ML20205C640
| ML20205C640 | |
| Person / Time | |
|---|---|
| Issue date: | 03/25/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-870320, NUDOCS 8703300226 | |
| Download: ML20205C640 (15) | |
Text
Rv DbR e
i March 25, 1987 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 20, 1987 A sumary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
General Counsel-F*
International Programs G
State Programs H*
Resource Management I*
Analysis and Evaluatien of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Special Projects L*
Regioral Offices M*
CRGR Monthly Reports N*
Executive Director for Operations 0*
Items Addressed by the Comission P
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
external distribution)
- No input this week.
'1
. i. c
,s 8703300226 070325 T. A. Rehm, Assistant for Operations 4
RP PDR Office o' the Executive Director hJbKL for Operatiuns
Contact:
T. A. Rehm, ECO 492-7781
(
HIGHLIGHTS OF WEEKLY INFORMATION REPORT c,
yl P
o WEEK ENDING MARCH 20,1987 Q ;
s(4 South Texas Project Units 1 and 2 i,
5 At 22:03 hours on March 11, 1987 whenUnitIwasbeingcooleddownfromh the Hot Functional Test, a severe water hammer event occurred in the t
Residual Heat Removal System (RHRS) heat-exchanger, The primary system
was at 350*F and 350 psig. The test being conducted was a demonstration of the 50*F/hr cooldown rate. The procedure for the test required Component Cooling Water (CCW) flow to be established beford primary coolant entered
-the RHR heat-exchanger. The operator apparently missed a step in the procedure, causing the hot fluid flow before the CCW flow. The piping experienced two-phase flow and subsequent water hammer events. Several hangers were bent or broken. Leakage was observed in at least one flange connection. Part of the CCW piping shows deformation.
1 The applicant is conducting a detailed review,of the event. The NRC resident,
staff is performing the appropriate follow-up. At this point, it is not clear as to how long it will take to recover from the event.
t4 NIOSH Study of NFS Workers' Health Effects The NRC has received an interim report from the National Institute for Occupational Safety and Pealth (NIOSH) describing the results of a pilot study on health effects experienced by workers at Nuclear Fuel Services (NFS). The pilot study consisted of a questionnaire given to male workers with at least 20 years of employment at NFS and to guards and security workers with no
/
production experience. The questionnaire consisted of, The ouestions about kidney disease, including kidney stones, kidney or bladder infections, blood or protein in the urine, and other kidney problems.s Both production and non-production workers reported more frequent kidney stones', urinary tract infections, and blood in the urine than did the guards. The interin report recomends that a more definitive medical study be conducted to clarify the nature and J'
probable cause of the kidney problems observed. NIOSH is currently planning to convene a peer review group to evaluate the findings and make recorsnendations s'
for further action. NRC Region II is arranging for a briefing of NRC staff on a
the pilot study by the NIOSH principal investigator.
West Valley Demonstratfor Project Lawsuit
?
7 A letter submitted to the NRC on January 26,19P,7, by the law office of
+
Terranova, Seeger and Galeziowski has notified the NRC of the possibility of its being named in the current West Valley lawsuit. The basis for NRC's being.
)
named in the lawsuit is the definition of the term " transuranic waste" as used t in the West Valley Demonstration Project Act (P.L.96-368).
If NRC has redefined " transuranic waste." then NRC will be named in the lawsuit.
Small Fire et Lucas Heichts, Australia i
The Australian Embassy advised IP on Thursday thet a fire had occurred at the Lucas Heights Nuclear Research Laboratory near Sydney, resulting.
in the release of a small amount of radioactivity into the air.
(The amcunt was one-fourth of the approved weekly limit.) The fire occurred in a plastic filter in an area used to process redical isotopes (apart from the research reactor).
It burned itself out in less than one hour after workers sealed off the chamber. Althouah eight fire brigades responded, none were needed.
/
0FFICE OF ADMINISTRATION Week Ending March 20, 1987 I
t ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT r
s
/
STATUS OF REQUESTS it i Initial Appeal of Request Initial Decision Carryovers, 1986 170 53 Received, 1987 162 13 Granted 119 5
Denied 41 10 Pending 172 51 ACTIONS THIS WEEK l
Received Martin Siegel, Requests copies of all files regarding the 08-50 failure Bishop Liberman at the Salem nuclear power plant on February 25, 1983,
(
& Cook and all NRC inspections and other reports concerning (87-152) such inspections of Westinghouse or any affiliated company during the period January 1, 1978 to date.
