ML20214P691
| ML20214P691 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/07/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2436, NUDOCS 8609240022 | |
| Download: ML20214P691 (24) | |
Text
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CERTIFIED MINUTES OeRs-M36
, m 7] DATE ISSUED: August 7, 1986 EBE h lit 4
SUMMARY
/ MINUTES ACRSSUBCOMMITTEEONDAVISBESSE(RESTART)
WASHINGTON, D.C.
JUNE 27, 1986 A meeting was held by the Davis Besse Subcommittee. A notice of the meeting was published in the Federal Register on June 9, 1986 (Attachment A). The schedule of items covered in the meeting is in Attachment B. The list of attendees is in Attachment C. A list of the meeting handouts is in Attach-ment D. The handouts are filed with the office copy. Herman Alderman was the Designated ACRS Staff Member. The meeting was convened at 8:30 a.m.
Principal Attendees ACRS G. Remick, Subcommittee Chairman C. P. Siess G. A. Reed H. Alderman, ACRS Staff Toledo Edison J. Williams, Jr. S. Jain S. Smith P. Hildebrandt J. Wood NRC OcCracken D. Persinko C. Vanderberg R. Kendall E. Tominson Introductory Statement - Chairman Remick 8609240022 860807 6 PDR
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', MINUTES / DAVIS BESSE RESTART 2 JUNE 27, 1986 Dr. Remick noted that the Subcommittee would continue with a review of those activities not previously reviewed and having to do with the Staff's safety evaluation report for the start-up of the Davis-Besse plant. He also noted that today's session would be the basis fcr the full Committee presentation which is scheduled for July lith from 8:30 to 11:30 a.m. He then called upon Mr. J. Williams of Toledo Edison for the first presentation.
J. Williams, Vice-President Nuclear Toledo Edison Mr. Williams discussed some of the organizational changes since the last subcommittee meeting. He noted that the company's nuclear review Board which had totally in house membership now has four outside representatives on it.
Mr. Williams noted that an Independent Safety Review Board has been estab-lished. Dr. Remick asked if the merger of Toledo Edison and Cleveland Illuminating has affected the operating organization. Mr. Williams replied that it hadn't.
Mr. Williams pointed out that a Quality Verification Manager and an Engineer-ing Assurance Manager have been added to the quality assurance organization.
The Staff .'or Davis Besse Unit One has grown to 1008 people. Dr. Remick asked if there was any problem attracting young engineers to work for a utility. Mr. Williams responded that they have far more applicants than the number they will take.
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. . MINUTES / DAVIS BESSE RESTART 3 JUNE 27, 1986 S. Smith, Assistant Plant Manager for Maintenance at Davis Besse, Toledo Edison Mr. Smith discussed the changes in maintenance since the last meeting. He noted that they are currently authorized 199 permanent maintenance employees.
The current staffing is 185 employees. The remaining 14 are craft personnel that can't be replaced until the current strike is over. In addition, there are about 150 contract personnel that assist on a part-time basis.
A new position has been added. The new position is that of training foreman.
Three of the four training foremen have been staffed. The last one to be filled is in the electrical area. One individual is working in that area and the paperwork is being processed for his permanent assignment to that area.
Dr. Remick asked if the training foreman is qualified to sign off on call cards? Mr. Smith replied that he was but that is not his primary function.
The primary function is to coordinate the individual draft participation in the training program and to assure that they are keeping up with their training schedules and that they are not dropping tests. He arranges for remediat'on if they drop a test. He makes sure they progress to the quali-fication program, t
. . MINUTES / DAVIS BESSE RESTART 4 JUNE 27, 1986 l i
Mr. Reed asked if the maintenance people are MAST tested. Mr. Smith respond-ed that according to the union agreement they can only do the MAST testing on new people and those individuals coming into the nuclear mission from outside of the organization.
Mr. Smith noted that 15 percent of the maintenance manpower is committed to training on a full time basis.
In the area of work orders, as of June 9th, there were 40 work orders required for restart out of a total of 247. In the area of preventative maintenance, there were 9 work orders open as of June 9th. These 9 work orders will be done during power ascension.
Mr. Smith pointed out that new controls have been established for preventa-tive maintenance. These controls require the approval of Mr. Smith and the assistant plant manager for operation, for any changes or additions to the preventative maintenance program.
