ML20154H860
| ML20154H860 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/07/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2368, NUDOCS 8603100387 | |
| Download: ML20154H860 (38) | |
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CERTIFIED MINUTES s- - DATE ISSUED:Jan.7, 1986 ' MINUTES ACRS SUBCOMMITTEE MEETING ON BEAVER VALLEY UNIT 2 CAR 0 POLIS, PENNSYLVANIA NOVEMBER 1, 1985 A meeting was held by the ACRS Beaver Valley Subcomittee. Notice of the meeting was published in the Federal Register on October 22, 1985 (Attachment A). The schedule of items covered in the meeting is in Attachment B. The list of attendees is in Attachment C. A list of the handouts is in Attachment D. The handouts are filed with the office , copy. H. Alderman was the designated ACRS staff member for tMs meet-ing. The meeting was convened at 8:30 a.m. Principal Attendees ACRS NRC Staff D ylie, Subcommittee Chairman G. Knighton J. Ebersole B. Singh W. Kerr E. Wenzinger F. Remick R. Walton Duquesne Light Company J. Arthur J. Carey J. Sieber G. Kurtz R. Martin R. Swiderski T. Jones G. Ewing T. Burns K. Grada e F. Schuster E. Eilmann Qg R. Fedin R. Druga g K. Troxler g Opening Statement - Subcommittee Chairman Wylie mm Mr. Wylie announced that the purpose of this meeting is to review the Se@ application by Duquesne Light Company for an operating license for
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.* Beavsr Valley Unit 2 2
, Novemb;r.1, 1985 Meeting Beaver Valley Power Station Unit 2. The subcommittee was polled for cosents. There were no comments so Mr. Wylie called upon J. Carey as ,
the first presenter. l J. Carey, Vice-President, Nuclear Group, Duquesne Light Company - (General background and Unit 2 schedules) , Mr. Carey noted that he and the nuclear group was responsible for the engineering, construction, start-up, and operation of the Number 2 unit. He gave a brief history of Unit 2. The unit was contracted for in 1971. The construction permit was received in January 1974. The anticipated date of commercial operation is August 1987. The plant is presently about 90% complete. The projected date for hydrostatic testing of the reactor coolant system is March 1986, with hot functional testing scheduled for October 1986 and fuel loading in April 1987. He noted I that they are presently on schedule to meet all the major milestones to l accomplish the commercial operation date of August 31, 1987. l Mr. Carey stated the ownership shares of Beaver Valley Unit 2 were as follows: The Ohio Edison Company owns 41.8 per cent; Cleveland Electric Illiminating Company 24.4 percent; Toledo Edison 19.91 percent; and Duquesne Light Company 13.74 percent. Duquesne Light Company, even though a minority owner, is responsible for the engineering and con-struction, and will be responsible for the operation of the facility.
Beaver Valley Unit 2 3
, November 1,1985 Meeting R. Martin, Engineering Manager, Duquesne Light (Design Differences Unit Ia'd2) n Mr. Martin noted that Beaver Valley Unit 2 was designed to duplicate Beaver Valley Unit _1 whenever possible. Certain modifications were made in order to optimize safety and reliability considering information that was gained from the continuing study of Beaver Valley #1 operating
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characteristics. The design of Beaver Valley 2 has incorporated many lessons learned in the nuclear industry over the time span that Beaver Valley Unit I has been operating. As examples of differences between Units 1 and 2, Mr. Martin mentioned the following: The Start-Up Feed Pump This pump takes its. suction from the condensate system. It can be used for hot stand-by operation or light loads up to 30 megawatts. It can be used in place of one of the two motor driven main feed pumps. Alternate Shutdown Panel The purpose of the alternate shutdown panel is to bring the plant to cold shutdown within 72 hours following a single exposure fire that is postulated to occur in one of four areas. The cable spreading area, the relay room area, cable tunnel, and the west communication area. An operator at this panel can transfer control without change in the equipment status from the control room to the alternate shutdown panel. The transfer is accomplished at the alternate shutdown panel.