1
(
Ken Bossong, Requests three categories of records related to imported i
Critical Mass goods poss'ibly contaminated as a result of the accident (87-153) at the Chernobyl nuclear power plant.
Lyle Graber, Requests a copy of the May 10, 1984 memo from R. Lemas N '
regarding NRC's position on application of Fitzpatrick NUS Corporation (87-154) y' exemption for spurious operation of high-low pressure interfaces.
Cecilia Staudt, Requests a copy of the technical proposal submitted by i
The Information Keyboard Connunications, Inc., for contract NRC-10-87-174.
People y
(87-155) f, Kennari Samet, Requests copies of (1) abstracts of FY86 SBIR Phase I A
The Small Business and Ptase li selectees and (2) a list of proposers for
/>
High Technology the FYS6 solicitation.
Institute (87-156) g; (NRCemployee)
Requests a copy of a specified investigation report (67-157) related to her allegations.
CONTACT: Donnie H. Grimsley 73 492-7211 7
f' l
ItARCH 20, 1987 ENCLOSUP.E A f
0 2
Received, Cont'd i
Carol Steinsapir, Requests copies of 0 ) the license issued to Radiac Hunter College
'Research Corporation, (2) any environmental impact (87-158)'
statement, and (3) 10 CFR Parts 19, 20, 32, and 71.
Joy Adams Requests copies of all NRC licenses issued to DuPont (87-159)
Corporation.
John Menz, Requests copies of records which pertain to testing and Simpson Tnacher evaluation of pressure suppression containments
& Bartlett conducted at the GKSS facility in West Germany.
(87-160)
Robin Miller, Requests a copy of the technical proposal submitted in Macro Systems, Inc. response to Solicitation No. RS-ADM-87-171.
(87-161)
Robin Miller, Requests a copy of contract No. NRC-10-87-171.
Macro Systems, Inc.
(87-162)
Granted Ophelia Williams, In response to a reqtiest for copies of communications J/R/A Associates generi.ted between the Commissioners and the.NRC staff (86-806) regarding environmental qualification for the time frame of 1934 through 1986, made available one record.
Informed the requester that additional records subject to this request are located in PDR file F01A-86-810.
Marguerite Hrebenach In response to a request for a copy of the proposal (86-815) submitted by Itasca Consulting Group in response to RFP RS-NMSS-85-002, made available a copy of the non-proprietary version of the proposal.
Janice Foster, in usponse to a request for records providing the names (86-892) of the bidders, the amount of their bids, and which bidder was awarded the contract for the Medical Services Program for Region IV employees, made available a copy of the requested record.
ushuc Jordon, In response to a request for three categories of records Critical Mass related to the Seabrook plant, made available three (87-43) records.
Informed the requester that 13 records subject to this request are already available at the PDR.
Robert Hallman, In response to a recuest for a copy of a March 1979 Cahill Gordon investigation report (78-154-A) by Region I, informed
& Reindell the requester that this record is already available (87-57) at the PDR in file F01A-79-490.
i MARCH 20, 1987 ENCLOSURE A
3 Granted, Cont'd Linda Bauman, In response to a request for records related to a Government October 30, 1986 letter from NRC to the utility regarding Accountability ataff evaluation of circuits for the Comanche Peak nuclear Project power plant, made available three records.
Informed the (87-62) requester that two records subject to this request are already available at the PDR.
Daniel Stenger, In response to a request for records relating to (1) plant-Bishop, Liberman, specific backfitting claims or appeals under Manual NRC-Cook, Purcell &
0514 regarding Safety Parameter Display Systems (SPDS),
Reynolds and (2) technical appeals by licensees or applicants (87-68) regarding SPDS, made available 12 records.
Informed the requester that 20 additional records subject to this request are already available at the PDR.
Joseph Cuthbert, In response to a request for copies of the abstracts for Advanced Technology the Phase I SBIR awards, made available copies of the Center of South-requested abstracts.
