ML20040F227
| ML20040F227 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/24/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1922, NUDOCS 8202080535 | |
| Download: ML20040F227 (16) | |
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f ISSUE DATE: 11/24/81 CV2415D MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON COMANCHE PEAK
. UNITS 1 & 2 WASHINGTON, D.C. h0VEMBER 11, 1981 The ACRs Subcommittee on Comanche Peak held a meeting in Room 1046, 1717 H St. NW., Washington, D.C., on November 11, 1981. The Subcommittee met with representatives of the Texas Utilities Generating Company and the NRC Staff.
Notice of this meeting was published in the Federal Register on Thursday, October 22, 1981.
A copy of this notice is included as Attachment A.
A list of attendees is included as Attachment B.
The schedule for this meeting is included as Attachment C A complete set of handouts is attached to the office copy of the minutes as Attachment D.
The meeting began at 1:00 p.m. with an opening statement by Mr. Bender, who introduced ACRS Members J. Ray and D. Moeller, and ACRS Consultants J. Arnold and F. Binford.
Mr. Bender stated the purpose of the meeting was to continue the review of the application of the Texas Utilities Generating Company for a license to operate Comanche Peak Units 1 & 2.
Mr. J. McKinley was introduced as the Designated Federal Employee and Mr. H. Alderman of the ACRS Staff was also present. The first speaker was Mr. S. Burwell of the NRC Staff.
NRC Staff Presentation, Overview Mr. Burwell noted the FSAR was docketed on April 25, 1981. The Subcommittee visited the plant June 29, 1981. The Safety Evaluation Report was issued July 14,1981. The first supplement to the SER was issued on October 16, and a full Committee meeting on Comanche Peak was scheduled for November 13,
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1981. HeTisioWpned that hearings for this plant start on December 2,1981.
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J COMANCHE PEAK UNITS 1 & 2 11/11/81 Supplementary Safety Evaluation Report - Open Items Mr. Burwell remarked that at the time of SSER issuance there were eight non-TMI items and nine TMI items remaining open. The open non-TMI items were listed as:
1.
The pipe break damage analysis outside of containment.
The applicant has not submitted this analysis.
2.
Equipment qualification for seismic load.
3.
Environmental qualification of electrical equipment, IEEE-1974.
A site audit is necessary in both these cases and that is de-layed until the applicant completes these programs.
4.
Pre-service /in-service inspection program.
The pre-service inspection program has been submitted.
5.
The transfer of the containment spray system from the injection made to the recirculation mode.
The applicant proposes manual initiation rather than automatic.
The Staff is concerned that the refueling water storage tank will run dry before the operator transfers suction to the sump.
6.
The low temperature over pressure protection system control design.
Mr. Burwell noted that this is, for all practical purposes, resolved.
7.
Consequences of control system failure from a harsh environment associated with a high-energy live break - has been resolved.
8.
Fire protection program - two items remain to be resolved.
a.
Completion of the remote shutdown system.
b.
Conformance with Appendix R.
2 CDMANCHE PEAK UNITS 1 & 2 11/11/81 Overview of Plant - Mr. Schmidt, TUGW Mr. Schmidt noted that Comanche Peak consists of two units, each rated at 3425 megawatts thermal, and they are Westinghouse RESAR-3 design reference pl ants. The circulating water is provided from a 3200 acre surface lake.
There is a seismically designed safe shutdown impoundment dam on one portion of the lake.
This is the ultimate heat sink.
The construction status of Unit 1 is about 89% complete. Unit 2 is about 52%
compl ete. The overall project is about 78% complete. The fuel. loading date is estimated at June 1983.
Mr. Schmidt stated that one intervenor voluntarily withdrew from the pro-ceedings which leaves two active intervenors.
The licensing board has schedu-led hearings to begin December 2, in Fort Worth, on three issues. These are quality assurance, financial qualifications and radioactive releases.
Organization and Management Structure - Mr. Clements, TUGC0 Mr. Clements introduced himself as the Vice President and Corporate Officer directly responsible for the operation of Comanche Peak. He mentioned that he has no other assigned duties. Mr. Clements noted that TUGC0 is the licensee and will operate Comanche Peak. Texas Utilities Services has been designated by TUGC0 to furnish design, engineering, construction, licensing, f'uel manage-ment and engineering technical support.
There was some discussion regarding certification of the health physicists.
