ML20127N259
| ML20127N259 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/25/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2276, NUDOCS 8505230479 | |
| Download: ML20127N259 (24) | |
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March 25, 1985 l MINUTES OF THE MEETING OF THE ACRS SUBCOMMITTEE ON BRAIDWOOD STATION, UNITS 1 AND 2 JANUARY 29, 1985 WASHINGTON, D.C.
The ACRS Subcommittee on Braidwood Station, Units 1 and 2 met in Washington, D.C. on January 29, 1985 to review the Commonwealth Edison Company's (CEC 0's) application for an operating license. This was a continuation of the Braidwood Subcommittee meeting held in Joliet, Ill.
on March 8, 9, 1984.
Notice of this meeting was published in the Federal Register on January 14, 1985 (Attachment A). A copy of the schedule of presentations is shown in Attachment B. A list of attendees is shown in Attachment C.
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Attachment D is a list of handouts kept with the office copy of the minutes. The meeting was open to the public except for the session on physical plant security. There were no written or oral statements received or presented from members of the public at the meeting. E.
Igne was the cognizant engineer.
C. Mark, Subcommittee Chairman, read the opening statement and reviewed the items on the agenda. D. Moeller complimented the applicant on the I background document provided to the subcommittee before the meeting. He stated that it was a very good factual summary. The NRC Staff concurred. D. Moeller questioned some of the PRA results that compared the early fatality cancer risks between Byron and Braidwood plants. '
This matter will be addressed later in the meeting.
J. Stevens, NRR Licensing Project Manager, provided an overview of the .
licensing activities for the Braidwood Station. The Byron and Braidwood Stations use a duplicate plant design in accordance with the NRC's
" Statement on Standardization of Nuclear Power Plants" dated August 31, 1978. She stated that the Braidwood Station Unit 1 is 80% complete and k 7 pg sa g 9 esosas 2276 Dzsc u noawun .
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Min.Braidwood Units 1 and 2 '2 January 29, 1985 M:eting n
that Unit 2 is 54% complete. The applicant estimated fuel dates are April 1,1986 for Unit 1 and July 1,1987 for Unit 2. A status of onstanding items for Braidwood Station show six open items. In conclu-sion of her presentation she stated that NRR is prepared to recommend licensing of Braidwood Station pending favorable resolution of the outstanding items, and the construction issues. There are no differing NRC Staff professional opinions relating to the Braidwood operating license review.
W. Forney, Region III, discussed the NRC construction inspection experi-ence at Braidwood. He stated that numerous construction related prob-lems exist in the areas of 1) piping traceability and minimum wall thickness, 2) HVAC hanger fitup and welding and 3) electrical . cable separation, unauthorized use of butt splices, incomplete records and control of rework. He stated that Commonwealth Edison Corporation has programs to identify and correct these construction deficiencies. A concern of Region III is with the ability of CECO to manage the multiple reinspection efforts and the ongoing work. Region III has increased its inspection personnel and its inspection and management oversight activities to ensure that Braidwood is constructed satisfactorily.
D. Heishman, I&E, presented a preliminary status report of the con-struction appraisal team (CAT) inspection recently completed at Braidwood. He stated that the CAT inspection program was started in L September 1982 in order to assess on a national basis some of the I
problems that were being identified at various construction sites across the country. This program was designed to be a hardware inspection program. Ten of these CAT inspections have been performed in various plants in the country thus far. At Braidwood 15 inspectors were on site for four weeks. By NRC standards the CAT inspection program at Braidwood was larger than normal. Some of the areas inspected were 1)
! electrical and instrumentation, 2) welding, 3) NDE of pipes, pumps and -
valves, 4) configuration of hangers and restraints, 5) design change efforts, 6) corrective action programs, 7) material traceability and 8) ,
project management functions, f
Min.Braidwood Units 1 and 2 3 January 29, 1985 Meeting s
Preliminary result of the CAT inspection would be ..."somewhere in the low part of the average category." R. Heishman stated that they have identified a list of deficiencies but that in their judgement they have not identified anything that cannot be satisfactorily corrected prior to the issuance of the plant license. He stated that his real concern is how well CECO can continue the corrective action programs and also keep up with the ongoing new work.
