ML20003G873
| ML20003G873 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/14/1981 |
| From: | Bender M, Mathis W, Ward D Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1838, NUDOCS 8105040089 | |
| Download: ML20003G873 (7) | |
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SUMMARY
/ MINUTES OF THE SAN ON0FRE 2 & 3 SUBCOMMITTEE MEE
/)C)t'S.,1889 MARCH 11,1981 WASHINGTON, D.C.
g The ACRS Subcommittee on San Onfore 2 & 3 met in Washington, D.C. on March 11, 1981 to continue its review of the plants as part of the ACRS review for operating licenses.
Principal Attendees:
H. Rood, NRR M. Bender, Chairman P. Collins, NRR D. Ward, ACRS Member R. Benedict, NRR W. Mathis, ACRS Member J. Knight, NRR M. Carbon, ACRS Member C. Thomas, NRR J. Ray, ACRS Member I. Catton, ACRS Consultant W. Moody, SCE J. Willis, SCE S. Ditto, ACRS Consultant J. Hosmer, Bechtel E. Abbott, ACRS Fellow lin
'J. Purucker, Bechtel d"g<
D. E. Bessette, ACRS Staff K. Baskin, SCE G. Quittschreiber, ACRS Staff W. Burchill, CE
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R. Phelps, SCE
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e W. Schmus, SCE p#
E. Richardson, Bechtel
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D W. Strom, SCE V. Fisher, SCE R. Daleas, CE R. Turk, CE l
M. Redd, Singer-Link B. Katz, SCE Attached No oral or written coments were received from members of the public.
is the presentation schedule and a list of documents considered by the Subcomittee.
PLANT STAFFING REQUIREMENTS AND SCHEDULE l
H. Rood (NRR) described the status of plant staffing and schedule.
Fuel loading is scheduled for 10/15/81, initial criticality for 11/23/81, and 100%
power for 4/8/82.
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e SONGS 283 Currently, there are 66 startup engineers and 102 startup technicians on-site.
A startup engineer is defined as an engineer whose time is 100% dedicated to The Staff indicated that; the startup crew at San Onofre startup activities.
There are 301 total station personnel with was large compared to other plants.
Mr. Bender noted that NRC had not 490 required by fuel loading (9/15/81).
provided a basis for determining adequacy of staffing with regards to the It was noted that NRC has no number of individuals and their qualifications.
criteria for qualifications of non-operations personnel.
STANDRDS FOR OPERATOR TRAINING _
P. Collins (NRR) discussed operator training requirements on simulators.
The requirements include operating experience at a comparable facility.
Altnough San Onofre is a CE olant, a Westinghouse simulator could be utilize Mr. Bender requested the Staff provide in writing a statement on what they fee is adequate plant and simulator train.ing for operators.
MANAGEMENT EVALUATION
_Mr. Benedict (NRR) presented results of the NRC evaluation of SCE managemen A seven-member team from the Staff performed a management audit of SCE in The primary objective was to obtain assurance of corporate February 1981.
It was noted by the auditors that t*
dedication to safe plant operation.
Shift Technical Advisors are inexperienced, and that there had been some shortcomings in the Unit 1 maintenance program which have since been corr f
Mr. Bender inquired about the Staff's assessment of the functions and effectiv Onsite Safety Review the tarious Safety Groups, There are five separate Safety Groups:
Committee (0SRC); Nuclear Concrol Board (NCB); Shift Technical Adviso
)
The OSRC pendent Safety Engineering Group (ISEG); and Nuclear Safety Group (NSG The is comprised of onsite management, wherea,s high-level management m purpose of the NSG is to review operating experience, design change The STAS and the ISEG are to be comprised of the same group and risk assessment, etc.
Mr. Bender asked The addition of an ISEG is a requirement for NT0Ls.
of individuals.
l t that the Staff compare the ISEG/STA practice at San Onofre with that of othe and give more thought to the matter before they draw conclusions on t Mr. Bender noted that the Staff review of the Safety Groups was Onofre plan.
insufficient.
