ML20028C002
| ML20028C002 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/30/1982 |
| From: | Hernan R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8301050202 | |
| Download: ML20028C002 (15) | |
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c December 30, 1982 Docket Nos: 50-329 and 50-330 APPLICANT:
Consumers Power Company FACILITY:
Midland Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF MEETINGS HELD WITH CONSUMERS POWER DURING THE WEEK 0F MARCH 31, 1982, TO RESOLVE SER OPEN ITEMS On March 31 to April 2,1982, the NRC staff met in Bethesda, Maryland with Consumers Power Company, Bechtel, and Babcock & Wilcox to discuss resolution of open items prior to issuance of the Midland SER in May 1982. A list of meeting attendees is attached as Enclosure 1. is a detailed summary of the discussions held each day.
This summary was prepared by the applicant and has been reviewed by the staff for accuracy. is the agenda which was published with the meeting notice.
/S/
Ronald W. Hernan, Project Manager Licensing Branch No. 4 Division of Licensing
Enclosures:
As stated cc: See next page i E001050202 821230 PDR ADOCK 05000329 i
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MIDLAND-Mr. J. W. Cook Vice President Constaners Power Company 1945 West Parnall Road Jackson, Michigan 49201 cc: Michael I. Miller, Esq.
Mr. Don van Farrowe, Chief Ronald G. Zamarin, Esq.
Division of Radiological Health Alan S. Farnell, Esq.
Department of Public Health Isham, Lincoln & Beale P.O. Box 33035 Three First National Plaza, Lansing, Michigan 48909 Sist floor
- Chicago, Illinois 60602 Mr. Steve Gadler 2120 Carter Avenue James E. Brunner, Esq.
St. Paul, Minnesota 55108 Consumers Power Company 212 West Michigan Avenue U.S. Nuclear Regulatory Commission Jackson, Michigan 49201 Resident Inspectors Office Route 7 Ms. Mary Sinclair Midland, Michigan 48640 5711 Summerset Drive Midland, Michigan 48640 Ms. Barbara Stamiris 5795 N. River Stewart H. Freeman Freeland, Michigan 48623 Assistant Attorney General State of Michigan Environmental Mr. Paul A. Perry, Secretary Protection Division Consumers Power Company 720 Law Building 212 W. Michigan Avenue Lansing, Michigan 48913 Jackson, Michigan 49201 Mr. Wendell Marshall Mr. Walt Apley Route 10 c/o Mr. Max Clausen Midland, Michigan 48640 Battelle Pacific North West Labs (PNWL)
Battelle Blvd.
i Mr. Roger W. Huston SIGMA IV Building Suite 220 Richland, Washington 99352 7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. I. Charak, Manager NRC Assistance Project Mr. R. B. Borsum Argonne National Laboratory Nuclear Power Generation Division 9700 South Cass Avenue Babcock & Wilcox Argonne, Illinois 60439 l
7910 Woodmont Avenue, Suite 220 Bethesda, Maryland 20814 James G. Keppler, Regional Administrator U.S. Nuclear Regulatory Commission, Cherry & Flynn Region III Suite 3700 799 Roosevelt Road Three First National Plaza Glen Ellyn, Illinois 60137 Chicago, Illinois 60602 1
Mr. J. W. Cook 2-cc: Lee L. Bishop Harmon & Weiss 1725 I Street, N.W., Suite 506 Washington, D. C.
20006 Mr. Ron Callen Michigan Public Service Canmission 6545 Mercantile Way P.O. Box 30221 Lansing, Michigan 48909 Mr. Paul Rau Midland Daily News 124 Mcdonald Street Midland, Michigan 48640 Billie Pirner Garde Director, Citizens Clinic for Accountable Government Government Accountability Porject Institute for Policy Studies l
1901 Que Street, N.W.
l Washington, D. C.
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Enclosura 1 LIST OF ATTENDEES March 31'- April 2, 1982 NRC CONSUMERS POWER CO.
