 course, not with nuclear reaction going on, but we can get 13 a view during this one.
14 And also the flanges associated with those Control 15 Rod Drive Mechanisms, we think weve solved leakage 16 problems there, but this will be a good opportunity to 17 check for us also.
18 The Bonnet Nozzles, Reactor Incore Monitoring 19 Instrumentation. We have a couple cameras set up 20 underneath there, so if we have any significant leakage, 21 well be able to see that through the insulation. And I 22 believe, when were hot, were going to take a couple peaks 23 under the insulation, but well do a thorough check when 24 were done with that, well pull the insulation and look 25 closely at all those penetrations.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
34 1 Well take a look at our Steam Generator, our 2 Pressurizer manways and hand-holes. Those can be subject 3 to leakage at times. We want to make sure we have good 4 torques on those.
5 Reactor Coolant Pump covers and seals. Those are 6 always areas you want to be careful of. So, well check 7 those out. We have a pretty robust plan for Reactor 8 Coolant pumps; you put the lid on, there is a gasket there, 9 and between those seals, leak monitoring capability. We 10 have a pretty aggressive plan to go check those and watch 11 to see if there is any leakage on the way up. If there is 12 leakage while we heat it up, then theres leakage on the 13 way down.
14 Sometimes you can get some leakage on the way up or 15 on the way down on those joints, because the metal expands 16 and contracts. Typically, if you have any minor leakage on 17 the way up or on the way down, when you get up at full 18 pressure, near temperature, you dont have any more 19 leakage.
20 So, we have a pretty aggressive plan to go check 21 that out, specifically on the two pumps that we just worked 22 on taken apart and on the two pumps that we havent taken 23 apart.
24 Then our Reactor Coolant System -- or Pressurizer 25 Heaters, there is flange joints there we will be checking, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
35 1 and Pressurizer safety and relief valves. Again, well 2 check those connections, and then well also check for any 3 true leakage we might have on those components, because 4 thats something we want to take care of prior to restart 5 if there was any leakage there.
6 And, numerous, like I said, there is a thousand plus 7 things were going to be looking at; Reactor Coolant System 8 valves, packing associated with those valves, and again, 9 bolted connections and flanges.
10 Okay, so, those are just some of the checks well be 11 performing.
12 Okay, next slide, please.
13 This is just a pictorial of the plant. In the 14 Auxiliary Building, that houses a lot of the safety systems 15 that I talked about earlier, and weve done a number of 16 modifications, a lot of work on those, and were in the 17 final testing of those components to make sure theyre 18 ready to support mode change and its Normal Operating 19 Pressure Test.
20 Weve been inside Containment. Ill talk a little 21 bit about some of the things weve done in Containment.
22 Weve been pouring over that, making sure its as clean as 23 it can be. And its probably in the best shape its been 24 in, in 25 years. So, we think weve done a good job there, 25 not only from a housekeeping standpoint, but also from a MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
36 1 radiological standpoint.
2 And with the exceptions of a few areas, we can 3 probably walk in there in street clothes today. I know 4 that the desire, once we get through with this, once we 5 finish up, whatever work might be needed to be done, that 6 we would like to go in there in street clothes.
7 Lastly on the turbine side, thats the power 8 generation side. Again, well get a good chance to check 9 it out and see what its health looks like. Its been 10 pretty much out for the last 16 to 18 months, so well get 11 a chance to check that out.
12 Cooling Tower is in service and you might see a 13 little coolant there, not a whole lot when we check, but 14 there might be a little bit there.
15 So, thats a little pictorial on the plant.
16 Okay. Next slide, please.
17 Accomplishments. Some of this is a repeat from 18 previous meetings, but I think its worthwhile going 19 through this. Some of these we had to do. Some of these 20 weve chosen to do to improve our margin of safety at the 21 Davis-Besse plant.
22 We replaced the Reactor Pressure Vessel Head.
23 We improved the Containment Emergency Sump. We 24 probably have the, we probably have the most robust sump in 25 the PWR industry right now. Were pretty proud of that.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
37 1 We modified our High Pressure Injection Pump 2 Recirculation Line. There are some scenarios, some 3 accident scenarios, where we would have to align the high 4 pressure injection pumps off the low pressure injection 5 pumps while theyre taking suction from the Containment 6 Sump. And weve put in a modification now to allow those 7 pumps to have good minimum flow protection while theyre in 8 that mode. And, although, we dont expect to need that, 9 its there if you would need it.
10 We painted the Containment Dome. We believe we have 11 the dome in good shape from a coating standpoint.
12 As I said, weve installed the FLUS Online Leak 13 Monitoring System.
14 Weve replaced Containment Air Coolers and a lot of 15 the duct work and registers associated with that system.
16 Weve enhanced the Decay Heat Valve Enclosure.
17 There is a couple of valves that are low in the Containment 18 Building that we need to ensure stay dry if theres an 19 accident for some period of time. And weve essentially 20 built a new enclosure around those components. And we just 21 completed the final, final testing prior to Mode 4, and the 22 leak rate was probably the best weve ever seen on that 23 enclosure, so we feel good and confident about that 24 modification.
25 We cleaned the Reactor Vessel. That was with fuel MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
38 1 out. And I believe back in the April timeframe, just as we 2 were getting ready to put the fuel in, we noticed a couple, 3 what looked like paint chips, and stuff. Went back, 4 revacuumed, cleaned that all out prior to putting fuel in.
5 So, we feel good about that.
6 We confirmed the Fuel Integrity. We sift sip all the 7 fuel thats up on the fuel pins to see if there is any 8 leakage on those assemblies and on the pins. We believe we 9 have good fuel cladding integrity, and we also are pretty 10 careful when were putting those assemblies in to make sure 11 we didnt have any grid strap which are there to help 12 support the fuel pins, make sure those things behaved and 13 we didnt grab any of those or tear any of those when we 14 put the fuel back. So, we feel pretty good about our fuel 15 integrity.
16 Again, we will not be using nuclear fuel and heat 17 for this first Normal Operating Test, but the fuel is in 18 the vessel, and its, its there.
19 MR. THOMAS: Mark, before you 20 move on. Youve had some challenges with the --
21 (mike squealed) -- with the microphone. No, with the fuel 22 integrity over several cycles, past cycles. Whats been 23 done differently going forward to, to maybe prevent that in 24 the future?
25 MR. BEZILLA: Okay. Lew said he MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
39 1 would like to answer that, Scott.
2 MR. THOMAS: Or to prevent 3 similar challenges going forward.
4 MR. MYERS: We inspected all 5 the fuel; fuel assembly by fuel assembly. We checked all 6 the grid straps and we reconstituted with some stainless 7 steel rods some of the, some of the fuel thats in position 8 where you have, I call it jet impingement, vibration 9 inducement. So, we reconstituted that through the fuel 10 assemblies that area.
11 So, going forward from a Framatone standpoint, weve 12 made all the, who supplies our fuel, we made all the 13 improvements that they suggested.
14 MR. THOMAS: Okay.
15 MR. BEZILLA: You okay with 16 that, Scott?
17 MR. THOMAS: Okay.
18 MR. BEZILLA: Okay. Boric Acid, 19 weve scoured the plant inside Containment, outside 20 Containment. We did the 50 pound and 250 pound test, so we 21 feel pretty good heading into this Normal Operating Test as 22 far as knowing what our baseline is and being able to 23 detect any leaks, leakages at this point.
24 And then, finally, Ive already talked a little 25 about Containment Building, but weve cleaned the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
40 1 Containment Building and Ive had my Ops guys and RP guys 2 and Services guys essentially in there nonstop for the last 3 couple weeks just making sure theyve looked at every nook 4 and cranny and got just about everything out of there that 5 shouldnt be in there. So, were feeling pretty good about 6 the Containment condition as far as this first Normal 7 Operating Test.
8 Next slide, please.
9 Dave had talked about the, getting the specimens 10 that were required out of the old Davis-Besse head. This 11 is just a picture of it on the train. As Dave said, we 12 shipped that off to Envirocare in Utah and it will be 13 disposed of properly.
14 Next slide.
15 This is just a, a roll up of the actions completed.
16 So, since the spring of 2002, these are the things that 17 weve done.
18 Weve done approximately a hundred modifications to 19 the plant. Again, some of which we needed to do, some of 20 which weve chosen to do to improve safety margin of the 21 plant, the reliability of equipment.
22 We processed through about 7700 work orders.
23 Weve written over 14,000 Condition Reports, issues, 24 problems, questions. Weve completed about 23,000 25 Corrective Actions in response to those questions, issues, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
41 1 and problems.
2 Weve performed over 15,000 surveillances. About 3 5,000 of those are shift routine types, so there has been 4 about 10,000 other surveillances that we performed on our 5 equipment and systems.
6 And weve made, weve performed about 2200 7 Preventative Maintenance Tasks to help ensure the 8 reliability of our equipment.
9 And we processed about 2700 Procedure Changes trying 10 to make that tool as good as it can be for our people to 11 enable them to be successful in their tasks and 12 evolutions.
13 So, whats the point? The point is weve done a 14 lot of stuff. We think weve improved the reliability of 15 the plant. We think weve improved and weve gained the 16 safety margin of the plant. And I believe we set the stage 17 for a successful Normal Operating Pressure Test here in the 18 next couple of days. Okay.
19 Next slide, please.
20 So, what follows this Normal Operating Pressure 21 Test? Well, well complete the test. And as Lew said, 22 thats a 7-day evolution. The whole thing should take, 23 say, 9 to 11 days, 9 to 10 days to complete heatup, 24 pressurization, stabilization, testing, and the cooldown 25 depressurization.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
42 1 And when were done with that test, well return to 2 Mode 5, thats less than 200 degrees; and react, check on 3 margin, and well assess the results.
4 We know we have to remove and modify our high 5 pressure injection pumps. Jim will give you a little 6 update of where were at there.
7 Rick and Steve as well as our own assessments will 8 determine how our people and how our processes performed.
9 And I suspect theyre going to be things, actions we need 10 to do there. As much as I would expect us to be flawless, 11 I know thats not going to be the case and we will have 12 improvements to make. So, we will address the people, 13 plant, and process issues.
14 Were already in the transition from the Return to 15 Service Plan Practices to Normal Operating Practices.
16 Prior to restart, well need to be there fully engaged 17 doing our normal practices.
18 And then lastly, when we got our hands around all 19 that, we will be asking for permission to restart the 20 Davis-Besse facility.
21 Thats all I have. Any questions for me?
22 MR. PASSEHL: Yeah, just a 23 question from me. How do you plan to capture people, 24 plant, and process issues identified and evaluate those?
25 MR. BEZILLA: Dave, thats a MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
43 1 good question. We have assessment monitoring processes, 2 observations that we use. And then if we find any 3 deficiencies there, in almost all cases well write a 4 Condition Report and that gets us into our Corrective 5 Action Process. What that allows us to do is deal with 6 that specific issue.
7 And then one of the things that we havent done a 8 lot of during this time frame is trending. And by putting 9 that stuff in our Corrective Action Process, that will 10 enable us to look at low level items and see if there is 11 anything we need to roll up where we need to take action 12 where we dont have an issue or event.
13 Thats one of the areas I think you may hear Rick or 14 Steve talk about as training. We know we need to 15 reinvigorate that. Were in the process of doing that.
16 But to answer your question, well put those into 17 our Corrective Action Process and deal with them 18 appropriately.
19 Other questions?
20 MR. GROBE: I have one or two 21 things. First off, regarding the Decay Heat Valve 22 Enclosure, I know that you had a number of challenges 23 verifying the integrity of leak tightness of that 24 enclosure. Could you describe what was the final cause of 25 the leakage that you were seeing and how you resolved that?
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
44 1 MR. BEZILLA: It will be my 2 pleasure, Jack. I have become up close and personal with 3 this thing. Okay.
4 What we essentially had was a pit. All right. In a 5 pit, okay. What we did was, we turned it into a tank. So, 6 we made a stainless steel enclosure inside this head. We 7 had about, oh, shoot, miles, we had miles of weld that we 8 had to perform on this enclosure to build this enclosure.
9 Those earlier attempts at solving the leakage 10 problems, we had to go back and do some touch-up on those 11 welds. You do that much welding, you have some veracity 12 there. So, we went back and touched up those welds.
13 Then our final challenge was there was penetrations 14 that go into this enclosure, the actual piping 15 penetrations. And the way we solved that issue was we made 16 a boot, put a flange on the tank and made a boot; had that 17 boot come up outside the enclosure; welded that tank, 18 welded that boot to the tank; and then we put about 18 19 inches of fire retardant, foam-type material on that; and 20 then finally a protective cover over that whole enclosure.
21 And we finally went and had the test here a couple 22 days ago. Like I said, we had the best results ever. We 23 just kept after it. Made sure we had the welds all solid 24 and good, and fixed this penetration issue. Like I say, 25 probably the best results Ive seen.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
45 1 MR. GROBE: Thanks, Mark. I did 2 have some questions regarding Containment Air Coolers, but 3 I peeked ahead and saw that Jim is going to be talking a 4 little about those, so Ill hold those questions for you.
5 MR. BEZILLA: Understand the 6 Containment Air Cooler questions youll do after Jims 7 presentation. Okay. Very good.
8 MR. RULAND: Mark, could you 9 tell me a little bit more about the cameras that will be 10 under the insulation?
11 MR. BEZILLA: Bill, theyre not 12 under the insulation, theyre down underneath the vessel.
13 To get to our vessel, there is a ladder, you go down a 14 ladder, go down some steps alongside the heat cores.
15 When you get underneath there, you look up at about 16 9; 8, 9, 10 feet, okay, 8, 9, 10 feet, you have insulation 17 package. The cameras will be pointed at those, at the 18 insulation package. So, well be able to look at that.