Mr. Smith discussed changes in the preventative maintenance program regarding equipment that has had recurring problems and failures. A group of system engineers have been established. Their primary responsibility is to review all the equipment within their system and help make determination of what P.
M. can be applied to that system or component to improve its performance and serviceability.
. . MINUTES / DAVIS BESSE RESTART 5 JUNE 27, 1986 J. Wood, Nuclear Plant Systems Director, Toledo Edison Mr. Wood gave a summary of the event investigation and he also discussed the reactor coolant pump status.
He noted that the main feed pump turbine was the initiator of the June 9th event when it tripped out on overspeed. The investigation concluded there was a failed circuit board in the speed control circuit which was replaced to remedy that situation.
Regarding the spurious actuation of the steam feedwater rupture control system, which closed.the main steam isolation valves. This was determined to be caused by a pressure oscillation sensed by the low level transmitters.
This was rectified by installing additional filtering in the network.
During the June 9th event, both steam-driven auxiliary feed pump turbines tripped out on overspeed. The overspeed was caused by control difficulty due to water ingestion into the turbine. The problem was due to long cold inlet lines. This was rectified by putting the steam admission valves close to the turbine to provide hot steam at this point.
During this event, the operators had trouble using the turbine trip and throttle valves to reset the turbines. Toledo Edison has. developed training which will be conducted prior to going back into service.
. MINUTES / DAVIS BESSE RESTART 6 JUNE 27, 1986 The problem with large motor operated valves has been addressed by the use of M0 VATS equipment for diagnostics. The dimensions, wiring, and equipment qualification for those valves has been verified.
The problems with the nuclear instrumentation neutron source range detectors were found to be an improper ground-in one case and a faulty cable in a containment penetration in the other case.
The safety parameter display system problems was traced to difficulty with the fiber optics. It was corrected by installation of new fiber optics and by improving the connections which were improperly done.
Mr. Wood discussed the Reactor cooling pump shaft cracking at Davis Besse.
The Crystal River plant had a reactor cooling pump failure on January 1, 1986. Investigation found the shaft severed near the top of the journal bearing on the "A" coolant pump. The "B" pump had a crack in the 48" region.
Broken bolts holding on the main impeller were found on the "A" and "B" pump at Crystal River.
Since Davis-Besse and Arkansas 1 have the same design Byron Jackson. pumps as Crystal River it was decided to ultrasonic test the pumps at Davis Besse.
The Ultrasonic testing concluded that shafts in all four pumps have cracks in the "52" region. The impeller bolts could not be evaluated without pump disassembly.
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, , MINUTES / DAVIS BESSE RESTART 7 JUNE 27, 1986 The shaft from reactor coolant pump 2-1 was removed for further examination.
Examination at the Babcock and Wilcox Lynchberg Research Center showed axial cracking at "48" of about 5 inches deep and no crack at "52". One bolt was broken, two bolts cracked and one bolt and all pins were intact. A spare rotating assembly was installed in reactor cooling pump 2-1. The remaining rotating assembly / shafts) will be replaced with the first delivery expected in July. Babcock and Wilcox is investigating the anomalous U.T. indications.
S. Jain, Nuclear Engineering, Director, Toledo Edison Mr. Jain noted that he would discuss improvements to the auxiliary feedwater system, the steam and feedwater control system, the feed and bleed cooling capability, and longer-term changes that would be made after restart.
He noted that one of the.important things that they have done is to place the steam admission valves next to the turbine. This alleviates the problems of l
condensation in the long and cooled steam lines from the generators.
Local indication for the trip throttle valves for the turbines has been added. This will facilitate local manual control by the operator in case he has lost control from the control room and has to maneuver the turbine locally.
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, MINUTES / DAVIS BESSE RESTART 8 JUNE 27, 1986 The suction valve from the condensate storage tanks has had the power removed from these valves. This will preclude spurious closure of the valves which could cause the loss of the primary supply.
Mr. Jain noted that communication in the cubicles has been improved. This allows the operator, if he is manually operating the trip throttle valve to control levels in the steam generator, to be in constant communication with the control room.
The motor driven feed pump will provide more than 100 percent capacity auxiliary feedwater flow. The discharge of the pump would be aligned to the auxiliary feedwater headers during full power operation. The suction for this pump will normally be aligned to the condensate storage tanks.