C. Reed, VP of Nuclear Operations, opened CEC 0's presentation by in-troducing T. Maiman, Manager of Projects, who has overall responsibility for engineering, construction and startup of both Byron and Braidwood Stations. T. Maiman was designated by C. Reed to be the " quarterback" for CEC 0's presentations. l T. Maiman in his introductory remarks stated that as a leader in the nuclear power industry, CECO has a continuing obligation and desire to strive to achieve the highest level of performance in both construction and ongoing operation of their plants. He further stated that CECO's commitment to achieving excellence in its construction program, in particular, begins with the top officer in the company, Mr. O'Connor, CEC 0's Chairman and President.
.M. Wallace, Braidwood Project Manager, commented on the I&E presentation L. of the CAT inspection results and INP0's team evaluation of Braidwood.
He stated that a Task Force consisting of CECO personnel and all of its major contractors was mobilized to interface with the CAT team on a day-
-to-day basis in order to review the NRC activities. Observations which were judged to represent discrepant conditions were documented and evaluations and corrected actions taken. The INPO evaluation team consisted of 24 experienced individuals. They examined several broad areas of the project including organization and administration, design control, construction control, project support, training, quality and .
test control. The INP0 team found that the systems in place at CECO to control the quality of design and construction were being effectively implemented. An important strength at CEC 0 which the INP0 team identified is the positive attitude of the project personnel at the
'* - Min.Braidwood Units 1 and 2 4 January 29, 1985 Me:: ting s
Braidwood site. Sonie QA/QC deficiencies were noted by the INP0 team and corrective actions taken.
Mr. Wallace next discussed the Braidwood project update. The Braidwood project was authorized in September 1972, and the construction permit was issued in December of 1975. First concrete was poured in March 1976 and the switchyard was livened in November 1981. Cold hydro of the reactor vessel was performed in August 1983. CECO plans to complete integrated hot functionals in July 1985 and be ready to begin fuel loading in March 31, 1986. Plant service is presently anticipated for October 30, 1986.
Mr. Wallace next discussed management changes made since our last subcommittee meeting in March 1984. CEC 0 has established a project licensing and compliance group. This is a unique organization, one that did not exist in either LaSalle or Byron. It represents CEC 0's learning experiences from those two plants and a desire to be in a position of being fully responsive to NRC and other regulatory concerns. It is the responsibility of this group to be the primary interface between the project organization and the on-site NRC residents, as well as any other regulatory bodies which visit the site, including the NRC CAT team and the INP0 team. In addition, CEC 0 has established a Quality First program. Through this program individuals have a mechanism established to raise any concerns they might have about the quality of the ongoing construction activities without any fear of reprisal. In reply to a subcommittee question, C. Reed stated that the Quality First Program will be put on the INP0 network such that other utilities, if desired, can share in Braidwood's Quality First type program.
E. Fitzpatrick, Asst. Manager of Quality Assurance, discussed CECO's quality assurance efforts at Braidwood concentrating on the changes and developments since our last subcommittee meeting in March 1984. Since .
last January 1984, the QA personnel assigned to Braidwood increased by more than 160 percent. This increase is necessary to cover the ongoing corrective action programs and also the work activities in progress.