19 Theyre not, I dont believe theyre inside the 20 insulation. If I remember, theyre looking at the 21 insulation package. Okay?
22 MR. RULAND: Are those cameras 23 going to be live outside Containment, do you know?
24 MR. BEZILLA: What well do is 25 well, because we dont have like dedicated penetration MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
46 1 through the Containment for those, well have them all set 2 up, well have the cable run out to a low, low heat area.
3 In this case, I was going to say low doze, but in this 4 case, its just a cooler area. I believe were setting it 5 up right inside the personnel air lock. So, we can go in, 6 it will go inside Containment and well be able to view it 7 from right there by the personnel air lock.
8 MR. RULAND: Okay.
9 MR. BEZILLA: Any other 10 questions?
11 MR. PASSEHL: I thought you were 12 going to be a doing a bare metal inspection. Maybe I was 13 mistaken.
14 MR. BEZILLA: Dave, like I said, 15 I think were going to take the heat. When were hot, the 16 thing is 532 degrees.
17 MR. PASSEHL: Right.
18 MR. BEZILLA: To pull the 19 insulation off, its pretty intense. I think were going 20 to take a peek.
21 Then, we know we have as found. We have pictures of 22 the penetrations. We have, Ill say, as-left prior to this 23 Normal Operating Pressure Test. When were done, well 24 pull the insulation off and we can get hands-on, check that 25 out. So, we will do bare metal, but its after the 7-day MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
47 1 hold test. Okay?
2 MR. PASSEHL: Thank you.
3 MR. BEZILLA: With that, I turn 4 it over to Jim.
5 MR. POWERS: Okay. Thank you, 6 Mark.
7 This afternoon I would like to demonstrate that the 8 technical issues are coming to close here at the plant. As 9 you know, weve described a number of the challenges that 10 weve had and substantially improving that into safety 11 margin at Davis-Besse. And weve made good progress.
12 As I think you can see from our closure curves over 13 on the wall for the Corrective Action Program, weve worked 14 through a lot of issues, and are largely crediting our 15 Return to Service Plan we put in place last year.
16 We completed inspections. And can I have the next 17 slide, please?
18 Completed inspections, identified and documented our 19 issues in depth through our Corrective Action Program. As 20 Mark alluded, weve answered over 14,000 Condition Reports 21 in the course of this outage.
22 So, we have tackled many issues. At this point 23 those issues are clearly understood and are bounded. Three 24 of the major issues that remain are High Pressure Injection 25 Pumps, the Electrical Distribution System, and Containment MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
48 1 Air Coolers. And Ill talk about each one of those.
2 First one I would like to go over is the High 3 Pressure Injection Pumps. Qualification testing is now in 4 progress at our laboratory in Alabama. As you know, weve 5 done quite a bit of industry leading research on our High 6 Pressure Injection Pumps and performance of Containment 7 Emergency Sumps and the debris definition in Containment in 8 post-accident environment. So, were quite proud of that.
9 And much of the initial work that had been done to 10 set up the progress weve made today is now set in place so 11 that were in the formal qualification stage of that. That 12 means putting the actual parts that will constitute the 13 final design into a proof test, which will be a 21-day 14 test, and were starting that test now, and its ongoing.
15 We finalized our debris characterization. Of 16 course, one of the big questions was just what kind of 17 debris are we talking about; fibers from insulation, grit, 18 pieces of, flakes of coating, paint thats in Containment, 19 for example. Characterized all that and provided a basis 20 for what the pumps would see for this 21-day test in that 21 post-accident condition environment.
22 And we had a very comprehensive Design Review 23 Meeting in Alexandria, Virginia, on August 28, 29, attended 24 by not only our engineers, but contract specialist 25 engineers, third party consultant reviewers for us to MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
49 1 assure the design is appropriate, our Engineering 2 Assessment Board representatives, as well as the NRC in 3 attendance to review it. So, a very comprehensive review 4 was held of our final design plans.
5 We succeeded in getting the hydrostatic bearing 6 design from Pump Guinard in France, who originated the 7 hydrostatic bearing. And the French, as we mentioned in 8 past meetings, part of their pumps and bearings for debris, 9 potential debris and pumpage.
10 So, we took their design and adapted it and improved 11 it for the Davis-Besse application. And the improvements 12 being, the addition of screens that weve talked about in 13 the water supply that goes to those bearings, as well as 14 what we refer to as the escape groove in the bearing to 15 allow any small debris that gets in there to escape.
16 Thats been working very well in our testing 17 environment, and were pleased with the evolution of this 18 design.
19 One of the other things we learned in our testing 20 program is that we wanted the hardface, the fine clearance 21 parts, thats wearings, bearing surfaces, for example.
22 Weve done that. Weve worked those parts and they are 23 available.
24 Were waiting for results of our qualification 25 testing prior to doing final machining, particularly on the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
50 1 hydrostatic bearing. So, that is awaiting the test results, 2 but were positioned to make those modifications to the 3 pumps within the window after our Normal Operating Pressure 4 Tests and that supports the schedule as we have it laid 5 out. So, were looking good from that perspective.
6 Then the last bullet talks about that, the 7 modification schedule. So, weve reinstalled the original 8 pumps to support the Normal Operating Pressure Test.
9 Theyve done what we refer to as a surveillance test 10 completed on those to demonstrate that they work 11 appropriately at the plant; achieved the approval by the 12 Nuclear Regulatory Commission on the license amendment 13 request to support our testing.
14 Once we complete our Normal Operating Pressure Test, 15 well remove the pumps, modify them, reinstall them, and 16 proof test them, again surveillance test them to 17 demonstrate they work properly installed at Davis-Besse.
18 So, that issue is coming to closure. Well have 19 substantial margin to the understanding of these pumps and 20 the Emergency Containment Sump, plus help the environment 21 for the industry.
22 MR. HOPKINS: Jim, have you 23 decided on a final design, strainer design?
24 MR. POWERS: Yes, we selected a 25 final design for the strainer. Its a 50 mil strainer MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
51 1 size, which we have seen perform well relative to the 2 debris mix and in the long term; and were observing that 3 and testing that.
4 MR. HOPKINS: Is it any sort of 5 special design of, the volcano design or anything like 6 that?
7 MR. POWERS: Its a flat 8 perforated plate design. We havent hardfaced it because 9 we found that pumping this amount of grit and debris 10 through the pump and entering through the holes, that there 11 was some wear, so we went to a hardened material design on 12 that; otherwise, its a flat perforated plate.
13 MR. HOPKINS: Okay, thank you.
14 MR. GROBE: Jim, I couldnt 15 understand you; was that 1-5 mill or 5-0?
16 MR. POWERS: 5-0.
17 MR. GROBE: Good. Thank you.
18 MR. MYERS: Do you have any 19 other questions? We have an expert in the audience.
20 MR. POWERS: Our expert.
21 MR. GROBE: Were you ready to 22 go on?
23 MR. POWERS: Yes.
24 MR. GROBE: Before you do 25 that, I just want to make a couple observations.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
52 1 We had engineers down in Alabama observing some of 2 the testing of these pumps and also we had an engineer and 3 an engineering manager from our Nuclear Reactor Regulation 4 Office in Rockville visit MPR and Associates, the 5 engineering firm thats doing this work; and so far we 6 havent identified any questions. So, thats good news.
7 MR. POWERS: Um-hmm.
8 MR. RULAND: Jim, so, I know 9 you said you were doing the 21-day proof test, I think is 10 your word. So, based on when it started, is it 21 days 11 from today or?
12 MR. POWERS: Essentially, yes, 13 Bill, 21 days from today. What well do is modify that 14 test, and determine the results. Were also going to go 15 through our Normal Operating Pressure Test at the plant, 16 determine the results of that. Determine what type of work 17 we need to do, maintenance work, after the Normal Operating 18 Pressure Test to finalize the outage. We can make a 19 decision either waiting through the 21 days for the final 20 determination of bearing design or take a, make a decision 21 earlier in time.
22 We believe once weve operated for a substantial 23 amount of time, bearing design will be proven and complete 24 out the 21 days qualification, we can decide later.
25 Okay. With that Ill move into our Electrical MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
53 1 Distribution System. Weve certainly talked about this 2 over the past several meetings as well. This was a 3 conversion that weve done in the analytical software that 4 predicts how the electricity is distributed through the 5 plant to all the safety-related and nonsafety-related 6 systems and shows the voltage is adequate.
7 Weve completed the ETAP analysis, thats the 8 electrical analysis program, for the first Mode 4. Then, 9 as well as defining Corrective Actions that will be 10 required to restart the plant. And those are well 11 understood and relatively straightforward.
12 For example, we have actuators on several of our 13 dampers for H-Vac systems at the plant. That voltage for 14 those actuators needs to be improved, and we are looking at 15 changing the power supply cables to those actuators by 16 pulling a larger size cable through the conduit to the 17 actuator.
18 Very straightforward modification has been scoped 19 out, proceeding down that track now. And I would say that 20 characterizes the handful of things that we need to do 21 after the Normal Operating Pressure Test to fully restore 22 the electrical system, and improve its margin.
23 Another big step forward, we believe, in the margin 24 of safety at the plant is the much improved understanding 25 of design basis of the Electrical Distribution System and MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
54 1 correcting the problems that have been in that system over 2 the years, what we have referred to as latent issues, 3 bringing it up to industry standards.
4 So, following the Normal Operating Pressure Test, 5 well make those modifications that weve identified, and 6 provide resolution, final resolution prior to restart of 7 the plant.
8 The changes that weve made to support this initial 9 entry into Mode 4 and Mode 3, Im sure we have substantial 10 margin available in the system pending making those final 11 modifications; and that is, like, we increase voltage 12 settings on some of the transformers. We are also ensuring 13 that all of the main transformers, power supply feeds are 14 available, so we have plenty of equipment, plenty of margin 15 going into the testing sequence.
16 MR. GROBE: Jim, could you 17 briefly describe the modifications that are necessary for 18 the second Mode 4 and 3, and also whether or not youve 19 identified a license amendment request that would need to 20 be evaluated?
21 MR. POWERS: We do not believe 22 any license amendment will be required. In previous 23 meetings, since we were looking at various options of 24 approach to resolve our issues with the system, there were 25 some of those that could have involved license amendment.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
55 1 The one that we selected does not. Maintains the, 2 all flexabilities that we have in the system as originally 3 licensed by the Nuclear Regulatory Commission. And the 4 modifications were required to essentially restore the 5 capability involving the components, essentially, the 6 existing overall configuration.
7 But the modifications consist of things like pulling 8 a larger cable to hydro actuators for H-VAC dampers.
9 Theres also three fans in ventilation system, looks like 10 well be pulling cable to those as well. And there were 11 several other areas where we needed to complete more 12 detailed analysis and manufacture input to us to fully 13 understand the needs of our equipment. And thats being 14 completed. So, theyre not very complex modifications.
15 MR. GROBE: Whats the status 16 of the design change documentation for those modifications?
17 MR. POWERS: That is getting 18 started at this point, Jack. Weve done, one of our 19 engineering, architect engineer has done a review of the 20 scope of that and laid it out for us and were proceeding 21 forward at this point.
22 Weve been focused pretty intensely on our 23 electrical system entering into Mode 4 and make sure our 24 work is complete there. Now, were turning our attention 25 on this follow-up for finding resolution.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
56 1 Ill move on to the Containment Air Coolers. This 2 is, this is also a major piece of work that we did at the 3 plant restoring our Containment Air Coolers. Weve talked 4 about that item at past meetings, essentially rebuilt 5 them.
6 What happened though during the loss of offsite 7 power event on August 14th, we had what appears to be a 8 water pressure surge in the service water supply to those 9 Containment Air Coolers. And the reason for that, what 10 happened is when the power is lost to the site from the 11 grid, of course, the equipment stops, all the motors stop, 12 and that includes the service water pumps which were 13 pumping water through the, to the CACs and through the CACs 14 that were in service.
15 So, when that pump motor stops, pressure drops off 16 in the very high spots of the system, voids can be created.
17 So, when the pumps restart, what happens is the emergency 18 diesel generators start the sequence on low start repower, 19 the service water pumps restart, and water rushes back 20 through the system and refills.
21 When that happened during the loss of offsite power, 22 one of our Containment Air Coolers, number one, indicated 23 some deformation of flexible metal bellows that we have as 24 part of the piping system connected to the Containment Air 25 Cooler; and those bellows were there as part of the pipe MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
57 1 stress analysis and support design criteria to assure that 2 the nozzle loadings on those Containment Air Coolers were 3 appropriate.
4 Now, what we did is, after observing the 5 misalignment and expansion of the piping bellows assembly, 6 especially deformation of them, we issued a Significant 7 Condition Adverse to Quality and assembled an Investigation 8 Team.
9 This is a pretty broadly based Investigation Team.
10 We have an Engineering Root Cause Mentor, as well as 11 representatives from the engineering company that designed 12 the piping system for CAC, and the bellows manufacturer 13 provided us a representative who was on site for virtually 14 two weeks full time helping us assess this. Water analysts 15 were evaluating the, the pressure surge in the piping 16 system by running computer programs. And we had pipe 17 stress analysts from the Design Engineering Section, system 18 engineers from our plant, Engineering Section, on the team 19 as well. So, it was pretty broadly based composite team 20 evaluating it.
