ML20136E292
| ML20136E292 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/27/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2359, NUDOCS 8601060496 | |
| Download: ML20136E292 (20) | |
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DATE ISSUED:
November 27, 1985 AU-bi
SUMMARY
/ MINUTES ACRS SUBCOMMITTEE ON DAVIS-BESSE 0AK HARBOR, OHIO OCTOBER 4, 1985 A meeting was held by the ACRS Davis-Besse Subcommittee to review the course of action prior to restart. Notice of the meeting was published in the Federal Register on September 25, 1985.
(AttachmentA) The scheduleofitemscoveredinthemeetingisinkttachmentB. The list of attendees in Attachment C.
A list of the handouts is in Attachment D.
The handouts are filed with the office copy.
H. Alderman was the ACRS Staff member for this meeting.
The meeting was convened at 1:05 p.m.
Principal Attendees ACRS NRC Staff F. Remick, Subcommittee Chairman J. Stolz J. Ebersole A. DeAgazio C. Wylie D. Wessman C. Michelson D. Ward Toledo Edison J. Williams J. Wood W. O'Connor S. Jain S. Smith J. Legenfelter J. Williams - Senior Vice-President, Toledo Edison 8601060496 851127 PDR ACRS 2359 PDR Mr. Williams unt.us3eu organizational changes that he had made since he assumed his position. He noted that he had created a nuclear
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SUMMARY
/ MINUTES DAVIS-BESSE 2
OCTOBER 4, 1985 MEETING engineering group which. reports to the plant manager. A newly created o
position was that of materials manager.
The materials manager provides spare parts support for the maintenance department.
Mr. Williams remarked that he established a nuclear plant systems group.
This group makes sure that the operating procedures reflect the design of the equipment. This group also established maintenance requirements for systems.
A committee member asked if there is a plan or program for analyzing and identifying symptoms which may lead to unsafe conditions in the plant.
Mr. Williams replied that he has set up a talented group of people to look at that, and to recommend short term and long tenn action.
Mr. William noted that he had increased the organization from 630 people to 960 people. One of the benetits of increasing the organization is engineering can be done in-house instead of relying on contract person-nel.
W. O'Connor, Assistant Plant Mancger for Operations Mr. O'Connor noted changes for the Shift Technical Advisor. The STA duty schedule has been changed from a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duty day to a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> duty day. The Shift Technical Advisor will be licensed as a Senior Reactor Operator.
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SUMMARY
/ MINUTES DAVIS-BESSE 3
OCTOBER 4, 1985 MEETING All emergency / abnormal procedures will be reviewed to assure that the control room instrumentation is adequate when unusual actions are i
required.
i All emergency / abnormal procedures will be reviewed to assure that the control room instrumentation is adequate and properly calibrated to support operator actions.
l Under the category of training, increased emphasis will be placed on adherence to procedures. Also under training is included training of all the operators on high priority infrequent operator actions. An example of this is every operator must start the auxiliary feedwater pump with live steam pressure.
Mr. O'Connor.noted that their investigation revealed that the operators must take manual control of automatic safety systems during certain circumstances. On these occasions the reactor operator must inform the Senior Reactor Operator of his intent to manually activate the system.
The Senior Reactor Operator must concur with the action.
Mr. O'Connor remarked that the emergency operating procedures are sympton based and all the operators have been through them.
A committee member asked if the Davis-Besse design is such that it would fail safe on loss of air?
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SUMMP'.Y/ MINUTES DAVIS-BESSE 4
OCTOBER 4, 1985 MEETING i
I Mr. O'Connor replied that the design for the safety system is fail safe on loss of air.
A second question by a committee member asked what wa.s the present status on requalification examination for your operators?
1 Mr. O'Connor replied that two reactor operators did not pass the exam; 4
l they were retrained for 6 or 7 weeks, retook the exam and now have
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licenses.
Regarding plant simulators, Mr. O'Connor noted that presently the B&W simulator is used and a plant specific simulator is an order and is t
1 scheduled to be on site in 1988.