- . Beaver Valley Unit 2 4 Novembor 1, 1985 Meeting Full Flow Condensate Demineralizers There are five units required with one as a spare. The flow is 17,000 ,
gallons,p'er minutes. The objective performance is ten parts per million dissolved solids. The condensate demineralizer system has its own air supply system, and the flow of condensate would automatically be divert-ed around all of these units on a ,high differential pressure. Reduction in Concentration of Boron The main steam line break size limitation to 1.4 square feet by the installation of flow limiters in the steam generator discharge nozzles allows for a lower concentration of boron. The boron injection tank which in previous designs had a concentration of about 20,000 parts per million is not required since the refueling water storage tank, or the boric acid tank, has a 2000 part per million boric acid solution which is adequate for reactivity control. J. Sieber, Senior Manager, Beaver Valley Unit 1 and General Manager, Nuclear Service Unit - (Plant Organization) Mr. Sieber pointed out that in 1985, Duquesne Light Company had accu-mulated 28 continuous years of reactor operation. The operating history includes Shippingport Atomic Power Station which began in 1957, and Beaver Valley Unit I which was licensed to operate in 1975. He also noted almost all of the operating, maintenance, engineering, construction and corporate personnel are located on site. With both Beaver Valley Units I and 2 on the same site, all the people above are readily available.
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Beaver Valley Unit 2 5
, November 1, 1985 Meeting Both Beaver Valley Units 1 and 2 will be operated as though it were a single facility.
At the Board of Directors level is a Nuclear Review Committee whose interest lies in the operation of Unit 1. The construction of Unit 2, and other projects with which Duquesne Light Company is involved. Some of the specific organization units are: o Nuclear Operations - This is responsible-for operations, maintenance, and testing of the operating units o Nuclear Services - This performs technical and administrative functions for the entire r.uclear group o Nuclear Engineering and Construction - This unit is responsi-ble for plant design modifications, engineering support to operations.. maintenance of the plant, and construction activ-ities on site. The Nuclear Services. Unit has the following departments reporting to it: Administrative Service Department - This department is respon-o sible for all the clerical and records support of the site; and labor relations and security.
Beaver Valley Unit 2 ~ 6
, November 1, 1985 Meeting o Nuclear Safety Department - This department is responsible for
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the licensing activities at Unit I and shortly will take over licensing activities for Unit 2. These activities include, compliance with regulations, independent safety engineering, and fire protection, o Radiological Cont'rol Department - This includes radiological surveys, discharge permits, radiation work permits, dosimetry, and environmental monitoring. o Nuclear Training Department - This department trains both operators and technical and crafts people. Included under the nuclear training department is an Emergency Planning section. Mr. T. Jones - General Manager of the Nuclear Operations Unit (Nuclear Operations) Mr. Jones noted that the nuclear operations unit has three general functions; production, technical services, and planning and outage management. The production responsibility is assigned to the plant manager who is responsible for operations, maintenance, instrumentation, and control and testing. i There was a number of questions regarding the role of STA's. Mr. Jones j explained that the STA's will not be licensed and they will not be used as a second SR0 on shift. The STA's will be maintained as a separate position. The STA's are graduate engineers and undergo a training i l l
BeavGr Valley Unit 2 7 November 1, 1985 Meeting program based upon INP0 requirements. The intent is not to have li-censed operators for STA's.
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The STA is involved in reviewing all plans to take engineering safe-guards equipment out of service. He is also involved in control board walk-downs and the observation of control room activities at different times'on the shift. His role is that of an advisor to the shift super-visor. The shift supervisor is responsible for the operation of the station. F. Sehuster, Technical Advisory Engineer - (Beaver Valley Emergency Operating Procedures) Mr. Schuster stated that the Beaver Valley Units 1 and 2 Emergency Operating Procedures ~(E0P's) will be based on the emergency response guidelines (ERG's) Revision 1 developed by the Westinghouse Owners Group. The ERG's are based upon improved analyses of emergencies. Their format utilizes improved human factor qualities and techniques and the scope of the procedures is much broader. The Beaver Valley Unit 2 procedure generation package (PGP) was submitted to the NRC in July 1984. Its purpose is to describe the process to be used in developing plant specific E0P's from the generic ERG's.