21 What we determined looking into it, was that because 22 of the nature of the outage that we were in, maintenance 23 ongoing, Number One Containment Air Cooler was bound out of 24 service while he were completing work on an air-operated 25 valve, part of our air-operated valve project, improvement MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
58 1 project, associated with that Containment Air Cooler. And 2 that was on one train of the Service Water System.
3 The other train we had the operable, operating 4 Containment Air Cooler in it, there was water flowing 5 through it.
6 When the pumps restarted, the pump that pressurized 7 the train with the Containment Air Cooler from the one 8 thats isolated, resulted in the pressure surge because of 9 the closed valve in that train, with the maintenance 10 alignment there.
11 When there is a closed valve and water pressure 12 would reflect off, it can essentially double the pressures 13 in a system. And similar at home, if you close a water 14 faucet too fast, you hear a bang. Thats the type of event 15 that were talking about.
16 And so, the other operating Containment Air Cooler 17 unit sustained that loss of offsite power event very well.
18 We had some questions as we examined the details of the 19 bellows installation and looked at exactly what we had 20 there for configuration; and we had some, we have some 21 issues with that, that we feel we want to correct prior to 22 return to service, after this, following this pressure test 23 pending.
24 But CACs number 2 and 3 that were in the operating 25 mode sustained the event rather well. In fact, all the, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
59 1 all the piping system, pressure integrity was maintained.
2 Also, the team determined that we had designed this 3 system for a water flow, pressure surges. The NRC had 4 previously issued an Information Notice, 9606 is the number 5 of it, that talks about post-accident conditions in these 6 Containment Air Coolers that could lead to steam voids 7 inside of that because of very hot conditions in 8 Containment in the early stages of an accident. And then 9 when the water flow is reinitiated, what happens with the 10 steam.
11 So, we designed for those loads and, but the loading 12 from the loop, what we found was, the loading from the loop 13 was very similar to those loads, but when you have a 14 Containment Air Cooler isolated, no flow going through it, 15 and with a set of conditions in the service water system, 16 set of conditions we had with relatively high pressure in 17 the system, we could have a much larger load.
18 So, the Containment Air Coolers were normally 19 operable in Modes 1, 2, and 3. Were in Mode 5. And, we 20 learned quite a bit from this, in terms of how were going 21 to lay out our CACs that are in standby, how the system is 22 designed to perform when its in operation, one CAC in each 23 group.
24 We determined thus far from our examination that the 25 analysis that was done for Information Notice 9606, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
60 1 pressures do apparently bound the loss of offsite power 2 condition pressures in the inoperable loops. And that was 3 good news. But, if you have an isolated CAC, has those 4 conditions, those pressures can be twice, twice what have 5 been analyzed.
6 MR. GROBE: Jim, you 7 mentioned that there were other conditions that were in the 8 Service Water System that might have been exacerbated the 9 situation, can you go into that in a little more detail?
10 MR. POWERS: Yes, normally, a 11 system like a Service Water System is, has flow rates that 12 are based on temperatures of the season, heat loads in the 13 plant, it provides normal heat exchangers. So, whether --
14 depending on the season with the lake temperature, how cold 15 is your cooling water; depending on the operation of the 16 plant, how much heat are you trying to remove from your 17 systems; depends on how much flow is going.
18 And on the day that the incident occurred, there was 19 not much heat going to the plant, of course, because weve 20 been offline shutdown for a year and a half.
21 So, the pressure with the alignment of the heat 22 exchange system was relatively high. It was over, a little 23 over a hundred PSI. Normally, normal operation, we would 24 expect it to be more around the range of 70 PSI. In fact, 25 thats what the original analyses were based on.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
61 1 So, we learned from this, that there was an 2 additional amount of pressure, about 30 PSI, that needed to 3 add to the analysis to get a full bounding assessment of 4 potential pressures.
5 MR. GROBE: This is really an 6 interesting issue. Im not sure if youve gotten far 7 enough along in your event investigation team work to 8 completely answer this question.
9 What would prevent these kinds of situations from 10 occurring during normal operation? Are you permitted to 11 take one CAC out of service during normal operation?
12 MR. POWERS: Yes, during normal 13 operation, we have three CAC units, and youre required to 14 have two. We are required to have two in service, and 15 thats one on each train.
16 So, during normal operation, you have flow paths 17 open on each train. Thats very important those flow paths 18 are open. So, when the pumps restart, the flow can proceed 19 through the CACs and pressure waves are relatively low.
20 So, the bottom line is, in Modes 1, 2 and 3 when the 21 CACs are required to be operable, theyve aligned them such 22 that the pressure waves are not so high.
23 MR. GROBE: But do your 24 technical specifications permit you to go down to one CAC 25 for a period of time?
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
62 1 MR. POWERS: Yeah, Mark has 2 said, for a limited amount of time, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3 MR. GROBE: Are there any 4 operating restrictions that prevent pressure from getting 5 higher in the Service Water System?
6 MR. POWERS: What were doing 7 is, basically were providing analysis, were revising our 8 calculations, Jack, to be sure we encompass that 9 condition.
10 And I should go on and add, weve done the 11 assessment for the short term, and taken actions for the 12 entry into Mode 4, done a full structural assessment of 13 bellows and piping system, very detailed walkdown, finite 14 element analysis of the bellows in their as-found 15 conditions for CACs 2 and 3.
16 Also, had an independent third party bellows expert, 17 if you will, somebody whos participated in the Expansion 18 Joint Manufacturers Association Standards Boards, take a 19 look at the situation for us from a third party perspective 20 and be sure we have good margin for entry to Mode 4. And 21 we do, providing operability evaluation of that effect.
22 But the long term actions will be taken. Well add 23 further margin in the system as well, not only revising the 24 calculations to encompass this; system pressure could be 25 higher, we are also looking at things like providing tie MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
63 1 rods on the bellows to further provide structural margin 2 there.
3 So, there is a number of things were looking at 4 right now to improve the margins.
5 MR. GROBE [Unknown]: Even the one we 6 had out of service, that took the 2X water hammer when it 7 was out of service. It still has margin left even after 8 the water hammer. Its the form, bellows deform, there is 9 still margin there, and structurally sound.
10 MR. THOMAS: Sir, are you 11 saying that you could put CAC 1 back in service and call it 12 operable in its present condition? Is that what you just 13 said?
14 MR. POWERS: Yeah, we possibly 15 could be able to do that, based on the analysis that weve 16 done today, Scott. (mike adjustment) 17 What I said is, based on the analysis weve done 18 today, that could be possible. Weve examined it, because 19 we want as much margin as possible in the plant as we 20 proceed to Mode 4. And so, examined, was there a 21 possibility, what was the actual condition of the CAC 22 number one bellows.
23 And the stress analyst will tell you from a plastic 24 deformation standpoint with a straining criteria on the 25 material, has the capability of a 30 percent strain. We MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
64 1 believe that CAC number 1, there is about a 10 percent 2 strain has occurred, based on that two times water surge we 3 were talking about. CACs 2 and 3 were at about 5 percent.
4 So, there is still margin available. And these 5 bellows, for those of you, perhaps a good description of 6 them would be like a radiator hose made out of metal. So, 7 they are kind of like an accordion.
8 So, what were evaluating here is something thats 9 designed to move and looking at whether its in its design 10 specifications and what we refer to as ASME Code, which is 11 the piping pressure code, design code requirements that we 12 are licensed under.
13 MR. MYERS: We dont have an 14 intention to declare it operable, but we do have an 15 intention to declare it functional, so we have additional 16 margin, so were trying to get as much margin as we can.
17 So, I asked them to go back and analyze those valves 18 also, and they indicated to me there is margin there.
19 MR. THOMAS: So, let me 20 understand. Youre saying that CAC 1 will be available for 21 service during the Mode 4 test?
22 MR. MYERS: Yeah.
23 MR. POWERS: Were evaluating.
24 MR. THOMAS: Okay.
25 MR. POWERS: Scott, thats MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
65 1 based on preliminary calculations that have been done up to 2 about noon time today. Thats preliminarily results of 3 stress analysis calculations. So, there is further work to 4 do. There is also the air-operated valve associated with 5 that CAC also has work remaining on it, but I think Lew had 6 a good point here in terms of would it be available to us 7 should we want to utilize it as a backup.
8 MR. THOMAS: Where is that 9 evaluation documented?
10 MR. POWERS: Its currently in 11 preparation. As I said, preliminary calculations. So, we 12 will head down the track of operability evaluation with 13 that to formalize it, if all the analysis supports that.
14 MR. GROBE: Does your design 15 basis earthquake analysis include a loss of offsite power?
16 MR. POWERS: I believe so, 17 Jack, but I would want to reserve and go back to be sure.
18 MR. GROBE: I believe it does 19 too. So, in the stress analyses that you did, did you for 20 these bounding calculations, did you include design basis 21 earthquake concurrently with the offsite power and pressure 22 surge?
23 MR. POWERS: I believe we 24 included the combinations that would be appropriate for the 25 license basis, Jack. I have to go back, I want to go back MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
66 1 to verify that to the level of detail I dont have today, 2 but I believe so.
3 MR. GROBE: Okay, as far as 4 the long term actions that are being finalized, you havent 5 finally determined what actions you need to take; is that 6 correct?
7 MR. POWERS: Thats right.
8 MR. GROBE: As far as design 9 activities, those have to be determined yet?
10 MR. POWERS: Thats right. We 11 have a design team looking at that now, at options, at 12 materials availability, which is valves, and that type of 13 equipment; and looking at what the, the most appropriate 14 way to go about it is.
15 MR. GROBE: Okay.
16 Any questions?
17 MR. THOMAS: Is your intention 18 to put the leak valves back on the CACs?
19 MR. POWERS: Right now, yes.
20 Were looking at that. Thats been a question weve had, 21 Scott.
22 The CACs in the past years at the plant, there was a 23 question about thermal, whats referred to, again, pressure 24 design code is thermal overprotective pressure protection.
25 If you close valves on a vessel filled with water and it MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
67 1 heats up, pressure will, like a pressure cooker, which has 2 a relief valve.
3 There has been various special systems that theyve 4 done in the past that had resulted in the removal of small 5 relief valves from these Containment Air Coolers, and with 6 actions being taken to assure that they would not 7 overpressurize. Were reevaluating that now, and heading 8 down the track of putting some of those reliefs back in.
9 MR. MYERS: Yes.
10 MR. POWERS: Yes.
11 MR. THOMAS: Prior to startup?
12 Is this a prior to startup action?
13 MR. POWERS: Currently, thats 14 what were talking.
15 MR. THOMAS: Okay.
16 MR. RULAND: Jim, I would like 17 to bring you back to the, the HPI pumps. If you remember, 18 we had some discussion about whether --
19 (mike problem) 20 We have been having some discussion in the past 21 about having a public meeting with the HPI pumps. Sounds 22 like now, like, you know, you want to start possibly 23 planning a public meeting to kind of flush out, not only 24 for our benefit but the public, exactly where youre at; 25 and given that your design is not complete, and sounds like MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
68 1 your debris is finalized, it appears that this might be, 2 you should go forward and start planning meetings. So, 3 well be having further discussions on that matter.
4 MR. POWERS: That would be 5 good.
6 MR. GROBE: That meeting will 7 most likely occur in our headquarters office.
8 MR. POWERS: Okay.
9 Okay, if there is no more questions on the closure 10 of technical issues, I would like to turn it over to Rick 11 Dame, who will talk about our Operational Readiness 12 Assessment Program.
13 MR. PASSEHL: Jim, before we 14 move on, we covered about half of the agenda. Lets take a 15 ten minute break until 20 minutes to 4, and rejoin. I 16 notice Rolland Lickus, our State Government Officer is 17 here, so he must have brought those monthly reports with 18 him. So, go ahead and pick one up if you like.
19 Thank you.
20 (Off the record.)
21 MR. PASSEHL: Okay, were ready 22 to get started. Go ahead, Rick.
23 MR. DAME: Thank you.
24 My name is Rick Dame and I would like to talk a 25 little about the two roles I was brought up to the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
69 1 Davis-Besse facility to help out with. Im from the Perry 2 Nuclear Power Plant and the first role that I talked about 3 last month was assistance with planning the Integrated 4 Restart Test Plan.
5 Now, my background at the Perry Plant was a former 6 Senior Reactor Operator and I had put together the shutdown 7 and startup sequences for the Perry Plant for a couple of 8 refilling refueling outages. So, I brought that knowledge to the 9 Davis-Besse Station and it helped them put together a very 10 comprehensive plan called the Integrated Restart Test 11 Plan. Now, this plan is a detailed evolution all the way 12 from initial Mode 4 to a hundred percent power.
13 We talked earlier about the 7-day Normal Operating 14 Pressure Test. Thats a big segment of this particular 15 test sequence. And this plan covers the structure, 16 expectations, assignments, and detailed schedule, 17 contingencies that will be put in place to support the safe 18 and event-free startup of the Davis-Besse plant.
19 And this particular document for the sake of the 20 panel will be included as part of our revision to the 21 Implementation Action Plan, which was Checklist Item 5.d.i.
22 So, well be revising that. This is sort of up and beyond 23 what you already have seen in that plan. Again, its an 24 extremely detailed and comprehensive test plan.
25 One additional note, we talked about some of the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
70 1 work thats been done at this facility; all 2 post-maintenance testing captured in this particular 3 document, as designated down to the owner by night shift to 4 day shift depending on the disciplines, and those have been 5 published and have been distributed to the organization and 6 folks are walking down those activities, so theyre well 7 prepared to handle those tests when they come up.