S. Smith, Assistant Plant Manager for Maintenance Mr. Smith noted that he would discuss the changes that have been implemented as part of the maintenance improvement program. The mainte-j nance organization consists of approximately 209 peopie, 40 of which are not directly involved with maintenance activities but are performing support activities such as system engineering, planning, and scheduling.
l The maintenance organization has two levels of supervision. This allows the superintendents and the general foremen to become part of industrial I
forums such as INPO, ASME, and others.
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SUMMARY
/ MINUTES DAVIS-BESSE 5
OCTOBER 4, 1985 MEETING The number of foremen in the organization has beer increased. This keeps the foremen from being tied down with paperwork and personnel matters and allows them to spend more time in the field.
Each of the maintenance personnel is required to spend a r.t9fmum of one hour per day in the plant.
Each one has an inspection check list for his assigned area and the check list is filled out.
Mr. Smith noted that they will rewrite all the administrative precedures that e10 ct maintenance and control of maintenance. The current techni-cal precedures will be upgraded and new technicil procedures will be writter.
l In response to a question from a committee member, Mr. Smith remarked i
that accreditation of the maintenance training program is currently scheduled for the end of next year.
Mr. Smith also noted that the maintenance laboratory should be in existence by the end of the year.
I A connittee member asked about how Davis-Besse is learning from mainte-nance experience? Specifically how does the Davis-Besse staff learn from the experiences of others.
The reply was that the way the management staff was laid out, people would be available to meet with INP0 and other organizations do learn what is happening and bring back the knowledge and make use of it.
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SUMMARY
/ MINUTES DAVIS-BESSE 6
0CTOBER 4, 1985 MEETING i
l Mr. Smith also noted that they have a formalized review process which has a tracking program that requires when information comes in that is considered of importance, it should be investigated as to applicability in the plant.
It is tracked through a data base system and a formal response is required as to whether it applies to th'e plant. The more important topics are~also reviewed by the SR0's.
There was a brief discussion regarding the effectiveness of the STA during the June event. Mr. O'Connor noted that.he was on the telephone to the STA during the event and everything was proceeding according to established procedures.
Mr. Williams stated he plans to make the STA's plant shift managers.
They would hold Senior Reactor Operator licenses and the reactor operators would report to them.
In times.of trouble, he would be the expert on site and he would take over.
Mr. Wood, Mechanical Structural Engineering Manager Mr. Wood noted that he would talk about some of the equipment problems experienced during the June 9th event.
The first item he discussed was the main feedpump turbine. During the review process, a failed circuit board capacitor was found in the G.E.
control system. The failed capacitor caused the control systems to increase speed, and the turbine ended up tripping on overspeed.
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SUMMARY
/ MINUTES DAVIS-BESSE 7
OCTOBER 4, 1985 MEETING The corrective action was to replace the faulted board, and testing some of the control circuits.
The second concern was the steam and feedwater rupture control system (SFRCS) which spuriously closed both main steam isolation valves and isolated the steam to the main feedpump.
This was found to be due to pressure oscillations as a result of the Rosemont transmitter being very sensitive to level changes.
One of the most significant items that the licensee discovered during its investigation of the June 9th event, was the difficulty the operators had resetting the auxiliary feedwater turbine trip and throttle valves. The main problem appears to be that the procedures in the prior training were not exactly sufficient. The remedy includes improved hands on training.
The last item, Mr. Wood discussed had to do with the auxiliary feedwater valves 599 and 608. These failed to open on demand after closing early.
The operator used the wrong two push buttons, however, after he correct-ed his mistake, a minute or so later it should have opened automatical-ly.
The finding was that the limit switches and torque switches were not set up correctly for motor operator valves.
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SUMMARY
/ MINUTES DAVIS-BESSE 8
OCTOBER 4, 1985 MEETING 1
Mr. S. Jain, Senior Nuclear Engineer Mr. Jain noted that during the June 9th event, most of the system involved were those pertaining to heat removal. A task force was set up to identify changes that would improve reliability and to decrease 1
problems and complexity. The task force was composed of senior level people with experience in engineering operations, and licensing.
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Mr. J. Lingenfelter, Operations Engineering Manager Mr. Lingenfelter pointed out the System Review and Restart Test Program I
objectives.
He noted for systems important to safe operation the objectives includ-ed.
i Identify significant and recurring maintenance and operations problems.
Identify testing required to assure that systems will perform
-their specified function i
Conduct a test program to assure that the systems are fully i
functional.
