ML16148A302
| ML16148A302 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 04/05/1980 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | Kane W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004180490 | |
| Download: ML16148A302 (6) | |
Text
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UNITED STATS FIL* CP NUCLE AR REGULATOR WASHINGTON, D. C. 20555 April 5, 1980 Docket Nos.2 69 2
50-270 50-287, 50-289, 50-302, 50-312, 50-313, 50-346 MEMORANDUM FOR:
W. F. Kane, Acting Chief, Standardization Branch, Division of Project Management FROM:
R.
A.
- Capra, B&W Project Manager, Standardization Branch, Division of Project Management
SUBJECT:
FORTHCOMING MEETING WITH THE BABCOCK & WILCOX (B&W)
OPERATING PLANT LICENSEES TO DISCUSS IMPLEMENTATION OF RECOMMENDATIONS BY THE "B&W REACTOR TRANSIENT RE SPONSE TASK FORCE."
TIME & DATE:
9:30 AM, Wednesday April 23, 1980 LOCATION:
Phillips Building - Room P-118 7920 Norfolk Avenue Bethesda, Maryland PURPOSE:
To meet with the B&W operating plant licensees to discuss the results of the Risk Reduction Potential Study. The purpose of the study is to determine the effectiveness of each of the recommendations contained in the report, "Transient Response of Babcock & Wilcox Designed Reactors," (DRAFT NUREG-0667). Based upon the results of this study and discussions with the licensees at this meeting, the B&W Reactor Transient Response Task Force will recommend an implementation schedule of the recommendations contained in DRAFT NUREG-0667..
This is a followup meeting to the one held on April 3, 1980 with the B&W operating plant licensees.
PARTICIPANTS:
NRC:
R. Tedesco and members of the B&W Reactor Transient Response Task Force LICENSEES:
Duke Power Company (Oconee 1, 2, and 3)
Metropolitan Edison Company (TMI-1)
Florida Power Corporation (Crystal River 3)
Sacramento Municipal Utility District (Rancho Seco)
Arkansas Power & Light Company (ANO-1)
Toledo Edison Company (Davis-Besse 1)
B&W:
J.
Taylor, E. Womak, R. Ham, et al R.A. Capra,.B&W Project Manager Standardization Branch Division of Project Management cc: 3&W Licensees 80041s 09so
MEETING NOTICE DISTRIBUTION
- -Docket Files M. Rubin
- Docket Nos.: 50-269
- -NRC PDR S. Newberry 50-270
- -LPDR B. Wilson 50-287 SB Reading D. Thatcher 50-289 ORB#4 Reading P. Matthews 50-302 NRR Reading P. Norian 50-312 H. Denton B. Sheron 50-313 E. Case V. Panciera 50-346 D. Eisenhut D. Tondi R. Vollmer R. Capra D. Ross E. Blackwood S. Hanauer D. Quick (IE RII)
R. Mattson M. Cunningham T. Novak J. Olshinski S. Varga J. Beard T. Ippolito B. Siegel R. Clark J. Cresswell R. Reid M. Taylor R. Denise F. Rowsome D. Hood D. Rathbun T. Bornia J. Anderson (ORNL)
B. Grimes OSD G. Lainas Receptionist, Phillips P. Check J. Souder -(Adv. copy for Rancht beco and TMI LPDRs)
R. Satterfield W. Butler F. Rosa R. Tedesco T. Speis J. Stolz P. Collins D. Ziemann F. Schroeder K. Kniel C. Berlinger W. Russell G. Vissing M. Fairtile D. Garner D. Dilanni H. Silver S. Wookey R. Ingram P. Kreutzer V. Stello I&E (3)
S. Lewis R. Black IL. Schwart R. Fraley, ACRS (16)
J. Buchanan TERA W. Kane S. Israel G. Mazetis
-, C U'
0p UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 APR 4 1980 Docket Nos.