8 So, that was the first role that I was brought out, 9 and, as Lew mentioned, this was approved earlier today.
10 So, this plan is in place.
11 Now, I get an opportunity to move to the second 12 role, which is a little bit different and I would say maybe 13 a little more challenging. Thats to take a look at 14 Operational Readiness in the Davis-Besse Nuclear Facility.
15 So, Im here to talk about the Operational Readiness 16 Assessment Plan.
17 Next slide.
18 The desired outcome of this assessment is to 19 demonstrate the readiness of the people and processes to 20 safely and reliably operate the plant.
21 We have heard through the different presentations 22 over the months the amount of time and effort that has gone 23 into improving processes, trying to change attitudes, 24 trying to improve culture of the station with regards to 25 nuclear safety. So, what this Operational Readiness Plan MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
71 1 is going to do is more or less take a step back and see how 2 effective we have been at those particular measures.
3 Next slide, please.
4 There is a couple ways you can do assessments; you 5 can test people; you can put forth surveys; you can 6 interview people, but probably the most effective way of 7 assessing the behavior of an organization is through 8 observations. So, thats the method that were going to be 9 utilizing for the Operational Readiness Assessment Plan.
10 So, were going to conduct observations and 11 assessments during the 7-day Normal Operating Pressure 12 Test. This is a very, very unique opportunity, because 13 its a complex task. Its going to involve a lot of 14 operation evolutions, a lot of post maintenance testing, 15 potentially a lot of decision-making if emergent issues 16 come up. So, this is going to be a very, very unique forum 17 to assess the organization.
18 Were going to perform potentially some exercises, 19 depending on the amount of activities that are going on at 20 the facility. Ill talk about these a little bit later, 21 but weve put some together to take a look at standards and 22 processes to ensure appropriate, safe and reliable 23 operation. Again, well talk about this a little bit 24 later.
25 One thing before we move from this slide, Im here MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
72 1 talking about the assessment plan. Its not just myself 2 doing an assessment. Youll see that we have a very, very 3 comprehensive team thats going to be brought in to assess 4 the organization on various levels. I think youll find it 5 a very unique structure and its going to be very, very 6 beneficial to the Davis-Besse station.
7 Next slide.
8 The Assessment Criteria. Any time that youre doing 9 an assessment, youre going to want to evaluate against 10 standards. The Davis-Besse station has a couple of 11 standards they use internally specific to the operation of 12 the power plant. One, is they have a Conduct of Excellence 13 handbook.
14 What this is, is a handbook thats been passed out 15 to the entire Operations Organization. Its issued by the 16 Operations Manager, and it more or less communicates his 17 expectations with regard to the operation of the facility.
18 That also works hand in hand with the procedure called 19 Conduct of Operations.
20 Besides those two criteria, again looking back at 21 some of my past experiences, I was a host peer at the Perry 22 Nuclear Power Station for a World Association of Nuclear 23 Operator Assessment. The World Association of Nuclear 24 Operators utilized performance objectives and criteria.
25 Theyre very similar to another organization thats MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
73 1 domestic to the U.S., the Institute of Nuclear Power 2 Operations.
3 So, next slide, please.
4 Lets talk a little about the World Association of 5 Nuclear Operators Performance Criteria. This group is a 6 worldwide group. They look at nuclear operation, 7 domestically, and across the world. What theyve done is 8 theyve assembled a set of consistent standards of 9 excellence to determine station strengths and weaknesses.
10 For this particular assessment, were going to 11 select a couple portions of this. Its really a 12 comprehensive book of different criteria, but were going 13 to focus on "Operational Effectiveness" and "Operations."
14 Now, for those not familiar with the criteria, what 15 the particular criteria might look like under 16 Organizational Effectiveness is there is a number of 17 different things that would be looked at. One type of 18 example would be, how much the management staff challenges 19 each other when they look at different situations.
20 For example, if Dave were to come up to me with a 21 Condition Report, which is one of the ways we document 22 issues; it gets issued; it ends up the next morning getting 23 evaluated by the management team. How much interaction is 24 there and challenging, healthy challenging amongst the team 25 to assure that an effective decision is made. So, this is MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
74 1 some of the types of things well look at.
2 Well look at also how operators take a look at 3 equipment. Do they recognize normal trends? What they do 4 when they see abnormal trends? Is it documented? How 5 effective is it documented? What measures are taken?
6 Again, testing a questioning attitude, a lot of the thought 7 processes with regards to nuclear safety culture and 8 operation of station.
9 Next slide, please.
10 MR. GROBE: Rick, I have a 11 question before you go on.
12 MR. DAME: Yes?
13 MR. GROBE: Are the weight of 14 performance indicators or performance criteria, are those 15 publicly available?
16 MR. DAME: I believe they 17 are. Id have to verify that. The criteria were using 18 are the 1999 version, and I could get back to you with more 19 information on that, Jack. I do know that the INPO, the 20 new evaluation criteria, there is a lot of similarities 21 with respect to the WANO criteria.
22 MR. GROBE: Okay, thank you.
23 MR. DAME: Lets talk about 24 the Integrated Assessment Team. I mentioned that Im 25 certainly not working alone with regards to this MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
75 1 assessment. In fact, Im very, very fortunate to have a 2 very, very talented staff thats going to be assisting me 3 with this assessment.
4 Really, you probably need to look at this Integrated 5 Assessment on three levels. One, there is going to be a 6 line assessment. Myself will be the leader of that 7 particular assessment, and what well be looking at is 8 different evolutions within the plant. Again, looking for 9 conduct of Ops, if the behaviors in the field match the 10 expectation of station management.
11 So, Ill be looking at that from one level. Lets 12 call that the Internal FirstEnergy Nuclear Assessment, 13 because in addition to myself, there will be support from 14 our corporate office, folks from the Perry station, their 15 Senior Reactor Operator Level, also from the Beaver Valley 16 station. So, again, those are all FirstEnergy power 17 stations, nuclear power stations, that will be working on 18 that portion of the assessment.
19 Were fortunate enough to have a number of external 20 operational assessors coming in. Most of these individuals 21 are talented, visionary, change agent Senior Nuclear 22 Executives that have helped turnarounds at other stations 23 or improve station performance. This group will be taking 24 a look at mostly the organizational effectiveness. Theyre 25 going to lend their talents not only in observations, but MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
76 1 going to look for that talented group of people to provide 2 recommendations.
3 For example, if they were in charge of facilities, 4 things they would be thinking of doing to improve 5 performance in certain areas. Again, its a great 6 opportunity. We have a whole week to more or less pick the 7 brains of some of the industrys best with regards to 8 running nuclear power stations. So, that will be the 9 second group of assessors.
10 Lastly, I dont want to steal any thunder from Steve 11 Loehlein, but we have Quality Assessment going on during 12 the entire Normal Operating Pressure Tests. And Ill let 13 Steve talk about that quite a bit more, but its really the 14 third level of assessment. Teams will be working in 15 conjunction with each other to assess station performance, 16 operational readiness during the 7-day Normal Operating 17 Pressure Test.
18 Well talk about the products here a little later.
19 Again, if you look at the diagram, again, the middle 20 portion is that line assessment that I talked about, some 21 of the interaction with plant management, plant staff.
22 Okay, you see down at the bottom part the External 23 Operation Assessment tying in along with the Quality 24 Assessment. Well talk about some of the products and 25 deliverables that will be coming out of this particular MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
77 1 assessment.
2 Next slide, please.
3 Okay. As I mentioned, the 7-day Test provides a 4 very, very unique gathering opportunity, as I put it on 5 this slide. Well be looking mostly at evolutions that are 6 already in place and scheduled and activities tied directly 7 with performance of Normal Operating Tests.
8 We talked about some of the processes and 9 improvements. Well be looking at a lot of things with 10 regard to inspections, the way were doing business there; 11 again, some of the problem-solving of emerging issues.
12 These are new processes that have been enhanced to help 13 support the restart at the Davis-Besse facility.
14 Second bullet, we talk about organizational response 15 to actual emergent issues. Were very proud of the 16 document that weve sort of built upon industry experience; 17 both problem-solving and decision-making procedure. When 18 emergent issues come up, the management team can declare 19 the use of this particular document; really, anyone can, to 20 help systematically and rigorously work through issues to 21 find the best solution and most effective solution. So, 22 well be taking a look at how the station is utilizing that 23 instruction.
24 Last, but not least, organizational response to 25 emergent issue exercises. You heard Mark Bezilla talk MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
78 1 about earlier a lot of the different things weve worked on 2 in the plant. We do expect some minor emergencies to come 3 up. Its sort of the nature of starting up a power plant 4 thats got thousand and thousands of components; however, 5 if were pleasantly surprised with day 3, 4, 5, 6 of this 6 test, everything is running completely smooth and we 7 havent seen certain types of organizational response to 8 issues, well have some exercises we can utilize and well 9 talk about those on the next slide.
10 "Emergent Issues" Exercises. Again, these are more 11 or less contingencies that we expect to see in a number of 12 different observation opportunities that well take 13 advantage of, but we do have some we put in place. Ill 14 describe some of these in a little bit of detail as we walk 15 through the things that we potentially look at.
16 The one thing, having been a Senior Reactor Operator 17 at a nuclear power facility, I have utmost respect for the 18 control room crews, especially in the middle of a complex 19 evolution, to minimize distractions; and every measure will 20 be taken to ensure that there will be no distractions to 21 the control room crew, more or less moving them away from 22 that sole mission or primary mission of safe event-free 23 operation.
24 So, you might ask what kind of exercise would that 25 be? Again, we would like to look at the cognitive thought MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
79 1 process of how people take a look at issues, look at their 2 significance, and how they may react to them, again, in the 3 spirit of nuclear safety culture.
4 Interestingly, we talked about 14,000 odd Condition 5 Reports this year. Some of those may have looked innocuous 6 on the surface, but once it got dug into proved to be 7 pretty significant. We might just go back in that whole 8 database, so to speak, and maybe utilize one of those to 9 improve, see if some of the lessons learned applied from 10 some of those Condition Reports have been retained and how 11 they react to them. That might be one way to look at 12 things.
13 There is other ones where we might bring up a 14 Condition Report, and again, we bring it up, again, 15 assessing the determinations made by the shift manager.
16 There might be absolutely nothing wrong with this Condition 17 Report, but well see if maybe they overreact or 18 underreact.
19 Again, we want to take a look at the response and 20 maybe the thinking aspect of the shift manager, but then, 21 more importantly, we would like to see what happens once he 22 does look out for help, because again, were moving towards 23 an operating facility. Thats the mission of the entire 24 station to support operations when issues come up.
25 Okay. So, we want to see how apt those shift MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
80 1 managers are to ask the organization for help. We dont 2 want a shift manager particularly trying to solve all the 3 issues they can. We have a whole lot of people around.
4 Theyre very talented to support that operation staff.
5 Again, its got to be about operations leadership when you 6 start talking about an operating facility. We need to make 7 sure that organizational support is used accordingly.
8 Some of the types of cognizant-type exercises, maybe 9 some of the things we would take a look at, mentioned 10 Condition Reports, one aspect of those are Operability 11 Determinations. What those are, is lets say, Bill were to 12 find an issue out in the plant, writes a Condition Report, 13 and it happens to be on a piece of equipment. That piece 14 of equipment, probably very important to the operational 15 staff; hell take a look at it. One of first questions 16 hell ask himself; am I operable or not.
17 Okay. So, we may put some of those exercises in to 18 exercise that thinking again. Not stuff thats obvious, 19 stuff that requires some thinking to put together, ask some 20 questions, I would like this looked into a little more.
21 Priority 200 Work Order. What those are, is an 22 organizational response to a work issue or a problem that 23 needs to be addressed on a 24/7 or around-the-clock basis.
24 Really, well be looking at the organizational response, 25 not necessarily what the control room is doing as they are MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
81 1 asking for that help. Okay.
2 Procedure changes. I know one of the things Lew 3 Myers is always talking about is procedure changes. Lets 4 take a look at some of our processes there, things we can 5 do to get better. Again, its an aspect of operating a 6 power plant that is important.
7 Immediate investigation and off-hour equipment 8 challenges. Things to take a look at. Again, when you 9 look at off-hour challenges, something happens at 3 in the 10 morning; I know at my station more often than not, Ill get 11 a phone call, "Hey, Rick, what do you think about this?"
12 So, well see if those kind of things are happening here 13 with regard to decision-making and response to issues, 14 again, weighing significance of issues.
15 Next slide, please.
16 MR. GROBE: Excuse me, 17 Rick. I just had one quick question. You may have said 18 this and I just didnt understand it. What exactly is a 19 Priority 200 Work Order?
20 MR. DAME: The priorities at 21 the station with regard to work orders, there is basically 22 a tiered approach. Priority 100 is absolutely emergent.
23 It would be something you have to do to protect the health 24 and public safety by an issue. What that means, you would 25 go out and basically fix it and some of the paperwork MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
82 1 sometimes would follow; for example, work order.
2 Priority 200 is something that needs to be responded 3 to in a round-the-clock type of action. Might be something 4 that puts you into, for example, a 7-day limiting condition 5 of operation for tech specs. Okay. So, there is a, a 6 desire to recover that piece of equipment and bring it back 7 to its operational function to support operation of the 8 facility.
9 A Priority 300 would be something that would be 10 addressed ideally within a 21-day period of time.
11 And Priority 400 would be following your normal work 12 schedule, which would be 12-week rolling average.
13 So, again, its just a prioritization system.
14 MR. GROBE: Okay.
15 MR. MYERS: A tech spec 16 change would be expected.
17 MR. PASSEHL: Rick, I have a 18 question too. Your second bullet there says, "Exercises 19 will be designed to have minimal impact on Control Room 20 Crews." Yet, you have listed an example of exercise being, 21 say, immediate investigation. I dont quite understand how 22 those two match.
