ML20040F224
| ML20040F224 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/09/1982 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| TASK-1.C.1, TASK-1.C.8, TASK-1.D.1, TASK-2.B.2, TASK-3.A.1.2, TASK-TM ACRS-1920, NUDOCS 8202080528 | |
| Download: ML20040F224 (25) | |
Text
y.
hDE-/-/
NY5 - /MC CERTIFIED COPY:
i N
6:
DATE ISSUED: 01/0 9/82 g
9g tilNUTES OF THE ACRS SUBC0tE4ITTEE IEETING ON THE CALLAWAY PLA'iT, UNIT NO. 1 COLUTOI A,14IS50VRI NOVEIGER 4-5, 1 981 The ACRS Subcommittee on the Callaway Plant. Unit Ho. I met at the lloliday Inn-West in Columbia, 141ssouri, on Hovember 4-5, 1981, to review the applica-tion of Union Electric Company for a license to operate the Callaway Plant.
Unit No. 1.
Prior to the meeting the Subcommittee and its consultants toured the Callaway Plant on the morning of November 4,1981. Notice of this meeting was published in the Federal Register on October 19,1981, and on October 23, 1981.
The Federal Register Notice is Attachment A.
A copy of the detailed schedule of presentations is shown in Attachment B.
The attendee list is Attachment C.
There were no written or oral state-ments from members of the public. A complete set of presentation slides is on file in the ACRS offices. Mr. Richard Major was the Designated Federal Employee for this meeting. The entire meeting was open to the public.
l 4
WEDNESDAY, NOVEIEER 4,1981 PLANT TOUR Hembers of the Subcominittee (M. Carbon, C. Mark, J. Ray) and consultants (J. Arnold, W. Lipinski, Z. Zudans) toured the Callaway Plant with repre-sentatives from Union Electric Company and their contractors on the morning of November 4,1981. The tour lasted approximately four hours and covered i.he majority of structures at the Callaway Plant.
K25 m C
(, k
- p. p{.M C,g?
o a s.<
h
'Y' 8202080528 820109 O
!11NUTES CALLAWAY PLANT, UNIT NO. 1.
SUBC0fif1ITTEE 14EETING Chairman's Introduction-Dr. Carbon opened the meeting at 2:00 p.m.
He noted that this meeting was an open meeting of the Advisory Committee on Reactor Safeguards Subcommittee on Callaway Plant, Unit No.1.
He stated the purpose of the meeting was to review the application of Union Electric Company for an operating license for Callaway Plant, Unit No. 1.
Introduction by NRC Staff Dr. Gordon Edison, NRC Staff Licensing Project fianager, presented an overview of the HRC Staff Review of the Union Electric Company's application for an operating license for Callaway Plant, Unit tio.1. He noted the basis for the review was the SNUPPS (Standardized Nuclear Unit Power Plant System) FSAR through Revision 7 and the Callaway Plant, Unit No. 1 Site Addendum through Revision 4.
The principal review matters included: site characteristics; design, fabrication, construction, test criteria and expected performance l
characteristics; response of the facility to anticipated operating transients and postulated accidents; applicant's engineering / construction organization, plans for the conduct of operations, plans for industrial security, plans for emergency preparedness; design of systems to control radiological effluents from the facility; applicant's ~qsality assurance _ program; and financial qualifications. The results of the review are published in NUREG-0830. the Callaway Plant, Unit No.1 Safety' Eva'luation! Report.
Issues with iesolution - ~
still pending will be reported in supplements to the SER. There ar'e,no.
7 dissenting NRC staff techn'ical opinions _ on this case.
'mm w4--
y T
S a
i
MINUTES CALLAWAY PLANT, UNIT NO. 1 Introduction by Applicant - Union Electric Company, D. F. Schnell D. Schnell, Vice President-Nuclear, made an introductory presentation and briefly described the site, plant, and gave the remainder of the construction schedule. He noted the Callaway site was selected from six sites considered.
Callaway is 80 miles west of the metropolitan St. Louis, Missouri area. It is 10 miles east-southeast of Fulton, Missouri (pop. 12,000);25 miles east-northeast of Jefferson City, Missouri (estimated 1980 pop. 34,000); and 30 miles east-southeast of Columbia, Missouri (pop. 59,000). The site is located on an 8-square mile plateau, 325 feet above the Missouri River flood plain and about 5 miles north of the river. The plant site is 3.188 acres.