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Min.Braidwood Units 1 and 2 5 January 29, 1985 Mesting E. Fitzpatrick then briefly discussed the quclity assurance overview of the Braidwood Construction Assessment Program, BCAP. BCAP is being implemented under the applicable requirements of a Commonwealth Quality Assurance Program. To assure that quality and programmatic requirements of BCAP are met, CECO has established a dedicated BCAP quality assurance overview group. This group consists of 18 individuals and is organized into four subgroups, one for each of the three elements of the BCAP program i.e., construction sample reinspection, reverification of procedures to specification requirements and review of significant corrective action programs, and an overinspection group. These elements will be discussed in detail later in the meeting. The BCAP program has been submitted and approved by NRC. Noteworthy activity at Braidwood in 1984 were 11 stop works at the construction site, 10 of which have been resolved and lifted. Most of these stop works were imposed because of procedure or documentation deficiencies. Some of these stop works were implemented by the contractors under their quality assurance program; several through their own initiative. In summary, E. Fitzpatrick stated that CEC 0 believes there has been significant improvement in the past year in the Braidwood site quality assurance performance.
K. Ainger, Project Engineering, discussed the principal design differ-ences between Braidwood and Zion. Braidwood, it was stated, is concep-tually similar to Zion Station. Each power plant consists of two identical generating units comprised of a pressurized water reactor (PWR) furnished by Westinghouse Electric Corp. The turbine generator is also furnished by Westinghouse. Sargent & Lundy is the architect / engineer for both stations. Many of the people from Westinghouse, Sargent & Lundy and CECO were involved in the development of the design of Zion and Byron /Braidwood stations. K. Ainger stated that the design differences between the two stations do not represents a major departure from the Zion design but rather an enhancement of what CECO consider to be an existing safe design. .
Site specific characteristics have dictated some of the design differ-ences'between the two stations. Zion uses lake water and a once-through-cooling cycle for heat rejection while Braidwood cooling is
Min.Braidwood Units 1 and 2 6 January 29,'1985 Meating s
provided by a large, manmade cooling pond, constructed over a previously strip mined area, and Byron uses cooling towers. Essential service cooling is provided by an auxilary cooling plant which is integral with
-the main plant. Other site specific characteristics include extra cleanup.and filtration equipment to deal with the Kankekee River for Braidwood. Zion was designed for a 0.179safeshutdownearthquake(SSE) versus a 0.2g design _at Braidwood and at Bryon. The safety-related equipment for both Zion and Braidwood/ Byron was seismically qualified in an enveloping spectrum that takes into account the limiting cases for both stations.
The polar crane inside each containment at Braidwood is mounted on the containment wall rather than on the missile barrier as at Zion. The auxiliary building at Braidwood has greater volume and contains more usable space than Zion's. The arrangement of equipment allows for greater physical separation of redundant systems, piping and cables than was possible at Zion. Refueling water storage tanks at Braidwood have been located outdoors, thus creating more usable space in the auxiliary-building. In addition, the layout in the auxiliary building at Braidwood has been enhanced with respect to radiation shielding based on ALARA lessons learned at Zion. The remaining major site layout differ-ences consisted of a river screenhouse for Braidwood and lake screenhouse for Zion.
The NSSS at both stations utilize a four loop Westinghouse PWR. The power rating of the Braidwood units is slightly higher than Zion due to the development of the next generation of Westinghouse NSSS. Braidwood and Byron NSSS are identical. The fuel assembly design changed from a 15x15 array to a 17x17 optimized fuel design. Due to the uncertainty in the availability of silver, the control rod material at Braidwood was l
changed to hafnium rather than the silver, indium, cadmium composition that is the control rod at Zion. The steam generator design was changed . .
from a feed-ring to a preheater type, resulting in increased efficiency.
The reactor coolant pumps at Braidwood are of greater capacity than Zion's. The No. 3 seal design has been improved and a complete seal refurbishment can be accomplished without removing the pump motor at
- Min'.Braidwood' Units 1 and 2- 7-
-January 29, 1985 Meeting _
Braidwood.. The reactor protection system and safeguards actuation.
system were upgraded from the relay system at Zion to a solid state system at Braidwood.