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SUMMARY
/ MINUTES DAVIS-BESSE 9
OCTOBER 4, 1985 MEETING Mr. Lingenfelter pointed out that there were five system review groups.
Each is headed by Toledo Edison engineering personnel and supported by highly qualified industry representatives.
He noted that-the system review groups interview operations and mainte-nance personnel. All evaluation and decision making was guided by specific criteria and review processes.
He remarked that overview is provided by an independent system review group.
John Stolz - NRC Staff Mr. Stolz noted that the NRC presentation would cover two things, the status of the ongoing review and the status of generic issues that arrived primarily from the June 9th event.
The NRC investigation team of the incident took the following actions:
Quarantined equipment which failed during the event.
Approved trouble shooting plans to determine root causes of failures and implement corrective actions.
Publish findings in NUREG-1154 l
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SUMMARY
/ MINUTES DAVIS-BESSE 10 0CTOBER 4, 1985 MEETING Concluded that the underlying cause of the event was the licensee's lack of care in maintenance of plant equipment.
There was a brief discussion as to whether maintenance was the underly-ing cause of the event. Mr. Stolz amplified his previous remarks to include engineering as well as maintenance and the underlying cause of the June 9th event.
Mr. DeAgazio noted that Toledo Edison is responding to a 50-54(f) letter issued August 14, 1985. This letter addresses the staff concerns regarding the June 9th event. The concerns were categorized in three broad areas:
1.
Follow up in the investigations of the event 2.
Look at the specific circumstances surrounding the event 3.
Examine the programmic management issues surrounding the way the plant was performing.
With regard to the first category, completion of the event inves-tigation, Toledo Edison provides 13 root cause reports related to equipment failures that occurred during the event.
The 13 are as follows:
(1) adequacy of loss of feedwater analysis (2) adequacy of design / operation of SFRCS (3) physical security and administrative features r,,,-,
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SUMMARY
/ MINUTES DAVIS-BESSE 11
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OCTOBER 4, 1985 MEETING (4) role of STA (5) -reliability of AFW containment isolation valves and other safety-related valves (6) adequacy of ENS reporting 1
j (7) reliability of AFW system, pumps, and need for diverse pump i
(8) reliability of PORV (9) adequacy of control room instrumentation and controls (10) inability'to place startup FW pump in service from control room (11) resolution of other equipment deficiencies (12) adequacy of procedures for " drastic" action (13) adequacy of safety system testing i
Mr. Deagazio reported that the NRC Staff has reviewed 6 of the 13 reports and provided responses to four of these reports to Toledo Edison.
In response to a subcommittee question regarding security requirements and the impact they might have in a event like this, Mr. Wessman re-sponded that it was identified as a generic issue ensuing from this event and the staff would look at security on an generic basis for all plants.
R. Wessman, NRC, Division of Licensing Mr. Wessman briefly reviewed the generic review process at the start of i
his presentation. He noted that when a generic issue is identified, it 4
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SUMMARY
/ MINUTES DAVIS-BESSE 12 OCTOBER 4, 1985 MEETING is first and immediately identified to the operating reactors assessment branch division of licensing so that the staff of that branch may look at it and determine if there is some immediate safety significance so that the staff may act on it very promptly.
If it is not a matter of meeting safety significance, the issue is evaluated and a decision is made whether staff resources should be committed to that particular issue.
Because of limitations on staff resources, those issues that are clas-sified as low are generally dropped.
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Those issues that are classified as high are pursued as high are pursued as rapidly as possible within the bounds of resources, i
l Medium issues are handled somewhere in between but they are not put into the "to be dropped" category.
i Mr. Wessman listed the generic issues derived from the June 9th event as i
follows:
i inmediate generic issues - None short term generic issues o
potential inability to remove decay heat 1
l because of questionable reliability of AFWS adequacy of emergency procedures, operator o
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SUMMARY
/ MINUTES DAVIS-BESSE 13 1
0CTOBER 4, 1985 MEETING training and available plant monitoring systems for determining need to initiate feed and bleed 2
Cooling o
physical security system constraints which could deny timely access to vital equipment o
prioritization of short term issues is nearly complete Potential Long Term Generic Issues 1.
availability and role of STAF 2.