During low power operation for start-up, this pump will be utilized as a start-up feed pump with suction from the storage tank and the discharge line to the main feedwater headers. The pump has the capability of being started from the control room, being loaded on the diesel from the control room, and has control room capability for the discharge valve. This control room control of the discharge valve would allow under accident conditions, a steam line break or a steam safety stuck open, for example, flow to be provided to the respective steam generator.
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. . MINUTES / DAVIS BESSE RESTART 9 JUNE 27, 1986 Mr. Jain discussed changes in the Steam Feedwater Rupture Control System (SFRCS). The logic has been changed to remove closure of the main steam isolation valves and the main feedwater valves. This is to preserve the primary source of feedwater even if a low level condition were to occur.
To alleviate complete isolation of auxiliary feedwater from the steam genera-tors which could occur using the SFCRS, when both steam generators sense low pressure, the logic has been changed so that auxiliary feedwater will be isolated only from the generator that first senses the low pressure condi-tion. The second steam generator sensing a low pressure condition will not have the auxiliary feedwater isolated. This will prevent complete isolation of auxiliary feedwater from both of the steam generators.
Toledo Edison has performed an analysis which shows that with a complete loss of main feedwater, if operator action is taken within 10 minutes after reactor coolant temperature of 600 degrees F, the collapsed liquid level .
would be 11.9 feet and the mixture height is "much" above the top of the core.
The operator action is to start the two makeup pumps, open the PORY and the pressurizer and hot leg high point vents.
Mr. Jain noted that if nothing was done for about 30 minutes, the core would not be uncovered.
. . MINUTES / DAVIS BESSE RESTART 10 JUNE 27, 1986 On the long term basis, blowdown valves at the top of the steam generator upper hemisphere are being considered. This system would be used after a loss of main feedwater, auxiliary feedwater, the motor-driven feedpump and the start-up feed pump.
These motor operated valves would be opened at 20 minutes if 600 F. is reached and allow significant depressurization of the primary system and would allow the ECCS to be actuated and maintain pressure and cooling.
P. Hildebrandt, Nuclear Engineering Group, Director, Toledo Edison Mr. Hildebrand discussed the review of 34 systems important to safe plant operation. A program was established to look at these systems to identify the important recurring design maintenance and operation problems and to determine whether corrective actions are required prior to restart and what corrective actions should be taken over the long term.
i The next step was to evaluate the scope of the existing periodic surveillance testing program to identify any additional testing that was needed to insure the required functiens will be performed on an ongoing basis over the long l term.
The next step was to conduct a test program specifically to assure that these 34 systems important to safe plant operation are functional at restart and l
. . MINUTES / DAVIS BESSE RESTART 11 JUNE 27, 1986 that testing was performed to verify adequacy of the systems modification that were completed during the current outage.
The approach used was to have a team for each system headed by a Toledo Edison Engineer. The result of the review was in turn reviewed by the Independent Process Review Committee which is composed of individuals with a broad nuclear industry background and specific knowledge of the Davis Besse plant design.
After these two reviews, then detailed test procedures for the restart test program were approved and implemented by the joint test group and the restart test organization.
For the 34 systems there were approximately 150 problem areas that required resolution prior to restart.
Approximately 200 problem areas required resolution over the longer term.
Those resolutions range from engineering evaluation to hardware changes in the plant.
Mr. Hildebrand mentioned the problems with the improper installation of the Raychem shrink tubes. These tubes slip over cable connectors that are connected via lugs and a bolting arrangement. The tubes are then heat shrunk over the cables.
. . MINUTES / DAVIS BESSE RESTART 12 JUNE 27, 1986 It was discovered during a training program that the Raychem tubes were not properly installed.
Toledo Edison is going through all the plant cabling to check the Raychem tubes. This is being done prior to restart.
C. McCracken, NRC Mr. McCracken discussed the Staff's evaluation of the restart.
Mr. McCracken noted one big area was motor operated valves. He remarked that the licensee has determined the limiting conditions of operation for all valves. Tests were performed on representative valves to demonstrate that after having gone through the M0 VATS program, that a valve that has been fully tested by M0 VATS will function under the design basis conditions.
The next area of concern that has been resolved is main steam safety valves and atmospheric vent valves. There were pressure fluctuations in the system that created a problem with the transmitters that night have led to a partial trip. The automatic vent valve control system was repaired. Some drift was found in the ICS modules. There may still be some problems with the atmo-spheric vent valve. The System Review and test program is still working on i this.
