ML20206S807
| ML20206S807 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/01/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2430, NUDOCS 8609220376 | |
| Download: ML20206S807 (14) | |
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ISSUED: JULY 1, 1986 COMBINED
SUMMARY
/ MINUTES OF THE JUNE 25, 1986 MEETING OF THE ACRS SUBCOMMITTEE ON BABC0CK & WILC0X REACTOR PLANTS SUBCOMMITTEE WASHINGTON, D.C.
A meeting was held by the ACRS Subcommittee on Babcock & Wilcox Rcactor Plants on June 25, 1986. The purpose of the meeting was two-fold.
First, the Subcommittee heard the results of the NRC's Incident Investigation Team's review of the loss of integrated control system power and overcooling transient at Rancho Seco on December 26, 1985.
Second, the Subconnittee was briefed by the NRC Staff and the B&W Owners Group on the Trip Reduction and Transient Response Improvement Program (STOP-TRIP Program for short) established as a result of NRC concerns regarding the frequency of reactor trips and complex transients on B&W plants. Notice of this meeting was published in the Federal Register on Monday, June 9, 1986 (Attachment A). Attachment B is a schedule of presentations and Attachment C is a list of slides and handouts on file in the ACRS office. The meeting was entirely open to the public.
Richard Major was the cognizant ACRS Staff member for this meeting. The meeting began at 8:30 a.m.
Attendees ACRS NRC Staff C. Wylie, Chairman F. Hebdon, AE0D D. Ward, Member D. Hinckley H. Lewis, Member J. Ramsey J. Ebersole, Member R. Jones, NRR W. Kerr, Member G. Kalman, NRR G. Reed, Member E. Branagun, NRR R. Major, Staff G. Schwenk, NRR D. Crutchfield, NRR R. Hernan, NRR l
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(( h Certificj py h92 6 860701 2430 PDR
B&W Reactor Plants 2
Jun2 25, 1986 Me: ting BWOG Others C. Tally, B&W S. Levy, SLI C. Doyel, FPC T. DuPree, Group W W. Wilson B&W D. Conner, Group W J. Ritts, TVA R. Boyd, KMC D. Welington, SMUD W. Brawn, PG&E R. Ganther, B&W N. Todreas, MIT S. Mays, Toledd' Edison C. Brinkman, CE J. Taylor, B&W B. Royster, Outlet Comm.
W. Wilgus, FPC E. Flandtai, Outlet Comm L. Reed, DPC F. Tayloe, ACE J. Carlton, Duke Power Co.
N. Brodsky, BETA R. Dorman, B&W M. Heiskican, Rep. Matsui S. Rose, Duke S. Grayman, Outlet, TV G. R. Skillman, GPU M. Ferronte, ANI J. Langenback, GPU D. Hanson, INEL N. McCole, MPR L. Connor, WA J. Nurmi, QA Tel S. Letouraceau, Bechtel S. Savage, NUS Loss of Integrated Control System Power and Overcooling Transient at Rancho Seco on December 1985 - Report of NRC's IIT - F. Hebdon Mr. Hebdon reported on the findings of NRC's Incident Investigation Team (IIT) review of the 12/26/86 transient at Rancho Seco. He noted the goal of the IIT is fact finding, that judgments on the incident are left for others to make.
It was noted that a member of the Institute of Nuclear Power Operations (INP0) accompanied the team as an observer.
Rancho Seco nuclear power station is operated by the Sacramento Municipal Utility District.
It is located 25 miles southeast of Sacramento, Calif.
It is a Babcock and Wilcox-designed reactor that was licensed in 1974. The various systems involved in the event were described.
The description of the event from the ISI Report, NUREG-1195 follows:
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3 June'25, 1986 Meeting I
B&W Reactor Plants 26, 1985, the plant was operating at 76 percent power, "At 4:14 a.m. on December when a loss of integrated control system (ICS) de power occurred as a result of The loss of dc power to the ICS (a nonsafety-related system) a single failure.
caused a number of feedwater and steam valves to reposition automatically and also caused the loss of remote control of the affected valves from the control In addition, the main feedwater (MFW) pump turbines slowed to minimum
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The immediate result room.
speed and the auxiliary feedwater (AFW) pumps started.
was a reactor coolant system (RCS) undercooling condition that resulted in'~the reactor tripping on high pressure.