Concerning development around the site, there are no airports, industry, or military facilities.
The Callaway Plant employs the SNUPPS concept. The power block is duplicated for a number of plantr..
(Since Callaway 2 was cancelled in October 1981 due to financial consideration, only the Wolf Creek Generating Station remains from the original SNUPPS group of plants.) The SNUPPS design envelope was developed by use of the most restrictive site conditions imposed by any one of the four original sites. The standard portions (Reactor Building, Turbine Building, Fuel Building, etc.) were designed to one composite set of criteria.
The plants use identical equipment and systems. The structure is built to with-stand a.2g safe shutdown earthquake, and a.12g operating basis earthquake.
The NSSS for Callaway is a Westinghouse RESAR-3.
(This is very similar to Comanche Peak and McGuire.) The reactor core is designed for an output of 5 Y o
4.-
HINUTES CALLAWAY PLANT, UNIT NO. 1 3.411 IWt. When the reactor coolant pump input of 14 IWt is added to the core output, the warranted nuclear steam supply system output is 3,425 MWt, which is defined as the rated power in the license application. The power block AE is Bechtel Power Corporation; the AE for the site is Sverdrup &
Parcel, St. Louis.
The turbine generator is supplied by GE. The generator rating is 1,120 11We net output.
Normal cooling is from a closed cycle, natural draft tower, with makeup water being furnished by the Missouri River, five miles away, through buried pipe-line. Backup cooling is from an excavated retention pond and mechanical draft cooling tower which are both seismic Category I structures. Three 345-KV transmission circuits serve the plant on two separate right-of-ways.
l The expected date for fuel load is June 1983.
This will be 86 months after
(
j issuance of the CP.
Organization and Itanagement - Union Electric The Organization and lianagement structures of Union Electric Company (UE) were reviewed.
Callaway will be the first nuclear power plant in the State of Missouri.
It is Union Electric's first nuclear unit. The management organization of the Callaway Plant is composed mainly of long-time UE personnel. Many have been with the Callaway project since its inception.
l
MINUTES CALLAWAY PLANT, UNIT NO. 1.
Both onsite and offsite organization were described. There was a lack of commercial nuclear experience held by UE rranagement. However, management did possess formal training in nuclear fundamentals through universities and from Westinghouse. Management has participated in nuclear industry organizations such as EPRI, EEI, and INP0.
There was also some transfer of experience by participation in the SNUPPS organization which through 807, of the design ptase included utilities with operating nuclear plants.
Members of management have spent time at other operating facilities as observers, and more participation at operating facilities is planned for operations management and operators.
The start-up organization has had extensive experience. The NRC Staff will condition the license so that at least one operator per shift for the first year will have had commercial nuclear experience.
In addition, the radiation protection manager will spend time at operating facilities as an additional staff requirement, along with instrumentation and controls personnel.
Special Safety-Oriented Groups Callaway will have three special safety review groups. An Onsite Review l
Committee will be chaired by the plant superintendent. Members include the QA supervisor.
The Nuclear Safety Review Board will be chaired by the general manager of engineering. 1lembers include the QA manager and plant superintendent. The Independent Safety Engineering Group / Shift Technical i
l Advisors (ISEG/STA) group is based onsite.
It reports offsite to the manager-nuclear engineering.
l a-
MINUTES CALLAWAY PLANT, U; LIT NO. 1 SNUPPS Association Mr. N. Petrick, the executive director of SNUPPS, explained the SNUPPS organization and the relationship between the utility and SNUPPS, SNUPPS was originally made up of five utilities. Now only three utilities remain although all five original members participated through 80% of the plant design. The two utilities which now participate to only a minor extent in SNUPPS (Northern States Power and Rochester Gas and Electric) are long-time nuclear utilities.
The SNUPPS organization (Nuclear Projects, Inc.) serves as an interface between the utilities and prime contractors (NSSS-Westinghouse. A/E-Bechtel, and Turbine Generator-General Electric). The SNUPPS representatives felt there is a safety advantage in the SNUPPS concept from cost-sharing. A pool of additional nuclear expertise is maintained through the SNUPPS organization and experience is exchanged among the units.
Offsite Oraanization - iir. Schukai lir. Schukai, the general manager of engineering, noted that there were four offsite groups which report to him.
The four departments include nuclear engineering, nuclear development, nuclear fuel, and nuclear services. This entire grouo is composed of 65 individuals of whom 45 are professional technical engineering personnel.