23 MR. DAME: Okay, unique 24 investigation is actually done by the line organization 25 outside the control room. So, what that would be is, for MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
83 1 example, one of the Condition Reports or certain criteria 2 might be you want or need investigation done and thats 3 usually a 24-hour response by Engineering Organization to an 4 issue.
5 Again, one thing about these exercises, I talk about 6 the utmost expect respect for the control room crew, none of these 7 will be put into play without the consent of the entire 8 Integrated Assessment Team. So, that would include not 9 only the line staff, but the external staff.
10 So, again, I think well have plenty of opportunity 11 to take a look at these, a sort of contingent if were 12 pleasantly surprised and the plant is operating flat out 13 perfect throughout 7-day test. So, again, that was a 14 desire to put together some exercises.
15 MR. MYERS: You know, running 16 drills on shift is nothing new. We have fire drills, 17 safety drills, weve been exercising for years on shift.
18 So, you have to be cautious about it. Were sitting there, 19 once we get the plant stablized, run the NOP, just sitting 20 there; this is pretty routine, so being able to run some of 21 these things.
22 What we have to do also, is simply being shut down, 23 we have this whole support core around, working around all 24 day and night, because then you have the team calls the 25 facility man. We have to run these drills in a manner MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
84 1 where, or the exercises, so that we evaluate how it would 2 be done if that support crew wasnt there. Because thats 3 the next step when we ask to go restart the plant, right?
4 You wont have that support, your support team there 24 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> a day, 7 days a week.
6 So, you know, do we have the right duty calls? Do 7 we have the right procedures? One of the things that we 8 use at our other plants is, in the middle of the night, we 9 would call key members, we have a duty list. We get the 10 team out there and utilize the organization to help the 11 shift supervisor solve his problem. We all work 24/7 when 12 you call on us.
13 How does this team respond? I havent seen that, 14 you know, so we need to look at that.
15 MR. THOMAS: Lew, I agree that 16 testing is done on shift, but I would, I guess, question if 17 its normally done during an infrequently performed test 18 evolution, which the NOP Test would be. And I guess our 19 concern would be that, and likewise yours, Im sure, that 20 it didnt impact the control rooms focus on the test 21 itself. So, thats, I guess, whats driving our interest 22 in this.
23 MR. MYERS: We considered, 24 you know, the infrequently performed test and the evolution 25 were using for this. What that does is add additional MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
85 1 layers of management to monitor stuff like that.
2 MR. THOMAS: I understand.
3 MR. MYERS: You know, bringing 4 the plant up, and heating it up and getting all the pumps 5 running and everything, and testing your equipment once we 6 get there is pretty tough, and cooling back down. Once we, 7 for 7 days just sitting there, there will be several days 8 there where its pretty, pretty, just not much going on, so 9 thats the time period were looking at.
10 MR. THOMAS: All right.
11 MR. DAME: Again, Scott, I 12 want to reemphasize, these are sort of contingent plans and 13 activities and not all of them will be initiated. We want 14 to again look at organizational effectiveness too. If an 15 issue is happening, its in Engineering, if its in their 16 house; are they addressing it with a matter of priority it 17 measures, deserves, and bringing responses and solutions to 18 Operations versus maybe Operations always calling out.
19 Again, were trying to look how these organizations 20 work together for operational readiness. Well be very, 21 very cautious. Again, it will be a group decision before 22 we head out.
23 MR. MYERS: At our other two 24 stations, we have clerical support on shift to help out 25 with procedure changes. So, I dont see that right now.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
86 1 So, how would it work here in the middle of the night?
2 We need to understand.
3 MR. THOMAS: Okay.
4 MR. DAME: Okay, the last 5 slide that I would like to talk to, is how were going to 6 document these assessments. This is a question that came 7 up at the last 350 public meeting. And, there is actually 8 a couple different vehicles that we can use to document the 9 assessments.
10 My particular team, Internal Assessment Team, is 11 going to use the FirstEnergy Nuclear Focus Self-Assessment 12 Report document. A Report Number 2003-21, so, this will 13 capture all the different operation from the Internal 14 Assessment Team.
15 We also have a computerized data base which we can 16 put observations on, and, again, were going to sort of 17 leave it up to the teams once we have our initial 18 coordination meeting. Its going to happen probably 19 tomorrow or the day after with regards to the vehicle we 20 would like to use to document these observations.
21 The External Assessment Team as part of this plan.
22 Again, this plan covers all three of these reports that 23 well see here as deliverable documentation. Theyll be 24 supplying a report within 10 days to the President of 25 FirstEnergy Nuclear.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
87 1 That same 10-day due date, okay, is also applied to 2 the Internal Assessment Team, as well as the Quality 3 Assessment Team; and thats all part of this report here.
4 So, again, I dont want to steal any of, steal any of 5 Quality Assurances discussion which is coming up next 6 here, so theyll talk quite a bit about the assessment 7 report, what theyll be looking at.
8 All these reports are going to be included in the 9 final Integrated Restart Report. So, again, one of the 10 Checklist items, I believe its 5c, talks about Operational 11 Readiness for Restart, a lot of these observations and 12 assessments will be documentation, support documentation 13 for them for the final Integrated Restart Report.
14 With that, I open the floor to questions.
15 MR. GROBE: Just one 16 additional question or comment actually. If we could put 17 slide 33 back up, three slides back, I appreciate it.
18 Thank you. I just wanted to make a couple 19 observations about this plan. Engineers love drawings like 20 these, love to have that up there.
21 The Quality Assurance Assessment is something thats 22 required by NRC, and were going to hear Steves plans for 23 what kind of assessments hes going to do. I think this 24 overall plan is very well conceived. It will provide a 25 very solid insight augmenting Quality Assurance for putting MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
88 1 people in at the experience, all quality people in at the 2 working level, looking from the inside at whats going on; 3 and if there isnt enough going on, you have this plan for 4 exercise, which is something I havent seen before. It 5 will be interesting to see how it works.
6 In addition to that, you have this External 7 Assessment with experts across the industry. I think this 8 is a very solid plan and it will give you a lot of insight, 9 and I look forward to our next meeting, hearing the results 10 of what you learned.
11 MR. MYERS: I think, is Russ 12 Carney here now?
13 MR. DAME: Yeah, Russ Carney 14 the Operations Manager of the Perry station will be 15 participating in this.
16 MR. MYERS: Is he here?
17 MR. DAME: He was here 18 earlier.
19 Again, were going to be getting the best and the 20 brightest of the Operations Departments across First 21 Nuclear to help out. Again, well be making observations, 22 at the same time making recommendations, things that can be 23 done to improve organizational effectiveness and 24 Operations.
25 MR. MYERS: Okay. Steve.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
89 1 MR. LOEHLEIN: Thank you.
2 While the rest of the organization has just finished 3 up discussing all the progress theyve made, all their 4 plans for finishing preparations for plant restart; the QA, 5 we have sort of a different role, its our job to continue 6 to assess their activities and assure that they continue to 7 make improvement in areas where its needed.
8 So, the focus of my discussion today will be really in 9 three areas; first will be the Corrective Action Program, 10 then Ill talk to you about some of the observations weve 11 made recently in the last several weeks, and then at the 12 end I want to discuss these activities that we have planned 13 during the Normal Operating Pressure Test that has been 14 mentioned earlier today.
15 So, this first slide here is an update on the 16 Corrective Action Review that we spoke about in several 17 previous meetings. Ill kind of remind everyone about what 18 some of this data is.
19 The Quality Organization some months back led an 20 investigation review of the Corrective Actions associated 21 with quite a number of Condition Reports. We looked at it 22 from the standpoint of Corrective Actions generated out of 23 it. There were 5,402 completed Corrective Actions that we 24 looked at, at the time, which include all of the 0350 25 Checklist related Corrective Actions.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
90 1 That review team some weeks back concluded in 92 92 2 percent of those cases, there was an acceptable connection 3 between the Corrective Actions that were taken and the 4 records and documents that led back clearly to the 5 condition described in the initial Condition Report.
6 In about 8 percent of the cases, the team concluded 7 was inconclusive or unacceptable and they generated 37 8 Condition Reports as a result of; and those 37 Condition 9 Reports documented 422 sort of discreet occurrences of 10 issues they had questioned.
11 Since last months tally, now as of the other day, 12 it is, 221 of those 422 issues have been investigated. And 13 the fallout of it is, 185 is proved to be documentation 14 errors or inadequacies, which means that in those cases an 15 appropriate action was taken in response to the condition, 16 but the documentation that led from the initiation to the 17 ultimate action that was taken needs to be improved.
18 There were 36 cases found so far, missed items or 19 procedure errors. Of those 36, found to be dominated by 20 two specific types of errors. We found 8 cases in which 21 there were issues closed, assuming they would make a change 22 to the Preventative Maintenance Task that would cover an 23 ongoing action. So, in many cases that did not happen.
24 There were also about 15 cases so far, that issues 25 that were expected to be in the Checklist for the walkdowns MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
91 1 to be done for the Mode 3 Pressure Test, QA found in these 2 15 cases, they were not on the checklist.
3 Sort of the conclusion of this thus far, is if you 4 look at these cases, none of these has been a significant 5 condition adverse to quality. They represent in a certain 6 percentage of the cases only a small percentage of the 7 cases some more minor items were missed, and they are being 8 addressed.
9 Any questions on this review?
10 Next slide, please.
11 Because of the importance of the Corrective Action 12 Program, I thought I would update you, Jack, and the rest 13 of the team on some of the things weve been doing. Im 14 sure that your Residents know that weve been following the 15 Corrective Action Program pretty closely. We do that every 16 quarter as part of our Continuous Assessment Process. So, 17 we get data on a regular basis. And, I want to share with 18 you those things we are emphasizing to the organization in 19 terms of requiring attention by management.
20 First, the, since last month we talked about 21 transition and how the organization would be going into 22 some of its more normal practices, back to their daily 8:00 23 Management Review Board Meetings with Condition Reports, so 24 forth; given us a chance to observe the categorization 25 process.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
92 1 And, conclusions we have at this point is that the 2 categorization process appears to be working properly to 3 the procedure, but we believe that challenges by the 4 organization of each other in that categorization has been, 5 is being held up primarily by three or four key managers 6 who are making the challenges, and that interchange needs 7 to be more of the managers in a more active way. Thats 8 one of the things we provided to management as some 9 insight.
10 Also seen some cases, theyre not using all of the 11 available barriers in reviewing these conditions.
12 Sometimes a Condition Report analyst isnt used or a 13 supervisor has been delegated to approve a Condition Report 14 that normally would be a managers signature. And while 15 thats all okay, we have seen when we look at those 16 examples, that more frequently that those additional 17 barriers or management barriers are not used, we see that 18 the quality of the evaluation tends to droop. So, weve 19 been providing that insight as well.
20 Probably the overall most important thing that needs 21 to happen, I think its been mentioned here before, is this 22 reinstitution of the trending effort. The whole Corrective 23 Action Program as its devised right now is based on the 24 concept that lower level issues will be treated and managed 25 as low level without requiring a great deal of intervention MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
93 1 by management at high levels, not every issue is treated as 2 an earth-shaking type of issue.
3 Thats a good practice when you have a complex 4 machine, like one of these units, and you have a lot of 5 minor tasks, if you will, on the process, but what comes 6 key with that, is that when you use trending to show, to 7 tell yourself where are we seeing peak types of 8 occurrences, and where does it then represent some more 9 important challenge, something that may have a more 10 important cause behind it, needs to be investigated.
11 The current status is that the performance 12 improvement is reinstituting, reinstituting a trending 13 process and their data, as I understand it from them, was 14 collected up to the end of August, and the first report to 15 the management of various departments on their part of the 16 process will be out in September. So, this is being 17 instituted, but we can not have QA pass any judgment on the 18 quality as yet, because there hasnt been an outcome from 19 that process yet.
20 It is critical that this, for the future health of 21 this Corrective Action Program, that that be effectively 22 implemented; and thats something were going to continue 23 to monitor.
24 Questions?
25 MR. MYERS: One of the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
94 1 differences we found when we first came was that our other 2 two plants, went through all the corrective CRs, every 3 morning, and here you --
4 (mike problem) 5 MR. MYERS: The differences, 6 we had the same Corrective Action Process being implemented 7 here and at our other two plants. Our other two plants, we 8 review them. Every night, we would write Condition 9 Reports. And, the next day, we, as a management team would 10 review those and properly classify them.
11 At this plant, we have been shoving it down to a 12 subcommittee, those are being done managers -- by managers, 13 so we lost that ownership. So, we raised that back into 14 the management area. And, we need to continue to focus. I 15 think were classifying right, but I think hes right, we 16 see three or four people challenging every one. We should 17 go over all those CRs at the managers meeting.
18 MR. GROBE: Just one 19 observation. Were going to be talking about this a lot 20 more on October 1st when you talk about your status of your 21 Safety Culture improvements and your long term vision for 22 that. Ive peeked ahead at some of the slides, youre 23 going to be talking about some of these issues also.
24 I understand that youre going to have some monthly 25 performance indicators that are going to give you insight MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
95 1 into the cultural performance of your organization, and 2 well talk more about those on October 1st.