Questions were raised if any of the health physicists were certified or planned to apply for certification. Mr. Clements said they will take another look at certification when he and his staff return to Dallas.
COMANCHE PEAK UNITS 1 & 2 11/11/81 Operator Training - Mr. Seidel, TUGC0 The operator training at Comanche Peak has three aspects; initial licensed operator training program, replacement operator training pro-gram, and a requalification training program.
The pretraining program consists of between five to nine weeks of mathematics and science review. The exact leno'h depends upon the class background.
Following the pretraining is the Westirghouse certification program.
Involved in this training program is fundamental nuclear training which includes about 12 weeks of classroom lectures in reactor theory, core physics, radiation protection and chemistry.
Included are about three weeks of training in reactor operations at the Westinghouse Training reactor.
Following this phase, the operators go into en operating PWR Observation program. Thi: is about a 10 week program during which the operat,rs learn about the systemsand design of a 4 loop PWR similar to Comanche Peak.
The next aspect of the training is a simulator training program involving about 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on cFe simulator. This training involves normal operations, malfunctions and transients.
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certification exam that is designed to simulate the NRC examination.
After the coerators have completeo the certification training, they spend i
about 30 full time weeks of indepth studies of the Comanche Peak systems.
COMANCHE PEAK UNITS 1 & 2 11/11/81
.Following all this training is the NRC licensing exams.
Training for Serious Accidents - Mr. Siedel, TUGC0 The training programs involve study in heat transfer, fluid flow, thermal dynamics, natural circulation, mitigation of core damage, small breaks, multiple failures, and the actual accident analysis.
The training emphasis is an recognition of critical parameters that are involved in restoration of subcriticality reactor coolant system inventory, the heat sink and the containment conditions that are needed in order to mitigate a serious accident, or an accident even beyond the DBA.
Training for Maintenance Personnel - Mr. Blevins, TUGC0 Mr. Blevins noted that one of the shortfalls he found in the craft areas is that people are generally very good in perfcraing_ their own particular skill, but they generally aren't able to relate that to its impact or plant operations and how what they do can impact the plant.
In order to alleviate this, TUGC0 has developed a three-week systems training course.
By sending the maintenance personnel through the training, it should integrate their skills in plant systems.
They should have a better understanding of what their work objectives are, and it should give them more of a sense of accomplishment in what they do.
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.j COMANCHE PEAT UNITS 1 & 2 6-1 f
Control Room Design and Human Facters Engineering - Mr. Estes, TUGC0 Mr. Estes described the computer displays for the Emergency Response d
Facilities (ERF). Mr. Estes noted that Texas Utilities worked with 12 utilities to develop the software for the ERF computer displays.
The software will be plant specific and is expected to be delivered in carly 1982.
The display will be a color CRT. There will be a total of seven color graphic CRT's in the RRF computer system.
Two will be in the control room, three in the technical support center, and two in the Emergency Response Facility.
The CRT's will display in bar graph, in digital, and in target form.
On demand, the CRT will display critical safety function tries to aid the operator in making his decisions.
Reliability of Station Electric Power and Loss of All AC Power - Mr.
Calder, TUGC0 Mr. Calder noted that there are three 345-KV ties coming into the switch-yard and one 13F-KV tie into the startup transformer for Unit 1.
The 345-KV ties divert very rapidly. For each safety train, there is one 7000 KW diesel for that train.
With loss of AC power, decay heat can.be removed by the steam turbine driven auxiliary Feedwater pump that feeds all four steam generators.
The flow can be regulated with flow control valves that have air accumu-lators.
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COMANCHE PEAK UNITS 1 & 2 The primary source of feedwater for the auxiliary feedwater system is the condensate storage tank.
This tank has a capacity of 500,000 gallons, with 276,000 gallons reserved for auxiliary feedwater flow.
At fuel flow, there.is four hours capacity with 276,000 gallons.
If the tank is full, there is 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> capacity. At reduced flow the condensate tank has from 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to 65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> capacity.
If additional sources cf auxiliary feedwater are needed, the demineralized water storage tank, with a capacity of 400,000 gallons, may be used.
Ir.
a last ditch effort the diesel fire pump can be hooked up to the lake to keep-the core in a cooled condition.
The steam generators have spring-operated code safety relief valves, so they can remain at hot standby.
The plant can be orderly cooled down using preumatic PORV's.
