ML20062J689
| ML20062J689 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1980 |
| From: | Jensen W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062J670 | List: |
| References | |
| NUDOCS 8011040508 | |
| Download: ML20062J689 (6) | |
Text
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U:;1TED S1/105 0F l.l.LI:lCA
!!UCLEAR RECULATORY col.MlSSION BUCRE THE AT0lilC S/JETY /.l D LICENSING BOARD In the I:atter of
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f:Lil:0POLITAN EDIE0N CC:'.PANY, DUCKET No. 50-2E9 et al.
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1 (Three l'ile Island I:uclear
)h Station, Unit 1 NRC STAFF TESTII:0NY Of tl ALTON L. JEf;SEN, JR.
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-IRARDitCTfhi5)LitI AND ACCTDLHT h!.ALY$1T7AD~FECCEUURLS
tPARD 7 EdI wn ii EC/.RD QUESTION
- The board is not satisfied with the staff findings in the SER with respect to Reco:nendation 2.1.9.C (transients and accidents) of NUREG-0578. The staff ccncludes that satisfactory progress has been r.:ade and the itera is
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couplete. SER, pp. C-10, CE-49. According to Table 8-2, the analyses and precedures t.cre scheduled for con:pletion by early 1980. L'e cbserve that in
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l'ay of this year, it was reported that "the Staff is performing a generic revicw of transients and other accidents in accordance with Re"cmendation c
2.1.9 of NUREC-0578 (NUREG-0067, p. 5-26).
l'e expect the licensee and the staff to present evidence that the require-r.cnts on p. A-45 of NUREG-0578 will be n:et and to explain the schedule for
- .ceting those requirements.
The board, as well as the staff, cust have sufficient information to decide t;hether satisfactory progress is being r_.
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senoa
R:sponse:
The TMI-2 Lessons Learned Task force recona ended in Secticn 2.1.9 of I:UREG-0578 E
that plant 'cn:erscncy procedures be develop 6d based on plant analyses of strall treak LOCf, inadequate core cooling and transient and accidents. The transients cnd accidents to he considered should include the design basis events of Section 15 of each FSAR and shculd include the effect of single failure of cach system required to function and the effect of operator error. Using event trees and computer analyses, operator guidelines are to be developed f
1 hich will be developed into plant en,ergency procedures and utilized in epcrator training.
The requiren.cnts of Section 2.1.9 of RUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recor.ziendations" have been incorporated in Task 1.C.1 of the TMI-2 Action Plan. The NRC staff proposed a schedule for completion of this task in " Letter to All Licensees of Operating Plants end Applicants for Operating Licenses and Holders of Construction Permits" dated September 5, 1980. This schedule has not yet been approved by the NRC b
Commissioners. The schedule proposed by the staff required that guidelines for development of plant procedures be submitted to the NRC by January 1,1981 and -
that the procedures be revised by January 1, 1982.
7.s discussed on page C8-49 of the TMI-l Restart SER NUREG-0680, the Babcock S L'ilcox Plant Duners Group of which Metropolitan Edison is a r.:erder has consnitted to accomplish the requirements of Recommendation 2.1.9 as part of
a
- the AT0G program. This program is designed to develop emergency procedures
'for treating the symptoms of transients and accidents 'rather than requiring E
that the operators identify the plant failure tihich occurred in order to select the correct procedure. Any accident or transient including LOCA uhich l
produces abnonnal plant conditions should be covered by the re/ised emergency a
- procedures. Pecause of plant differences each of the B&W plants will require different guidelines and cmergency procedures.
These will be cor.pleted in a sequential schedule developed by the Duners Group. The lead plant in the
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sequence is ANO-1. A draft of the operational guidelines and supporting analyses for AMO-1 was co,pleted in July 19S0 and copies were provided to i
the CRC staff in a ccating with the Owners Group August 21,_1980. The Owners Group also presented a schedule for development of Event Tree's, Analysis and guidelines for the other BSW plants. A copy is attached to this testimony..
'The schedule indicates that guidelines for TMI will be completed in February of 1981.
For the interim period before emergency procedures based on AT0G are completed, k
the NRC is reviewing the current Emergency Procedures for TMI-1. This review is described on pages Cl-15,* Cl-16, C2-4, C2-5, C6-15 and C6-16 of NUREG-0680.
This revieu will be completed before restart. The operators at TMI-l are also being retrained to deal with events similar to those which occurred at TMI-2. This training is discussed on pages Cl-6, C2-4 and C2-16 of GUREG-06SO.
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WALTON L. JENSEN, JR.
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PROFESSIONAL QUALIFICATIONS I ce a Senior Nuclear Engineer in the Reactor Systecs Branch of the Nuclear Regulatory Com.ission.
In this position I am responsible for the technical analysis and evaluation of the public health and safety aspects of reactor-( systems.
i Fres June 1979 to December 1979, I was assigned to the Bulletins and Orders Task Force cf the Nuclear Regulatory Commission.
I participated in the preparation of NUREG-0565, " Generic Evaluation of Small Break Loss-of-Coolant Accident Eehavior in Babcock & Wilcox Designed 177-FA Cperating Plants."
From 1972 to 1976, I was assigned to the Containment Systems Eranch of the NRC/AEC, and from 1976 to 1979, I was assigned to the Analysis Branch of the NRC.
In these positions I was responsible for the develcpment,and evaluation
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of computer programs and techniques to calculate the reactor system and centainment system response to postulated loss-of-coolant accidents.
From 1967 to 1972, I was employed by the Babcock and Wilcox Ccmpany at Lynchburg, Virginia. There I was lead engineer for the ' development of loss-of-coolant co puter prograEs and the qualification of these programs by comparison witn experimental data,
From 1963 to 1967, I was empicyed by the Atomic Energy Com ission in the Division of Reactor Licensing.
I assisted in the safety reviews of large y
power reactori, and I led the reviews of several small research reactors.
I received an M.S. degree in Nuclear Engineering at the Catholic University of America in 1968 and a B.S. cegree in tJuclear Engineering at I:ississippi State University in 1963.
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I am a graduate of the Oak Ridge School for Reactor Technology, 1963-1954.
I am a member of the American Nuclear Society.
I am the author of three scientific papers dealing with the response of S&W reactors to Loss-of-Coolant Accidents and have authored one scientific paper dealing with containment analysis.
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