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. MINUTES / DAVIS BESSE RESTART 13 JUNE 27, 1986 In the case of the main steam safety valves, they were removed, reworked and retested. There has been a whole series of problems with these valves blowing down too much. The Licensee has committed to give the NRC a long-term maintenance plan which will state how frequently they intend to rework the valves and demonstrate the fact that they will lift when they.are supposed to and blow down the percentage they are supposed to.
The Safety Features Actuation System has been modified. There was a concern, prior to the June 9th event, that the SFAS did not have sufficient indepen-dence to meet the single failure criteria. This was based upon the system having a common ground and could lead to a common failure mode. The SFAS system has been modified to meet the channel independence criteria of IEEE standards.
1 Regarding Human Engineering Defects (HEDs), prior to the June 9th event, 29 HEDs were identified in the detailed control room design review'. Permanent fixes have been instituted for six of these. The others have interim fixes.
The final changes will be made by the sixth refueling outage (1989).
The entire reactor protective sys'em has been reviewed for single failure l
considerations. The Staff has concluded that the RPS meets single failure consideration without fixes.
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i Unde', the heading of commitments, Mr. McCracken noted the following:
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. . MINUTES / DAVIS BESSE RESTART 14 JUNE 27, 1986
. Primary blowdown capability to be installed in the future
. Prior to or during restart, final rework and testing of all safe-ty-related motor-operated valves
. The resolution of the control room human engineering deficiencies after restart ,
. Within 90 days of restart submit inspection plan for main steam safety valves
. 90 days after restart submit technical specification for turbine stop valve closure time
. 90 days after restart submit a auxiliary feedwater reliability study which~will incorporate all of their new components C
. 60 days after restart submit a technical specification for the motor driven feed pump.
D. Persinko, NRC l Mr. Persinko noted he would discuss the staff surveys that were conducted in the area of maintenance at Davis BEsse.
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' gs second in March 1986. The September survey team consistsd of two merbers y 3
from NRR, two people from Region 3, one person frcm the Office of Inspection ' k A 1- '
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and Enforcement and two contractors from Pacific Northwest Laboratories. -)"
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contractors, Mr. Persinko replied they h(been working on NRR'k r3fntenance '
/ s and surveillance program plan and were fre,iliar with the area
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Both surveys used extensive interviews with- plant;personnet.'/ '
All levels of
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4 The findings prior to the September survey was that there were weaknesses fn ,
the following areas: the area of corporate coc-;,itment', spare parts material l I
readiness, supervision, preventive maintenance, maintenance work order 1(
backlog. The area of maintenance procedures communications' within the organization, weakness in the area of responsibilities and in the area of training. i k
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. . MINUTES / DAVIS BESSE RESTART 16 3 JUNE 27, 1986 ft .
1 After the September survey the conclusions were that the modifications that the licensee was pursuing were addressing all the above weaknesses.
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During the March survey, the same areas were reviewed. In addition, there
, were some concerns about whether the planning and scheduling group would be
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able to function effectively and efficiently.
The conclusion was the considerable progress has been made in implementing the new program by the utility.
Mr. Persinko concluded his remarks with the observation that the NRC team has concluded that the maintenance organization is now functioning as intended with no major weaknesses. Region 3 will continue to monitor the conduct of maintenance at Davis Besse.
C. Vandenberg, NRC, Region 3 Mr. Vanderberg is a reactor inspector and a team leader for the system review and test program (SRTP) review group.
The Staff decided on an eight point program for the review of the SRTP. The first four of these points were:
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, . MINUTES / DAVIS BESSE RESTART 17 JUNE 27, 1986
- 1. to evaluate the progress of the SRTP to determining if it could achieve the program objectives.
- 2. to assess whether the list of systems important to safe plant operation is sufficiently complete to provide reasonable assurance of safe plant operation.
- 3. to review the list of systems function important to safe plant operation to determine whether they are complete.
- 4. to review selected test outlines to ensure that they encompass all the system functions.
All four of these items are completed and discussed in the safety evaluation report. The safety evaluation report identifies a few open items as commit-ments and these will be tracked by the region.
To implement the last four items, the region has decided to audit 10 out of the 34 systems designated as important to the safe operation of the plant.
The region will:
- 1. Review these system's review reports to insure that they are accomplished within the guidelines of the SRTP.