R. Hernan T. Sullivan
- R. Kirkwood D. Perry
- J. Bransner
- B. Cloutier
- J. Rajan
- T. Thiruvengadam
- B. LeFave
- T. Hollowell
- W. Jensen
- L. Gibson
- S. Wu
- J. Webb
- J. Holonich R. Huston
- R. Meyer
- N. Leech
- k. Lobel
- P. Hearn
- F. Pagano J. Mathis
- R. VanNiel BECHTEL BABCOCK & WILCOX D. Sullivan F. Levandoski H. Fontecilla R. Griese D. Lewis R. Borsum R. Schomaker Part-time Attendees e
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ENCLOSURE 2 CONSUMERS POWER COMPANY Meeting Summary March 31 - April 2, 1982 Bethesda, Maryland During the period March 31 through April 2, 1982, the NRC staff met in Bethesda, Maryland with Consumers Power Company (CPCo) Bechtel, and Babcock &
Wilcox to discuss the potential outstanding open items for the Midland SER.- A list of meeting attendees is attached as Enclosure 1.
Each portion of the meeting was opened by stating the meeting purpose, and noting that while draft SER sections have been compiled, they will not be formally issued.
In addition to open items in the draft SER sections, the open items in the March 30, 1979 NRC letter (Varga letter) to CPCo were covered.
Many of the Varga items have been closed by virtue of updated information provided since 1979, however such closure has not yet been officially documented.
1 CPCo prepared an open items list from (a) issues identified in draft SER sections, (b) the NRC March 30,1979 -letter (containing open items), and (c) areas where the review is known to be incomplete. The list was prepared in a format consistent with the format normally used by the staff. The purpose of the meeting was (a) to ensure issues were properly classified..(b) to determine the latest status as determined by the reviewer, and, (c) to provide additional information as appropriate. The change in status for numerous items reflects information and work performed since the draft SER sections were prepared.
(In many cases additional information had been formally submitted by CPCo since the draft SER sections were prepared.)
In addition, entries in the open items list which are solely cross-references, are deleted where this could be done without creating confusion.
It should be noted that items classed as " tentatively closed" are shown as open item until closure is confirmed by the project manager.
l The below abbreviations are used in this summary:
l l
01 open issue in draft SER section 1.7 CI confirmatory issue in draft SER section 1.8 ASB-1 open issue, identified by Branch, in NRC March 30, 1979 letter to CPCo A.
SER Chapter 3 Meeting, March 31, 1982 The following items were addressed with the Mechanical Engineering Branch:
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l 1.
Bechtel described the component cooling water system, which, as modified after TMI, provides one train of safety grade cooling to each reactor coolant pump. The system is considered acceptable in SER section 9.2.2.
The reviewer indicated that he would revise section 4
3.2.1 to agree with 9.2.2 upon receipt of revised FSAR section (including Table 3.2-1).
2.
Section 3.1 addressing conformance with CDC and other regulations is missing. The project manager indicated that he will assist the reviewer to write this section.
3.
OI Provide assurance that pipe whip restraint design did not exceed a 10 percent increase in minimum yield strength (SER Section 3.6.2).
The reviewer indicated that he does not consider BC-TOP-9 applicable to pipe whip restraint design and that NRC criteria are still based on BN-TOP-2 and ANSI standards. He also indicated that the Structural Engineering Branch considers an increase of 20% on the material yield strength is required to be acceptable. He indicated that acceptance of the 20% increase would necessitate a change to the Branch Technical Position and would need to be justified in the SER. CPCo and Bechtel representatives explained why BC-TOP-9 is considered applicable, and provided copies of papers by Bodner and Symonds in support of this position.
The issue remains open.
4.
OI Postulate breaks at branch connections (3.6.2).
Agreement on this section was previously reached and the current reviewer indicated that he would close the issue if appropriate documentation is provided.
CPCo was asked to provide a letter documenting meetings and telecons reflecting agreements reached with NRC staff.
5.
OI Provide LOCA and jet impingement (3.6.2).
Results of analyses are to be submitted in April 1983. This item is considered j
confirmatory.
l 6.
OI Update stress intensities in FSAR section 3.6 (3.6.2).