In response to a question by Mr. Ray regarding " black start" capability, i.e.
the capability to start out without any power being brought in, Mr. Calder -
estimated about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for Camanche Peak.
In summary, Mr. Calder remarked that in the case of loss of offsite power, procedures will be in place, the operator will be trained to mitigate the effects and to restore power with the end result of keeping Comanche Peak safe.
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COMANCHE PEAK UNITS 1 & 2 Hydrogen Control - Mr. Madden, TUGC0 Mr.-Bender inquired what was involved if TUGC0 planned to inert, and if not, why not? Mr. Madden replied that they were not planning to inert.
Mr. Madden reported the results of their analysis to demonstrate contain-ment integrity.
Based upon a 75% metal-water reaction, about 1800 pounds of hydrogen is generated. The Comanche Peak containnent has a free volume of about 3 million cubic feet.
Distribution of the hydrogen that was generated uniformly throughout the containnent results in a concen-tration of about 11 volum? percent.
Based upon a parametric study including a complete 100 percent burn of the 1800 pounds of hydrogen, the worst case was where the resulting p essure was 66 psig.
The rough cut estimate of ultimate containment strength is 83 psig calculated at yield.
Thus TUGC0 feels the highest pressure is well below yiald.
Emergency Planning - Mr. Braswell, TUGC0 Mr. Braswell noted that the emergency plan met the criteria outlined in.
NUREG 0654 and 10 CFR Appendix E.
The emergency plan involves the re-sources and efforts of Comanche Peak.
The state of Texas and Hood and Somervill Counties.
Responsibility for radiological emergency response in the state of Texas is in the Bureau of Radiation Control of the Department of Health. The local governments are responsible for pro-viding security assistance, ambulance service, medical facilities and fire-fighting assistance as needed.
There are four classes of emergencie:, each requiring respective actions.
The four classes are notification of an unusual event, alert, site area
COMANCHE PEAK UNITS 1 & 2 11/11/81 emergency and general emergency. When the shift supervisor in his assessment and evaluation of plant conditons indicates a potential for a real hazard, he then declares the appropriate emergency classi-fication and activates the applicable emergency organization.
Instrumentation to Follow the Course of a Serious Accident, Reg. Guide 1.97,
- Mr. Estes, TUGC0 Mr. Estes mentioned that the utility is working in conjunction with Westinghouse and Gibbs and Hill to develop an overall approach to meeting the requirerents of Reg. Guide 1.97, Rev. 2.
TUGC0 is developing a design basis document which will list the types, categories, ranges and accuracies of the instruments required in Reg. Guide 1.97, Rev. 2.
Decay Heat Removal - Mr. Feist, TUGC0 Mr. Feist noted that there were two functional requirements which must be f
achieved for adequate decay heat removal. The first is to provide a means for transferring oeat through the reactor coolant system to a heat sink.
The second is to maintain a sufficient water inventory in the reactor coolant system to ensure adequate cooling.
Safety grade shutdown decay heat removal is provided by the auxiliary feed-water system, the steam generators and the steam generator safety and PORV's.
Heat from the reactor coolant syste'm is transferred via the steam generators to the atmosphere via the safety and PORV's.
Hot standby can be maintained by the steam generator steam relief via the steam gene-rator safety valves.
In the event of the loss of all feedwater or the loss of the RHR system, the feed and bleed mode can be used to cool the reactor system by use of the centrifigal charging pump.
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-COMANCHE PEAK UNITS 1 & 2 11/11/81 Systems Interaction - Mr. Marshall, TUGC0 Mr. Marshall identified system interaction as the system failure combi-nation that can reduce the effectiveness of any one of a number of basic functions.
Mr. Marshall mentioned fire protection, structural types of components that could fall on Seismic Category I equipment and heavy load analysis as examples where systems interaction studys have been used.
At-6:50 p.m. the meeting was recessed to reconvene in closed session.
Plant Security The plant security force will be contract guards supplied by Bruns Inter-national. TUGC0 can refuse any candidate Credentials are checked.
There will be three check points and three fences to pass to the pro-tected area. Any material going into the plant will be placed in a holding warehouse and inspected before entering the plant.
The meeting adjourned at 7:20 p.m.
NOTE: A complete transcript of the meeting'is on file at the NRC Public Document Room at 1717 H Street, N.W., Washington, D.C. or can be obtained from Alderson Reporters, 300 7th St., SW, Washington, D.C.