The reactor trip was followed by an over-cooling condition that resulted in safety features actuation and excessive RCS cooldown.
As The operators were not immediately able to restore de power within toe ICS.
a result, nonlicensed operators were sent to isolate the affected steam and During the first 7 minutes' of the feedwater valves locally with handwheels.
incident, the excessive steam and feedwater flows resulted in a' rapid RCS cool-down of over 100 *F. The', pressurizer emptied and a small bubble formed in the The RCS cooldown continued and the RCS depressurized to reactor vessel head.
This repressurization resulted about 1064 psig and then began to repressurize.
in the RCS entering the B&W-designated pressurized thermal shock (PTS) region.
The atmospheric dump valves and turbine bypass valves were isolated within 9 However, the operators experienced difficulty minutes after the reactor trip.
One of the AFW flow closing the ICS-controlled AFW flow control valves.
control valves was finally shut; however, the second AFW flow control valve was l
The associated AFW manual isolation valve was found damaged and failed open.to be stuck open. Therefore, both AFW pumps continued to feed and Since the plant has no main steam isolation valves, water steam generator.
began to overflow into the main steam lines.
About 26 minutes after the reactor trip, the operators restored power within The operators were then j
the ICS by reclosing two switches in an ICS cabinet.
able to close the open AFW flow control valve from the control room, which The RCS had stopped the RCS cooldown, and started stabilizing the plant.
cooled down a total of 180 *F in this 26-minute period.
While changing a valve line'up in the suction of the pump used to supply RCS makeup (mak"eup pump), the last suction v11ve to the makeup pump was inadvertently This resulted in the overheating and destruction of the makeup pump.
This shut.
About 450 gallons of contaminated water were spilled on the floor.
failure did not directly affect the incident since a high pressure injection In addition, the spilled water (HPI) pump was available to supply RCS makeup.
did not result in any significant onsite or offsite radioactivity release or personnel dose.
Operators later stabilized the plant and brought it to a cold shutdown without a significant release of radioactivity to the environment and without signiff-Because of the potential signifi-
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cant additiunal damage to plant equipment.cance of the event, an NRC Te their investigation of the incident on' December 28. The five-member Team wa.,
selected on the basis of their knowledge and experienc The Team was directed to:
happened; (b) identify the probable cause as to why it happened; and (c) make control systems.
appropriate findings and conclusions which would form the basis for any necessary follow-on actions"
B&W R:: actor Plants -
4 June 25, 1986 Meeting i
The principal findings and conclusions were reported. The IIT reported that the fundamental causes for this transient were design weaknesses and vulnerabilities in the ICS and in the equipment controlled by that system. These weaknesses and vulnerabilities were not adequately compensated by other design features, plant procedures or operator
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training. RanchoSecoEmergencyOperatingProcedures(EOPs)donot address the loss of ICS power; the lack of specific guidance seems to be a weakness in the plant-specific E0Ps available to the operators on December 26, 1985. These weakness and vulnerabilities were largely known to SMUD and the NRC staff by virtue of a number of precursor events and through related analyses and studies.
Yet, adequate plant modifications were not made so that this event would be improbable, or so that its course of consequences would be altered significantly. The information was available and known which could have prevented this overcooling transient; but in the absence of adequate plant modifications, the incident should have been expected.
NRC Reassessment of B&W Plant Designs - D. Crutchfield, i:RR Mr. Crutchfield noted the NRC encouraged the B&W Owners Group (BWOG) to take the leadership role in this matter. BWOG documented their program in a May 15, 1986 submittal, " Trip Reduction and Transient Response Improvement Program," BAW-1919. The Staff is continuing to have meetings with the Owners Group and to comment on the program. The Staff's initial assessment indicates the program is generally on target.