0 269 0-270, 50-287, 50-289, 50-302, 50-312, 50-313, 50-346 FACILITIES:
Oconee Nuclear Station, Units Nos. 1, 2, & 3 (Oconee)
Three Mile Island Nuclear Station, Unit No. 1 (TMI-1)
Crystal RiverNuclear Generating Station, Unit No. 3 (CR-3)
Rancho Seco Nuclear Generating Station (Rancho Seco)
Arkansas Nuclear One, Unit No. 1 (ANO-1)
Davis-Besse Nuclear Power Station, Unit No. 1 (DB-1)
LICENSEES:
Duke Power Company (DPCO)
Metropolitan Edison Company (Met-ED)
Florida Power Corporation (FPC)
Sacramento Municipal Utility District (SMUD)
Arkansas Power & Light Company (AP&L)
Toledo Edison Company (TECO)
SUBJECT:
SUMMARY
OF MEETING HELD ON APRIL 3, 1980 WITH THE B&W OPERATING PLANT LICENSEES TO DISCUSS DRAFT NUREG-0667 ENTITLED "TRANSIENT RESPONSE OF BABCOCK & WILCOX-DESIGNED REACTORS" On April 3, 1980, members of the NRC's "B&W Reactor Transient Response Task Force" (the Task Force) met with representatives of the B&W operating plant licensees and the Babcock & Wilcox (B&W) Company, in Bethesda, Maryland, to discuss the findings and recommendations of the Task Force as documented in Draft NUREG-0667 ("Transient Response of Babcock and Wilcox-Designed Reactors,"
April 2, 1980). is a list of attendees and Enclosure 2 is a copy of the viewgraphs used during the presentation.
BACKGROUND On February 26, 1980, the Crystal River Unit 3 Nuclear, Generating Station experienced an incident involving an electrical malfunction in an instrumenta tion and control system. This resulted in.:
a.reactor and turbine trip; the opening of the pressure power-operated relief valve (PORV), the pressurizer spray valve, and a code safety valve; decreased feedwater flow to the steam generators; actuation of the engineered safety features (ESF) systems; and a discharge of approximately 40,000 gallons of primary coolant into the con tainment building. The reactor was designed by B&W.
Certain of the events were similar, in some respects, to those that took place at the Three Mile Island Unit 2 (TMI-2) approximately one year ago and to those that have occurred at other B&W plants in recent years.
APR 4 1980 l
eeting Summary
- April 3, 1980
-2 Faced with the CR-3 incident and the apparently high frequency of near sirilar types of transients in other B&W plants, a special task force (i.e., B&W Reactor Transient Response Task Force) was established by the Director, Office of Nuclear Reactor Regulation (NRR), on March 12, 1980, to assess the generic aspects of operating experiences of the B&W plants. The time estimate to complete this effort was established to be approximately two weeks. This assessment would include consideration of the apparent sensitivity of the B&W plants to overcoolin and undercooling events, small break loss-of-coolant accidents ?LOCAs), and the consequences of malfunctions and failures of the integrated control.system (ICS) and non-nuclear instrumentation (NNI). This study would be made in conjunction with all of the actions already taken or proposed in response to the TMI-2 accident.
The Task Force presented the results of its review to the Director, NRR and the NRR Division Directors in a briefing on March 28, 1980.
On April 2, 1980, the Task Force published a draft copy of its study entitled "Transient Response of Babcock & Wilcox-Designed Reactors," (NUREG-0667). This meeting was called by the Chairman of the Task Force in order to share the findings and recommendations of the Task Force with the B&W operating plant licensees.
DISCUSS IO The Director, NRR opened the meeting by presenting his personal views on the acceptability of recent events in B&W operating plants,.such as the one that occurred at CR-3 on February 26, 1980.
He stated that while he agreed that the CR-3 event did not endanger the public health and safety, the dis charging of 40,000 gallons of primary coolant in~to thecontainment building was not an acceptable plant response to a transient event. In the relative short period of commercial operation of the B&W plants (approximately 38 reactor years), there have been too many undesirable incidents involving B&1-designed reactors.
He stated that as a result of his concerns, he established the B&W Reactor Transient Response Task Force to give him an assessment of the acceptability of operating these plants in light of their apparent sensitivity to transients originating in the secondary systems. He stated that while he could not give a formal position on the recommendations of the Task Force (pending completion of Section 7 of the draft report "implementation of Recommendations Based Upon Risk Reduction-Potential"), he encouraged B&W and the licensees to vigorously pursue ways to improve their safety record and, in particular, improve plant response to operational transients such as loss of feedwater events. This will be necessary to support long-term operation of the licensed plants as well as those presently under construction.