Eastern Pennsylvania (87-70)
William Shook, In response to a request for copies of seven categories Preston of records related to a contract awarded to the National Thorgrimson, Ellis Academy of Sciences, made available five records.
Informed
& Holman the requester that additional records subject to this (87-79) request are already available at the PDR.
R. Buckles, In response to a request for copies of (1) transcripts of January (31,1984, NUS Corporation Consission meetings on April 22, 1983,
- 2) the (87-110) and July 2, 1984, regarding Diablo Canyon and Secretary's November 4,1983 limited distribution memo regarding Diablo Canyon, made available a copy of item 2.
Informed the requester that no Commission meetings were held on the dates identified in item 1.
Joe Mendez In response to a reonest for a copy of a preliminary risk (87-117) analysis report on radioactive release at a plant based on studies at five plants, as noted in a February 18, 1967 article in the Seattle Post-Intelligencer, informed the requester that the requested report is already available at the PDR.
Sue Agnihotri.
In response to a request for the mailing list of EQES Inc.
recipients of the NRC's daily press releases, made (87-130) available the requested mailing list.
l MARCH 20, 1987 ENCLOSURE A
4 Granted, Cont'd Chui Yuen, In response to a request for copies of mailing lists Energy and for seven specified subjects, made available the.
Business requested mailing lists.
Newsletters (87-145)
Michael Minns, In response to a request for a list of byproduct material Attorney At Law licensees located in three specified counties in Ohio, (87-148) made available a copy of the requested record.
Denied David Repka, In response to a request for copies of all records Bishop, Liberman, interpreting or establishing policy regarding the Cook, Purcell &
notification requirement of 10 CFR 50./2 and 50.73, Reynolds specifically NRC guidance on the issue of timing of (86-729) required reports, made available 69 records.
Informed the requester that additional records subject to this request are already available at the PDR.
Denied three records in their entirety, disclosure of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Stephanie Murphy, In response to a request for three categories of records Nuclear related to issuance of a full-power operating license Information and for the Shearon Harris nuclear power plant, made available Resource Service 13 records.
Informed the requester that additional (86-843) records subject to this request are already available at the PDR.
Denied five records in their entirety and portions of one record, disclosure of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
John Harris, In response to a request for two categories of records Austin American-relating to the South Texas nuclear project, made Statesman available three records.
Informed the requester that (86-885) one record subject to this request is already available at the PDR. Denied eight records in their entirety, disclosure of which would interfere with an enforcement proceeding. Denied portions of three records, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
R. Buckles, In response to a request for copies of specified closed h0S Corporation Commission meeting transcripts regarding the Diablo Canyon (87-45) nuclear power plant, made available a copy of one transcript.
Denied three transcripts in their entirety pursuant to Exemption 10 of the Government in the Sunshine Act.
MARCH 20, 1987 ENCLOSURE A
5 Denied, Cont'd William Hendrick, In response to a request for copies of records Texas Nuclear supporting amendment 24 to add conditions 24 and 25 on (87-123) license l?-11286-01 issued to ADC0 Service. Inc.,
Tinley Paik, Illinois, made available three records.
Denied portions of one record, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
l 1
i I
11 ARCH 20,1987 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MARCH 27, 1987 RFP ISSUED RFP No.: RS-RES-87-069
Title:
" Environmental Degradation of Overpack Materials"
==
Description:==
The contractor shall conduct confirmatory research on the corrosion behavior of metallic containers. This research is important in determining if the licensee meets the containment requirements stipulated in 10 CFR 60.
Period of Performance: Five years Sponsor: Office of Nuclear Regulatory Research Status: RFP issued on March 16, 1987. Proposals due on April 16, 1987.
PROPOSALS UNDER EVALUATION RFP No.: RS-NMS-87-001
Title:
" Survey of State and Tribal Emergency Response Capabilities"
==
Description:==
Conduct a survey of State and Tribal Emergency Response Capabilities in order to evaluate the nature and amount of Federal Assistance which may be required in the event of an emergency.
Period of Performance:
18 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: RFP closed on March 17, 1987. Proposals forwarded to Source Evaluation Panel for review on March 18, 1987.