The auxiliary systems for the plants are also different in various areas. The safety related equipment at Zion is distributed across three electrical divisions per unit that are backed up by two diesel genera-tors per unit and one common diesel generator that can serve either-unit. At Braidwood, there are two electrical divisions per unit and two diesel generators per unit. The quantity and capacity of unit and
> system auxiliary transformers also differ between the two stations. Mr.
Ainger' stated that Braidwood grid reliability is about the same as in the' Zion plant. The radwaste systems at Braidwood have been designed with a greater capacity and general improvements over the system at Zion. In addition, Braidwood's design includes a volume reduction system which provides for alternate means of waste disposal.
r In answer to an earlier subcommittee question regarding early fatality risk estimates, J. Holman, NRR stated that Braidwood has a higher risk
- than Byron because there are more people living within five miles of the plant. Regarding latent cancer fatality risk Byron exceeds Braidwood because there are more people closer, within a mile or two, from the plant.
1 In response to a subcommittee question regarding an evacuation speed of 1.1 mph, the staff stated that this value is reasonable on the conserva-
> tive side and'it accounts for data obtained on a large number of evac-uations from earthquakes, fires, hurricanes and floods. It was stated by CECO that the 1.1 mph evacuation rate is based on methodology
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formulated in the 1970-1980 timeframe. Using today's techniques a recalculation of evacuating times would yield about 6 mph. J. Holman- .
i- stated that the subcommittee's suggestion of considering the uncertainties associated with the evacuation speed on fatalities will be considered in future environmental impact statements.
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T.-Maiman, Manager of Projects, CECO, provided additional information on the BCAP-program. This program was undertaken to provide an additional level of: assurance in the quality of construction at Braidwood. The BCAP definition is a program of inspections and reviews undertaken as a prudent measure.to answer any legitimate questions concerning the-overall quality of. construction at the Braidwood station.-
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The objectives of BCAP are 1) to assure that there are no programmatic
? design-significant problems in the construction of Braidwood which have not been identified and addressed 2) to assure that on-site contractors L procedures governing the on-going safety-related construction and I quality assurance activities address applicable design and regalatory 4'
requirements, and 3) to assure where past construction problems have I been identified which resulted in significant corrective actions, those
-corrective actions have been adequately implemented and documented.
N. Kaushal, Director of BCAP,~ described the various elements of the BCAP and current status of the program. BCAP consists of three principal
-elements, 1) the construction sample reinspection (CSR), 2) reverifica-tion of procedures to the specification requirements (RPSR) and 3) review of significant corrective action programs (RSCAP).
The objective of CSR is to assure that there are no programmatic design-significant. problems in construction of the Braidwood' plant which have not been identified and addretsed. The objective of RPSR is to assure that on_ site contractors procedures governing ongoing safety related construction and quality assurance activities address all applicable !
design and regulatory requirements. The objective of RSCAP is to assure i that where past construction problems have been identified, which j resulted in significant corrective actions, that such corrective have been adequately implemented and documented. In sunnary, CECO recognized that it was prudent to further demonstrate the quality of construction .
l at Braidwood. With the three elements described, CEC 0 believes that f this goal of providing additional verification will be obtained.
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Min.Braidwo:d Units 1 and 2 9 January 29, 1985 Me: ting i In response to a subcommittee question, W. Forney, Region III, stated j that the BCAP program has been reviewed and approved and that if the program is properly implemented, it should resolve the question of the quality of the construction at Braidwood. Region III is monitoring the program closely. Some deficiencies have been identified and the licensee has provided corrective actions in a timely manner.
Regarding postulating of arbitrary intermediate pipe breaks, the NRC Staff has approved for Braidwood the concept that no arbitrary interme-diate pipebreaks in pipe run or branch line need be postulated if the values of stress and fatique calculations are within the code allowable limits. This means that some pipe whip restraints and jet shields or deflectors can be removed. The leak-before-break concept has not yet been approved by the NRC Staff for Braidwood.
A closed session on physical plant security was presented.