During plant operation it is expected that the SNUPPS organization would be retained to perform any design changes necessary and the home office technical staff would play a lead role in
MINUTES CALLAWAY PLANT, UNIT NO.1 :
reviewing those changes which could be site-specific for Callaway and common to both Wolf Creek and Callaway.
Uses of the STA and Feedback of Operating Experience to Operators There will be Shift Technical Advisors (STAS) in the Independent Safety Engineering Group (ISEG).
All seven will be scheduled for rotating shift duty.
If required, the group will be expanded to ten. The duties of an STA are to independently observe plant status and advise shift supervision of conditions that could compromise plant safety.
They will review and evaluate operating and maintenance experience to improve plant safety. STAS will be responsible for the dissemination of information to the appropriate utility staff.
They will review and evaluate safety-related matters assigned by corporate management or required by regulatory requirements. STAS will also report offsite to management on the overall quality of plant operations.
ISEG/STA qualifications include an engineering or related science degree.
They will have two years of nuclear-related experience and will have been onsite for six months. STAS will complete supplemental college level courses in accordance with INP0 guidelines.
Five STAS are currently in training.
This presentation also contained a discussion of the Safety Parameter Display System. The nature of the Safety Parameter Display System has not been finalized. There is still not a firm understanding of what will be required, especially concerning seismic design and necessary backup to a CRT. computer-driven system.
E
HINUTES CALLAWAY PLANT, UNIT NO. 1
- Startup Organizations The Callaway test program consists of the construction completion and initial test program. The construction completion test program is designed to verify proper installation and functional opera'ility. The initial test program a
consists of a pre-operational test phase followed by an initial startup phase. The pre-operational test phase verifies that plant systems are consistent with their design and respond properly. The startup test program provides an orderly and safe power ascension test series from initial core loading to power operation.
It also verifies that design parameters are met and includes sufficient transient testing to verify efficient operation.
The startup organization consists of personnel from Union Electric and outside contractors. The experience levels throughout the startup organiza-l tion are consistently high, with most of the contractor personnel having 1
directly participated in at least two previous nuclear plant startups. The startup organization includes 44 startup engineers and supervisors with an average nuclear experience level of 7 years, and a total power plant experience level of 11 years.
Operations Staffing The operating organization for Callaway is currently 80% staffed. There will be a rotating 6-shift approach to operating staffing with one shift in training full-time, one week out of six. The 12 shift supervisors (SR0s)
/
are taking tours at other operating nuclear plants and observing commercial nuclear station operation from 6 weeks to 1 year with the average being 2 months.
NINUTES CALLR't,Y PLANT, UNIT NO.1.
The basic approach in staffing was to avoid active recruitment from other utilities.
The goal was to develop Union Electric personnel through the selection of key experienced personnel from fossil stations with special training or interest in the nuclear area. These personnel, when supple-mented c/ specialists through the time of commercial operation, are expected to yield a mature, dedicated organization.
All key plant members who do not have commercial plant experience will, in the course of their training program, experience at least one refueling at a commercial station and observe one to two months of normal operation.
Training Program The selection criteria for operators, as well as training of operators for normal and off-normal situations, were covered. Selection criteria for operating personnel and technicians include a review of experience, testing in basic science and math, a psychological test series, physical examination, and an interview. The experience levels in the training department were presented.
Currently 20 out of 22 positions in the training department are filled.
The operations training program includes a refresher course in mathematics and science.
Phase I of the program teaches theory in nuclear fundamentals, thermodynamics, fluid and heat transfer; health physics and chemistry; and instrumentation. A research reactor is used as a teaching aid in startup operations, HP controls, and for lab demonstrations. Phase II of the program includes plant systems training and observation training at the Zion plant. Another training phase includes simulator training. The
i MINUTES CALLAWAY PLANT, UNIT NO. 1 -
simulator is used for normal operations, transient / casualties and cold license certification exams.
The final phase is onsite training, including familiari-zation with plant systems, procedures, checkouts, and review.
A Callaway-specific simulator will be installed in the Callaway training center which is adjacent to the plant by February 1982. Most of the training for the plant staff will be conducted onsite.
Emeroency Planning In the area of emergency planning, a plan has been submitted by the Applicant, updated to 10 CFR 50 Appendix E, and NUREG-0654 requirements. This plan is for the Callaway onsite and corporate activities only. Offsite, state and local entities within the plume emergency planning zone have not yet been included.
