ML19345E753
"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.
| ML19345E753 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/15/1981 |
| From: | Birkel R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8102060018 | |
| Download: ML19345E753 (15) | |
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i Cccket Nos.:
50-369 yu b u u e/u% J dJL m
and 50-370 APf LICAfiT: Cuke Power Company FACILITY:
l'cGuire fluclear Station, Units I and 2 SUEJECT:
SUtWEY OF PEETING FELD ON JAfafARY C,1981 A recting vas held.with the arrlicant en January P,19P1 in Petbesda, Pd.
tc discuss surveillance requirements for piping syster snubbers as described in the preresed t'cCuire Technical specificatien 3/t. 7.8, " Snubbers, limiting Ccndition for Orcration". A list of attendees is sheen in Enclosure f?o.1.
The Frcrosed T.S. 3/4.7.8 was discussed in detail with the applicant and suitably revised to reflect the PcCuire design. Significant Ciscussien related to functional testing of snubbers and the sampling plan to be used for this testing.
It was acreed that a representative sample of each type of snubber shall be functicnally tested acccrding to Technical Specification Ficure 4.7.1 which includes acceptance and rejection criteria. On Technical Specification Figure d.7.1 "C" is the total number of snubbers found with locking velocity er bleed rate not recting the acceptance recuirements. The total number of snubbers tested is dencted by "f4".
At the end of each days testing, the new total values of f4 and C (previous day's tntal plus current day's increments) shall be plotted on Technical Specificaticn Ficure 4.7.1.
If at any time the point plotted falls in the "Peject" Pegien, all snubbers of that type shall be functionally tested.
If at any time the point plotted falls in the " Accept" region testing of that type of snubber shall be teminateri. When the point pictted lies in the " Continue Testing" region, additional snubbers shall be tested until the point falls in the " Accept" region or the "Peject" region, or all snubbers of that type have been tested.
The results of the discussion with the applicant till be included by the staff in the final technical specification. A draft of these Technical Specification is provided in Enclosure 2.
Origina13WW:
g ph A. Birkel P. A. Cirkel, Project Panager Licensing Franch flo.1 Division cf Licensing Erclosure:
(1) Attendance List Mreaft ennhher Jdhnical Srecifications ?/d.7.P
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OFFICIAL RECORD COPY
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.gcou meemcwcm 8102060 O\\
Mr. William O. Par ker, Jr.
Vice President, Ste.2m Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 cc: Mr. W. L. Porter Dr. Cadet H. Hand, Jr., Director Duke Power Company Bodega Marine Lab of California P. O. Box 2178 P. Q. Box 247 422 South Church Street Bodega Bay,-California 94923 Charlotte, North Carolina 28242 Richard P. Wilson, Esq.
Mr. R. S. Howard Assistant Attorney General Power Systems Division State of South Carolina Westinghouse Electric Corporation 2600 Bull Street P. O. Box 355 Columbia, South Carolina 29201 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith Office of Intergovernmental Relations 116 West Jones Street EDS Nuclear Incorporated Raleigh, North Carolina 27603 220 Montgomery Street San Francisco, California 94104 County Manager of Mecklenburg County 720 East Fourth Street Mr. J. E. Houghtaling Charlotte, North Carolina 28202 NUS Corporation U. S. Environmental Protection Agency 2536 Countryside Boulevard
=
Clearwater, Florida 33515 ATTN: EIS Coordinator Region IV Office Mr. Jesse L. Riley, President 345 Courtland Street, N. W.
The Carolina Environmental Study Group Atlanta, Georgia 30308 854 Henley Place Charlotte, North Carolina 28207 Mr.-Tom Donat Resident Inspector McGuire NPS J. Michael McGarry, III, Esq.
c/o USNRC Debevoise & Liberman Post Office Box 216 i
1200 Seventeenth Street, N. W.
Cornelius, North Carolina 28031 l
Washington, D. C.
20036 l
Shelly Blum, Esquire l
Robert M. Lazo, Esq., Chairman 1402 Vickers Avenue Atomic Safety and Licensing Board Durham, North Carolina 27707 I
U. S. Nuclear Regulatory Comission Washington, D. C.
20555
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Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Washington, D. C.
20555
ENCLOSURE NO. 1 ATTENDANCE LIST McGUIRE NUCLEAR STATION, UNITS NOS. 1 & 2 January 8, 1981 Duke Power Company D. M. Collings A. H. Shub K. S. Canady L. J. Bare L. M. Coggins Paul H. Barton W. i;. Keisler W. E. Smith NRC Staff R. A. Birkel R. J. Kiessel H. K. Shaw Keith Wichman Marty Virgilio David Vito David Rubenstein Ashok Thadani Adel El Bassioni W. Vesley p
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ENCLOSURE 2 PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERA 8LE.