Documentation of the results of the Staff review is planned for December 1986.
The Staff will perform certain actions themselves, including:
reviewing the BWOG effort, rereviewing the disposition of previous Staff i
recommendations, and performing a comparison to other PWRs.
In response to questions, Mr. Crutchfield said that currently B&W reactors meet the regulations and can operate safely while the reassessment is performed. When asked if the reassessment was focused on hardware rather than people problems, the response was that both
B&W Reacter Plants-5 Juna 25, 1986 Meeting 1
issues are under consideration. The Staff is giving equal emphasis to
_ hardware and people-related issues. However, it was noted that a
management activities are outside the current scope.
It was felt other programs are addressing how the plants are managed and run.'
It was also i
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stated that the Staff will use the PRA information to compare potential changes that the Staff believes may be necessary to see if there is an improvement in safety.
i.
B&W Owners Group Stop Trip Program Presentation to the 87W Plant ACRS I
Subcommittee i
Introduction - W. Wilgus and G. R. Skillman It was noted that the purpose of the meeting was to describe the BWOG j
Trip Reduction and Transient Response Improvement Program and to receive 4
ACRS comments on the program. The objective of the program will be to reduce the number of trips and reduce complex transient frequencies and
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to ensure acceptable plant response during those trips and transients which do occur.
l The goals of the program are to by 1990 reduce the average per plant trip frequency to less than two per year.
In addition, by the end of 1990 the number of transients as classified by measurable parameters (Category "C") will be reduced to 0.1 per plant per year based on a moving three-year average.
The transient categories are defined as:
Normal response classification -
Category A - plant response parameters remain within preferred, or expected range Category 2 - plant response slightly exceeds the expected range in one or more parameters, but does not reach the 1
category C limits and is not a significant concern.
l This category is used to better focus efforts on trip reduction and transient response improvements as these I
may be precursors to category C events I
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BtW R:act:;r Plants 6
Juna 25, 1986 Me: ting Abnormal response classification -
Category C - system conditions reach limits which require safety system and extensive operator response to mitigate the transient.
Information Gathering Process - BWOG The information gathering process will perform a broad and comprehensive search for problems in both the NSSS and the balance of plant.
Included in this effort will be a review of the transient assessment program (TAP) data (which will use the graded TAP reports to review operating data from 1980 to the present).
Interviews with operations and maintenance personnel will be conducted to search for trouble spots.
The project will also review any other pertinent data.
The BWOG will employ an outside consultant (MPR) to assess the relative B&W plant sensitivity compared to other PWR designs.
It is also planned to interface with the NRC Staff on their concerns.
The sensitivity study will attempt to quantify the perception of sensitivity by defining measurable, quantitative indices of thermodynamic behavior during normal operations, anticipated occurrences,anddesignbasisaccidents(throughanalysisofFSAR information).
The sensitivity study will evaluate the relative differences among PWR designs in these indices and establish safety margins. The effort is to identify areas of potential improvements in the B&W design and operations based upon an anlysis of the observed differences and their significance.
It is also planned to identify specific areas which would be appropriate for consideration in risk or other studies.
The detailed key actions to be taken during this effort are:
1.
Review 1154 Task Force items (the June 9, 1985 Davis-Besse event response).
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B&W Reactor Plants E
June 25, 1986 Meeting 4 -
2.
Review Rancho Seco events 3.
Perform operating experience review 4.
Perform operator and maintenance personnel interviews
- 5.. Perform sensitivity study.
6.-
Review ICS/NNI system design 7.
Review MFW system designs 8.
Perform risk assessment 9.
Review EFW/AFW systems designs
- 10. Review secondary plant relief system designs
- 11. Review instrument air system designs
- 12. Review procedures A root cause program is planned. This effort was undertaken out of recognition that more thorough and more consistent investigations are crucial to solving problems. The program will be utilized in future events to:
ensure thorough investigations, determine root and contributing causes, identify effective corrective action.
I Integration Phase Key Projects - BWOG The BWOG provided details on three of the twelve key projects. These were the ICS/NNI system review, MFW system review, and the risk j
assessment effort.