*- Beaver Valley Unit 2 8
, Novtmber 1, 1985 M:eting The E0P's will be verified and validated. Verification provides a i process to be followed in determining if the E0P's are technically ,
l correct and written to reflect the PGP guidelines. N Validation provides methods of assuring that the E0P's a're first us'e-able, that is they can be understood and followed by trained operators without confusion, delay, o'r error; and that they are oper'ationally correct, that is there is a correspondence between the control room plant hardwear and the E0P's, and that they are capable of directing'the operating crew in managing the event with consideration for the number, qualification, experience and training of the crew. B. Singh, NRC Project Manacer, Beaver Valley Unit 2 (Licensing Overview) Mr. Singh pointed out that the construction permit was issued on May 3rd, 1974. The FSAR was docketed on May 18th, 1983; and in October 1985 the Safety Evaluation Report was issued. He noted that at present there were 11 open items, 44 confirmatory items, and I license condition. He explained that the 11 open issues are simply.because the applicant has not provided the information yet or the staff has reviewed it and asked for additional ir. formation and they have to provide additional information. Mr. Singh noted that there were 16 backfit issues. He pointed out two of the backfit issues that he considered significant. r
l l - B; aver Valley Unit 2 9
. November 1, 1985 Meeting One issue concerns steam generator level control and protection. The staff's position is that the applicants design of the control system does not meet IEEE-279. Mr. Singh stated the applicant has two options, either to meet IEEE-279 or to demonstrate that an operator can take action within 10 minutes.
Theapplicanthasappealedi.hisdecision,andtheDirectorofthe Division of Licensing decided that pending the resolution of A-47
" Safety Implication of Control System"' operation does not pose a threat to the health and safety of the public. d The applicant has agreed to abide by the resolution of A-47. The position of the applicant on steam generator level control in Beaver Valley Unit 2 is that it does provide an acceptable level of safety. The applicant pointed out that this same system is used on Beaver Valley Unit 1. The applicant also noted that this same system is NRC approved on 26 other operating plants.
The other significant backfit issue is fire suppression in the cable spreading room. The applicant proposed a carbon dioxide fire sup-pression which the NRC Staff ruled was unacceptable. Following the appeal process, the decision was reached that the carbon dioxide system backed by a manual water suppression system and fire brigade training would be sufficient. During fire brigade training, the NRC Staff felt it would be very difficult to reach the northwest corner of the cable spreading room. The applicant has proposed to improve access to the northwest corner prior to operating the reactor and has purchased a special fog nozzle to facilitate reaching that corner.
Beaver Valley Unit 2 10
~ November 1, 1985 Meating
[ E. Wenziner, Branch Chief' Region I, NRC (NRC Inspection and Enforcement) Mr.'Wenziner noted that the purpose of his presentation was to provide a basis for the current Region I staff conclusion that the overall licens-ee performance during construction of Beaver Valley Unit 2 has been g satisfactory, and compliance with NRC requirements and safety objectives has been acceptable. He noted that this conclusion has been reached after consideration of certain key factors, namely, corporate involve- ~l ment by the licensee in construction activities, NRC inspection of construction quality arid licensee management attention to NRC concerns.
- i l Mr. Wenziner noted that inspections from the initial inspection of July 11, 197^ to the present have total approximately 130 inspections.
I 1hese inspections include soil and foundation, concrete work, safety related structures, piping, welding, electrical activities, safety related mechanical components and instrumentation. Mr. Wenziner remark.ed that 66 non-conforming conditions have been l' identified for Beaver Valley Unit 2. This compares very favorably with i
- i four other plants at a similar point in construction.
!l Two regional construction team inspections have been conducted. These inspections provide an in-depth assessment of construction quality. The team is a multi-disciplinary team and conducts a coordinated inspc:: tion of various functional areas to examine program effectiveness.
Beaver Valley Unit 2 11
, November 1, 1985 Meeting The first inspection was conducted in April 1983. One weakness iden-tifled in this inspection was design control.
The second team inspection was conducted in March of 1985. While no major hardware problems were identified as a result of this inspection, there were ling'ering problems that persisted in the engi-neering construction interface for electrical connections. This conclu-sion was reached during the inspection when certain cable pulling and
. electrical termination procedures were conducted improperly.
The conclusion reached by Region I is that the overall licensee perfor-mance during construction of Beaver Valley Unit 2 has been satisfactory and compliance with NRC requirements and safety objectives has been acceptable. E. Ewing, Manager of Quality Assurance - (Quality Assurance and Quality Control Mr. Ewing noted that he was responsible for maintaining and managing the Duquesne Light Company Quality Assurance Programs; and he was authorized to report quality problems directly to any level of management'necessary to assure corrective action. The quality assurance unit administers the quality assurance and quality control activities and the in-service inspection' programs for both Beaver Valley units.