APPLICABILITY: MODES 1, 2, 3, and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.
If less then two snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date.of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *#
0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3,4 124 days T 25%
5,6,7 62 days T 25%
8 or more 31daysi25%
The snubbers may be categorized into two groups: Those accessible i
and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.
"The inspection interval shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection may be lengthened one step the first time and two steps thereafter i
if no inoperable snubbers are found.
- The provisions of Specification 4.0.2 are not applicable.
McGUIRE - UNIT 1 14 1 JAN 141981
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows:
(a) At each refueling the main steam system (upstream of the main steam isolation valves) the main steam safety and power operated relief valves and piping, auxiliary feedwater system, main steam supply to the auxiliary feedvater pump turbine, and letdown and charging portion of the CVCS system shall be inspected to determine if there has been a severe dynamic event.
(b) In the event of a severe dynamic event snubbers in that system which experienced the event shall be inspected during the refueling outage to assure that the snubbers have freedom of moveme.-t and are not frozen up.
The inspection shall consist of verifying freedom of motion using one of the following:
(i) Manually induced snubber movement; (ii) evaluation of in place snubber piston setting; (iii) stroking the mechanical snubber through its full range of travel.
If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power.
Re-inspection shall subsequently be performed according to the schedule of 4.7.8(a), but the scope of the examination shall be limited to the systems listed above.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.8.d or 4.7.8.e, as applicable.
Hydraulic snubbers which have uncovered fluid ports shall be tested by starting with the piston at the as found setting and extending the piston rod in the tension mode direction.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
l c.
Functional Tests At least once per 18 months during shutdown, a representative sample
- of either (1) at least 10% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional l
test acceptance criteria of Specification 4.7.8.d or 4.7.8.e, an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers have been functionally tested.
"The requirements of this section for functionally testing mechanical snubbers may be waived until startup following the first refueling outage.
JAN 141981 McGUIRE - UNIT 1 3/4 7-20
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) or (2) A representative sample of each type of snubber shall be functionally tested in accordance with Figure 4.7.1, which includes acceptance and rejection criteria. On Figure 4.7.1, "C" is the total number of snubbers found with locking velocity or bleed rate or drag force (if applied) not meeting the acceptance requirements.
The cumulative number of snubbers tested is denoted by "N".
At the end of each day'r testing, the new values of "N" and "C" (previous day's total plus current day's increments) shall be plotted on Figure 4.7.1.
If at any time the point plotted falls in the " Reject" region all snubbers of that type shall be functionally tested.
If at any time the point plotted falls in the " Accept" region testing of that type of snubber shall be terminated. When l
the point plotted lies in the " Continue Testing" region, additional snubbers shall be tested until the point falls in the " Accept" i
l region or the " Reject" region, or all the snubbers of that type have been tested.
i The representative sample selected for functional testing shall include the various configurations, operating enviror,ments and the range of size and capacity of snubbers. The representative sample shall be selected randomly from the total population identified in Tables 3.7-4a and 3.7-4b.
Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample." Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period.
Test results of these snubbers shall not be included in the sampling plan.
If any snubber selected for functional testing either fails to lockup oc fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the_same defect shall be functionally i.asted. This testing requirement snall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
I Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
l JAN 141981 McGUIRE - UNIT 1 3/4 7-21
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
l Mechanical Snubbers Functional Test Acceptance Criteria e.
The mechanical snubber functional test shall verify that:
1 1.
The force that initiates free move !nt of the snubber rod in either tension or compression is less than the specified maximum drag force.
Drag force shall not have increased more than 50 percent since the last surveillance test.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3.
Snubber release rate, where required, is within the specified I
range in compre'ssion or tension.
For snubbers specifically required not to displace under continuous load, the ability of,
the snubber to withstand load without displacement shall be verified.
f.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and main-tenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.
McGUIRE - UNIT 1 3/4 7-22 JAN 141981
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the ir:tallation and mainenance records for each snubber listed in Ta5Jes 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been excerded or will not be exceeded by more than 10% prior to the next e
scheduled snubber service life review.
If the indicated service life will be exceeded by more than 10% prior to the next scheduled snubber service life review, the snubber service life shall be reevalunted or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.
The results of the reevaluation may be used to justify a change to the service life of the snubber.
This reevaluation, replacement or reconditioning shall be indi',ated in the records.