- 2. Review the licensees test program
- 3. Witness, review and evaluate specific tests on these systems
- 4. Make sure the licensee has performed and evaluated the rest of the test results i
, , MINUTES / DAVIS BESSE RESTART 18 JUNE 27, 1986 The region has not informed the licensee which 10 systems they will review on an audit bases.
Mr. Vandenberg stated the conclusion. "The regional conclusion at this point is that the program is working; it is being implemented properly. The con-clusions from the SER can be said that the program should meet its stated objectives if implemented. The progrart is continuing, albeit slowly; to a large extent, the situation is outside the licensee's control and we anticipate continued monitoring, and if the licensee maintains the present attitude and the commitment to correct the problems as they are identified that they have shown in the past, I don't anticipate any problem with the restart."
J. Stolz, NRC Mr. Stolz concluded for the staff "we conclude that the licensee has met all the programmatic requirements described in the 50-54(f) letter, and we will be relying on the region to verify implementation, the maintenance work that is left and the systems testing. I think that that would be sufficient then ,
to warrant restart of the Davis Besse plant."
Chairman Remick discussed with the licensee and staff, what material should l
l be presented to the full Comittee on July 11, 1986.
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. . MINUTES / DAVIS BESSE RESTART 19 JUNE 27, 1986 The Subcommittee meeting was adjourned at 11:30 a.m.
NOTE: A transcript of the meeting is available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D. C. or can be purchased from ACE-Federal Reporters, 444 N. Capitol Street, Washington, D.
C. 20001 (202) 347-3700.
1
kWkWMPVN T Fed:r21 Register / Vol. 51, No. <110 / M;nd;y,- }stn2 9019e3 f Notices 1 0907 Dated. lune 2.1986. Dated;]' une 2,1986.
( Morton W. Libarkin. advised of any changas jrt schedule.1tc Morton W. Ubarkin,
, ' AssistantEnecutiveDirectorforProject _ which may have occurred.
Renew. Assistant Executive DimctorforProject Dated: lune 2,1988.
Review.
[FR Doc. 86-12922 Filed tk+4% 8 45 sm) Morton W. Uberkin. -
sumo coes rseo-e,-as [FR Doc. 86-12921 Filed 6-4-est at45 aat!
asumo coor neo4*as AssistantExecutiw DireciprferMw/ect a,yj,,, ,
[FR Doc. 4th-12B23 Filed 6-4-se; eds em)
. ,7AsMoory Cessuulltee on Rsector Advisory Committee on Reactor
- numa coor me*as '
{4~ Safeguards, Subconunittee on Davis. Safeguards Subcommittee on Gas '
Besse; R4eeting Coolad Reactor Plants; Meeting
.. Regulatory Goldeo;leeuence and '
The ACRS Subcommittee on Davis. The ARCS Subcommittee on Gas Availability Besse will hold a meeting on June 27, Cooled Reactor Plants will hold a 1986. Room 1046,1717 H Street. NW., meeting on June 26,1986, Room 1(M6, The NuclearRegulatory Commission Washington, DC.
1717 H Street, NW., Washington, DC. has issued a new guide in its Regulatory The entire meeting will be open to The entire meetin Guide Series.This series has been public attendance. public attendance. g wul be open to developed to describe and make The agenda for the subjc.i meeting The agenda for the subject meeting available to the pubh,c methods shall be as follows: shall be as follows: acceptable to the NRC staff of 0
Friday, June 27,1986- -8.30 a.m. until the , N[ec cuslon us conclusion of business. s * *
- 8 I 0 " * *"'
The Subcomimnee will mview the cases, to delineate techniques used by The Subcommittee will review start- the staffin evaluating specific problems up activities for Davis-Desse. applicability of NRC requiremmte for equipment qualification and cable or postulated accidents and to provide Oral statements may be presented by guidance to applicants concerning members of the public with the testing and other topics related to Fort St. Vrain, an HTGR. certain of the information needed by the concurrence of the Subcommittee staffin its review of applications for Chairman: written statements will Oral statements may be presented by permits and licenses.
be accepted and made available to the members of the public with the Regulatory Guide 3.56, .' General .