The ICS/NNI system review will study the relationship between these nonsafety systems and safety functions. The processing of control signals will be the focus. The original design as well as modifications will be studied.
The main feedwater reliability improvement program has as its objectives:
to identify root causes of main feedwater upsets, develop recommendations for the resolution of plant problems that will improve MFW reliability, and to provide a technical basis for each recommendation. The risk assessment effort is 4
geared toward assessing the significance of category C events with respect to core damage frequency using Oconee and Crystal River-3 PRAs.
4
. - _ - _ _ _ _ _ - _..~
B&W Reactor Plants 8
June 25, 1986 Meeting Schedules - BWOG Currently the Owners Group is scheduled to meet with the Staff and
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review progress on the Stop Trip Program in August and October of this year. BWOG activities related to Davis-Besse and Rancho Seco transients are continuing and are being integrated into the overall program oni transient performance.
s.,
' Executive Session The Chairman asked the members if they thought the program was meeting its stated goals and, if not, what are the deficiences or concerns.
Second, if the programs do satisfy the objectives and goals outlined, will the results satisfy the NRC safety concerns? Third, what oth'er e
concerns are there?
One member stated more emphasis was needed on methods to remove decay heat. Alternative principles for decay hear removal address a more fundamental safety concern than reducing the number of trips.,
Itwasnotedbyanothermemberthatthe"stoptrip"programwould improve operations of plants with B&W systems, but may not have as. its prime focus safety. A concern was expressed over the fact that in a list of complex transients to be studied, a third of the B&W operating units did not con, tribute to these transients. The question was raised, what is the reason for such a situation not being p'ursued.
Another subcommittee comment centered on the fact that many of the B&W e
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transients were initiated by failures in power supplies.
It appeared
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that early stages of transients were not receiving enough attention. A concern was again expressed that safety may not be the central focus of this program.
It was noted that the B&W
- esign has a unique geometry, well fitted to d
decay heat removal. This situation should be used to an advantage.
Further study on the reliability of the auxiliary feedwater system j
seemed appropriate.
9
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, EN B&W React".r Plants 9
June 25, 1986 Me: ting 3
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Two and one-half hours of full Censnittee time has been allotted on
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Friday, July 11, 1986 between 3i00 p.m. and 5:30 p.m.
Thirty minutes will be used for a subcommittee report, and fifteen minutes will be used k
for a Staff presentation. The remainder of the time will be given to 7
the BWOG for presentations.
The meeting was adjourned at 6:05 p.m.
s 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 St.,
Washingten, DC 20011 [(202) 347-3700]
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cnd has n3 cth r environmentlimpict.
h;ld a meeting en June 25.1986. Room g
10cchet No.50-2511 Florida Power and Li9ht Co'-
there are nc measurable tsdiological or DC. '
Cnvironmental Assessmentand nonradiological environmental impacts The entire meeting will be open to nding of No Significant impact associated with the proposed public attendance.
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He agenda for the subject meeting exemption.
The U.S. Nuclear Regulatory shall be as follows:
Commission (the Commission)is' Alternatim to the ProposedAction Wednesday fune25.1986-6:300.m.
considering issuance of an exemption Since the Commission has concluded untilthe conclusion ofbusiness.
fram the requirements of10 CFR
,here is no measurable environmental
%e Subcommittee wi!! consider the 50.48(c)(4) to Florida Power and I.ight impact associated with the proposed B&W Owners Group plans to reassess-Company (the licensee). for the Turkey exemption, any alternatives with equal the long. term safety of B&W reactors.
Point Plint. Unit No. 4. located at Dade or greatu environmentalimpact need including. the implications of operating Cour.ty, ilorida.
not be evaluated.The principal experience on the adequacy of B&W Ensironmental Assessment alternative to the exempt:en would be to plant designs.The focus of this section require rigid compliance with the of the meeting will be the B&W Owners Idintification ofProposed Action 50.48(c)(4) requirements. Such action Group Trip Reduction and Transients The exemption would grant schedular would not enhance the protection of the Response improvement Program.The cxtensions for the completion of the environment and would result in Subcommittee will also be briefed on following fire protection items for Unit 4 unjustified costs for the licensee.
the NRC Staff's incident Investigation Team's (IIT) findirgs related to the Alternative Use of Resources December 26,1985 loss of integrated 1 a r oute
- 2. Penetration seals.