3 But I also view the trending program as very 4 important. Trending programs Ive seen implemented at 5 various nuclear stations over the years have varying 6 amounts of value added, but an effective training program 7 can be a very good precursor indicator for evaluating 8 Safety Culture attributes, whether theyre procedural 9 adherence issues or quality of technical documents or 10 personal performance issues, things of that nature.
11 Prior to reinstituting the trending program, we did 12 have some good feedback that were trends, coming from the 13 nature of trends, but they were coming from individuals, 14 not a structured trending program. The one that comes to 15 my mind right now, is that the Engineering Administration 16 Supervisor was seeing a trend of administrative errors in 17 documentation packages that were coming to him or her. I 18 dont remember the individual. And said, Ive seen enough 19 of this and I want you guys to get to the bottom of it, and 20 wrote a CR on that trend.
21 Thats the kind of thing that is really critically 22 important, as I said, and provides a precursor to more 23 significant issues.
24 So, he deserves or she deserves a pat on the back 25 for identifying that trend, but you need to have a MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
96 1 structured program to continually evaluate what your 2 Condition Reports are saying to you and whether there are 3 any trends.
4 MR. MYERS: Thats really 5 interesting. We write about, on the average, we wrote 6 about 15,000 Condition Reports. What, several thousand 7 Condition Reports a year received at the station.
8 My belief, my personal belief, you know, I hate 9 condition reporting systems. Its not part of the 10 precondition reporting. Ive been to a lot of plants where 11 I find them, the subsystem. We pretty well eliminated 12 that. We have one Corrective Action Program, and our 13 procedures go through there, our engineering questions go 14 through that program and properly classify stuff.
15 We also -- so then that gives us the ability to 16 amend stuff and look at it, and really from a management 17 team understand it.
18 A good example; one of our other plants, say that; 19 we found a Corrective Action in the training program we 20 didnt know about. Found we had like three or four 21 thousand Corrective Actions we needed to take over there, 22 that our management team at the plant didnt know about.
23 So, we had to fix that.
24 So, if you know who is writing the information, the 25 right information or data, not trending is not too good.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
97 1 So, you got to make sure thats the case.
2 Additionally, not only can we do that, one of the 3 things we typically did at our other plants, process called 4 Collective Significance Reviews, Ive mentioned here 5 before. Once a quarter or two, we had at our other plants, 6 our licensing group take a look at all of our corrected CRs 7 and Corrective Actions thats in our database.
8 We also go back and look at other stuff, like INPO 9 reports that we receive, NRC LERs that we are writing, 10 industry experience that were finding; and we try to put 11 that all together as a senior leadership to figure out, do 12 we have an overall site problem with procedure adherence, 13 seek the limits of mechanical maintenance group or 14 something.
15 So, what that helps us do is every year develop 16 focus areas where we want to go with the plant, I would use 17 the words, you use the words Safety Culture awhile ago. I 18 dont think that if you find a negative trend thats 19 necessarily procedure adherence, means you have a 20 materially bad safety culture, but if you start eliminating 21 all these barriers, you wind up with a bad safety culture.
22 Remember the slide I showed last time? So, as we watch the 23 barriers, you see negative trends on the barriers and we 24 act on the trends, so you dont have failures in any of 25 them.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
98 1 So, the Collective Significance Process sort of does 2 that. So, we have those two processes.
3 Once again, Ive been over here at this plant for 4 about a year and a half now and Ive not seen how we really 5 do business. I know the way we do business here is often 6 the way it looks on surface to our other two stations, but 7 when you go dig down, its quite a difference.
8 So, we have a sense of that, make sure that we have 9 consistency. As Chief Operating Officer, my job is real 10 simple, make sure we have good standard implemented and we 11 implement them at all three of our sites. Thats exactly 12 what I intend to do.
13 MR. LOEHLEIN: Okay. This next 14 slide. This one covers some of the things we are doing 15 more at the present time.
16 First of all, the ongoing oversight of qualification 17 testing. That speaks to the high pressure injection pump 18 related testing going on at the laboratories in Alabama.
19 One of my assessors from the engineering side has been 20 there several times in the past. He is there this week. I 21 will be going there myself tomorrow morning to spend a day 22 looking at how that is progressing.
23 Some of the other focus areas, Ive listed the key 24 ones, kind of areas that were looking at to provide you 25 with some of the things weve identified through the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
99 1 organization.
2 One would be, weve talked about Containment Air 3 Coolers today, the valves that were dealing with on 4 Containment Air Cooler Number 1.
5 There was a case that response to the loss of 6 offsite power, that QA thought pretty well performed by the 7 station, but we felt the identification of this particular 8 problem should have been more timely, took longer to 9 identify than it should have.
10 The area of procedure compliance I know is one of 11 significant interest to the NRC, as well as to us. In our 12 second quarter assessment of the organization, we found 13 some data, there might be something to the issue of 14 procedure compliance, I would say, but now were starting 15 to get some data and issues we find that may start to point 16 to what some of the causes might be for the problems that 17 weve had in the area. All, what constitutes work to 18 procedure as opposed to working to the skills that youve 19 been trained to do.
20 Just as an example, we had this week seen a Senior 21 Reactor Operator from Beaver Valley who is on rotational 22 assignment to Quality Assessment at Beaver, came up this 23 week to spend a few days with us, observing testing 24 activities and so forth.
25 And he observed some of the service water testing MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
100 1 that was going on in his summary assessment. The 2 observation was that the operators performed very well. He 3 felt when he compared it to what was done at his station; 4 that the procedures lack quite a bit of guidance in some 5 areas and the operators were more reliant on their own 6 historical knowledge than they would have been at his 7 station.
8 And weve seen some other cases in which the 9 operation staff or the maintenance staff is operating under 10 the assumption that they, this is within their task 11 capability.
12 So, we think now were starting to put together some 13 insights that will help us investigate further where there 14 may be some improvements. There may be not just in 15 performance, but maybe in understanding better what you 16 need a procedure for and what you dont. And that all goes 17 back to training and so forth.
18 So, we want you to know we are starting to get some 19 data along those lines, Jack, you asked me about that some 20 time back.
21 I think -- there are a number of other activities I 22 could talk about, unless you have questions, Id probably 23 prefer to move on to the Normal Operating Pressure Test 24 activities that we have planned.
25 Sort of as a way of context, we have a nice little MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
101 1 map, you pointed out on the slide 33, Jack. It shows how 2 were all working, how we have these roles associated with 3 Normal Operating Pressure Test.
4 Some of the things that QA is going to be looking at 5 there, as it relates specifically to that part, is were 6 going to be looking at, heres some of the specific 7 things. Verifying four hours after reaching normal 8 operating pressure that there is a Mode 3 walkdown to 9 ensure technical leakage is accomplished. Thats one of 10 the things thats required by the process. Well be 11 looking at that.
12 Were going to be observing the Reactor Coolant 13 System Inspection Team. Well be accompanying those teams 14 in the Containment on those walkdowns.
15 Well be observing the work order, procedure 16 process, corrective action activities of the two 7-person 17 maintenance teams that will respond to whatever theyre 18 given.
19 Well be verifying the proper institution of the RCS 20 leakage procedure, and a number of other things. Thats 21 specific to the actual Mode 4 activities.
22 Throughout these evolutions though, we are observing 23 a control room manned control, and a number of other 24 activities that involve coordination with the control room 25 and personnel out in the field.
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102 1 Part of the context I would like to give to this is 2 that were not in QA just doing support of or oversight of 3 this Normal Operating Pressure Test. The whole Restart 4 Test Plan has been under development for sometime some time, and QA 5 has done oversight of the development of that plan. We 6 have provided insights into that.
7 And we are engaged in assessments throughout this 8 Continuous Assessment Process, that includes running up to 9 Mode 4 and 3 and coming back down to Mode 5, and along with 10 that, lots of support activity, Just-In-Time Training. And 11 anybody thats familiar with our Continuous Assessment 12 Process knows other support things that we look at.
13 Probably what I would like to share with you, all 14 this is going to go on in the next few weeks, well share 15 this same importance with the line organization in the last 16 few days. Were particularly interested, not just in the 17 process and how the equipment performs, but in three key 18 areas that relate all the way back to what the organization 19 needs to learn on the reactor head event. The Operations 20 leadership that we displayed, the proper demand and control 21 and guarding of the safety of the plant; the safety 22 culture, which well be able to observe well through how 23 promptly issues are identified and whether theyre 24 prioritized and resolved appropriately and what condition 25 they are. And well be looking at procedure compliance, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
103 1 which was another key ingredient. So, those are kind of 2 the big picture things that well be looking for on top of 3 the others.
4 I would say, finally, the one thing that we get to 5 do that maybe others dont get to do as easily, well be 6 observing line organizations oversight for how well they do 7 oversight. So, that will be interesting for us.
8 Any questions?
9 MR. GROBE: Nope. Thank 10 you.
11 MR. MYERS: I would like to 12 take a couple moments and try to talk about some of the 13 changes we take into the improvements to Anchor the 14 Long-Term Permanent Improvements that we have at FENOC.
15 Next slide.
16 Since the last time we met, there has been many 17 changes made within FENOC to sustain safety focus and 18 improve performance at our nuclear stations. At our 19 corporate level, Gary Leidich has now been named President 20 of FENOC. And I think that happened since our last 21 meeting.
22 We have Staff Improvement Executive, gentleman by 23 the name of Joe Hagan, that reports on the 22nd of 24 September, and Senior Vice President of Engineering and 25 Support to replace Gary.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
104 1 Joe comes to us from the Excelon Corporation. So, 2 you may know Joe. At that company, he was Senior 3 Vice-President, Nuclear Operations-PECO. I knew Joe as the 4 Site VP with Entergy, where he was the Site VP of the Grand 5 Gulf Nuclear Plant. So, were really pleased to have Joe 6 come to us, and in this position.
7 And once again, the other thing that he runs, since 8 shutdown has gone on besides improved our executives, 9 also in charge of our Quality Oversight Group as Vice 10 President. He not only reports to the President of FENOC, 11 he reports to our Board of Directors also, our new 12 Committee Board.
13 At the plant level, weve installed an experience 14 Senior Leadership Team since the shutdown, and well be 15 announcing a new member in the near future. Randy Fast, 16 the previous Plant Manager, Jack, I think you know this, 17 is being moved to the corporate position to ensure the 18 organizational effectiveness for all of our plants.
19 The Safety Culture issues and Organizational 20 Effectiveness, its got to the point now that we want to 21 take Lessons Learned from here and focus on all of our 22 plants. And, Randy will be primarily responsible for 23 consistency and looking at our Safety Cultures and Safety 24 Conscious Work Environment, as well as our training 25 programs at our facilities. There is a lot of ground to be MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
105 1 made at our facilities, you know, consistent training 2 program, consistent with all three facilities. So, Randy 3 will be focusing in that area.
4 The plant senior leadership team now, which is the 5 directors and vice president at Davis-Besse Plant is 6 looking, has over 150 years of nuclear experience. Its a 7 pretty good senior leadership.
8 Nonetheless, theres 13 managers at the plant now, 9 and they form a management team. Thats been a significant 10 strength since the outage. And that team has over 260 11 years of nuclear experience.
12 Another 15 managers, 18 managers as directors that 13 we have in place now, over 15 of those people have either 14 Senior Reactor Operators or Senior Reactor Operator 15 certification. I think one of the major things that you 16 look at, at the decline of this plant, was that we had done 17 a good job in the past of developing the top line of 18 managers, gain SRO and SRO certification, and that went 19 from an SRO pipeline down to a certification, and over time 20 to nothing at all, you know, so we think weve regained 21 that level of operation of experience that we need at the 22 station. And well really be focusing on the SRO pipeline 23 in the future.
24 From improvements to improve safety margin, many 25 improvements have been made that have added safety margin MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
106 1 to the Davis-Besse plant. We talked about several of those 2 today. A couple come to mind. We think the Containment 3 Sump that weve installed sets a new industry standard.
4 Thats the most robust PWR sump Ive seen. We brought some 5 of our experience over from our Perry Plant to develop 6 that. So we think, thats another example of how the fleet 7 approach is serving us well.
8 The new reactor safety seal that we installed will 9 greatly improve, reduce the dose I think we receive each 10 outage, and also our exposure of the reactor vessel. The 11 leakage that we saw, when we inspected it, now corrected.
12 So, we think that is a good improvement to our plant.
13 The FLUS Monitoring System is the first of a kind to 14 be installed in the United States. You know, people say 15 what they want; when you go out and inspect RCS every 16 outage and do all whatever you want to do, but there is 17 nothing there, that we got the only system that I know of 18 thats live time one hundred percent of the time that will 19 tell you if you develop a leak. So, thats, thats going 20 to be a very unique piece of equipment.
21 Im really excited about testing it during this 22 7-day test. Probably one of the ones Im watching the 23 most.
24 The Electrical Transit and Analysis Program we 25 installed, we talked about earlier, called ETAP, allows us, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
107 1 it really is an interesting piece of software. With Jim, I 2 characterize it, as most plants use, when this plant was 3 built, used software, when the plant was built, it didnt 4 have software, but it went to a type of software that 5 allowed us to look at electrical distribution as a whole.
6 Our electrical distribution system has always been 7 robust, but with the new software were able to run 8 transcients; you ask about our switchover, we can make any 9 kind of assumption you want to make. We can make breakers 10 out, equipment out, different pieces out, and run different 11 transients to see what the voltage does and the currents do 12 down, down the component level. It actually takes into 13 consideration the wiring and connectors.