actions to improve reliability of PORV, and need for failure mitigation 3.
adequacy of requirements for SPDS availability 4.
need for plant-specific simulator 5.
adequacy of safety system testing 6.
re-evaluate NUREG-0737 Item II.E.1.1 (AFW System 4
l Reliability) 7.
adequacy of maintenance requirements 8.
adequacy of single-failure aspects of steam line/ feed line break mitigation systems 9.
effects of loss of feedwater on OTSG 10.
thermal-hydraulic aspects of loss of feedwater l
event on reactor vessel
- 11. re-examine PRA-based estimates of core damage resulting from Loss of Feedwater Other Additional Issues, as identified 4
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SUMMARY
/ MINUTES DAVIS-BESSE 14 OCTOBER 4,1985 MEETING O
The meeting was adjourned at 4:45 p.m.
Future Activities The Davis-Besse startup activities are scheduled to be discussed during the 306th ACRS meeting, October 10, 1985, t
NOTE:
A complete transcript 'of the meeting is on file in the NRC Public Document Room at 1717 H St., NW., Washington, D. C. or can be obtained from Cefaratti, Rennillo & Matthews Court Reporters, Cleveland, Ohio'(216)687-1161.
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38908 Federal Register / Vol. 50. Nm 186 / Widn:sdiy. Sept;mber 25, 1985 / N:tices
. NUCLEAR REGULATORY nonradiological impacts, the proposed Besse Nuclear Station Unit I will hold a COMMISSION exemption does not affect plant meeting on October 4.1965, at the Davis-IDocket No. 50-2401 nonradiological effluents and has no Besse Administration Building Route 2 other environmental impa ct. Therefore.
Oak Harbor. Ohio.
Commonwealth Edison Co.;
the Commission concludes there are no
%e entire meeting will be open to Environmental Assesament and measurable radiological or pub!Ic attendance.
Finding of No Significant impact nonradiological environrnental impacts The agenda for the subject meeting associated with the proposed
%e U.S. Nuclear Regulatory exemption.
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shall be as follows: Fridoy, Octoberv.
Commission (the Commissfon)is
- Alternatives to the ProposedAction business.
19es-1Mp.m. untilthe conclusion of f
ert n ting requ emen s Since the Commission has concluded
%e Subcommittee will review setions Appendix } to to CFR Part 50 to the there is no measurable environmental taken prior to nstarting following the Commonwealth Edison Company impact associated with the proposed loss of feedwaterincident and other (CECO)(the licensee) for Dresden exemption, any alternatives with equal relatM satters.
Nuclear Power Station. Unit No. 3 or greater environmental impact need Oral statements may be presented by located at the licensee's site in Grundy not be evaluated.%e principal members of the pub!!c with the County. Ulinois.
alternative to the exemption would be to concurrence of the Subcommittee l
Environmental Assessment require rigid compliance with the Chairman; written statements will be Appendix J requirements. Such action accepted and made available to the Identification ofPmposedAction would not enhance the rotection of the Committee. Recordings will be permitted
, environment and woul result in j
%e proposed action would grant an unjustified costa.
only during those portions of the meeting when a transcript is being kept, exemption from certain requirements of Ap endix J to 10 CFR Part 50 for type B Alternative Use ofResouxes and questions may be asked only by C testing of certain valves, vents.
%fs action do'es not involve the use of members of the Subcommittee.Its an drains, sumps and penetrations which resources not considered previously in consultants, and Staff. Persons desiring maintain containment integrity at design the Final Environmental Statement for to make oral statements should notify
~ bases accident conditions. He Dresden Unit 3.
the ACRS staff member named below as exemption is strictly schedular in that it Agencies andPersons Consulted far in advance as is practicable so that would allow a 30-day extension of the 2*
appropriate arrangements can be made.
year test interval for the above De NRC staff reviewed the licensee's During the initial portion of tha components required by Appendix J.
request and did not consult other meeting the Subcommittee, along with agencies or persons.
TheNeedforthe PmposedAction any ofits consultants who may be Finding of No Significant Impact present, may exchange preliminary re utage on Sept m er and was scheduled to shut down for its to repare en entalimpact to d
Cycle to refueling outage in the Sprin8 NsNpon bth Sen'tg ption.