State and local plans must be submitted to NRC prior to fuel load. These plans will also be submitted to FEMA and a finding will be made relevant to the state of offsite emergency preparedness. No operating license will be issued until NRC finds the onsite and offsite emergency preparedness acceptable.
Prior to fuel load, the Applicant must complete successfully, a full-scale exercise with state and local officials. This joint exercise, observed by fella and NRC, must be an integrated emergency exercise which will include a test of the capability of the basic elements existing within all emergency preparedness plans and organizations. The full-scale exercise is currently scheduled for December 1982.
In the pre-sentation on emergency planning, UE covered the four standard emergency classes (unusual event, alert, site emergency, and general emergency) thct
MINUTES CALLAWAY PLANT, UNIT NO. 1,.,
have been established as well as notification methods and procedures. Also covered were emergency training and drills and exercises for an emergency.
A description of and manning for emergency support facilities were covered.
It was noted that, in general, coordination with state and local organiza-tions has been good.
AC/DC Power System Reliability Callaway Plant AC/DC power reliability was discussed.
Covered in the discussion was the Union Electric tranrmission system and stability, the Callaway AC distribution and AC/DC systems, and loss of AC power to Callaway.
The load flow and transient stability of the Callaway Plant were described.
The grid will provide uninterrupted power to the Callaway 345-KV switchyard for a number of 3-phase fault conditions on the transmission lines between the plant and grid as well as a full load trip of Callaway. To have a total loss of AC power at Callaway, all three 345-KV transmission lines would have to be lost and both emergency diesel generators would have to fail to start.
It was noted that, since the 345-KV transmission system has been installed, i
l there has never been a total loss of power.
If all AC were lost at the plant, still remaining would be four safety battery systems, four 120-VAC vital buses, and eight nonsafety battery systems.
On loss of AC poder, the operator would lose the ability to add make-up water to the RCS mass inventory.
Operators would isolate the system and check that PORVs are closed. With cooldown and normal seal leak, there would be 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before the water level reached the top of the core.
Vital battery systems will operate-i 7-14 hours depending on the battery system and given the operator sheds some
MINUTES CALLAWAY PLANT, UNIT NO. 1 of the loa.i. The vital batteries will operate for 200 minutes at full capacity. A management commitment has been made to provide power back to the Callaway Plant on a priority basis following a system blackout.
Instrumentation to Follow the Course of a Serious Accident The reactor vessel level instrumentation system was. described.
It uses two sets of two delta P cells. Each set covers a range from the hottom of the reactor pressure vessel to the top.
In each set, one cell perfonns in a narrow pressure range (natural circulation). The other wide range cell detects level with any combination of operating reactor ecolant pumps.
Temperature measurements are made of impulse lines to correct for induced errors.
In addition, existing reactor coolant temperature RTDs and wide-range pressure measurements are also used to correct the water level measurements for water density changes. The systera meets NRC requirements.
Callaway will have a thermocouple monitoring system which meets NRC require-ments. The thermocouple core cooling system in conjunction with the reactor vessel level measurement system provides the operator an indication of inadequate core cooling. The primary thermocouple system measures all 50 core exit thermocouples. The primary system is electrically independent and has l
a Class IE power source up to an isolator; hardware and display beyond the isolator is non-Class IE. A backup system has two channels. Each channel monitors 25 core outlet thermocouples. The entire backup system is Class IE.
1 i
MINUTES CALLAWAY PLANT, UNIT NO. 1 -
A core cooling monitor (saturation margin) will be installed at Callaway, which meets NRC requirements.
It will be a Class IE system with redundant channel s. Saturation margin is determined from the lowest of three pressure signals and core outlet thermocouples and hot and cold leg RTDs.
Open Items Open items contained in the Callsway SER were discussed.
There are 11 non-T!!I outstanding issues and 5 T!!I-related issues. Ilany of these issues remain open due to ongoing analyses by the Applicant that have yet to be submitted to the Staff for review, or items remain open pending the comple-tion of Staff review or an onsite audit.
On the whole, there are no items of serious contention between Union Electric and the Staff, and resolution of the open items appears to be progressing orderly.
1.
Ice Load Analysis for ESW - This issue involves the Applicant doing further work in analyzing possible ice loads on the emergency service water pump house, which could result from freezing of the retention pond and emergency service water system which is not heated in any way.