202-554-2345.
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Federal Register / Vol. 46. No. 204 / Thursday. October 22, 1981 / Notices 51827 I
will pubhsh within 90 days an airwerthiness a meeting on November 11.1981. Room meeting to public attendanca to protect directive to make compliance with CIB-1144 1046.1717 H Street. NW, Washington, proprietary and Industrial S-curity mandatory. (46 FR 40Ie54. 8-13-81)
DC to continue the review of the information.ne authority for such application of the Texas Utilities closure is Exemption (4) to the Sunshine through 7 am 7s Se t I ending I
completion this year of a study of navigation Generating Company for a license to Act. 5 U.S.C. 552b(c)(4).
safety in Tampa Bay. USCG has made operate the Comanche Peak Units 1 and Dated: October 19.1981 l
temporary changes in navigational aids for
- 2. Notice of this meeting was published
}ohn C. Ho>le' vessels passing under the Sunshine' Skyway September 23.
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Bridge. Prohibition of vessels from meeting in accordance with the procedures near this Bridge is being assessed. USCG is outlined in the Federal Register on lM Dec swa33 W mru ses u) unable to determine the feasibilty of September 30,1981. (46 FR 47903), oral asm cm ww insta! Lng nonstructural bridge protection or written stater'.ents may be presented devices and lacks authority to require such by membus of the public, reco4' s Advisory CommRtee On Reactor systems or to set standards. USCG seeks legislation to act against a pilot's Federal will be Permitted only during those h Safeguards Subcommittee On St.
license for acts committed while serving Portions of the meeting when a
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under authority of his State license; an transcript is being kept, and questions l
amendment under R.S. 4450, allowing USCC may be asked only by Enembers of the The ACRS Subcommittee on St.Lucie to act against a pilot'a Federal license for acta Subcommittee,its consultants, and Staff Plant Unit No. 2 meeting scheduled to be l
committed whi!e serving under authority of persons desiring to make oral held on October 30th has been changed l
. his State license. is under consideration in statements shcrold notify the Designatd to 100 p.m. Instead of 1:30 p.m. and l
USCG a Proposed Legislative P ogram fer the Federal Employee as far in adva ice as October sist at 8 00 a.m. Instead of 8:30 h
to e e eand f
ei Practicable se that appropriate a.m. at the Holiday Inn. Century Village.
rformance, ard location of structural arrangements can be made to s!!aw the 6255 Okeechobee Road. West Palm t
hndge pier protection systems; a study. "Thenecessary time during the meeting for Beach,Fl.
State of the Art Bridge Protectise Systems such statements.
Notice of this meeting was published o' 1 Devices."is available (NTIS Accession The entire meeting wiD be open to in the Federal Register on October 9.
No. AD A 08S7001 USCG expects to finish a public attendance except for those 1981 (46 FR 50178) and all other items
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atudy of Tampa Bay's traffic management sessions which will be closed to protect remain the same except for the chan needs by the end of 1981. (46 FR 28'72. 5 proprietary and Industrial Security of time on October 30th as indic o i
m f/imois CentielCulf R-41-44 and-45 information (SUNSHINE ACT above.
4 (Sept. 29)-Revised hotbox detector EXEMPTION 4). One or more closed Dated: October 19.1981.
instructions, requiring more specific action by sessions may be necessary to discuss John C.Ho3 a, 1
l railroad personnel. hase been distributed to such information.To the extent
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practicable, these closed sessions will I
mechanical / operating crafts and personnel at I" D" "-** * '" *" "I l~
the central readout location. if a car or diesel be held so as to minimize inconvenience unit is stopped a second time for suspected to members of the public in attendance.
bot journal. the car must be set out regard'ess The agenda for subject meeting shall s'
oflack of evidence. A training audio visual ge as ggg;ows:
(Docket No. 50-360) film has been developed in connection with
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botbox detection and followup procedures.
Wednesday. November 11.198L 1:00 p ra.
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(48 FR 462.38. Ik-17-41) until the conclusion of business Nota-Sirgie copies of Board reports are During the initial portion of the meeting.
