ML20003H569
| ML20003H569 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 04/14/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1830, NUDOCS 8105060340 | |
| Download: ML20003H569 (7) | |
Text
DATE ISSUED:
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MINUTES OF THE SAN ONOFRE 2 & 3 SUBCOMMITTEE MEETING
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FEBRUARY 18, 1981 y
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\\.j The ACRS Subcocraittee on San Onofre 2&3 met in Washington, D.C. on February to continue its review of the plant as part of the ACRS review for 18, 1981 operating licenses.
PRINCIPAL ATTENDEES:
H. Rood, NRC/NRR M. Bender, Chaiman R. Lipinski, NRC/NRR D. Ward, ACRS Member A. Cappucci, NRC/NRR W. Mathis, ACRS Member G. Harrison, NRC/NRR J. Rs, ACRS Member W. Moody, SCE I. Catton, Consultant K. Baskin, SCE W. Lipinski, Consultant D. Pillmar, SCE
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S. Ditto, Consultant D. Nunn, SCE E. Abbott, ACRS Fellow Mr. Prickett, SCE R. Savio, ACRS Staff
- Mr. Fried, Bechtel D. E. Bessette, ACRS Staff A. Spinell, CE H. Windsor, CE R. Turk, CE E. Richardson, Bechtel R. Rosenblum, SCE No oral or written comments were received frca members of the public.
Attached is the presentation schedule and a list of documents considered by the Subcommittee.
APPLICANT ORGANIZATION There is a single K. Baskin (SCE) summarized the Applicant's organization.
officer with the title of vice-president (Robert Dietch) responsible for This individual. reports to a senior vice-president who in turnSan nuclear.
reports to tie president.
investments of SCE.
The plants currently lack sufficient hcalth physics and maintenance personnel, Most of the technical and are utilizing outside contractors in these areas.
SCE posesses staff consists of young engineers with little prior experience.
what they believe to be the requisite number of technical staff individuals.
The shift technical advisors are also young engineers with little perience.
from San Onofre.
The opinion SCE has INPO is that the organization currently is not sufficiently advanced as to be of much use.
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Fcbruary 25, 1981 San Onofre 283 The training is The plant training staff consists of about 20 persons. Currently the CE simula-operations oriented.
SCE will purchase a simulator.
tor is being used.
The Subcommittee questioned:
Whether SCE has given sufficient study to their planned simulator 0
purchase.
Whether SCE fully realices the benefits and limitations of simulators O
as a training aid.
The nature of the training program and the qualifications of the O
1*aining staff, inicuding the chief of training.
Mr. Bender also requested a presentation on the views of SCE management on staffing as to whether the qualifications of their personnel are adequate.
NRC SEISMIC AND FIRE PROTECTION REVIEW A.
(NRC/NRR) summarized the NRC seismic review of structures.
R. Lipinski Cappucci summarized the seismic review of equipment, which was performed for the NRC by Energy and Technology Engineering Corporation, Canoga Part, California.
Mr. Bender requested that the NRC Staff provide a clearer picture of the scope For and depth of the NRC review, including the systems interaction review.
example, how did the San Onofre review compared with Diablo Canyon and Zion /
Indian Point reviews.
The review G. Harrison (NRC/NRR) summarized th'e fire prttection review.
Each plant included the use of a fire protection consulant and a site visit.
has an alternate shutdown center that can fun: tion independently of the cable The plaats have Standard Technical I
spreading room and the control roorg.
The Specifications for surveillance testing of fite protection equipment.
fire protection design conforms to current NRC regulations.
OPEN ITEMS Dr. Catton requested H. Rood (NRC/NRR) summarized the remaining open items.(1) population more information on:
the site locale; (3) the CE analysis of seismic-plus-LOCA loads on reactor internals, including the fuel assembly, and (4) justification for using e ONBR i
ratio of 1.19.
EMERGENCY PLANNING The Subcommittee D. Pillmer (SCE) described emergency planning for the plants.
l requested that SCE define what it perceives the role of the NRC and other.
government agencies to be in the event of an accident.
PREOPERATIONAL TESTING The R. Rosenblum (SCE) gave the status of the preoperational testing program.
various test procedues are written for the most part by Bechtel and CE, and are The test program satisfies the NRC regulatory guides require-reviewed by SCE.
ments. Mr. Bender inquired how the adequacy of the preoperational test is l
It was noted that NRR will meet with AE00 to review the San established.
Onofre preoperational test program.
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,. February 25, 1981 San Onofre 2&3 QUALITY CONTROL EXPERIENCE D. Nunn (SCE) summarized quality control experience during plant construc-It was said that the Q4/QC program was well-run and that there were tion.
relatively few major problems encountered.
HYDROGEN CONTROL PROVISIONS As Mr. Fried (Bechtel) presented information on containment hydrogen control.
long as the containment air circulation fans are operating, the atmosphere The containment volume is 2.3 million cubic feet, with a will be well-mixed.
A The containment has been tested to 69 psig.
design pressure of 60 psig.
study, performed by Bechtel for Pilgrim, was referenced as providing supporting analysis that the containment could survive the burning of an amount of hydrogen equivalent to 75% clad reacted.