In addition, the Staff has indicated that they feel the highest loading would be due to a combination of the once-in-25-years ice load simultaneously occurring with the safe shutdown earthquake. Options for the Applicant include reanalyzing the structure to show there is no concern. Warming the water is another option. An argument could be made that this is a low probability event, and a fourth option is to write a technical specification requiring that tne ice on the retention pond be broken up when it gets too thick.
L
MINUTES CALLAWAY PLANT, UNIT NO. 1,
2.
High-Energy Pipe Break Hazards Analysis - This analysis is 80% completed.
Portions of this analysis dealing with jet impingement' effects of a pipe break through a room by room analysis have yet to be completed.
It is expected that the analysis will be complete by February 1,1982.
3.
Vibration Damping Analysis for Cable Tray and Conduit Support Systems -
In this case the Staff has not approved the use of any damping factor in the structural analyses for support systems above 7%. The Applicant has used a damping factor greater than 7%. Since the Staff had never approved a damping factor greater than 7% and were still reviewing the Union Electric submittal, this item remains open. This item is very close to being closed out.
4.
Pump and Valve Operability Assurance Program - This item remains open until tne Staff has conducted an onsite audit and onsite inspection of test records. This item will remain open until mid-1982.
5.
Pipe Support Baseplate Flexibility Effect on Anchor Bolt Loads -
The concern here is that flexing of the baseplates from the pipe supports can put. additional loads on the anchor bolts. Nr.C has required a mechanical engineering analysis be made of these loads. This item could be closed out by mid-1982.
6.
Seismic and Dynamic Qualification of Hechanical and Electrical Equipment -
This item remains open until the Staff has conducted an onsite audit and onsite inspection of test records. This item will re.nain open until mid-1982.
s_e--.
HINUTES CALLAWAY PLANT, UNIT N0.1 -
- 7.. Environmental Qualification of Safety-Related Electrical Equipment -
This item remains open until the Staff has conducted an onsite audit and onsite inspection of test records. This item will remain open until mid-1982.
8.
Fuel Assembly Structural :,esponse to Seismic and Local Forces - The concern here is that either a seismic event or a LOCA would put lateral loads on the fuel assembly and distort grip spacer straps in such a way as to cause cooling degradation.
Union Electric has made an analysis of this event; the analysis is currently under Staff review.
It appears near to resolution.
9.
Steam Generator Level Measurement Errors Due to Environmental Temperature Effects on Instrument Reference Legs - The concern with this item is l
that steam generator level, measured by a delta pressure cell in a l
reference leg, could give erroneous information when subjected to the environment caused by a LOCA or steam line break. The Applicant appears near to resolving this issue.
10.
Fire Protection Program-Alternate Shutdown Panel - Fire Protection j
remains a confirmatory type item until the Staff has made its site visit and inspection. The Applicant has submitted an analysis as to how they compare with Appendix R requirements.
Currently the Applicant is deciding how to protect the alternate shutdown panel from an event like a control room fire. Until the type of protection is decided and reviewed this item will remain open.
i l
t I
MINUTES CALLAWAY PLANT, UNfT N0. 1,
- 11. System and Components On the "Q" List - This item remains open, because the list of components to be included on the Q-list had not been completed at the time the SER was published.
This item is near to resolution.
- 12. There are five THI Action Plan items that are open. These include I.C.1, Guidance for Evaluation and Development of Procedures For Transients and Accidents.and I.C % Pilot lionitoring of Selected Emergency Procedures For Hear Term OL Applicants. These items will remain open until these pro-cedures are written later in the plant's development.
Item I.D.1, Control Room Design Review, remains an open item until the control room is complete enough for Staff reviewers to complete their inspection.
Item II.B.2, Plant Shielding For Access to Vital Areas And To Protect Safety Equipment For Post Accident Operation, will remain open until the Applicant submits shielding designs later in the plant's construction l
r process.
Item III. A.l.2, Upgrade Emergency Support Facilities, remains open because the Staff has not completed their review of the Applicant's submittal.
l l
t
CALLAWAV PLANT (10. 1 3'
^
f40VEf!3ER 5,1981 Safety Evaluation Report - Confirmatory Items There are 39 confirmatory issues listed in the SER (27 non-TMI and 12 TMI issues).
Confirmatory issues are items which have essentially been resolved to the Staff's satisfaction, but for which certain confirmatory information has not yet been provided by the applicant.
In these in-stances, the applicant has committed to provide the confirmatory infor-mation.