14 So, we think this piece of software that was 15 installed at our plant is not only helping us analyze our 16 electrical distribution better, but its also causing us to 17 make some modifications to our system. Jim talked about 18 several, that there is some more that well be making after 19 the outage. Were going to look at some of the electrical 20 the MCC motor control centers that we have daisy chain at 21 our plant. So, well be making improvements there.
22 So, from a modification standpoint, there has been 23 unique things done at our plant we think that will make 24 this plant an industry lead when its all said and done.
25 From a FENOC standpoint, weve also changed our MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
108 1 vision at our plant, in all our plants, to try to focus on 2 safety more. And we also developed new matrix that we 3 think will be an industry lead. Our vision used to be 4 operational excellence. That was pretty good, but it 5 really didnt send some of the messages we think we want to 6 send. So, weve changed our vision to all our plants to be 7 people with a strong safety focus, delivering top fleet 8 operative performance.
9 The new matrix now monitors Safety Culture. I think 10 that you go look at our, our corporate performance 11 indicators and matrix, I dont know of anyone else thats 12 going to have a routine matrix monitoring Safety Culture 13 and Assessment Program where every couple years they assess 14 Safety Culture of the plant. We built that into our 15 program now. I certainly believe that will make us unique 16 to the industry.
17 Weve taken several actions. I think theyre long 18 term improvements to the Personnel Performance. Next 19 slide.
20 From a training standpoint, weve trained everyone 21 on Lessons Learned. And Ive talked about that before, 22 wont go through everything here.
23 Weve got new training for the managers and 24 supervisor that focus on supervisors focusing now on 25 nuclear safety and professionalism, nuclear MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
109 1 professionalism.
2 There is improvement in our evaluation process. We 3 now have two new areas that we evaluate on, the managers 4 and supervisor under, but what I think is more interesting 5 and really not here, I want to talk about is, Jack, I think 6 you attended our ROP meeting, and observed that for part of 7 this week. Were getting ready to roll out a new tool 8 called Root Learning Map that will be used as what I would 9 call an alignment tool for each and every one of our 10 employees.
11 You know, I find this tool quite, one of the more 12 exciting things that Ive seen. They did a demonstration 13 where the, myself, and the, and the senior leadership team 14 on Saturday, and they used this product, with a cola 15 company project. And we were so interested in, the senior 16 leadership team before it was over with, we were ready to 17 go up to the nuclear power and get a cola. So, it was --
18 maybe we need to do that.
19 But anyway, we thought that was, thats really a 20 good product, and were excited about using it in our 21 plant. So, weve worked with this company for several 22 weeks now on the senior level and manager level to develop 23 this product. Its important that each employee 24 understands the unique responsibilities that we have as a 25 company, for we have to the nuclear industry, and most MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
110 1 importantly, the responsibilities that we have to the 2 public.
3 You know, this tool is designed to make sure that 4 there is clear alignment in those areas. We will provide 5 this alignment training to each and every employee at our 6 plant before startup.
7 Next area. One of our major Building Blocks was 8 the Program Building Blocks, was to ensure that our 9 programs have good ownership, meet industry standards, and 10 give us assurance of good implementation.
11 We made progress with our Corrective Action Program, 12 but were just getting started. We have a long ways to go 13 there. That was evident yesterday.
14 Weve already contracted with an independent 15 contractor, independent review of our design calculations 16 program with Sargent & Lundy starting next week. So, that 17 would continue to improve the quality of our products. You 18 know, when I got through with the, even before that, there 19 is a couple of areas that comes to mind. Engineering 20 calculations are one of them. Make sure thats a good 21 product. So, were going after that already.
22 Weve already started a project to upgrade our 23 engineering design basis, with a new tool called ATLAS. I 24 had it available today. I was hoping to get some time when 25 you guys were at the plant to demonstrate that tool, but we MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
111 1 ran out of time today and got away, so maybe the next time 2 youre there, well be able to give you a demonstration of 3 that product.
4 It is a computerized product that allows, that I can 5 even use, to go in, and you give me an accident, Ill tell 6 you the systems with that product that you have to depend 7 on, the components that you have to depend on, and then it 8 allows me to go to curator and pick up the design basis for 9 each and every component.
10 So, very quickly, you have access to design 11 information at our station. So, I think this is a 12 tremendous tool that we implemented at our Perry Plant. We 13 already have the products in place to implement it here.
14 Next slide.
15 We also made great improvements I think in our 16 Oversight Process, our Management Observation Program.
17 Mark talked earlier, one of the main tools we used 18 in the 7-day Test is the Management Observation Program, 19 besides the Corrective Action Program. Each and every 20 activity, we already have a detailed schedules of managers 21 to be on shift to observe activities using our Management 22 Observation Program.
23 New performance indicators are visible at each and 24 every department. You walk around the site, even on the 25 walls, what we think, that we expect each and every MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
112 1 employee in that department to understand. So, weve got 2 these new performance indicators in place.
3 The Safety Culture Assessment, we think is not only 4 a good improvement, we think our process is probably, and 5 its our opinion, the best in the industry. And weve 6 looked at all of them.
7 The Engineering Assessment Board was put in place to 8 ensure quality of our engineering mods. And theres 9 probably some other areas we can use that in.
10 Then augmented independence and capability of our 11 Quality Assurance Group, I think has given us great 12 dividends. I look back at some of the Quality Assurance 13 reports that are written at our Davis-Besse station; and 14 read the reports, I find them quite good. I just cant 15 come up with the same conclusions that the Quality 16 Assurance group did. So, we think this independence will 17 help us to be self-critical.
18 And then improvements in the Nuclear Review Board of 19 our company and borrowed oversight has really been 20 strengthened.
21 Thats all I have in that area. Any questions?
22 MR. GROBE: Just an 23 observation. I think thats a good bit of information to 24 wet your whistle on, on what were going to be covering 25 October 1st.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
113 1 MR. MYERS: Right.
2 MR. GROBE: Because thats the 3 foundation of what youve done.
4 MR. MYERS: Right.
5 MR. GROBE: Did you have some 6 closing remarks you wanted to make?
7 MR. MYERS: Yes, I did.
8 MR. GROBE: Okay.
9 MR. MYERS: You know, in 10 summary, I started out today discussing loss of offsite 11 power. All of our technical support centers were manned at 12 all three of our plants. We supplied the resources to each 13 other. At Beaver Valley we had food delivered to the Perry 14 Plant. So, those technical support centers were all 15 communications, demonstrating the effectiveness of our 16 fleet approach that we now have, that our three plants are 17 not being, not being operated in isolation anymore.
18 Once again, were confident enough that once we were 19 confident in the stability of our grid, we determined 20 together at our Perry Plant and our Davis-Besse plant, and 21 went back to offsite power at 1940 on August the 15th.
22 What Im most pleased with, is throughout that 23 transit, when Im talking to, talking to Canada and in 24 talking to Bill Pearce, I think our team consistently 25 focused on nuclear safety throughout. Every conversation MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
114 1 we had was focused on nuclear safety.
2 Employees responded both in a timely and effective 3 manner, which is a good sign, the response to our 4 facility. And finally, our equipment, our equipment 5 consists of redundant trains. That means we have two 6 redundant trains that are one hundred percent capable of 7 handling an event, and they all operated well.
8 You know, nuclear guys really like redundant 9 trains. And they like that redundancy. One of the things 10 Ive seen up here with Mark is, hes the only person I ever 11 seen bring two laser beams with him for presentation.
12 MR. GROBE: Do they both have 13 batteries?
14 MR. MYERS: Yeah.
15 We now, were now I think at a major milestone at 16 our plant. Weve entered our Restart Test Plan. Weve 17 tested our Containment. Demonstrated the leak tightness of 18 that area to the public. We performed the 50 pound, 250 19 pound test, and fixed the problems that we found in that 20 test.
21 Were now, were now at 210 pounds, with a bubble in 22 the pressurizer in our reactor. And weve already ran the 23 2-1 and 2-2 reactor coolant pumps. We ran all four since 24 weve been here, all four reactor coolant pumps today, and 25 I think were raw testing now as we sit here, testing our MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
115 1 main control rods.
2 Thats really important. We put the new head on the 3 reactor, but we have not stroked the control rods to make 4 sure they move properly with this new head since weve been 5 shut down. So, stroking these control rods is really 6 important to us. So, thats an exciting milestone there.
7 MR. THOMAS: Lew, could you 8 just for clarity sake, could you be a little more specific 9 with the control rod testing, whats going on, just what 10 exactly youre doing?
11 MR. MYERS: Oh. The control 12 rods are operated from the reactor head, the control 13 mechanism on the reactor head. What were doing is, were 14 proving the rods will move freely without interference, 15 and that the new reactor head is properly aligned to the 16 control rods in the reactor core. So, ensuring those rods 17 will move freely in our reactor core is very important.
18 Were doing that today cold. So, taking like one 19 bank of rods at a time and moving them, making sure they 20 move freely. Does that answer your question?
21 MR. GROBE: I appreciate 22 Scotts question. I think its important to note that in 23 the current operational condition theyre in, there is two 24 ways to control reactivity; one is with the control rods 25 and the other is with boric acid that you add to the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
116 1 reactor coolant.
2 In the shutdown condition youre in, you can 3 actually pull all of the control rods out of reactor and 4 the boric acid thats in the coolant will still maintain 5 the reactor to properly shut down.
6 So, people get sometimes a little "hinky" when you 7 start talking about pulling control rods, but in this 8 configuration, control rod testing is --
9 MR. MYERS: Were simply 10 doing rod testing.
11 MR. GROBE: -- a completely 12 safe activity.
13 MR. MYERS: And with that, 14 once again, our Boron upgrade at 2300 would be in rods, 15 which is quite shut down, so we were simply doing rods.
16 We ran all four of our reactor coolant pumps once 17 again, and beginning to increase reactor pressure the next 18 day up to 2155 pounds of temperature, about 532 degrees, by 19 the operation of reactor coolant pumps.
20 I guess thats sort of hard to understand too, but 21 generally as you start the reactor coolant pumps, and 22 reactor coolant pumps are large machines that circulate 23 about a hundred thousand gallons each of reactor coolant 24 through the core. When you run the reactor coolant pump, 25 you have about 16 megawatts thermal of heat, and so its MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
117 1 easy to heat up the reactor just by running the pumps.
2 So, well be running all four reactor coolant 3 pumps with a bubble in the pressurizers, normal way with a 4 steam bubble, normal way we operate, to increase 5 temperature up to 532 degrees and the pressure up to 2155 6 pounds, which is our normal conditions.
7 So, were doing that today. Were doing that to 8 show the integrity of our Reactor Coolant System and our 9 systems. And that is an exciting time.
10 Most of our technical issues, as Jim said, are 11 complete. We still have a couple out in front of us. We 12 have some electrical changes we want to make and high 13 pressure injection pumps that were working on, and we have 14 the parts and solution for that. And so were excited 15 about that.
16 Were performing the 7-day Test using the Lessons 17 Learned from other extended outages. I mean, you look --
18 Jack, youve been through some of these. We expect to find 19 and fix any equipment problems with the issues resulting 20 from the extended outage, many of them during this test.
21 So, we would expect that our power extension ascension program when 22 we do restart the plant will be smooth. And we would not 23 find some of the problems I think some of the plants had 24 that were in extended outages. So, Im excited about this 25 7-day test and the technical issues getting behind us.
MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
118 1 Well assess our people during this, during this 2 7-day process, our plant and how it operates; and then 3 finally, our processes. And once were satisfied that 4 weve -- and we dont expect this to be clean. We expect 5 to find more problems and go fix them. And once we assess 6 everything, and made the Corrective Actions, well write a 7 report with those Corrective Actions and present that 8 report as part of our Restart Test Plan to the, to the 9 Restart Oversight Panel.
10 Shortly after that, we would expect to, with their 11 approval and with Gary Leidichs approval to come forth to 12 the regulatory agency and tell you that were ready to 13 restart our plant and ask your permission to do that.
14 So, this is a very exciting time and a major 15 milestone for us. As we sit here today, Mark and I keep 16 getting beeps, pages about the status of the equipment as 17 its changing before us.
18 So, a very good opportunity for us, and we look 19 forward to it. We think this is a major milestone in our 20 plant. Thats all we have. Thank you.
21 MR. GROBE: Okay, very good.
22 Thank you. Any final questions?
23 I just want to make a couple of observations. One 24 of the current buzz words in business management vernacular 25 is having an organization built to last. Clearly, the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
119 1 meeting that were going to have on October 1st, and the 2 focus of that meeting is going to be not only what youve 3 done to-date to prepare for restart within the context of 4 Organizational Effectiveness and Human Performance, but 5 also what your structured plans are to ensure that that 6 continues on and how that would be monitored in the 7 future.
8 The panel is charged not only in evaluating the 9 activities that you conduct during a shutdown in making 10 recommendations to Jim Caldwell and Jim Dyer and Bill 11 Travers on whether or not we think the plant is ready to 12 restart at an appropriate time, but also to express the 13 view as to why it has confidence that this plant can start 14 safely and operate in the future safely.
15 So, the meeting on October 1st is a very important 16 meeting and it will provide additional insight beyond 17 Management/Human Performance Inspection Team activities 18 into that aspect of the activity, Return to Service 19 Activity, that is ensuring that the organization is built 20 to last.
21 If you get to the point in time where you restart 22 the plant, not only restarted safely, but it will continue 23 to operate safely in the future.
24 So, thats an important meeting. And we mentioned a 25 couple other meetings that were anticipating in the next MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
120 1 several weeks. One would be discussion of the results of 2 the Corrective Action Team Inspection, and the System 3 Health Inspection. That will be likely in Region III.