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Beaver Valley Unit 2 12 November 1, 1985 Meeting The design, procurement, fabrication and construction of Beaver Valley Unit 2 has been carried out in accordance with the Duquesne Light Design and construction quality assurance program. Ninety days prior to fuel loading, the Duquesne Light Company operations Quality Assurance Program will be applied to Unit 2. Mr. Ewing noted that one indication of their ability to implement and maintain an effective quality assurance program is reflected in the NRC SALP report. The most recent Unit 1 SALP evaluation resulted in five functional areas being rated category 1, and the remaining four functional areas received a category 2 rating. T. Burns, Director of Operations Training - (Training) Mr. Burns pointed out that the training center has 42,000 square feet in the Training Building and 28,000 square feet in the Simulator Building. He noted that the initial licensed operator training program consists of six phases: (1) Theory courses which prepare the Trainee with a sound techni-cal background for understanding plant system and overall plant operations.
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Beav:r Valley Unit 2 13
, November 1, 1985 Meeting (2) Plant-specific system training in the form of lecture series.
evaluated by written examinations, used to track comprehension
-and progress.
(3) Actual system tracing in-plant and completion of procedure review followed by an oral examination administered by a qualified instructor who is guided by a system qualification standard. (4) Simulator training which is interspersed throughout the program to. allow hand-on operations of various system controls and culminating with a start-up certification in abnormal and emergency operations. (5) On shift training which is interspersed throughout the train-ing program. (6) Trainees participate in instructor - led review of technical subjects and are administered written and oral' examinations, including a third party exam similar to the NRC examination. The licensee retraining program consists of five phases: (1) Annual written examination, modeled in scope and style to the NRC requalification txamination.
Beaver Valley Unit 2 14 November 1, 1985 Meeting (2) Formal classrocm training based in part on the results of the annual examinations. s (3) Plant manipulation training which is accomplished on the Unit I specific simulator. (4)' Review and self study of significant operating experience reports, incident reports, design changes and procedure review. (5) Performance evaluation, which is a combination of performance ratings as observed during simulatory training and actual performance on the job. R. Fedin, Senior Project Engineer - (Decay heat removal) Mr. Fedin noted that the Beaver Valley Unit 2 design has the capability to achieve both hot stand-by and cold shutdown. He noted.that there were many upgrades in non-safety systems since the early design in the 1970's. These upgrades include: o Upgrading all three pressurizer PORV's to safety grade statue o Upgrading the atmospheric dump valves and residual heat removal valves to safety grade status
Beaver Valley Unit 2 15
, November 1, 1985 Meeting o Redesigning the residual heat removal suction and discharge valves, along with the RHR system flow transmitters, to be
- above the maximum flood elevation inside containment.
s o Replacing the two manual valves on the line connecting the redundant RHR trains with motor operators capable of being
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operated from the control room. An additional back-up non-safety related water source was also provided for the auxiliary feedwater system. E. Eilmann, Senior Project Engineer - (Emergency and Alternate Shutdown ~ Panels 1) Mr. Eilmann noted that both the Emergency and Alternate Shutdown penels have the capability to bring Beaver Valley Unit'2 to a safe shutdown condition in the unlikely event the control room becomes uninhabitable. The emergency shutdown panel meets the requirements of GDC-19 and allows shutdown of the plant of the control room becomes uninhabitable. In the case of an interior fire in any of five rooms, control room, cable spreading room, cable tunnel, instrumentation room, and west communication room; the alternate shutdown panel will be used. The question was raised regarding an exposure fire at the alternate shutdown panel presenting the potential for spurious and undesired
B; aver Valley Unit 2 16 November 1, 1985 Meeting operation as well as inoperability. The response was that the applicant pla'ns to perform an analysis to study this. K. Grada, Manager of Nuclear Safety - (Station Blackout) Mr. Grada defined station blackout as a simultaneous loss of off-site power with failure of on-site emergency diesel generators. He noted that the mitigation systems and design features include the followirg to minimize the challenges to the critical safety functions and limit recovery time under blackout conditions: o Steam generator nower operated relief valves to provide controlled heat removal from the secondary system and limit the operation of steam generator safety valves. These valves can be manually operated with a loss of all A. C. along with the decay heat removal and auxiliary feed pump discharge valves, o Turbine-driven feed pump to maintain a secondary heat sink for the primary system. o Flywheels on the reactor coolant pump to ensure core cooling as the pump slows down until natural circulation conditions are established. o 25 percent design margin on Station Batteries.