The subcommittee recommended that the Braidwood OL application be reviewed by the full ACRS during the February 1985 meeting.
NOTE: 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 at cost from ACE - Federal Reports, Inc., 444 N. Capitol Street, Washington, D.C. 20001, Telephone (202) 347-3700.
- . _ . - _ _ . , _,_,,,y_.,. - - - - - -.- -.-, -- __--
ATTACHMENT A 1950 Federal Regi:ter / Vol. So, Nr. 9 / Mondly, Jrnunty 14, 1985 / Notices --
. TeCi final determination will serve to decide supplemental petitions and/or requests During the initial portion of the the wh:n the hearing is held. for hearing will not be entertained meeting, the Subcommittee, along with in v If the final determination is that the absent a determination by the any ofits consultants who may be The anindment request involves no Commission, the presiding officer or the present, will exchange preliminary anc significant hazards consideration, the Atomic Safety and 1.icensing Board views regarding matters to be ind
. Commission may issue the amendment designated to rule on the petition and/or considered during the balance of the nor cnd make it effective, notwithstandmg request, that the petitioner has made a meeting. pur th2 request for a hearing. Any hearing substantial showing of good cause for The Subcommittee will then hear exe h:ld would take place after issuance of the granting of a late petition and/or presentations by and hold discussions gy, tha amendment. request.That determination will be with representatives of the ,o, If the final determination is that the based upon a balancing of the factors Commonwealth Edison Company, the cmendment involves a significant NRC Staff, their consultants, and other Joh specified in 10 CFR 2.714(a)(1) (i)-(v) an Off h:zards consideration, any hearing held 2.714(d). invited persons regarding this review.
w:uld take place before the issuance of 2%
For further details with respect to this Further information about topics to be Ger cn amendment. action, see the applir:ation for discussed, whether the meeting has Normally, the Commission wiB not amendment which I available for public been cancelled or rescheduled, the issue the amendment until the inspection at the Commission's Public Chairman's ruling on requests for f"3 p,a expiration of the 30-day notice period. Document Room.1717 H Street NW opportunity to present oral statements H: wever, should circumstances change y, Washington, D.C., and at the Crystal and the time allotted therefor can be 339 during the notice period such that failure River Public 1.ibrary,668 N.W. First obtained by a prepaid telephone call to 12 cet in a timely way would result, for Cor Avenue, Crystal River, Florida. the cognizant ACRS staff member, Mr.
cxample,in derating or shutdown of the Elpidio G. Igne (telephone 202/634-1414)
,I, f;cility, the Commission may issue the Dated at Bethesda.' Maryland, this adi day between 8:15 a.m. and 5100 p.m., EST.
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or N at Regulatory Commission.
rso an o en m 8 x ratio o e ay o ce period, a przvided that its final determination is George W. IUvenba&*
individual one or two days before the ,
that the amendment invoives no significant hazards consideration. %e actin, cai,f. o,emtin, a,oc ,s omnca uo.
- d. Division ofLicensin,.
,cs,aoi,a m,, tin,,o be advisea or any gi-changes in schedule, etc., which may final determination will consider aD [FR Doc. 85-1041 Filed 1-11 a5. a45 am) have occurred.
public and State comments received. os m a coes mas.es.as "*'
Deted: [anuary 9.1985., suit Sh:uld the Commission take this action.