4 In addition, were expecting in the next several 5 weeks to have a meeting on the high pressure injection pump 6 redesign and testing activities, and that will be in 7 Rockville.
8 Then, I think we have a public meeting, our next 9 monthly meeting, if I look at my monthly newsletter, which 10 you can all pick up now in the foyer. But our next public 11 meeting is October 7th at 2:00 and again at 7:00; not in 12 the Oak Harbor High School as indicated in the newsletter, 13 but at the Camp Perry, at the Camp Perry facility which we 14 have been in before.
15 So, with that, I think the business portion of this 16 meeting is adjourned, and well reconvene in about five 17 minutes to discuss the, any questions and receive any 18 comments that members of the public have.
19 I think it should be clearly noted on the record 20 that this meeting adjourned the business portion at 1 21 minute to 5, and that is a record. I appreciate that.
22 Thank you.
23 (Off the record.)
24 MR. GROBE: What I would 25 like to do is first, if there is any representative of the MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
121 1 local level -- excuse me, local elected official here that 2 has a question or comment, I would like to give them a 3 chance to ask it, or if they have a statement, I would like 4 to give them an opportunity.
5 I dont see anyone. Ill just open it up for 6 general, general questions or comments.
7 MR. RIDZON: Paul Ridzon, 8 McDonald Investments.
9 On your website today, you indicated that you plan 10 to issue a final report on the NOP Test about 30 days after 11 conclusion of the test. Will this be the first feedback 12 you give, or will there be a preliminary report? And, 13 secondly, is issuance of this report a precursor to 14 restart?
15 MR. GROBE: I think you can 16 interpret every one of our inspection reports as something 17 that is before restart, but I dont believe its proper to 18 interpret the completion of the NOP Test as moments away 19 from restart. I believe that FirstEnergy has publicly said 20 that they anticipate restart during the fourth quarter of 21 this year. The NOP test is an opportunity to discover 22 problems, and to demonstrate that the facility is in a 23 leak-tight condition.
24 As Lew Meyers indicated earlier, and Mark Bezilla 25 also said this, they anticipate finding some problems. It MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
122 1 is not unusual in this kind of situation to find minor 2 leaks on valve packings and bolted connections and things 3 of that nature, which takes some time to complete. And 4 they also went over a number of activities that need to be 5 completed prior to restart, including the three that Jim 6 Powers highlighted today; high pressure injection pumps, 7 the Electrical Distribution System and the Containment Air 8 Coolers.
9 So, there is some work that was not necessary to 10 complete prior to the Mode 4, Mode 3 pressure test that is 11 necessary to complete prior to Mode 2, and those activities 12 will be ongoing.
13 With respect to public dialogue on the NOP Test 14 results, I anticipate that will be a significant agenda 15 item on our next public meeting, which I think I said was 16 October 7th. So, that will pre, that will occur before the 17 inspection report is issued on our inspection of the test, 18 so I anticipate significant dialogue at that time.
19 MR. RIDZON: Thank you.
20 MS. RICK: Hi, Im Shelly 21 Rick with Ohio Citizens Action; with me is Carrie Kree. We 22 are bringing 984 letters today that are written by people 23 across Northern Ohio to Jim Caldwell urging that the 24 Davis-Besse plant be kept closed.
25 These people are not convinced that the technical MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
123 1 fixes that are being made to the plant are sufficient to 2 warrant returning it to service. So were asking not only 3 that you deliver the letters to Mr. Caldwell, but also that 4 you weigh very carefully the points that are made by the 5 residents of Northern Ohio.
6 MR. GROBE: I appreciate --
7 you could leave the box down there, well pick it up. You 8 dont need to bring it up here. I appreciate receiving 9 these letters.
10 We have a new item in the last few months in our, in 11 our monthly update, our newsletter, which is called, I 12 think its called Mail Bag or Mail Call. Its called Mail 13 Call. And weve received over five thousand letters from 14 folks as far west I believe as Oklahoma and as far east as 15 New York State, many letters from people who reside in the 16 State of Ohio.
17 And, I believe all of those letters have been read.
18 Ive read a significant number of them. Jim has read a 19 significant number of them also. And were in the process 20 of responding to every one of those letters, and well also 21 read these letters and respond to them.
22 I wish these people would have the opportunity to 23 come to one of these meetings or spend more time reviewing 24 material thats publicly available on the website, as many 25 of the questions they address are already available MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
124 1 publicly, but we appreciate getting the letters. Well 2 respond to every one of them. And thank you for bringing 3 them to our attention.
4 Is there anyone else that has a question?
5 Yes, sir?
6 MR. KHAR: My name is Ashar Khar, 7 with Foresight Investments.
8 MR. PASSEHL: Would you please spell 9 it?
10 MR. KHAR: I just want to ask, 11 there is no way for us on site to get any kind of report 12 during the test period, you know, the 7 days and all that, 13 just after that, which would indicate whether there was 14 some, something unusual that happened or not, or did not 15 happen. I mean, I know you guys will be monitoring it on a 16 daily basis. So, there is no way that youll get any kind 17 of news relating to whether everything went, within the 18 normal sphere of stuff, or something abnormal happened, 19 earlier than, I guess, the October meeting or the report.
20 Can we expect in some part of your public relations 21 side, if there is something unusual it might come out with 22 something earlier than that?
23 MR. GROBE: There is, I think 24 I understood your question. There is a punch line from a 25 very old joke; no news is good news. But, if anything MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
125 1 significant arises during the course of this test, there 2 are reporting requirements that are in place that the NRC 3 has, that significant issues would need to be, very 4 significant issues would need to be promptly reported and 5 less significant issues would have a longer time frame on 6 reporting to us.
7 But, I believe that there will be information 8 available if there is a significant problem. So, I dont 9 think you need to worry about that. And I just want to 10 emphasize, that I anticipate that the results of that test 11 will be discussed in detail at our next public meeting.
12 And, this is not a short test. I believe its going to be 13 ten or twelve or fourteen days if everything goes well, 14 before the test is completed. And thats well towards the 15 next meeting. So, I think that will be a good opportunity 16 to conduct the test, evaluate the results, and I think 17 FirstEnergy will be prepared to discuss it at that 18 meeting.
19 MR. KHAR: So, if I can just 20 paraphrase it --
21 MR. GROBE: Could you speak 22 up, sir?
23 MR. KHAR: Yeah. You said it 24 will take about ten to fourteen days, starting say, todays 25 is the 10th, the 24th of September, if everything works by MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
126 1 schedule, we would hope to have the test completed. So, if 2 we dont hear anything from the NRC, as you indicated, 3 during that time frame until we come in October, it 4 identifies nothing of any substance happened which 5 required, you know, you to report a major occurrence to 6 headquarters or anything like that.
7 MR. GROBE: I would certainly 8 encourage you to contact FirstEnergy. I believe if, that 9 they would be more than willing to discuss the progress 10 theyre making at any time. So, contact FirstEnergy.
11 MR. KHAR: Okay. Thank you.
12 MR. BROOK: Hi, Im Shawn 13 Brook with HSBC Securities. I just had two quick 14 questions, to actually amplify what my other two financial 15 industry colleagues asked. First was, is there some, were 16 the test to be somehow halted, the important three day 17 period, when there is specifically high temperature and 18 pressure, would there have to be some issue of public 19 safety that would cause the test to be somehow interrupted?
20 MR. GROBE: I missed the very 21 last words, the test would be somehow what, sir?
22 MR. BROOK: Well, the test, 23 theres something wrong going to happen, supposed to last 24 between nine and eleven days; there is apparently from the 25 discussions today, a three-day period where there is very MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
127 1 high pressure and very high temperature. If the test were 2 to be halted for any specific reason, would it have to be 3 for public safety or for one of these potential problems 4 that have been identified?
5 MR. GROBE: Thats a very good 6 question. I appreciate the question. Let me make a little 7 bit of a clarifying statement and then answer your 8 question.
9 There is going to be a period of time that it takes 10 to raise the Reactor Coolant System temperature and 11 pressure up to the normal operating pressure, and normal no 12 load temperature. Then the, that pressure and temperature 13 will be held for 7-days. And then after the 7-days, the 14 plant will be cooled back down to Mode 5.
15 During that period of time, this is a, from a public 16 health and safety standpoint, this is a very low risk 17 evolution. And, its for that reason that the Restart 18 Panel concluded that there were only four of our checklist 19 items that were necessary to close prior to this first Mode 20 4, and the rest of the checklist items are required to be 21 addressed prior to restart of the plant.
22 Those four checklist items were making sure the 23 Containment sump was properly, the modification to the 24 Containment sump was properly modified and properly 25 designed and installed; that the Containment Integrated MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
128 1 Leak Rate Test was effectively conducted; that the Reactor 2 Coolant System Leakage Monitoring Program, that the company 3 has made significant improvements and provisions, was in 4 place and adequate; and that the Boric Acid Corrosion 5 Management Program thats been upgraded during the shutdown 6 has been properly implemented and is adequate.
7 So, those four checklist items have been inspected 8 and closed up. And as far as the agency is concerned, the, 9 no further activities need to be accomplished by us prior 10 to restart.
11 Again, the reason for that, there is very little 12 risk. There is essentially no decay heat in the fuel, and 13 so once the reactor coolant pumps, there is no heat 14 source. So, if there is any significant problem with the 15 Reactor Coolant System, its very easy to immediately 16 ameliorate that problem.
17 If there is a significant problem, obviously, the 18 test would be suspended, and I dont anticipate that.
19 Certainly, FirstEnergy is going to have a lot of people 20 paying close attention to that as is the NRC.
21 I anticipate that there will be a series of work 22 items that come out of this test, as the results are 23 evaluated, and those would be worked off. But I believe, 24 as far as work thats currently known, the critical path 25 work is the work that we heard Jim Powers discuss today, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
129 1 and thats the high pressure injection pumps, the 2 Electrical Distribution System and the Containment Air 3 Coolers.
4 MR. BROOK: Its only the 5 responsibility of FirstEnergy to report --
6 MR. GROBE: Get a little 7 closer to the microphone.
8 MR. BROOK: Im sorry. Its 9 only the responsibility of FirstEnergy to make those 10 reports to inform people that we have those problems, or?
11 MR. GROBE: Well, its the 12 responsibility of FirstEnergy to document problems in their 13 Condition Reporting System as part of their Corrective 14 Action Program. The NRC has regulations for certain more 15 significant Condition Reports that theyre required to be 16 reported to the NRC.
17 At a normally operating plant, there is likely to be 18 several thousand Condition Reports every year and just a 19 few would be required to be reported, just to give you some 20 context to the level of significance of the things that 21 need to be reported as drastically, the routine day-to-day 22 kind of issues that are dealt with.
23 Any work items that come out of this would be 24 handled through the Work Management System at FirstEnergy.
25 So, its their responsibility to identify issues, document MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
130 1 them in the Corrective Action Program, fix them through 2 their Work Management Process.
3 And well have people inspecting this program. We 4 have the three Resident Inspectors, as well as an 5 Operations expert from the regional office and Senior 6 Metallurgist from the regional office who will be on the 7 site.
8 MR. BROOK: Thank you. One 9 last question, if I might. You mentioned something, or 10 someone on the panel mentioned there is going to be a 11 Restart Inspection Team assembled in anticipation of 12 FirstEnergy coming to you to request a restart. My point 13 is, has that team already been assembled and what do you 14 think the advance notice would be, like, are we talking a 15 week, two weeks or a month before the, the team actually 16 receives a request from FirstEnergy to restart the plant?
17 Im trying to get an idea of the timeline.
18 MR. GROBE: There is a lot of 19 interest today in schedules and timeframes. The schedule 20 for the restart, what we call the Restart Assessment Team 21 Inspection, affectionately referred to as the RATI. That 22 schedule is not driven by anything FirstEnergy asks for.
23 That inspection will be conducted when we believe that 24 theyre sufficiently far along in having a routine 25 operating organization that we can get a good assessment, MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
131 1 independent assessment.
2 The team has not been assembled, because depending 3 on when the inspection occurs, the team will have different 4 membership, because all these people are not sitting around 5 in Chicago waiting for something to do; they all have 6 different work activities. So, well put together a group 7 of appropriate experts at the time that its time to 8 conduct that inspection.
9 There is no close relationship necessarily to the 10 Restart Assessment Team Inspection and the restart meeting 11 that Lew Myers referred to; or the restart decision, other 12 than the fact that the inspection needs to be completed 13 prior to the panel considering a restart recommendation.
14 It should not be inferred when that inspection starts, 15 were one week away from restart or anything of that 16 nature. Thats not the way it works.
17 MR. BROOK: Thank you.
18 MR. GROBE: Any additional 19 questions?
20 Okay, very good. Thank you very much. Well 21 reconvene at 7:00.
22 (Off the record.)
23 ---
24 25 MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO
132 1 CERTIFICATE 2 I, Marie B. Fresch, Registered Merit Reporter and 3 Notary Public in and for the State of Ohio, duly 4 commissioned and qualified therein, do hereby certify that 5 the foregoing is a true and correct transcript of the 6 proceedings as taken by me and that I was present during 7 all of said proceedings.
8 IN WITNESS WHEREOF, I have hereunto set my hand and 9 affixed my seal of office at Norwalk, Ohio, on this 10 21st day of September, 2003.
11 12 13 14 Marie B. Fresch, RMR 15 NOTARY PUBLIC, STATE OF OHIO 16 My Commission Expires 10-9-03.
17 18 19 20 21 22 23 24 25 MARIE B. FRESCH & ASSOCIATES 1-800-669-DEPO