Confirmatory Items have one or more of the followi~g characteristics:
the Staff agrees with the applicant's design, there is a need to com-plete documentation on an issue, the Staff may want to verify implementation of a design feature at the site, analyses are nearly complete and final touches will not change results, and the Staff may wish to inspect certain test results.
l Safety Evaluation Report - License Conditions The SER lists 20 license conditions. These license conditions may be i
desirabic to ensure that Staff requirements are met during plant oper-ation. The license condition may be in the form of a condition in the body cf the operating license, or a limiting condition for operation in the Technical Specifications appended to the license. However, the Staff expects a number of the proposed license conditions to be implemented prior to plant licensing and therefore will not become license conditions.
l l
l l
CALLAWAY PLANT !!O. 1
- io -
4 Preparation of Emergency Operating Procedures Emergency procedures are being written for Callaway using Westinghouse Owners Group guidelines. There are two sets of procedures. Optimal recovery guidelines are event oriented procedures such as for reactor trip or safety injection or loss of reactor coolant. These are coupled with emergency contingency actions such as for ATWS or' loss of all AC power. Also under development is a function restoration guidelines set which are symptom-based procedures which include response to RCS over-pressurization, response to inadequate core cooling, and response to saturated core cooling conditions.
Functional restoration guidelines are used in conjunction with a series of six flow diagrams that can be called up on the SPDS. A particular flow diagram is selected based on plant indications, which should then lead the operator to the appropriate emergency procedures and optimal recovery path. When these instructions have been written, it is Union Electric's intent to test them on their simulator.
Control Room Design Bechtel designed the SNUPPS Control room. The design was evaluated by licensed operators for man / machine interface; video displays, actual control layout; functional groups of controls, etc, The design was basically finalized in 1978. Currently, there is still some uncertainty as to where to locate the SPDS. Because of a large number of systems and items not available for Staff evaluation / inspection during the initial review, the Staff will further review the design after construction and installation are near to completion.
_ _ _ _ ~
1 CALLAWAY UNIT NO. 1,.
As a result of this review changes to the control room design were made, including a change to allos easier operator access to rear control boards.
Systems Interaction Review Union Electric presented their systems interaction review.
In addition to the initial design consideration, four additional activities address the concern of systems interaction. The four activities include a hazards analysis (fires, missiles, earthquake-induced failures, etc.), control systems failures, environmental impacts on control systems, and heavy loads analysis. Union Electric representatives noted thit the hazards analysis reviews were performed by an interdisciplinary task force. It was also noted that systems interaction reviews are not static, but rather J
ongoing, taking into account any changes to the plant.
Hydrogen Control Hydrogen control at the Callaway Plant was covered. Callaway will have redundant recombiners, a redundant hydrogen mixing systems, a redundant hydrogen monitoring subsystems, and a backup hydrogen purge system.
Callaway uses a large dry containment with a volume of 2.5 x 106 ft.3,
For a hypothetical case of 75% metal-water reaction, results indicate 12.5% hydrogen by volume in containment. A constant volume and adiabatic deflagration of hydrogen yields a pressure increase of 60 psi (75 psia),
the design pressure of the containment. This calculation assumes a dry l
containment with no steam.
l l
Decay Heat Removal System The applicant discussed the capabilities of the decay heat removal systems.
It was noted that the design basis of the plant was extended from the
t CALLAWAY PLANT NO.1,'
ability to reach hot shutdown using safety grade equipment to the ability to reach cold shutdown. This can be accomplished assuming loss of offsite power. Also covered was the use of feed-and-bleed cooling. Once steam geherators approach drycut, water can be fed to the primary system through the charging pumps and heat removed through the PORVs.
It was explained that the two PORVs at Callaway are Class IE qualified and can operate off the DC power supply.
Conclusion The Subcommittee Chairman polled the Subcommittee on whether or not they felt the Callaway case was ready for full Committee review.
It was decided to recommend this case to the full Committee. A listing of topics to be covered during the full Committee review was given to the applicant.
The meeting was adjourned at 12:40 p. m.
A complete transcript of the meeting is on file at the NRC Public Document Room at 1717 H St., NW., Washington, D.C. or can be obtained from the Alderson Reporters, 300 7th St. SW, Washington, D.C. (202) 554-2345.