He Subcommittee will then hear of1985.However because of an en unanticipated 4-month outage extension assessment. the NRC staff concludes pmsentauons by and hold discussions in 1984. the shutdown for refueling and thet the proposed action will not have a with representatives of the Toledo other modifications has been extended significant effect on the quality of the EdisonCompany NRCStaff,their to October 26.1985.nis will cause human environment.
consultants, and other interested CECO to exceed the 2-year test interval For further details with respect to this persons regarding this review.
required by Appendix j for type B and C proposed action, see the !!censee's letter Further information regarding topics testing of certain components.
dated August 16.1985.%Is letter is to be discussed. whether the meeting.
available for public inspection at the has been cancelled or rescheduled. the Envimamentallmpoet of thePmposed Commission's Public Document Room.
Chairman's ruling on 1. quests for the Action 1717 H Street NW., Washington. D.C.
and at the Morris Public Library, e04 opportunity to present oral statements N:
Liberty Street. Morris. Illinois 0045L and the time allotted therefor can be th interva tw nt certain obtained by a prepaid telephone call to components required to assure Dated at Bethuda. Maryland. this 20th day the cognizant ACRS staff member Mr.
containment integrity.Because the of September 1985.
- Herman Alderman (telephone 202/634-cperational period of these components For the Nuclear Regulatory Commiselon.
1414) between 8:15 a.m. and 5:00 p.m.
will be shortened due to the Deenis M. CmtcWield.
cforementioned 4-month Cycle 9 Persons planning to attend this meeting refueling outage extension, the Assistant Directorfor Sofety Assessment.
are urged to contact the above named operational challenge to these Division off.icensing.
Individual one or two days before the components has been less than usually
[m Doc 422920 Med 9-2W E45 am]
scheduled meeting to be advised of any occurs in the 2-year test interval Rus, same ecos repas Changee in schedule. etc, which may post-accident radiological releases will have occurred.
M**Y***h* *n pv us y and e propose exemption Safeguards, Subcommittee on Davle- - Ass tan DirectorforProject a,we,.
re olo e uent or pt nel
[m Doc. m Wed $44-45. 448 amj cxposures. With regard to potential
- ne ACRS Subcommittee on Davis.-
sa m e coes ress.e ws t
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M REVISED 9/26/85 PROPOSED SCHEDULE ACRS SUBCOMMITTEE ON DAVI5-BESSE NUCLEAR STATION UNIT 1 REVIEW OF COURSE OF ACTION PRIOR TO RESTART OAK HARBOR, OHIO OCTOBER 4, 1985 1.
Executive Session - F. Remick 10 Min.
1:00-1:10 p.m.
(NOTE:
H. Denton, NRR, requested that we hear the Davis-Besse restart program.
Does the NRR want a letter?)
2.
Licensee Presentation Toledo-Edison - J. Williams a.
Sumary of principal actions to 45 Min.
1:10-1:55 p.m.
be taken prior to restart in-cluding organizational changes, staffing, training QA/QC improve-ments and hardware improvements b.
Evaluation of June 9, 1985 event 20 Min.
1:55-2:15 p.m.
and effect on plant components c.
Questions and answers 40 Min.
2:15-2:55 p.m.
3.
NRC Staff Status Report a.
Opening Remarks - F. Miraglia/
10 Min.
3:05-3:15 p.m.
J. Stolz b.
Status of staff review of 30 Min.
3:15-3:45 p.m.
Licensee's course.of action and 10 CFR 50.54(f) response
- A. De Agazio.
c.
Generic issues under staff 15 Min.
3:45-4:00 p.m.
evaluation following June 9, 1985 event - D. Wessman d.
Questions and answers 50 Min.
4:00-4:50 p.m.
4.
Chairman's Closing Remarks 10 Min.
4:50-5:00 p.m.
- F. Remick To include, but not limited to the following items:
a.
Establish tentative schedule for 306th (Oct. ACRS Mtg.)
b.
Establish tentative meeting date to address Asselstine jp Sept. 19, 1985 letter.
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e I ~ ATTACHMENT D F HAND 0UTS 1. Toledo Edison Presentation to ACRS dated October 4,1985 2. NRC Staff Presentation I I l a ege -9}}