Committee. Recordings will be permitted concurrence of the Subcommittee only during those portions of the Chairman; written statements will be " ""' ' U**I "8 "8 " N"8 Operahg, and ham' ng M'sWn accepted and made available to the a meeting when a transcript is being kept- am e en at WanlunMs ,,
and questions may be asked only by Committee. Recordings will be permitted members of the Subcommittee,its only during those portions of the describes procedures acceptable to the meeting when a transcript is being kept, stahedgmng t consultants, and Staff. Persons desiring perating, and maintain mg\ these esung, to make oral statements should notify and questions may be asked only by the ACRS staff member named below as members of the Subcommittee,its eminlu cetml deWca to ensure h far in advance as is practicable to that consultants, and Staff. Persons desiring "*
appropriate arrangements can be made. to make oral statements should notify Comments and suggestions in During the initial portion of the the ACRS staff member named below as connection with (1) items for inclusion far in advance as is practicable so that in guides currently being developed or meet ng. the Subcommittee, along with appropriate arrangements can be made. (2) improvements in all published gmdes any ofits consultants who may be are acouraged at any time. Written During the intitial portion of the present, may exchange preliminary c mments may be submitted to the views regarding matters to be meeting, the Subcommittee, along with any ofits consultants who may be Rules and Procedures Branch, Division considered during the balance of the meeting. present, may exchange preliminary of Rules and Records. Office of views regarding matters to be Administra tion. U.S. Nuclear Regula tory The Subcommittee will then hear considered during the balance of the Commission. Washington, DC 20555.
presentations by and hold discussions meeting. Regulatory guides are available for with representatives of the NRC Staff.
its consultants, and other interested The Subcommittee will then hear inspection at the Commission's Public presentations by and hold discussions Document Room,1717 H Street NW.,
persons regarding this review.
with representatives of the NRC Staff. Washington. DC. Copies ofissued Further information regarding topics its consultants, and other interested guides may be purchased from the to be discussed whether the meeting persons regarding this review. Government Printing Office at the has been cancelled or rescheduled, the Furthe information regarding topica current GPO price. Information on Chairman's ruling on requests for the to be discussed, whether the meeting I
opportunity to present oral statements current GPO prices may be obtained by has been cancelled or rescheduled, the catacting the Superintendent of and the time allotted therefor can be Chairman's ruling on requests for the Documents, U.S. Government Printing obtained by a prepaid telephone call to opportunity to present oral statements Office, Post Office Box 37082, the cogdnizant ACRS staff member, h!r.
and the time allotted therefor can be Washington, DC 20013-7082, telephone llerman Alderman (telephone 202/634- obtained by a prepaid telephone call to (202) 27F2000 or (202) 275-2171, lesued 1414) between 8.15 a.m. and 5.00 p.m. the cognizant ACRS staff member, Mr. guides may also be purchased from the Persons planning to attend this meeting John C. htcKinley (telephone 202/634-are urged to contact one of the abose National Technical Informa tion Service 1414) between 8:15 A.M. and 5100 PAf. on a standing order basis. Details on
( named individuals one or two days Person planning to attend this meeting this service may be obtained by writing before the scheduled meeting to be are urged to contact one of the above NTIS,5285 Port Royal Road, Springfield.
advised of any changes in schedule, etc., named individual one or two days VA 22181.
which may bas e occurred. before the scheduled meeting to be. (5 U.s C. ss:(ap t '
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8:30 a.m. Introductory Remarks - Subcommittee Chairman 8:35 a.m. Organization - Toledo Edison Maintenance Auxiliary Feedwater Modifications System Review and Test Program 10:15 a.m. ****** BREAK ******
10:30 a.m. Safety Evaluation Review - NRC Staff 11:30 a.m. Subcommittee Discussion 12:00 N00N ADJ0 URN
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,' ATTACHMENT D HAND 0UTS DAVIS BESSE SUBCOMMITTEE MEETING JUNE 27, 1986 WASHINGTON, D. C.
- 1. Toledo Edison Presentation A. Update of Mission Activities - J. Williams, Jr.
B. Update of Maintenance Activities S. Smith C.
- 1. Summary of Event Investigation
- 2. Reactor Coolant Pump Status J. Wood D.
- 1. Auxiliary Feedwater System
- 2. Modifications and Decay Heat Removal E. System Review and Test Program P. Hildebrandt F. Closing Remarks J. Williams, Jr.
- 2. NRC Staff Presentation A. Davis Besse Restart - C. Michelson B. Maintenance Review at Davis Besse - D. Persinko C. System Review and Test Program - C. Vandenburgh l