'I
l 3
~
Federal Register / Vol. 46, No. 301 / Monday, October
- 19,1981 / Notices 81329
~
MUCLEAR* REGULATORY q
tredheedry.Neseeder & assi-Jap.m 4 milldeconcAnsionof6me/ mess COMMISSION 7E:., day,leveeder& aper-eapa.m Advisory Committee on Reactor smitilde oor.cluelon ofDuelasse Bafeguards, Subcommittee on
. Durtng the inttialportion of the imeeting.
Ca!!away Plant; Meeting to Subcommittee, aleeg with any ofits ne ACRS Subcommittee on
- * * ', ',"'I'F'",',",
Callaway Plant wul hold a meeting on mattere a be answered darks &e 6taar==
November 4 and 5,1981, at the Hilton dee moeums.
Inn 2200 I-70 Drive Southwest-De submaunftwo we een hear Columbia, MO.De Subcommittee wSI presentations by and hold discuselone with review the application by the Union sopruentativee of the Union Electric Electric Company for an Opereting Company, NRC StaE. their consultants, and License. Notice of this meeting was saber interested perooms regarding this published September 23.
soview.
In accordanceewith the procedures outlined in the Federal Register on FmMber Wormation abouMopics to be September 30,1981, (46 FR 47903), oral discussed, whether the meeting has or written statements may be presented been cancelled or reacheduled, the by members of the pubtle, recordags birman's ruling on ranunts for the will be permitted only during those ePPodunity to preunt oral statements
' portions of the meeting when a and the time eBotted therefor ran be transcript is being kept, and questions obtained by a prepaid telephone caU to may be asked only my members of the the cognizant Designated Federal Subconi'nfttee. its consultants, and Stag Employee. Richard Major (telephone
- Persons dotting to make oral 302/634-1414) between 8:15 a.m. and statements should notify the Designated 52 p.m EST.
Federal Employee as far in advance as Deted: October 14,seet.
practicable so that appropriate gehe C.Heyle, arrangements can be made to allow the WComun/sheMwogw.
mecessary time during the meeting for,
,, u m,,, m,,,
such statements.
_'- y~
public attendance. g wGI be open to De entire meetin De agenda for subject meeting shall be as fouows:
i, u FncMieurrt
O 10/21/81 TENTATIVE SCHEDULE
- FOR THE ACRS SUBCOMMITTEE MEETING ON CALLAWAY UNIT 1 l
AND PLANT TOUR l
NOVEMBER 4 & 5, 1981 CALLAWAY COUNTY AND COLUMBIA, M0 NOVEMBER 4, 1981 7:30 a.m.
Tour of Plant Leave Holiday Inn West, Columbia, MO in van with representatives of Union Electric Co. and tour plant and site (site approximately 30 miles away).
Return to Holiday Inn West and have lunch prior to start of meeting.
12:30 p.m.
Lunch 1:30 p.m.
Introduction by Subcommittee Chaiman 1:35 p.m.
Introduction by NRC Staff A.
Overview of OL Review B.
Any Dissenting NRC Staff Technical Opinions 1:50 p.m.
Introduction by Applicant - Union Electric Co.
A.
Discussion of the SNUPPS Concept (20 mins.)
B.
Overview of Plant and Site (10 mins.)
C.
Construction Schedule,. Including Estimated Date of Fuel Loading, Commercial Operation (5 mins.)
D.
Start-up Testina: Schedule and Description of Tests (20 mins.)
2:45 p.m.
Emergency Planning A.
Role and Coordination with FEMA State, and Local Agencies (test exercises)
(30 mins.)
B.
Emergency Support Facilities (20 mins.)
C.
Population Growth and Affect on Evacuation Times (10 mins.)
l 3:45 p.m.
BREAK 3:55 p.m.
AC and DC Power Reliability, Including Station Blackout and Scope of Stability Studies (20 mins.)
- NOTE:
Items may be added or deleted from this schedule at the discretion of the Subcommittee Chaiman. Prepared presentations should be Ifmited to half the alotted time in order to allow time for questioning.
Arresmem-8
~
4 l
10/21/81.
4.15 p.m.
Instrumentation to Follow the Course of a Serious Accident, Including Inadequate Core Cooling - Union Electric (20 mins.)
4:35 p.m.
Organization and Management - Union Electric (55 mins.)
A.
Utility Technical Capability and Organization Compliance with NUREG-0731, " Management Structure and Technical Resources" B.
Experience Levels of Management - Corporate and Operational C.
Feedback to Operators, STA, others of Internal and External (other plants) Operating Experience D.
Uses of STA E.
Staff Buildup (percentage complete) 5:30 p.m.