The necessary FSAR update is expected by May or June 1982. This item is considered confirmatory.
7.
Part of 0I Provide additional seismic subsystem analysis information (3.7.3), dealing with significant modes used in seismic analysis. The applicant indicated that all significant modes have been considered, although this is not explicitly stated in the FSAR. A forthcoming FSAR revision will clarify this. This item is tentatively closed.
8.
Part of 01-10 dealing with ME-101 (3.7.3).
Bechtel indicated that ME632 is no longer used, and all references to it will be deleted from the FSAR. They also made the verification of ME101 available for inspection during the meeting. This item is tentatively closed, pending verification that ME101 has been benchmarked by the NRC.
9.
Part of 01-10 dealing with Regulatory Guide 1.92 (3.7.3).
This issue was discussed in a November 19, 1982 telecon and is pending resolution by the staff.
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The applicant indicated that Regulatory Guide 1.92~is not used in the design of the plant but it will be applied to all systems undergoing reanalysis. The reviewer expressed his concern that the reanalysis will not cover a sufficient number of safe shutdown systems.
This issue is to remain open.
It will become confirmatory upon NRC acceptance of the seismic reanalysis program.
- 10. 01-10 dealing with the seismic reanalysis of buried pipes (3.7.3).
This item remains open pending resolution of the soils settlement issues.
11.
Part of OI-10 dealing with the interaction between Category 1 and non-Category 1 pipes (3.7.3).
The NRC staff indicated that ETEC has completed their review. This item is closed.
12.
Part of Section 3.9.1 dealing with confirmatory piping. The reviewer indicated that this issue would not be kept open pending the as-built drawings. This item is considered confirmatory pending results of the i
analyses.
- 13. OI Clarify the dynamic analysis methods used on major reactor coolant loop components (3.7.3).
It was agreed to. incorporate open items 11, 17 and 41, and Varga items MEB-4 asymmetric cavity loads, and MEB-5, review of reactor internals for LOCA plus SSE, and CSB-3, reactor cavity subcompartment analysis into open item 9.
These items are considered confirmatory pending the results of the dynamic analyses expected to be available by 1983.
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- 14. 0I Discuss integrity / operability of Class l',
2, and 3 item related i
to soils settlement (3.9.3, Items 1-6).
It was agreed to incorporate I
open items 18 and 62, PSB-3 (Diesel Generator building settlement),
l SEB-1 (Loading combinations for settling seismic category 1 structures), and SEB-3 (Adequacy of Category 1 structures to ACI-318 Code) into 01-12.
Review of these issues is not complete. This item is to remain open.
15.
01 Upgrade FSAR Tables 3.9-1 and 3.9-3b (3.9.3).
This item is closed.
16.
MEB-8, Regulatory Guide 1.121, is closed.
17.
MEB-2, Qualification of 18 inch containment purge valves, is closed.
- 18. 01 Describe SI system check valve full-stroke test (3.9.6), is closed.
- 19. 01 Revise low pressure system isolation valve leak testing (Technical Specification) (3.9.6), is closed.
- 20. 01 Justify stress values in FSAR Tables 3.9-9, -10. -11, -15, is closed.
21.
Part of Section 3.6.2 addressing pipe break freeze criteria.
This issue was not addressed in the old version of the SRP.
It is not applicable to Midland, and it is not considered an opcn item.
22.
Part of section 3.13 dealing with seismic anchor power motion is closed.
23.
Part of'section 3.9.3 dealing with bolting acceptance criteria is closed.
24.
MEB-9, Bolt and baseplate design. The staff is to check whether the response to I&E Bulletin 79-02 adequately covered the concerns in MEB-9.
This item is tentatively closed.
25.
MEB-1, Seismic qualification of equipment, is to be covered under the 4
seismic qualification review, outstanding item 16.
l 26.
MEB Finite break times and limiting break areas, dealing with elastic plastic analysis was addressed in a separate meeting. This item is tentatively closed pending review of the meeting minutes.
27.
MEB-3, Qualification of active safety / relief valves, is closed.
28.