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Beaver Valley Unit 2 17 November 1,.1985 Meeting
- 0 Floating ring seals installed in the main flanges of the reactor coolant pumps to limit leakage in the event of a s
- number one seal failure.
o System cross ties which assure a long term source of makeup to the safety related feedwater system. o Connection to six peaking units with a combined capacity of 204 megawatts electrical under the control of the system operator, one of which has block-start capability. J. Hultz, Deputy Project Manager - (Leak Before Break Applications) Mr. Hultz noted that leak before break (also known as alternate pipe rupture protection) has three main applications on Beaver Valley Unit 2. The first application is on the primary coolant loop and had resulted in the elimination of nine rupture restrains and associated impingement shields. The second application is on the area of arbitrary intermediate pipe breaks. This has resulted in the elimination of 127 pipe rupture restraints and associated jet impingment shields. The third application is on the balance of piping not covered by the two previous applications. This would result in the elimination of an additional 136 rupture restraints and associated jet impingement shields. l i
.- Baaver Valley Unit 2 18 November 1, 1985 Meeting The third application is termed the whipjet program. Whipjet is based on the principles of prevention and detection rather than mitigation. The whipfet program is composed of two main activities, determination of applicability to a specific pipe or piping system and implementation of leak before break approach after the applicability has been determined. During the determination of applicability phase, the extent that con-ditions are acceptable for fracture mechanics will be studied. This involves review of stress corrosion, water hammer fatigue and component support failure. If the above conditions are not satisfied, then conventional methods of pipe support will be used. In summary, Mr. Hultz stated the application of whipjet would result in decreased radiation exposure to the plant staff, improved plant acces-sibility for operation and maintenance, and decreased cost for con-struction and operation of the plant. The meeting was adjourned at 3:25 p.m. Additional Activities The application of Duquesne to operate the Beaver Valley Station Unit 2 was. discussed during the 307th ACRS Meeting on November 10, 1985; and a letter approving operation at full power was issued on November 13, 1985.
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Beaver Valley Unit 2 '19 Novemb:r 1, 1985 Mesting 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 at cost from ACE Federal Reporters, Inc., 444 North Capitol St., Washington, D. C. 20001, Telephone: * (202)347-3700
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Federal Regiat2r / Vrl. so, No. 204 / Tuesday. October 22. uns / htices M ). Ughting and Power thp= 'a "-v term for smeleer power paunt =ht=
'. Washingt:. . DC. On December 2 the application for an operating ==ae. and incidents. - , .Subcomm.t.t e will discuss the issue of AFW reli.b:hty, and on December 3 the 'M.Seleccan ofNacisarPtererMant '
Scrum Syvtema determined. Waabington.Relaobihty. DC.The Daar to be . Operators-Discuss proposed Subcommittee will continue the review comnaente regardag the meeboda used . of the NRR msolution position for USI Sabcomunittee will disanaa scram * ' A-45. " Shutdown Decay Heat Removal breaker reliability for B&W and CE for selection of anclear power plant Requirement." plants and contmue its review of the operatore.
- Qualification Prqgram forSafety. ATWS Rule implementation offort. , N.
Seismic Margin in Nuclearhverar CENuclearPlants, Date to be Plants-Osru== proposed AGLS .- l Related Equipment. December 4.1985, Washington. DC The Subcommittee will determined. Washington. DC.The comrnents regarding NRC activities i* discuss resolutbn and implementation Subcommittee will discuss the lasue of .related tobetter definition of the se6ande ' :. rapid depressurization for CE planta marei n la nuclear power plants. of US! A-46 '* Emergency Core Cooling Systems, without PORVs. *0. New ACRS MembeMecusa ACRS Full Committee Maeting qualifications requned for new ACRS . December to and 11.1985. Palo Alto- e member. CA.The Subcommittee will continue the November 7-9.1985: Items are .P. ACRSSubcommittee Activities-review of the joint NRC/B&WOG/EPRl/ tentatively scheduled. Discuss reports of ACRS subcommittees B&W joint IST Program. A visit la 'A. Polo Vede NwnSm.on- and subcommittee chairmen regarding planned to the EPRI-sponsored facilities Discuss resnits of the startup test supporting this Program and the status d onW subcendttee pmg yittee to Review' *** " Stanford Research Institute and Science 8 [RC Decemb' er 5-7.1985-Agenda to be
. Applications. Inc. Generic Requirements-Briefing ,
Quohty andQuohtf Assurance in sg announced. Design and Const.ruction. December 13.