RFP Nos.: RS-0IE-87-120, 125, 126, and 127
Title:
" Specialized Technical Training"
==
Description:==
Provide technical assistance to the NRC in the implementation of identified needs and/or further development of programs to meet future needs for specialized technical training of NRC inspectors in the areas of Boiling Water Reactors (BWRs), Pressurized Water Reactors (PWRs), Equipment or Systems, Inspection Techniques and Practical Engineering, and Radiation Protection.
Period of Performance:
36 months Sponsor: Office of Inspection and Enforcement Status: RFP closed and proposals forwarded to Source Evaluation Panel for review on March 19, 1987.
RFP No.: RS-0IE-87-119
Title:
" Technical Assistance in Developing and Implementing Programs and Procedures for Reactors Requiring Special Inspection Resources"
==
Description:==
Contractor will provide technical assistance to NRC Regional
& Headquarters staff in developing and implementing programs and procedures for reactors with unusual problems during design, construction or operation, including unplanned outages.
Perido of Performance:
Three years Sponsor: Office of Inspection & Enforcement Status: RFP closed and proposals forwarded to Source Evaluation Panel for review on March 20, 1987.
MARCH 20, 1987 ENCLOSURE A
Weekly Information Report Division of Contracts PROPOSALS UNDER EVALUATION (cont'd)
RFP No.: RS-RES-87-077
Title:
" Investigation of the Quaternary Structural and Tectonic Character of the Meers Fault (South Western Oklahoma)"
==
Description:==
Contractor will provide the data necessary to characterize the Meers Fault for seismic assessment and to determine if there are other such faults that may have been reactivated in the Quaternary within the fault zone.
{
Period of Performance: Two years j
Sponsor: Office of Nuclear Regulatory Research Status: The competitive range has been established and negotiations are scheduled for the week of March 23, 1987.
CONTRACTS AWARDED RFP No.: RS-ADM-86-372
Title:
" Selection of a Primary Interexchange Carrier"
==
Description:==
Contractor to provide Direct Distance Dialed Inter-Lata and International Voice and Data Communications Services (Long Distance) in conjunction with the availability of equal access.
Period of Performance: Three years Sponsor: Office of Resource Management Status: A fixed price requirements type Contract No. NRC-33-87-235 was awarded to AT&T Communications in the amount of $113,316.84 effective February 18, 1987.
RFP No.: RS-0GC-87-316
Title:
"NRC Practice and Procedure Digest"
==
Description:==
Review NRC, ASLAB and ASLB decisions to identify rulings affecting NRC practice and procedure.
Also, prepare abstracts of rulings for purposes of updating the NRC Digest.
Period of Performance: March 19, 1987 through March 31, 1987.
Sponsor: Office of the General Counsel Status: A cost-plus-fixed-fee type Contract No. NRC-18-87-316 was awarded to Aspen Systems Corp., in the amount of $72,243.97 effective March 19, 1987.
11 ARCH 20,1987 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending March 20, 1987 South Texas Project Units 1 and 2 At 22:03 hours on March 11, 1987 when Unit I was being cooled down from the Hot Functional Test, a severe water hammer event occurred in the Residual Heat Removal System (RHRS) heat-exchanger. The primary system was at 350'F and 350 psig. The test being conducted was a demonstration of the 50 F/hr cooldown rate. The procedure for the test required Component Cooling Water (CCW) flow to be established before primary coolant entered the RHR heat-exchanger. The operator apparently missed a step in the procedure, causing the hot fluid flow before the CCW flow. The piping experienced two-phase flow and subsequent water hammer events. Several
, hangers were bent or broken.
Leakage was observed in at least one flange connection. Part of the CCW piping shows deformation.
The applicant is conducting a detailed review of the event. The NRC resident staff is performing the appropriate follow-up. At this point, it is not clear as to how long it will take to recover from the event.
Beaver Valley Unit 2 The applicant's Manager of Regulatory Affairs called today to inform the staff that.the main steam isolation valves (MSIVs) will be replaced.
The installed FSIVs are of the globe type, and are used by only one other plant in this county - Nine Mile Point. The replacement MSIVs will be of a conventional design and will come from one of the cancelled plar.ts of Duke Power.
Fuel load date has slipped from April 30 to May 20, 1987. The delay is due to combination of several factors:
replacemet,t of the MSIVs, construction schedule slippage, pre-operational test schedule slippage and delayed implementation of the security program.