MEB-7, Inservice testing of pumps and valves,' is closed.
In addition, the following Auxiliary Systems Branch items were discussed with the reviewer:
1.
OI Perform subcompartment environmental analysis (3.6.1).
This item is closed, but the applicant needs to provide the NRC with information describing assumptions made in the calculations.
2.
ASB Protection against postulated pipe breaks outside containment, is closed.
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B.
SER Chapter 5 (except 5.2.3, 5.2.4, 5.4.1, 5.4.2, and 5.4.3),
I Chapter 6 (except 6.1, 6.4, 6.5 and 6.6),
Chapter 9 (except 9.5), and Section 10.4.9 Meeting, April 1, 1982.
1.
OI Revision to reactor vessel pressure-temperature limit curve 1
(5.2.2, 5.3.2, 5.3.3) is closed although the final figure may be revised.
(This is the same as RSB-9).
2.
OI RCS safety valve sizing calculations (5.2.2), is closed.
(This is the same as RSB-1.)
3.
OI Justify use of DYSID code (5.2.2), is closed.
4.
OI Applicability of POWER TRAIN code (5.2.2), is closed.
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5.
CI Verify CADDS code using startup data (5.2.2), is closed.
l 6.
01 Discuss manual action outside of control room including DHR Valves (5.4.7) remains open, and it will be the subject of management meetings.
7.
0I-31, 32, 33, 72 - Provide boron mixing calculations for cooldown (5.4.7), provide natural circulation calculations for cooldown (5.4.7),
provide details of natural circulation test (5.4.7), and natural
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circulation testing / training (14.2) (this covers RSB-7) are combined into two confirmatory items.
8.
01 Commit to boron mixing test during natural circulation (5.4.7),
is closed.
9.
RSB Pressurizer heaters, is closed.
10.
01 Provide reactor coolant system high point vents (5.4.12) will be included with 01-68 (Implement Emergency Operating Procedures based on ATOG (13.5.2)). The operating procedures review will determine if the vent system meets the required functions.
11.
01 Provide details of main feedwater overfill protection system (5.5.6), will be a confirmatory item to provide an analysis of the effects from overfill protection system operation.
12.
01 Provide details of auxiliary feed system level control (5.5.3).
The requirement to provide the test results may be a license condition.
13.
01 Modify HPI system to eliminate operator action following LOCA
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(6.3.3), is closed.
14.
RSB Small Break ECCS analysis, is closed.
15.
RSB Burnable poison rod and orifice rod modifications, is closed.
16.
RSB Initial RC flow for LOCA analyses, is closed.
17.
RSB Containment sump test, is closed.
18.
RSB Passive failt re af ter LOCA, is closed.
19.
RSB Dump-to-sump design, is closed.
20.
AAB Post-LOCA passive failures, is closed.
21.
RSB Check valve leak testing, will be included with SER section 3.9.6.
j 22.
RSB Auxiliary feedwater level control, is closed.
23.
RSB Worst case MSLB accident, is closed.
24.
RSB-6 Process steam operating modes, is closed.
25.
RSB Missile protection inside containmer.t. is closed.
l 26.
01 Provide information on light load handling (9.1.4), is closed.
27.
CI Implement actions for control of heavy loads (9.1.4).
This may be a license condition.
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- 30. ASB Auxiliary area ventilation system and engineered safety area ventilation system, is closed (This includes ETSB-4).
31.
AAB Turbine missile hazard.' CPCO will submit a report which will include taking credit for some items being protected by virtue of low i
tornado probability. A further meeting on the approach and progress is planned for around April 15, 1982. This item remains open.
- 32. CSB Main steam line break analysis for containment evaluations, is closed.
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- 33. CSB External containment pressure analysis, is closed.
, 34. OI Provide information on flow resistance of steam generator compartment fan openings (6.2.1), is a confirmatory item.
- 35. 01 Provide loads and moments on major components (6.2.1).
This will be included with 01-9 (Clarify the dynamic analysis methods used on major reactor coolant loop components (3.7.3)).
36.