8'rd t a; , fc rd ety January 9-11.1986-Aaends to be C announced.
1985. Washington. DC. The . Anal sis Report (CESSAR-ll)-Discuss Subcommittee will discuss with t,he NRC proposed ACRS report to the NRC Da ted. October 17.1985. Staff such programs at CAT. IDS P. IDI. regarding the FDA request for thia John C. Hoyle, and readiness review to ensure quality Advisory Committee Monqpement oficar. system. 8" 'D. Meeting with NRC Corr.missioners (nt Doc. as-zst sa ided to-21-ss. s s5 am) I"",*',*'gf,flc y y ,P ',*"g Q 'j *"~ & ntoe cuss S mp rts to ,og com ,,,, w - their program to deal with allegations at NRC reFardmg consideration of extreme , the OL stage (i e-. Comanche Peak). envit nmental phenomena in emergency / Emphasis should be on comparing the V Advisory Committee on Reactor resources required by the s arious pla.nning. E. Reactor Pressure Vessel Thermal safeguarda, subcommittee on Beaver programs nd the effecti ene ofthe ShocA-Discuss recommendations of Valley Power Station Unit 2; Meeting p S q ACRS consultant report on reactor design construction and read ness for pressure s essel thermal shock. 'The ACRS Sub' committee on Beaver
'F. Recent Operating Events at Valley Power Stanon Unit 2 will hold a OP"8'iO"- meeting on November 1.1985, at the Safety Research Progrcm. February Nuclear Plants-The ACRS will discusa 12.1986 (tent at h e). Wa shington. ,DC. the report ofits subcommittee and Holiday Inn Airport Hotel.1406 Beers School Road. Coreopolis, PA.
The Subconirruttee mil contmue its presentations by representatives of the ' resiew of the NRC Safety Research The entire meeting will be open to regulatory staff regarding recent prcyram and budget and will also incidents and accidents at nuclear Public attendance. dscuss a f nal dcaft of the ACRS report The agenda for the subject meeting po.wer plants. sha!! be as follows: to the Congress. G. NRC Outoge Inspection ' Tcrt St. Vrem. Date to be determined Progrom-Briefing by representatives of Friday. November J.1985-a30 a.m. * (Nm ember / December), near Longmont. the NRC Staff regarding proposed Uniff the Conclusion of Business C0Jlhe Subcorr.nuttee will tour the activities in connection with the NRC lac Aty. explore technical problems outage inspection program at nuclear The Subcommittee will review the aMessed during the recent extended application of the Duquesne Light pla.nts. Cornpany for an operating license. cu*.e.. and discuss management H. Bearer Vc!/ey Nuclear Power Oral statements may be presented by ch.mges made as a result of the Station Unit 2-Consider the requested lit ensee's independent assessment of members of the public with the operating license for this unit. m.m..gement controls. *l. ProposedNRCSofefy CoolPolicy ' concurrence of the Subcommittee Statement-Discuss proposed NRC Chairman; wruten statements will be Hamun roctor. Date to be determined (Dn ember). Washington. DC. The policy statement regarding use of accepted and raade available to the St.bccrnmittee will explore methods for Committee. Recordings will be permitted quantitative safety goals in the NRC deciding what actions should be regulatory process, only during those portions of the automated in nuclear power plant meeting when a transcnpt is being b4pt,
*). Future ACRS Activities-Discuss and questions may be asked only by eperations. anticipated ACRS subcommittee activities and items proposed for members of the Subcommittee, ha .
Rclicbihty andProbebilistic consultants, and Staft Persons desiring Assessment. Date to be determined consideration by the full Committee.
*K. Nuc. lear Power Plant Operator to make oral atstemasta should notify (Tall. tentative). Washington. DC. The Subcommittee will resiew the- Training-Discuss proposed the ACRS staff member named below as probabilistic risk assessment for estabidment of a nationalacademy for far in advance as is practicable ao that kl. stone 3. the tranning of nuclear power plant appropriate arrangemanas me be made.
operators. Dunng the initial portion of the M:th Texas Units J and 2. Da'e to be detarrained (January). Washington. DC. 1 Nuclect Annaient Source Term- meeting, the Subcommittee, along with
. W Subcomm:ttee will review Houston Discues proposed redioactive source any ofits canaultants who may be 8
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. r 22,1985 / Notices Federal Register / Vol 50' N , 204 / Tuesd:y October as is prac"lcable so that.