This action does not involve the use of c ntrol sysem power and overcooling
- 3. Raceway (conduit) protection by resources not considered previously in transieM at de Ranch Seco nelear fire rate barriers.
the Final Environmental Statement for P wer plant,
- 4. Alternate Shutdown System.
Turkey Point Plant. Units 3 and 4.
Oral statements may be presented by
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Agencies andPersons Consulted members of the public with the cammon procedures and areas (control
- Auxiliary Buildhg north.scath The NRC staff reviewed the licensee's c ncurence of the Subcommittee,ll be room. cable spreading rooms and the Chairman: written statements wi breezeway).
request and did not consult other accepted and made available to the he scope of additional work needed agencies or persons.
Committee. Recordings will be permitted in these areas was identified as the Finding of No Significant Impact only during those portions of the nneting when a transcript is being kept.
result of reverification effort by the The Commission has determined not and questions may be asked only by licensee.
to prepare an environmentalimpact members of the Subcommittee,its
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DeNeedfortheProposedActw.
statement for the proposed exemption.
consultants, a id Staff. Persons desiring n
When the reverification p ogram Based upon the environmental to make oral statements should notify indicated the need for additional assessment, the NRC staff concludes the ACRS staff member named below es modifications, necessary engineering that the proposed action will not have a far in advance as is practicable so that cnd procurement were required by the significant effect on the quality of the appropriate arrangements can be made, licensee.The magnitude of the work human environment.
I?uring the initial portion of the cssociated with the modifications is For further details with respect to thic meeting, the Subcommittee, alor.g with such that it does not allow the to CFR petion, see the requests for exemption any of its consultants who may be 50.4E(c) schedule to be met.The dated October 11.1985 and April 4.1966.
present, may exchange preliminary j
cxemptions are strictly schedular in that These letters are avaHable for public views regarding matters to be they allow the modification schedule to inspection at the Commission's Public considered during the balance of the be extended, with interim compensatory Document Room.1717 H Street. NW.,
meeting.
measures in place, which w'ili provide Washington DC, and at the The Subcommittee will then hear the necessary fire protection until the Environmental and Urban Affairs presentations by and hold discussions corresponding modifications are 1.ibrary. Florida Inf ernational with representatives of the NRC Staff.
completei University, hiiami. Florida 33199.
d'ing h revi w.
Dated at Bethesda. Maryland this 3rd day -
, gns r g Enrhunmentollmpact of the Proposed o June 198&
Further information regarding topics Actwn For the Nuclear Regulatory Commission' to be discussed whether the meeting The proposed action only affects the DanleMcDonald, has been cancelled or rescheduled. the 1:ngth of time for the required Acting Dimetor. PirR Project Dimeterate No.
- Chairman's ruling on requests for the modificationa to be completed. He
- #IEWN Li####i"8' A' mI### #I opportunity to present oral statements licensee has proposed interim and the time allotted therefor can be compensatory measures to provide the
[FR 86-12920 Filed 6+86; 8 45 am}
obtained by a prepaid telephone call to necessary level of fire protection until coes m**
the cognizants ACRS staff member. Afr.
the modifications are completed. Thus, Richard hiajor (telephone 202/634-1413) fire-related radiological releases will not between 8:15 A.ht. and 5:00 P.ht. Persons differ from those determine <8 previously Advisory Committee on Reactor planning to attend this meeting are cnd the proposed exemption does not -
Safeguards, Suticommittee on urged to contact the above named otherv.ise affect facility radiological Babcock and Wilcox (B&W) Peactor individual one or two days befcre the sfiluent or occupational exposures. With Plants; Meeting scheduled meeting to be advised of any regard to potential nonradiological The ACRS Subcommittee on Babcock changes in schedale, etc.. which may impacts. the proposed exemption does and Wilcox (B&W) Reactor Plants will have occurred.
not affect plant nonradiological effluents t
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Feder:I Regi:ter / Vol. St. No. '110 / Mindayc June 901g60 /* Natices
'90907 t
Dated. June 2.1986.