McGUIRE - UNIT 1 3/4 7-23 JAN 141981 i
n v
10 9
8
/
REJECT j
s Gj
/
m-
/
3
/
2
-t-ACCEPT 2
0 10 20 30 40 50 00 70 80 90 100 N
FIGURE 4.7.1 5AMPLING PLAli FOR SUNBBER FUNCTIONAL TEST McGUIRE - UNIT 1 3/4 7-23a JAN 141981
rT TABLE 3.7-4b e
SAFETY RELATED MECHANICAL SNUBBERS
- HIGH RADIATION 5
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT Q
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
The list of Safety Related Mechanical Snubbers will be incorporated into these Technical Specifications prior to commencing POWER OPERATION.
M a
Y$
" Snubbers may be added to safety related systems without prior license Amendment to Table 3.7-4b provided that a revision to Table 3.7-4b is included wi ;i the next ',icense Amendment request.
l
- Modifications to this column due to changes in high radiatic9 areas may be without prior License L
Amendment provided that a revision to Table 3.7-4b is included with the next License Amendment request.
=
>+
1 5
USb
+
PLANT SYSTEMS BASES STANDBY NUCLEAR SERVICE WATER POND (Continued) exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.
3/4.7.6 CONTROL AREA VENTILATION SYSTEM The OPERABILITY of the control area ventilation system ensures that
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A of 10 CFR 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/L.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM (ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM)
The OPERABILITY of the auxiliary building filtered exhaust system ensures that radioactive materials leaking from the ECCS equipment within the auxiliary huilding following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calcu-lations was assumed in the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies -inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time intervr.i has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
L McGUIRE - UNIT 1 8 3/4 7-4 g i 4 gg
PLANT SYSTEMS BASES STANDBY NUCLEAR SERVICE WATER POND (Continued) exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.
3/4.7.6 CONTROL AREA VENTILATION SYSTEM The OPERABILITY of the control area ventilation system ensures that
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rat'ng for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A of 10 CFR 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM (ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM)
%e OPERABILITY of the auxiliary building filtered exhaust system ensures th'.i. radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment.
The operation of ibis system and the resultant effect on offsite dosage calcu-lations was assumed in the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related Systems is main-tained during and following a seismic or other erent initiating dynamic loads.
Snubbers excluded from this inspection program are thosv installed on non-safety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new referent.e point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previcus schedule.
McGUIRE - UNIT 1 B 3/4 7-4 g i 4 193j
l PLANT SYSTEMS i
BASES f
STAN0BY NUCLEAR SERVICE WATER POND (Continued) exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear 5
Plants," March 1974.
3/4.7.6 CONTROL AREA VENTILATION SYSTEM The OPGABILITY of the control area ventilation system ensures that
- 1) the amt.ient air temperature does not exceed the allowable temperature for continuots duty rating for the equipment and instrumentation cooled by this system aad 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A of 10 CFR 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM (ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM)
The OPERABILITY of the auxiliary building filtered exhaust system ensures that radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calcu-lations was assumed in the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers.found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsec.
(nominal time.less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previou schedule.
McGUIRE - UNIT 1 B 3/4 7-4 g i 4 1981
PLANT SYSTEMS j
BASES 1
i 1
SNUBBERS (Continued)
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically suscestible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mef>. of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation o.,the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at'18-month intervals.
The sample size will be determined in accordance with Figure 4.7.1 which has been developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan. Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).
The requirement to monitor the snubber service life is included to l
ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical l
bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended l
to affect plant operation.
l l
McGUIRE - UNIT 1 B 3/4 7-5 JAN 141981 l
n.~~
......' d MEETING
SUMMARY
DISTRIBUTION G. Lear NRC PDR V. Noonan local PDR S. Pawlicki TIC /NSIC/ Tera V. Benaroya NRR Reading Z. Rosztoczy LB#1 Reading W. Haass H. Denton D. Muller E. Case R. Ballard D. Eisenhut W. Regan R. Purple D. Ross B. J. Youngblood P. Check A. Schwencer R. Satterfield F. Miraglia
- 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Vollmer W. Kreger J. P. Knight R. Houston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager R. Birkel W. Johnston Attorney, OELD J. Stolz M. Rushbrook S. Hanauer OIE (3)
J. Gammill ACRS (16)
T, Murley R. Tedesco F. Schroeder N. Hughes D. Skovholt M. Ernst NRC
Participants:
R. Baer C. Berlinger W. Vesley K. Kniel R. J. Kiessel G. Knighton H. K. Shaw A. Thadani Keith Wichman D. Tondi Marty.Virgilio J. Kramer David Vito D, Vassallo David Rubenstein P. Collins Ashok Thadani Adel El Bassioni D. Ziemann bec: Applicant & Service L'et i
a