428 9 d n ' the ACRS staff merobec rCed below cs ' far in c vanceappropriate arrangeme . During the initial portion of the prek:nt.may exchange pnliminafyfar la advance as is practicable so thatmeeting, vieus regarding matters to be - appupriate arrangements can be made. the Subcommittee may ' ding considered during the balance of tha - Curing the initial portion of the exchange preliminary views regar meeting. . meeting. the Subcommittee, along matters to be considered during the with balance of the meeting.ne The Subcommittee willthen hearany of its consultants who may be present:tions by and bold discussions present,may exchange preliminary Subcommittee will then hear < with representatives of the Duquesne views regarding matters to be presentations by and hold discussions Ught Company, NRC Staff, their - , considered during the balance of the with - representatives of the NRC Staff consultants, and other interested - meeting. and other interested persons regarding' pers:ns regarding this review. i The Subcommittee will then hearthis review. '
. Further infonnation regarding top cs Further information regarding topics to be discussed, whether the meeting presentations by and holdtodiscussionswith be discussed.whether the representatives meeting of has been cancelled or rescheduled, the its consultants, and other interested has been cancelled or rescheduled, the '
Chairman's ruling on requests for thepersons regarding this review.Further Chairman's ruling on requests for the ~. opportunity to present oral statementa information opportunity to present oral statements regarding topics .! to be discussed, whether the meeting and the time allotted therefor can be ? and the time allotted therefor can obt:ined by a prepaid telephone call has be - to - been cancelled or rescheduled, the . obtained by a prepaid telephon'e call to'
'the cognaant ACRS staff member,Mr.. Chairman's ruling ontequests fbr the the cognizant ACRS staff member,Mr.
Herman Alderman (telephone 202/634- opportunity to present oral statements . Richard Major (telephone 202/634-1414) 1414) between 8:15 a.m. and 5 00 p m. and the time a!!otted therefor can between be 8.15 a.m. and 5.00 p m.Pers'ons 1 Pers:ns planning to attend this meeting obtamed by a prepaid telephone call to planning to attend this meeting are tre urged to contact the above nacted the cognizant ACRS staff member.Mr.urged to contact the above named individual one or two days before the Anthony Cappucci(telephone 202/634-Individual one or two days before the sch:duled meeting to be advised of any 3267) between 815 a.m. and 5.00 p.m. scheduled meeting to be advised of any . changes In schedule, etc., which may Persons planning to attend this meeting changes in schedule, etc., which may
, have occurred. are urged to contact the aboved named , individual one or two days before the have occurred.
Da'ted. October 16.1985 ' scheduled meeting to be advised of anyDated 0ctober16,1985.
. Marton W.thMn, changes in schedule, etc., which may DirectorforPmject . Assistant Executive Directorfer Project -
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- Dated r 18.19ss. med 10 *1-85; 8 45 am)
[ c 85-25 a Exe Durctarfor Pmiect - As Review. ,
~Advloory Committee on Reactor - (R Doc. 85-25185 Fded W21-as,6.45 am)
-[Docheta Nos. 50-269,50-270 and 50-2871 3 Safeguarda, Subcommittee on ,g , coa, ,,,%
- Regulatory Polletes and Practices; -
_ Duke Power Co.; Consideration of laauance of Amendments to Facility l Meeting
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, mmn o eactor Operating Licensea and opportunity
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4 . '. .Regulatory .'Je ACRSSubcommittee on for Prior Hearing Policies and Practices will OPerationa; Meetfng bold a meeting on November 1,1985. The United States Nuclear Regulatory -
- Room 1046,1717 H Street, NW., ~
ne ACRS Subcommittee on Reactor . Commission (the Commission)la Washington, D.CJ Operations willhold a meeting considering onMonday, isst.anceNovember of amendmerus to 4,1985, De entire meeting willbe open to Facility Operating IJcenses Nos. DPR- ,, R 1717 H Street, NW., Washington, DC. 38,DpR-47 and DPR-55, issued to Duke .
-* public attendance.ne agenda for the Desub}ect meeting entire meeting willbe open to Power Company (the licensee), for shallbe as follows: -
public attendne agendafo the sukect operation meeting of the Oconee Nuclear ' Station, Units 1,2 and 3, located in
'dyy, November 1,1965-4J0shallbe a.m.as.follows: Oconee County, South Carolina. .