. SONGS 283 STRUCTURAL EVALUATION A structural J. Knight (NRR) summarized the Staff's evaluation of structures.
audit, performed by a three-member team from.the Staff, reviewed selected components and design codes.The structural au'dit by the Staff was similar to that performed for Diablo Canyon. The design review of San Onofre was performed The Staff concluded that the structural and by a consultant for the Staff.
The Staff believes that signi-mechanical design of San Onofre is excellent.
Mr.
ficant margins exist between operating stresses and code allowables.
Bender noted that the Staff should have a more formalized method of verifying codes used in design of the plant.
Dr. Catton noted that NRC's reviews of functional interactions to date have-The Staff is hoping to improve this area in the future.
been minimal.
PLANT STAFFING Mr. Dietch (SCE) provided information on plant staffing for San Onofre 283.
Currently there are 361 individuals on hand : 189 operations, 56 maintenance, 82 plant engineering, 9 health physics, 'and 25 administrative.
PERSONNEL TRAINING PROGRSMS The training programs meet Regulatory J. Willis (SCE) discussed training programs.
The training staff numbers 25 and will eventually grow to Guide 1.8, Revision 2.
The operators undergo a 52-week training program, including three to five 44.
Future Potential candidates are tested prior to entry.
weeks on a CE simulator.
candidates for operator will, typically, be high school graduates with no prior The candidates will have the opportunity to eventually progress nuclear experience.
There will be six operator crews, with one in training at all to shift supervisor.
times.
Mr. Bender inquired how the determination is made as to which maintenance personnel The reply was that the determination was the' duty are qualified for which duties.
For relatively important jobs, higher management of the responsible supervisor.
would become involved.
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r SONGS 233 SIMULATOR PROGRAM SCE utilized B. Katz (SCE) described SCE's plans for purchasing a simulator.
A contract a simulator consultant in determing the simulator specifications.
, The simulator will me the require-was awarded to Singer-Link for the purchase.
ments of ANSI 3.5.
SCE had discussions were held with two utilities with 3-unit There sites as well as with CE to guide them in their planning for the simulator.
uill be a program to feed back experience from use of the simulator into emergency Perforaance monitoring of the operators will be carried out.
procedures.
Dr. Catton expressed serious doubt about the claim made by SCE and Singer-Link that the simulator will realistically reflect thermal-hydraulic behavior of the plant and over the entire plant operating range, for both normal and abnorm 11 condition:
including two-phase flow.
SYSTEMS INTERACTIONS J. Hosmer (Bechtel) discussed functional interactions involving the interface between the air system and water systems. Bechtel has attempted to minimize the potential for water ingress into the' air system from water systems.
ALARA PROGRAM AND ACCIDENT SAMPLING CAPABILITY J. Purucker (Bechtel) discussed these two subject s.
Bechtel paid close attention For example, during plant design to features to minimize persunnel exposures.
where possible, components that require surveillance and maintenance such as instruments are located in low radiation areas.
The sampling lab as it existed prior to TMI would not have been capable of handling high radiation samples. A post-accident sampling system was designed and installed.
A separate reactor coolant system sampling line is provided for high radiation situations. Grab samples can be diluted or undiluted. Gamma-scan capability is provided. Shielding was reviewed for adequacy and improved where necessary.
ROLE OF NRC IN EMERGENCY SCE K. Baskin (SCE) discussed the perceived role of the NRC in an emergency.
expects the NRC would give oversight, advice, and t ecommencations, but that Press releases would be the operation of the plant is still SCE's responsibility.
coordinated between NRC and SCE. An emergency dr'.ll is planned for early April.
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5-SONGS 283 INSTRUMENTATION TO DETECT INADEQUATE CORE COOLING The instrumentation consists of the U.Burchill (CE) discussed this subject.
subcooling margin meter, the heated junction -thermocouple (HJTC) system, and The HJTC measures the inventory of water above
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The core exit thermocouples can be used to infer clad temperatures the core.