it will publish a notice of issuance and Morton W. IJhesia, Pea provide the opportunity for a hearing Advloory Committee on Reactor Assistant Executive Directorfor Project coll rfler issuance. The Commissi - expects Safeguards, Subcommittee on Review. Inic th:t the need to take this action w.!! Braidwood Station; Meeting [FR Doc. 85-1042 Filed 1-11-85r. s.45 am) cha occur very infrequently, same caos rose.es.m cov A reques' for a hearing or a petition he ACRS Sobcommittee on in v for leave to intervene must be filed with Braidwood Station will hold a meeting rett the Secretary of the Commission. U.S. on January 29,1985, Room 1046,1717 H use p
Nuclear Regulatory Commission, Street, NW, Washington. DC. E Washington, D.C. 20555. Attentiam The meeting will be for the most part Cor Compilance With Privacy Act of 1974 Docketing and Service Branch, or may open to public attendance. Ilowever, a Pric be delivered to the Commmission's portion of the meeting will be closed to Aotwev: Peace Corps. par Public Document Room.1717 H Street, discuss plant security relating to the AcTiose Notice of Adoption of Systems C8' NW., Washington, D.C., by the above Braidwood Station. of Records. * 8' date. Where petitions are filed during The agenda for subject meeting shall OfI th21est ten (to) days of the notice be as follows: sunsasAny: Notice is hereby given that in now Rec period. it is requested that the petitioner Tuesday, January 29,1E 8:30 a.m. util accord with 5 U.SsC. 522a(e)(4), Sec. 3 of promptly so inform the Commission by a the Privacy Act of1974 (hereinafter T to!!. free telephone call to Westem e c nc usi n f business referred to as the "Act"). Peace Corps is D.C Union at (800) 325-6000 (in Missouri The Subcommittee wiD continue to adopting the notice of systems of Im (800) 3424700). %e Western Union review the Commonwealth Edison records as set forth below. Diri cperator should be given Datagram Company's application for an operating This notice does not include specific p Id;ntification Number 3737 and the license for the Braidwood Station. identification of Office of Personnel not following message addressed to John F. Oral statements may be presented by Management (OPM) records in the Stolz: petitioner's name and telephone members of the public with the custody of Peace Corps. OPM has Not number; date petition was mailed; plant concurrence of the Subcommittee assumed responsibility for publishing Pre name; and pubhcation date and page Chairman; written stateaments will be government. wide notices pertaining to . *]
number of this Federal Register notice. accepted and made available to the Federal employee personnel records. not A copy of the petition should also be Committee. Recordmgs will be permitted Special note should be taken of the C sent to the Frarttive IJgal Dtrector, only during those portions of the Preliminary Statement to the systems of
- ope U.S. Naclear Regulatory Commissson, meeting when a transcript is being kept. records. It contains an Indication of wh Washington, D.C. 20555, and to R. W. and questions may be asked only by general routine uses, general procedures per N:Iser. Senior Vice President and members of the Subcommittee,its as to notification, access and contest. ma C:neral Counsel, Florida Power consultants, and Staff. Persons desiring and other information applicable to sys Corporation. P.O. Box 140042. St. to make oral statements shouki notify Peace Corps records systems generally. (
PetIrsburg, Florida 33733. the ACRS etaff member named below as Peace Corps desires to avoid per Nontimely filings of petitions for leave far in advance as practicable so that unnecessary repetition and duplication the to.innervene, amended petitions, appropriate arrangements can be made, in the publication of each system of J 6.
ATTACHMENT B .
? TENTATIVE SCHEDULE 0 ACRS BRAIDWOOD SUBCOMMITTEE MEETING ON BRAIDWOOD STATION UNITS 1 AND 2 JANUARY 20 1985 WASHINGTOF, D.C.
January 29. 1985 (8:30 a.m.-toendofbusiness) '
Tepic Presenter Time
- 7. Opening Statement C. Mark, Chairman 8:30 a.m.
' 8I. Report by NRC Staff 8:40 a.m.
A. NRR Discussion .
B. Region III Discussion EREAK (15 Min.)
C. I&E Discussion of 11:15 a.m.
( Construction Appraisal Team (CAT) Inspection Results
- 1. CECO Connents Wallace LUNCH (1 Hour) .
III. Presentations by Comonwealth Edison A. Principal Design Klopp 1:00 p.m.
Differences Between Braidwood and Zion B. Braidwcod Project Update
- 1. Overview of Plant Wallace 1:10 p.m.
and Startup Schedule ,
- 2. Management Changes Wallace 1:20 p.m.