Following the Director's remarks, the Chairman of the Task Force made a five F
psk presentation which included: (1) background material associated with the iakForce review, (2) composition of the Task Force, (3) general findings,
- )recomMendations, and (5) overall Task Force conclusions.
-rovides a summary of each of the five parts.
Meeting Summary
- April 3, 1980 A
1o The main areas of review by the Task Force centered around: (1).the sensitivity of response to and recovery from overcooling and undercooling events caused by feedwater-related transients, (2) the effects and consequences of mal functions and failures in the plant control system (i.e., the integrated control system (ICS)) and the non-nuclear instrumentation (NNI), and (3) the effectiveness of ongoing actions developed mainly from the work of the TMI-2 Lessons Learned Task Force and the Bulletins and Orders Task Force. The results of the Task Force review are provided in a draft document entitled "Transient Response of Babcock & Wilcox-Designed Reactors," which-was released on April 2, 1980. (NUREG-0667). Section 7 of the report, which covers the risk reduction potential associated with each of. the Task Force recommendations.and the recommended implementation schedule, is still being developed by the Task.
Force. It was pointed out that Section 7 should be completed in approximately two weeks.
Four general findings of the Task Force were highlighted during the meeting:
(1) The findings of the Task Force support previous staff conclusions that the B&W-designed 177-Fuel Assembly plants show some unique level.s of sensitivity in their response to and recovery from anticipated tran sients involving overcooling and undercooling events as well as small-break loss-of-coolant accidents.
(2) The once-through steam generator (OTSG), 'used in the B&W plants, is basically a sound design; however, its use requires a highly interactive and responsive control system (i.e., the ICS).
(3) Because of (1) and (2) above, a high degree of overall plant.interaction is inherent in the ICS and OTSG.
(4) Because *of the design features and the faster response of the B&W-designed plants to transient and upset conditions, the-operators of these plants are required to take more rapid action and have a better understanding of instrument response than operators of plants of other designs.
Based upon the general findings of the Task Force, recommendations were developed which were aimed at minimizing the frequency and consequences of secondary side perturbations by: (1) providing more reliable instrumentation and control systems, (2) assuring availability of a heat sink (OTSG), and improving plant recovery actions.
The Task Force divided its recommendations into four general action areas:
(1) Auxiliary (or Emergency) Feedwater, (2) Instrumentation and Control, (3) Design and Operational Matters, and (4) General Areas of Long-Term Improvement.
It is the intent of the Task Force that each of the specific recommendations, following approval, be incorporated into the TMI-2 Action Plan (NUREG-0660, "Action Plans Developed as a Result of the TMI-2 Accident). A listing of each of the recommendations of the Task Force is provided in pages 6 through 11 of.
Meeting Summary - April 3, 1980 APR 4 1980 In summarizing the work of the Tasl' -rce, the Chairman presented the overall conclusions.drawn from the study:
(1) Improvement in plant safety can be achieved by the continued implementation of the TMI-2 Lessons Learned and Bulletins & Orders Task Forces' recormen dations as well as the recommendations of this Task Force.
(2) Continued plant operation is permissible; however, Task Force recommenda tions related to the development of guidelines, emergency procedures and operator training should be completed expeditiously.
(3) Recommendations advanced by the Nuclear Safety Analysis Center and the Institute of Nuclear Power Operations, associated with the Crystal River 3 event, should be applied to all operating B&W plants.
(4) The NRC staff should expedite its review of the Crystal.River 3 event and the responses of the B&W licensees to the NRC's March 6, 1980 letter to All B&W Operating Plants.
Following the Task Force presentation, several topics were discussed:
(V) The B&W Licensees expressed.a strong desire to meet with the staff as soon as possible following the completion of Section 7 of the report.
In order.to implement the proposed action items in the most effective manner, they recommended staff/licensee interaction on prioritization of the recommendations as well as the development of an implementation schedule. The staff agreed.to meet with the licensees to discuss these matters as soon as Section 7 of the report became.available.