Operator Training - Union Electric (1 hr.)
A.
Selection and Training of Operators for Normal and Off-Normal Situations B.
Selection and Training of Maintenance Personnel C.
Use of Simulators in Training Program D.
Training for Serious Accidents (beyond DBA)
E.
Current Status of Operator Staffing 6:30 p.m.
Instructions to Applicant Recess until 8:30 a.m. on Thursday, November 5,1981 e
O e
3-., -, _ ___,,
7,
__,._c
.y,..,.,
W
e
( NOVEMBER 5, 1981 8:30 a.m.
Introduction by Subcommittee Chaiman 8:35 a.m.
Open Items from SER (Staff / Applicant) (1.5 hrs.)
5 A.
Presentation by NRC Staff of Each Open Item Followed by a Response by Applicant. (Each na Item Taken Individually)
)
10:00 a.m.
BREAK 10:10 a.m.
Summary by NRC Staff of Confimatory Issues (Applicant Response)
(20 mins.)
"8' t
10:40 a.m.
Summary by NRC Staff of Licensing Conditions (Applicant Response)
(20 Mins.)
g 11:00 a.m.
Preparation of Emergency Operating Procedures (30 mins.)
(including Emergency Procedures beyond the DBA)
,,ra.c 11:30 a.m.
Utility Interpretation of GDC 19 (Shutdown from Outside
-te i of Control Room) Description of Remote Shutdown Panel
2 (including the ability to withstand a single, random I,
failure in the instruments and controls of the systems controlled from the remote panel or in the systems themselves) (30 mins.)
12:00 noon LUNCH (Subcommittee check out of hotel) 1:00 p.m.
Control Roon (30 mins.)
A.
Design Including Human Factors B.
Habitability for Accidents Beyond the DBA 1:30 p.m.
Internal Flooding Studies (15 mins.)
1:45 p.m.
Staff Position on Hydrogen Control for Large Dry Containments ( Ability to deal with large amounts of Hydrogen) (Staff / Applicant) (15 mins.)
2:00 p.m.
Capability and Reliability of Decay Heat Removal Systems (Analysis of feed a bleed cooling) (consideration of USI A-45)
(15 mins.)
2:15 p.m.
Systems Interaction Review (15 mins.)
2:30 p.m.
Instructions to Applicant (15 mins.)
2:45 p.m.
ADJOURNMENT Leave from Columbia to St. Louis-Lambert Airport ( 80 miles).
ACRS SUBCOINITTEE MEETING ON ATTENDEES.
CALLAWAY PLANT, UNIT NO. 1 DN NOVEL @ER 4 & 5, 1981 ACRS NRC STAFF M. Carbon, Chaiman J. Younablood C. Mark, Member G. Edison
?'
J. Ray, Member J. Arnold, Consultant W. Lipinski, Consultant UNION ELECTP.IC CO.
- 2. Zudans, Consultant R. Major, Desionated Federal Employer-A. Passwater D. Schnell D. Capone ESTINGHOUSE ELECTRIC CORP.
KG8.E D. Shafer G. Penderaraff J. Irons G. Koester M. Taylor C. Tuley G. Rathbun A. Neuhalfen J. Swogoer F. Rhodes G. Huches J. Greshain J. Bailey F. Field
,D. Paddleford T. Keenan R. Leuther G. Lun9
!). Green F. Semoter W. Luce R. Wilks T. N Farland T. Timnons KCPL J. Kaelin G. Butterworth 1
J. Watson D. Rawlins J. Miller
- "U R. Cothren D. Crawford R. McLaughlin E. Dille SNUPPS STAFF (NUCLEAR PROJECTS INC.)
- 5. Miltenberger R. Dettenmeier F. Schwnerer P. Appleby J. Cermak RECHTEL P09ER CORD.
W. Reilly N. Petrick K. Lee MISSOURI DISASTER l
R. Stright D. Grove PLANNINra 5 DPERATIONS OFFICE l
F. Roddy P. Ward W. Johnson J. Pre 5ula E. Durham D. Gasda J. Houston t
l J. Smith OTHERS R. Fluegge - Missouri Public Service Comission A. Canner - Missouri Public Service Comission J. Provasnli - Arizona Public Service D. Bu11mann - Danes & Moore G. Lahelle - K0MV-TV News M. Nahrstedt - Colum5f a Missourian T. Plunkett - Illinois Power Company -
M. Reilly - (Self)
K. Drey - (Self)
(