CONTROL ROOM DESIGN AND ENGINEERING A working group was formed by SCE to Mr. Prickett (SCE) summarized this topic.
determine what improvements to the control room were necessary, and the adequacy Mr. Ditto noted that while it appears that much attention of the final design.
operator / machine was given to the operator / control panel interface, theMr. Abbott added that there is a interface was not given the same a, tention.
t considerable number of instruments and controls located outside the contr Mr.
room that receive much less attention than those in the control room.
Bender questioned whether sufficient attention was given to utilization of trend indicators.
INSTRUMENTATION TO DETECT INA0 EQUATE CORE COOLINGThe A. Spinell (CE) presented this topic.
Heated junction thermocouples, which are located in the vessel above the 0
upper core plate, to detect water level.
Core exit thermocouples (56 in number) located in guide tubes just O
about the top of the active core.
Subcooling margin meter, which uses hot leg thermocouples for tem-O perature input.
The Subcommittee questioned whether the heated junction thermocouples should The Subcommittee also noted that be restricted to the region above the core.
the core exit thermocouples are somewhat isolated, and inferring core tempera-tures from them is an uncertain process.
NATURAL CIRCULATION TESTING The
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H. Windsor (CE) described the natural circulation testing program.
testing will demonstrate horation and cooldown under natural circulation, and is similar to that nerformed, for example, at Sequoyah.
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February 26, 1981 San Onofre 2&3 STATION BLACK 0UT ANALYSES He noted that SCE has imple-E. Richardson (Bechtel) summarized this topic.
The mented the recommendations of a recent NUREG on diesel reliability.Also noted recommendations included improved maintenance and surveillance.The Subcommittee reque was the fact that SCE has never lost their grid.
further information on why this excellent record has been achieved.
The plants have been analyzed as being capable of withstanding loss of AC power for two hours.
AUXILIARY FEE 0 WATER SYSTEM IMPROVEMENTS R. Turk (CE) summarized improvements to the auxiliary feedwater system which were made as part of TM1 lessons learned.
FUTURE MEETINGS 11, 1981 to continue The Subcommittee will meet in Washington, D.C. on MarchThis topic will also b its review of San Onofre 2&3.
Committee meeting, March 12-14, 19,81.
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LIST OF DOCLHENTS 9
Safety Evaluation Report related to the operaf. ion of San Onofre Nuclear 1.
Generating Station, Units 2 & 3, Supplement 2.
Licensing Status - 5 slides Features of the San Onofre Structural Review - 7 slides 3.
Review of Seismic Design of San Onofre - 8 slides 4.
Southern California Edison Presentation - 84 slides 5.
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Tentative Presentation Sche.1ule ACRS Subcommittee on San Onofre 283 Washington, D.C.
February 18, 1981 Organization /
Presentation Approximate Speaker Time Time 5 min 8:30 am Oper.ing Remarks by the Subcommittee 1.
Chairman 2.
Staff Presentation NRR/H. Rood 5 min 8:35 am 2.1 Introduction 25 min 8:40 am 2.2 Scope of NRC Review
' Seismic Evaluation ER/Lipinski,
- 1. Capuchi ER/G. Harrison
' Fire Protection
' Detailed Systems Reviews ER/ Rood 10 min 9:20 am 2.3 Discussion of Open Items
' Differing Professional Opinions 3.
Applicant Presentation SCE/W. Moody 5 min 9:35 am 3.1 Introduction SCE/K. Baskin 25 min 9:40 am 3.2 Applicant Organization
'Intera: tion with INP0
' Personnel Qualifications 10 min 10:20 am l
Break SCE/D. Pilmer 10 min 10:30 am 3.3 Emergency Planning SCE/R. Rosenblum 15 min 10:45 am 3.4 Preoperational Testing SCE/D. Nunn 20 min 11:10 am
- 3. 5 Quality Control Experience and Problems 4
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2 Tentative Presentation Schedule ACR; Subcorx:ittee on San Onofre 283 Washington 0.C.
February 18, 1981 Organization /
Presentation Approximate Speaker Time Time 3.6 Secondary System Chemistry CE/G. Carruthers 15 min 11:40 a=
and Materials: Condensor, feedwater heaters, steam generator, water chemistry, plant chemis 60 min 12:05 pm Break for Lunch 3.7 TMI Related Issues
' Control Room Engineering, SCE/Prickett 20 min 1:05 pm including safety parameter display system and mimicking
' Hydrogen Control Provisions Bechtel/ Fried 10 min 1:40 pm
' Instrumentation to Detect CE/A. Spine 11 20 min 1:55 pm Inadequate Core Cooling
' Natural Circulation CE/H. Windsor 10 min 2:25 pc
' Auxiliary Feedwater System CE/R. Turk 10 min 2:40 pm i
Improvements
' Station Black-Out Analyses Bechtel/
10 min 2:55 pm E. Richardson 3.8 Simury and Conclusions SCE/W. Moody 10 min 3:10 pm i
10 min 3:20 pc 4.0 Executive Session 3:30 pm Adj ournment e
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