01 Provide information on containment purge / vent system (6.2.4),
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is a confirmatory item.
37.
01 Provide information on local leakage test of purge / vent system valves (6.2.6), is a confirmatory item.
38.
0I Discuss open duration of containment mini-purge valves (6.2.4),
t is closed.
39.
01 Discuss large volume containment purge valve closed verification (6.2.4), is closed. This will be in the technical specifications.
40.
01 Justify not performing local tetts on secondary containment isolation valves (6.2.6) is confirmatory as the staff review of applicant's information is not complete.
41.
01 Evaluate justification for not testing (Type C) DHR and RBCC system valves (6.2.6), is a confirmatory item.
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42.
01 Categorize systems penetrating containment as essential /non-essential (6.2.4), is confirmatory as the staff review of applicant's information_is not complete.-
C.
SER Chapter 4 (except 4.5) and Chapter 15 Meeting, April 1, 1982.
1.
01-22, Demonstrate compliance with NUREG-0630 (4.2), is confirmatory because this supplemental ECCS calculation will have to be verified with the approved version of TACO-2 when the staff review is completed.
If ~ no additional calculations are subnitted, the ECCS limits will be based on a 13.5 kw/ft THETA calculation.
2.
CPB(F)-1, Asymmetric loads will be included with 01-9.
3.
CPB(F)-2, Guide tube wear, is closed.
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l 4.
CPB(F)-3, Pellet / cladding interaction, is closed.
5.
CPB(F)-4, 1 percent cladding strain, is closed.
6.
CPB(F)-5, Thermal analysis and fuel performance code, is closed.
7.
CI-2, Complete review of CHATA code (4.4.2.1), is closed.
8.
CI-3,. Provide additional information on core stability (4.4.2.4), is closed based on information recently provided by CPCo. The existing SAR response will be amended.
9.
CI-5, Demonstrate the effects of crud on assembly lif t forces t
(4.4.3.2), is closed.
10.
CI-4, Proposed measures of offset DNBR reduction due to rod bow (technical specification) (4.4.3.1), is closed. The SER will include the staff calculated reductions.
11.
CI-6, Loose parts monitoring system (technical specification)
(4.4.4.2), is closed.
12.
0I-23, Resolve inadequate core cooling instrumentation (4.4.4.1),
remains open. CPCo noted the design effort is ongoing, and additional information is to be submitted in September 1982.
13.
01-24, Operation with less than four reactor coolant pumps (staff review) (4.4.5), which covers RSB-24, is closed. The technical specification will include specific conditions for operation with less than four reactor coolant pumps.
14.
RSB-12 is closed (see B-15 above).
15.
01-76, complete review of B4W-1461 on rod worth (staff) (15.1), is closed.
This covers RSB-22.
l 16.
OI-77, Provide information on the use of TRAP-2 code (15.1), is closed.
This covers RSB-19 and RSB-23.
l 17.
OI-78, Complete review of BWKIN code (15.2), is close'd.
18.
01-79, Demonstrate acceptable DNBR following double-ended steamline break (15.2), is closed.
19.
RSB-18, Steamline break analyses, is closed.
20.
01-80, Resolve questions on loss of feedwater event (15.2.7), is l
confirmatory. The staff requested additional information on how steam generator inventory is determined. Operating experience should be included.
21.
01-81, Analysis of loss of flow transients involving only one RCP (15.3.1), is confirmatory.
22.
PSB-5, Crid frequency decay effects on RC pumps, is closed.
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23.
01-82, Analyze RCP locked rotor / sheared shaft with turb(ne trip and
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loop (15.3.3), is a confirmatory item.
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1 24.
RSB-3, Boron dilution transient, is closed.
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RSB-24 SG tube failure will be a new confirmato'ry item to confirm the mass release.
The FSAR will be modified.
a-26.
01-83 Provide additional information on PORV isolation (5.4.10)', is' closed.
SER, and the open item is dropped. The issue is under generic review for all PWRs.
s 28.
01-87, Sequential loss of AFW analysis (15.5), is closed.