Dated:[une 2. 2906.
advised of any changes in schedule,*tc.,
Mc* ton W. Uberkin, Morton W. Ubarkin, which may have occurred.
A ssistant Executo ve Diracsorfor Pmiect Assistant En ecutive Dio ectorforProject Dated: lune 3.1986.
f.
Review.
Review.
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[FR Doc. 86-12922 Filed 64-a6; 8-45 arn)
[FR Doc. 86-12s21 Filed 6 o.40c 445 am)
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(FR Doc.8612923 Filed INFas: 645 mm)-
Advisory Committee on Reactor Advisory Cc,mmittee on Reactor a m ocoorr m oas Safeguards, Subcommittee on Davis-Safeguards Subcommittee on Gas Besse; Meeting Cooled Reactor Plants; Meeting Regulatory Guides; tesoonce 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 1966. Room 1(M6.1717 H Street, NW.,
meeting on June 26.1986. Room 1046 The Nuclear Regulatory 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 meeting will be open to Guide Series.This senes has been public attendance.
public attendance.
developed to describe and make The agenda for the subject meetin8 The agenda for the subject meeting available to the public methods
.l..JI be es follows:
sha!! be as fol'ows:
acceptable to the NRC staff of Friday. June 27.1986-6.30 a.m. until the Thurdsay. june 26,1986-100 P.M. until hmp enti"8 '
s conclusion ofbusiness.
the conclusion business gg 9n's gu s and n some The Subcommittee will review start-The Subcommittee will review the cases, to delineate techniques used by
.the staffin evaluating specific problems up activities for Davis-Besse-applicability of NRC requirementa for or postulated accidents and to provide equipment qualification and cable guidance to applicants conceming Oral statements may be presented by testing and other topics related to Fort members of the public with the St. Vrain, an HTGR.
certain of the information needed by the concurrence of the Subcommittee staffin its review of applications for Chairman: wntten statements will Oral staternents may be presented by permits and licenses.
be accepted and made available to the members of the public with the gulatory Guide WCen Guidance for Designing. Testm, ual concurrence of the Subcommittee Committee. Recordings will be permitted Chairman: written statements will be g,
only during those portions of the accepted and made available to the Operating, and Maintaining Emiss,lon meeting when a transcript is being kept, Committee. Recordings will be permi:ted utroWeWees at manium Ms.,
and questions may be asked only by only during those portions of the plaMe de affb des W members of the Subcommittee,its RC ns.
meeting when a transcript is being kept, consultaats. and Staff. persons desiring and questions may be asked only by E"
8' '" ""
" 8 to make oral statements should notify members of the Subcommittee.its rea iability of theirperformance. 'I
- the ACRS staff member named below as far in advance as is practicable to that consultants. and Staff. Fersons desiring to make oral statements should notify Comments and suggestions in appropriate arrangements can be made.
the ACRS staff member named below as connection with (1) items for inclusion During the initial portion of the far in advance as is practicable so that in guides currently being developed or meetmg. the Subcommittee, along with appropriate arrangements can be made.
(2) improvements in all published guides any ofits consultants who msy be During the intitial portion of the are encouraged at any time. Written omnt. may exchange preliminary meeting. the Subcommittee, along with comments may be submitted to the,
l uew s regarding matters to be uny ofits consultants who may be Rules and Procedures Bran::h, Division considered during the balance of the present, may exchange preliminary of Rules and Records. Office of meeting.
views regarding matters to be Administration. U.S. Nuclear Regulatory The Subcommittee will then hear considered during the balance of the Commission. Vyashmgton, DC 20555.
presentations by and hold discussions meeting.
Regulatory guides are available for with representatives of the NRC Staff.