Ttrminating Facliity Ucense f
f available without charge as long as hmited the Subcommittee, along with any ofits By application dated April 20.1981 l
supplies last. (Multiple copies may be consultants who may be present, will Battelle memorial Institute requested i
pt.rchased from the National Technical exchange preliminary views regarding terminab.on of Facility Ucense CX-28 Information Servict. U S. Department of matte-s to be considered during the balence for the Plutonium Recycle Facility s
Commerce. Spring ield. Va. 22161) Copies of of the meeting.
8 recommendation letters, responses and The Subcommittee will then hear (PRCF) now Richland Washington.The related correspondence are also free of
' presentations by and hold d;scussions with terms and conditions of Facility Ucense charge. Address wntten requesta, identified representatives of the Tues Uthties CX-28 specify that the facility license by recommendation or report number, to:
Cenerating Company, NRC Staff, their will expire automatically upon Public toquiries Section. National consa!! ants, and ober interated persons termination of the licensee *s authority Transportation Safety Board. Washington, regardmg this review.
under Contract AT(45-1)-1831 (use E 20m Further information regarding topics permit) between the Commission (now (49 U.S C. 2903(a)(2).1906) to be discussed, whether the Enecting DOE) and the licensee. In accordance Margaret L mher.
has been cancelled or rescheduled, the with the terms and conditions of Facility rederalRegisterLiaison Officer.
Chairman's ruling on requests for the License CX-28 this license has expired.
October te.1981.
opportunity to present oral statements Since the PRCF is a government-In om m-soon rmo. mat an ami and the time allotted therefor can be owned facility in the custody of Battelle sumo coot seio-ss-a obtained by a prepaid telephone call to under its operating contract with the the cognizant Designated Federal Department of Energy, all responsibility Employee. Mr. John C. McKinley for health, safety and radiation a
NUCL. EAR REGULATORY (telephone 202/634-1414) or the Staff protection is now under the control of u
COMMISSION Engineer.Mr. Herman Alderman the Department of Energy.
(telephone 202/634-1413) between 8:15 Derefore, pursuant to the application 1
((Adv!sory Com'mittee On Reactor..
a.m. and 5 00 p.m ED r.
by Battelle MemorialInstitute. Facility
'q Safeguards; Subcommittee On I have determined,in accordance with License No. CX-26. ls hereby terminated gComanche Peak Unfts 1 and 2; Meeting Subsection 10(d)of the Federal as of the date of this Order. ~
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%e ACRS Subcommittee on Advisory Committee Act. that it may be For further details with respect to this Comanche Peak Units 1 and 2 will hold necessary to close portions of this action see fil anolication fu I
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.t. '~ l TENTATIVE AGENDA FOR ACRS COMMANCHE PEAK SUBCOMMITTEE MEETING NOVEMBER 11, 1981 l 1717 H. St., W. Washington, D.C. I ~ 1 Approximate Time l 1:00 Introduction by Subcommittee Chairman i 1:05 p.m. NRC Staff Presentation - S. Burwell l A. Overview of OL Review B. SSER Open Items 1:30 p.m. Texas Utilities Generating Company Presentation i Brer schmidt A. Overview of plant and site, corstruction l schedule, including estimated date of fuel l loading, commercial operation l l John Marshall B. Response to SSER open items 2:00 p.m. Bill Clements C.. Organizaticraland management structure including j Jim Kuykendall QA&QC speciality skills and advisory services Dick Jones Staff buildup (percentage complete) 7bny Veca 2:30 p.m. mn seidel D. Operator Training C.L. Turner Mike Blevins 1. Use of simulators in training programs 2. Training for serious accidents including" accidents beyond DBA's 3. Training of maintenance personnel 3:30 p.m. kn Estes E. Control Room Design & Human Factors Engineering l 4:00 p.m. BREAK 4:15 p.m. Richard Calder F. Reliability of station electric power and DC power system St.rvival time for loss of all AC power 9 ATTACHNENT C
v. i' 4 COMMANCHE PEAK AGENDA 4:45 p.m. Fred Madden G. Hydrogen control and/or inerting 5:00 p.m. Dwight Braswell H. Emergency planning 5:15 p.m. Ron Estes I. Instrumentation to follow the Course of a serious accident 5:30 p.m. Chuck Feist J. Decay heat removal 5:45 p.m. John Marshall K. Systems interaction review 6:00 p.m. John R e ey L. Plant security 6:30 p.m. ACRS Subcomittee Discussion 1 6:45 p.m. ADJOURN 4 e e e m I l ,}}