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01-88, Small break LOCA Model (15.6.5) is a generic item, and
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reasonable progress is being made. The status of the issue is to be determined.
30.
RSB-6, Process steam operating modes, is closed.
31.
RSB-20, long-term cooling after MSLB, is closed.
- 32. RSB-21, Operator action after MSLB, is closed.
- 33. RSB-28, ATWS is closed.
D.
SER Sections 3.7 and 3.8 Issues Meeting, April 2,1982 1.
The open item in section 3.7 designated also as SEB-4, Floor response spectra, should be referenced to section 3.7.2.
This item is closed.
2.
The open item in section 3.7 designated also as SEB-5, Piping seismic analysis, should be assigned to MEB rather than SEB.
This item is considered closed.
3.
The open item in section 3.8.1 designated also as SEB'-2, Adequacy of containment using ACI 359 loads, is considered closed.
4.
The open item in section 3.8.3 designated also as SEB-3, Adequacy of Category I structures to ACI-318 code, is considered closed.
5.
SER section 5.2.3 is inappropriately assigned to SEB.
It should be assigned to MTEB.
E.
Midland Site Emergency Plan Meeting April 2, 1982.
Representatives of CPCo met with the Emergency Planning Licensing Branch to discuss the status of review of the Midland Site Emergency Plan. The review is essentially completed, but the results have not yet been written and reviewed. The status of the review will be reflected in the SER, however
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I the det' ailed eva'luation of the plan will not be available until the SSER.
7 This input should be available to support issuance of the SSER in June.
N-Some, implementing-procedures, or summaries thereof, will be required to Q
cosplete the review. The staff agreed to provide a list of the necessary procedures which'CPCo will attempt to provide as quickly as possible.
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, l s NRC has#ask d th'e' Federal Emergency Management Agency for an interim finding regarding offsite emergency planning by July.30, 1982. To support this, the
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local (county) emergency plans will have tokbe submitted earlier than now
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pinnned.CPCo agreed to attempt to expedite this submittal. The most
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for NRC information at this meeting.
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Eie staff agreed to' prepare an input for the SER which will reflect the extent of detailed information CPCo has submitted to date. A meeting will q ;be held in 2 to 3 weeks *th discuss the substantive results lf 4
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ENCLOSURE 3 MIDLAND SER OPEN. ITEMS MEETING AGENDA March 31 10:30 a.m. - 3:30 p.m.
SER Chapter 3 NRCPartipipants CPCo Participants R. Kirkwood D. Perry B. LeFave B. Cloutier J. Schiffgens T. Thiruvengadam J. Brammer T. Sullivan J. Rajan R. Hernan 3:30 p.m. - 4:00 p.m.
SER Treatment of : oils issues NRC Participants CPCo' Participants P. Kuo T. Thiruvengadam R. Hernan April 1 8:30 a.m. - 4:00 p.m.
SER Chapters 5 (except 5.4.1, 5.4.2, 5.4.3, 5.2.3,5.2.4),
6 (except 6.1, 6.4, 6.5, and 6.6), Chapter 9 (except 9.5), Section 10.4.9 (AFW)
NRC Participants CPCo Participants W. Jensen T. Sullivan B. Elliott L. Gibson, et. al.
W. LeFave P. Hearn B. Lee R. Hernan April 2 8:30 a.m. - 4:00 p.m.
SER Chapters 4 (except 4.5) and 15 NRC Participants CPCo Participants B. LeFave T. Sullivan W. Jensen L. Gibson, et. al W. Brooks A. Chu D. Power W. Brooks J. Holonich R. Hernan
f.r December 30, 1982 MEETING SUMARY DISTRIBUTION 4
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Local PDR NSIC PRC System LB #4 r/f Attorney, OELD E. Adensam Project Manager R. Hernan Licensing Assistant M. Duncan NRC
Participants:
R. Hernan R. Kirkwood J. Brammer J. Rajan B. LeFave W. Jensen S. Wu J. Holonich R. Meyer R. Lobel P. Hearn F. Pagano J. Mathis R. VanNiel d
bec: Applicant & Service List c
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