The Subcommittee will then hear inspection ut the Commission's Public its consultants, and other interested 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 regaruing topics its consultants. and other interested guides may be purchased from the to~be discussed, whether the meeting persons regarding this review.
Government Printing Cffice at the has been cuncelled or rescheduled, the Further informa tion regarding topics current GPO price. Information on I
Chairman's ruling on requests for the to be discussed, whether the meeting current GpO prices may be obtamed by I
opportunity to present oral st.tements has been cancelled or rescheduled. the contacting the Superintendent of
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and the time allotted therefor can be Chairman's ruling on requests for the Documents. U.S. Government Printing l -
obtained by a prepaid telephone call to opportunity to present oral statements OFice. Post Office Box 37082.
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the cogdnizant ACRS staff member Mr.
and the time allotted therefor can be Washington, DC 20013-7082, telephone lie man Alderman (telephone 202/634-obtained by a prepaid telephone ca!! to (202) 2m2060 or (202) h21714 sued il 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. McKinley (telephone 202/634-National Technical Infonna tion Service f
are urged to contact one of the above 1414) between 8;15 A.M. and 5:00 P.M.
on a standing order basis. Details on A
named individuals one or two days Person planning to attend this meeting this seruce may be obtained by writing b'efore 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 22161.
j which may base occurred.
before the scheduled meeting to be (5 U.S C. 5n(W
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8 REVISED JUNE 23, 1986 TENTATIVE SCHEDULE JUNE 25, 1986 MEETING OF THE ACRS SUBCOMMITTEE ON BABC0CK AND WILCOX REACTOR PLANTS ROOM 1046, 1717 H ST., N.W., WASHINGTON, D.C. 20555 8:30 AM 1.
Opening Remarks - C. Wylie, Chairman 10 Min.
8:40 AM 2.
Loss of Integrated Control System Power and 2 Hrs.
Overcooling Transient at Rancho Seco on Dec. 26, 1985 - Report by NRC's IIT - Fred Hebdon a.
Introduction b.
Description of Fact-Finding Effort c.
System Descriptions d.
Narrative of the Incident e.
Equipment and Personnel Performance f.
Event Precursors g.
Significance of the Incident to Additional Issues h.
Conclusions
[10 Min.]
10:40 AM BREAK cu pp/c/
10 Min.
10:50 AM 3.
Introduction by NRC Staff D Cro r 11:00 AM 4.
B&W Owners Group Trip Reduction and Transient 4 Hrs.
Response Improvement Program (STOP-TRIP) a.
Introduction
- 1. W. B. Wilgus ii. G. R. Skillman b.
Information Gathering
- 1. Transient Assessment Program S. T. Rose
- 11. Sensitivity Study S. T. Rose iii. Root Cause S. T. Rose iv. Interviews S. E. Mays
[1 Hr.]
Integration Phase
- i. ICS/NNI C. B. Doyel
- 11. MFW C. W. Tally 111. Risk Assessment S. E. Mays
[10 Min.]
3:00 PM BREAK d.
Implementation Phase L. A. Reed e.
Concluding Remarks W. S. Wilgus i
i c.,
J Babcock & Wilcox Reactor Plants 2
4:15 PM 5.
Open Executive Session 45 Min.
a.
Plans for Reporting to Full Connittee b.
Future Interactions with BWOG & Staff 5:00 p.m.
ADJOURN J
I d3
ATTACHMENT C LIST OF SLIDES AND HAND 0UTS JUNE 25, 1986 MEETING ACRS SUBCOMMITTEE ON B&W REACTOR PLANTS WASHINGTON, D.C.
1.
Slides, Loss of Integrated Control System Power and Overcooling Transient at Rancho Seco on December 26, 1986, F. Hebdon, AE0D, 41 slides 2.
NRC Reassessment of B&W Plant Designs, D. Crutchfield, NRR, 2 slides 3.
Slides, B&W Owners Group, Stop Trip Program Presentation to the B&W Reactor Plant ACRS Subcommittee, June 25, 1986, 79 slides s
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