Mr. Bender indicated that the ACRS will hold and, in turn, core water level.
a meeting to review the subject of water level indication in the reactor vessel on a generic basis.
IMPLEMENTATION OF REGULATORY GUIDE 1.97 Current re mirements call for R. Phelps (SCE) discussed Reg. Guide 1.97.
implementation by June 1983 except for NUREG-0737 items, which must be impl San Reg. Guide 1.97 addresses about 60 different variables.
mented earlier.
Onofre presently. meets about two-thirds of the Reg. Guide 1.97 requirements.
The remainder will reqaire addition of measurement channels, extended measure-SCE expected that the plants can ment ranges, or upgraded qualifications.
meet the intent of Reg. Gude 1.97.
GRID RELIABILITY W. Schmus (SCE) discussed this subject. The plant has four independent The area possesses a favorable climate with few lightning operating buses.
There are three 500 storms, and with no hurricanes, tornadoes, or ice storms.
kV ties with Pacific Gas and Electric, five 500 kV ties to Arizona, many ties SCE to Los Angeles Water and Power, and a tie to San Diego Gas and Electric.
There is an automatic load shedding I
has not lost their grid in 35 years.
system, and an islanding system to separate the utilities.
DC POWER RELIABILITY _
The batteries.have E. Richardson (Bechtel) discussed DC power reliability.
about two and one-half hours capacity should all AC power be lost. If load shedding were to be performed, the capacity could be stretched to 12 to 34 The DC controlled valves fail as-is. Mr. Ray asked whether spare hours.
inverters are kept on hand.
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FEEDBACK OF OPERATING EXPERIENCE This U. Strom (SCE) discussed mechanisms for feedback of operating experience.
The NSG will follow INP0 work, will be accomplished through the NSG and the -ISEG.
There will be coordination NRC circulars LERs, and other related infcrmation.
Mr. Bender urged between the review of this information and the training program.
SCE to continue their efforts to further aid the operator in accident diagnosis a response.
POST ACCIDENT DEPRESSURIZATION T.re is a reactor vessel vent installed, R. Turk (CE) discussed this subject.
The plant is not designed to accommodate feed and bleed.
but no PORV.
DESIGN TO PREVENT WATER HAMMER The feedkater line R. Turk summarized design features to prevent water hammer.
The feed ring employs J-tubes. This near the steam generator is at an angle.
design is in other CE plants and has not suffered from water hammer.
SYMPTOMATIC ANALYSIS OF ACCIDENTS V. Fisher (SCE) sumcarized the manner in which emergency procedures are prov The procedures, however, There is no computer diagnostic assistance.
the opertor.
are presented in logic patterns keyed to observable symptons.
APPLICATION OF NUREG-0660 TRANSIENTS AND ACCIDENTS R. Daleas (CE) and R. Turk indicated whether there are unique features of the S There are no substantive Onofre design that might influence accident sequences.
differences between San Onofre and other CE or Westinghouse plants, it was sa 7
INDUSTRIAL SECURITY The size and qualiff-j K. Hadley (SCE) summarized industrial security at the site.
,l cations of the guard force, and their duties, were described.
Features to ensure separation of Units 2 and 3 following startup of Unit 2 were summarized.
\\l ADDITIONAL INFORMATION CAN BE OBTAINED FROM THE NR NOTE:
ROOM, 1717 H STREET, N.W., WASHINGTON, D.C. 23555 OR AT COST FROM l
ALDERSON REPORTING COMPANY, INC., 400 VIRGINIA AVENUE, S.W., W DC 20024 i
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L L b l Ur vut.urstn s 3 Safety Evaluation Report related to the operation of San Onofre, Units 1.
2 and 3, Supplement 1.
2.
San Onofre Staffing and Schedule - 3 slides 3.
Management Evaluation - 9 slides 4.
SCE Presentation - 122 slides i
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