(2) TECO took exception to recommendation number 3 of the Task Force.
As written, the recommendation reads:
"Installation of an electrically driven AFW pump should be expedited at the Davis-Besse facility."
TECO is presently working on the feasibility of installing a diesel-driven AFW pump. The staff agreed to change the wording of the recommendation to allow for consideration of this proposal.
(3),
With regard to recommendation number 17 (a solution to the PORV unreliability/safety system challenge rate concerns (see page 10 of Enclosure. 2)): B&W requested to know, if the staff approved a pro posal similar to.that advanced by Consumers Power Company, would the reactor trip upon turbine trip feature, presently in place on the B&W plants, still be required? The Task Force said that if such a proposal was approved for backfit on operating plants, the staff would consider the removal of that trip function in its review.
(4) The Task Force presented its schedule for future action regarding the report. The Task Force will make presentations to the ACRS Subcommittee on B&W Water Reactors on April 8, 1980.and to the full ACRS on April 11, 1980. At both of these meetings, the B&W Licensees and B&W will be invited to make short presentations. The Task Force will conduct a Commission briefing during the week of April 14, 1980.
Meeting Summary - April 3, 1980
-5 CONCLUSIONS On April 23, 1980, the Task Force will meet with B&W and the B&W Licensees to discuss the results of the Risk Reduction Potential Study, presently underway by the NRC's Probabilistic Analysis Staff, and to discuss priorities and schedules for implementing the recommendations contained in Draft NUREG-0667.
Robert A. Capra, Project Manager Standardization Branch Division of Project Management
Enclosures:
- 1. List of Attendees
- 2. Viewgraphs used during the Task Force presentation cc w/enclosures:
See attached lists LIST OF ATTENDEES-04/03/80 Orcanization Name Position Duke Power Company R.L. Gill Licensing Engineer P.M. Abraham Licensing Engineer Metropolitan Edison/GPU C.W. Smyth Licensing Engineer Sacramento Municipal Utility No Representative District Arkansas Power. & Light Company D.G. Mardis Licensing Engineer Toledo Edison Company F.R. Miller Licensing Engineer J.R. Lingenfelter Operations Florida Power Corporation D.A. Morrison H.M. Perry Licensing Engineer Tennessee Valley Authority L.A. Haack Engineering/Design Babcock & Wilcox J.H. Taylor Manager, Licensing E.A.. Womack Manager, Plant Design R.E. Ham Product Line Manager NUS Corporation:
J.E. Slider Senior Engineer for NSAC/EPRI McGraw-Hill S. Wynkoop Washington Editor/Nucleonics Wk.
NRC (Task Force Members)
R.L. Tedesco Acting Deputy Director DOR V.W. Panciera Reactor Safety Branch, DOR B.W. Sheron Reactor Safety Branch, DOR D. Tondi Plant Systems Branch, DOR T.M. Novak Chief, Reactor Systems Branch,DS D.F. Thatcher Inst. & Cont. Sys. Branch, DSS R.A. Capra Standardization Branch, DPM B.A. Wilson Operator Licensing Branch, DPM E.B. Blackwood Headquarters, I&E D.R. Quick Reactor Inspection, RII, I&E M.A. Cunningham Probabilistic Analysis Staff, RE NRC Staff H.R. Denton Director, NRR D.J. Garner Project Manager, DOR M.
Fairtile Project Manager, DOR G.
Rivenbark Project Manager, DOR D.C. Dilanni Project Manager, DOR G.
Vissing Project Manager, DOR P.B. Anderson Project Manager, DOR
-2 (Continued)
LIST OF ATTENDEES-04/03/80 Organization Name Position NRC (Continued)
J.A. 01shinski Technical Asst., DOR P. Shemanski Plant Systems Branch, DOR.
J.T. Beard Plant Systems Branch, DOR B.L. Siegel Reactor Systems Branch., DE P. Norian Analysis Branch, DSS P.R. Matthews Aux. Systems Branch, DSS J.S. Creswell Anal. & Eval of Oper Data D.K. Rathbun Office of Policy Eval.
R.L. Black Staff Counsel