N "' ' ' - no Soboommittee wd! discuss SECY- Afonday, Novemberi,1985--f}00 The amendments p.m.would
. revise 45-rd (locident Investigation Program)Until the Conclusion of Busmess TechnicalSpecifications(TSs)of the and recommendations made h by ASLBPt neplSubcommittee will review .recent operating licenses to establish e degraded mode of operationif a a: ore 4
.and OPEreleted to.ethe establis ' -
operatingmenan experience. lacident Oralbevestigation statementsflood tank may be hesented Organir.ation boron concentration
. by. -
*
- e . .,.serthh NRCr e .n. ,. :.. .s dby members of the public with the decreases below the current requirement of 1835 ppm. Presently, the concurrence of the Subcommittee Oconee Nuclear Station, Units 1,2 and a e e Osalstatementamaybepresente +.**
- e e asetshenof thepubec with she- -
Chairman: written statements will be
' oonentrence of the Subcommittee accepted and made available 3,TSstorequire plant shutdownin theCommittee. Record Chairussa: wrstten statements will be core flood tank falls below 1835 ppm ) assapted and made available to the only during those portionsbaron.The of thechange -meeting proposed when by the a transc p C=etee.Rocardings willbe permitted 34 -
and questions enay be asked only bylicensee would allow the boron-er4 <iurtna those portions of thek t
,, meeting when a trenocorptis beEng members of the Subcommittee,its ep , concentration in one core flood tank t anst questions may be ==had only by conn!tanta, and Staff. Persons desiring decrease below the current minim 1835 ppm for up to 48 hours whife the to make oral statements should notify
( '., members of the Sobco-mittee,its
- con =4==aa and Staff.Penons desiring the ACRS staff membernamed below as
.to make oral statements should notify .
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9
ff f frWMDUT /3 TENTATIVE SCHEDULE REVISION 2 BEAVER VALLEY #2 10/15/85 PITTSBURGH, PA NOVEMBER 1, 1985 8:30 a.m. 1. Opening Remarks - C. Wylie 10 Min.
8:40 a.m. 2. Applicar.t Presentation A. overview of plant layout and principal 20 Min. design features 9:00 a.m. B. Construction Status and Plant Startup 15 Min. Schedule 9:15 a.m. C. Organization and Management 45 Min.
- 1. Corporate organization
- 2. Nuclear organization
- 3. Nuclear related experience of key personnel 10:00 a.m. D. Emergency Operating Procedures 20 Min.
10:20 p.m. ********** BREAK ********** 10:30 a.m. 3. NRC Staff Presentation A. Major Differing Technical Issues 15 Min.
'and Schedule for Resolution 10:45 a.m. B. Construction Experience (RegionI) 45 Min.
11:30 a.m. C. Backfit Items and Resolution 15 Min. 11:45 a.m. D. Significant Confirmatory Issues i 15 Min. and Licensing Conditions l 12:00-1:00 p.m. ********** LUNCH ********** i < APPLICANT PRESENTATION ! 4. Quality Assurance i l 1:00 p.m. A. Overview of Policy and Organization l 10 Min. l 1:20 p.m. B. Quality Control Problems Experienced 20 Min.
, During Construction and Resolution
. 7$ ' BEAVER VALLEY SCHEDULE 2 1:40 p.m. C. Operational Quality Assurance 30 Min.
2:00 p.m; - 5. Training 60 Min. ,
' A. Simulator B. Initial Operator Training Program C. Requalification Training Program D. R0, SRO, & STA Training E. Training for Non-Licensed Personnel 3:00 p.m. **********
. BREAK **********
- 6. Systems Required for Safe Shutdown 3:15 p.m. A. Safe Shutdown Systems 3:35 p.m. B. Remote Shutdown Capability 3:55 p.m. -
- 7. Alternate Pipe Rupture Protection 4:25 p.m. SUBCOMMITTEE DISCUSSION 5:00 p.m. ADJOURN 4
4
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. ATTACHMENT D
~
4 BEAVER VALLEY 2 - HANDOUTS 4
- 1. Evaluation of Construction Quality (Region I)
- 2. . NRC Staff Presentation to the Beaver Valley Subcomittee - November 1, 1985
- 3. Duquesne Light Company Presentatforf to the Beaver Valley Subcomittee, November 1,1985 d
e l 1 4
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