- 3. Quality Assurance Fitzpatrick 1:30 p.m.
C. Issues Remaining Open
- 1. Braidwood Construction .Naiman . 2:00 p.,m. .
Assessment Program ,
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.. Braidwood-Jan. 29, 1985 Mtg~.
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(BCAP) Kaushel BREAK (15 Min.')
D. Physical Plant Se:urity W111aford 3:15 p.m.
(closedsession)
E. AC 3 Coments on Issues 3:30 p.m.
of Interest
- 1. Leak-Before-Break
- Ainger
- 2. Elimination of Ainger Intennediate Pipe Break *
. .F. ACRS Coments on Issues Resolved 3:45 p.m.
- 1. Byron ASLB Supplemetal Delgeorge Initial Decision *
(' 2. Circurtstances Wallace Surrounding Braid-wood Civil Penalty *
- 3. Effects of Cooling McDonough Lake Dike Failure
- G. Supplement the Record
- Wallace 4:15 p.m.
IV. Public Presentationr, if any 4:20 p.m.
V .- ACR5 Sub:omittee Caucus 4:30 p.m.
VI. Development of Agenda for ACRS Full Comittee on February 7 .
or 8, 1985 VII. Adjournment
- Comanwealth Edison will be prepared to address coments (if any) from ACRS on material submitted in advance of meeting.
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$. IGNE ATTACHMENT C BRAIDWOOD STATION UNITS 1 AND 2 __
ACRS SUBCOMMITTEE MEETING ON ROOM 1046,1717 H St. NW. Washjngton, D.C, L,0CATIOl:
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ACRS SUBCOMMITTEE MEETING ON ROOM 1046,1717 H St. NW. Washington, D.C,
. A0CATID:1:
January 29, 1985 DATE:
ATTENDANCE LIST PLEASE PRINT:
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ACRS SUBCOMMITTEE MEETING ON ROOM 1046,1717 H St. NW. Washington. D.C,
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ATTENDANCE LIST PLEASE PRINT:
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ATTACHMENT D HAND 0UTS PRESENTED AT THE ACRS SUBCOMMITTEE FOR BRAIDWOOD STATION UNITS 1 AND 2 JANUARY 29, 1985 WASHINGTON, D.C.
- 1. NRC Staff Presentation by Janice A. Stevens, Licensing Froject Manager.
- 2. NRC Construction Inspection Experience, W. Forney, Region III.
- 3. Letter from C. E. Worelius, Region III, to E. Igne, ACRS dated January 28, 1985.
- 4. -CEC 0's Advance Presentation Materials, dated January 18, 1985, consisting of the following topics:
. Leak-before-break criteria
. Elimination of arbitrary intermediate pipe break
. Report on Byron ASLB Supplemental Initial Decision
. Circumstances surrounding Braidwood Civil penalty
. Effects of cooling lake dike failure
. Supplement the record of the March 8 and 9, 1984 meeting with the ACRS Subcommittee on Braidwood
. . Braidwood training programs
. Human factors
. Off-site Emergency planning
- 5. CEC 0's Presentation to the ACRS Subcommittee on Braidwood Station Units 1 and 2 on January 29, 1985.
. Comments on I&E CAT inspection results
. Principal design differences between Braidwood and Zion
. Overview of plant construction and startup schedule ,
BraidwoodConstructionAssessmentprogram(BCAP),Mainman&
Kaushal
. Leak-before-break
. Report on Byron ASLB Supplemental Initial decision
- - - _ . _ - ___- _- .. _ _ _ -~ . . _ , .____-__ __._ ___.._ _ _. -
'~' 2 ATTACHMENT D, Paga 2
.. Circumstances surrounding Braidwood civil penalty
.- Effects of cooling lake dike failure
. Supplement the record
. Braidwood Training programs
. Off-site emergency planning O
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