Vogtle Electric Generating Plant Unit 1 A license authorizing operatior at up to 100% power was issued to Georgia Power Company en March 16, 1987 for Voetle Electric Generating Plant, Unit 1.
MARCH 20, 1987 ENCLOSURE B
Calvert Cliffs Units 1&2 On March 10, 1987, Calvert Cliffs Unit I shut down due to a failure of a quench tank rupture disc. The indications received were a decrease of quench tank pressure and temperature to saturation conditions at atmospheric pressure, increased airborne activity in the containment and increased frequency of containment sump high level alarms.
The licensee stated that at approximately the time of the quench tank failure, a noise spike occurred on the PZR code safety valve acoustic monitors. The licensee is investigating whether the noise spike was due to the quench tank failure or to a possible lifting of one of the PZR code safety valves.
Previously, the licensee had observed an indicated leakage of about 0.3 gpm from the safety valves. Recently, this leakage had increased to 0.8 gpm.
The licensee performed lift tests on the pressurizer (PZP) code safety valves while in Mode 3 to determine if setpoint drift occurred. The lift setpoints of each PZR code safety valve was determined to be out of specification. The results were:
Valve Specification Result RC 200 2500 1%
2450 RC 201 2565 1%
2690 The licensee repaired the quench tank and replaced both PZR code safety valves. Unit I was restarted on March 15, 1987.
Calvert Cliffs Unit 2 was shutdown on March 14, 1987 for refueling in preparation for Cycle 8 operation. Major activities to be accomplished include 10-year ISI inspections, SPDS/DAS and plant computer installation, replacement of main steam line isolation valves and main turbine low pressure rotor replacement. The outage is scheduled to last until approximately May 12, 1987.
Fermi 2 On March 16, 1987, a major milestone was reached in the Fermi-2 startup test program when the loss-of-offsite-power test was successfully conducted.
All four of the emergency diesel generators : tarted up within prescribed time periods to provide pcwer to essential plant equipment during the test. The test was completed within 30 minutes, after which time recovery was initiated.
The loss-of-offsite-power test was the last test scheduled for Test Condition 2 of the startup test program which limits plant operation up to 50 percent of rated thermal power.
l l
MARCH 20, 1987 ENCLOSURE B
. The plant is being brought to cold shutdown and will enter into a planned maintenance outage which is to last for about 17 days. During this n.ainte-nance outage, the licensee is expected to rec;uest NRC to authorize contin-uation of startup testing under Test Condition 3, which would permit plant operation up to 75 percent of rated thermal power.
Arkansas Nuclear One Unit 1 On March 13, 1987, Arkansas Power and Light Company reduced the power of ANO-1 to 65% of full power. The power reduction was made partly because of reduced power needs and partly to schedule the refueling outage such that the refueling outage for ANO-1 would not be close to the refueling outage (January thru March 1988) for ANO-2. AP&L's current operating plans for ANO-1 are as follows:
March 13 - June 1, 1987 65% power June 2 - September 15, 1987 80% power September 16 - October 15, 1987 65% power October 15 - October 31, 1987 Mid-cycle shutdown October 31 - December 31, 1987 65% power January 1, 1988 - September 1, 1988 80% power September 1, 1988 Shutdown for refueling The mid-cycle shutdown will be used to service the steam generators and to perform necessary 18 month surviellances.
San Onofre Nuclear Generating Station Unit 1 (SCNGS-1)
On March 12, 1987 the NRC staff ccmpleted review of and found acceptable a recent submittal from Southern California Edison Company (SCE) which stated that the licensee no longer planned to implement a modification to enhance the availability of the second source of offsite power at SONGS-1.
In April 1986 as part of the review of the November 21, 1985 water hammer event, the licensee committed to implement this modification during the next refueling outage.
However, in a subsequent submittal SCE stated that cost-benefit analyses had shown that this modification (estimated to cost $14 million) could not be justified based upon the minimal improvements in safety it would provide. The licensee based this conclusion on a review of plant transients that occurred at SONGS-1 throughout the past 19 years. The study concluded that with the exception of the November 21, 1985 loss-of-power / water herr:er event, a second immediate access source of offsite power would ret have improved system i
response or have enabled the plant to continue to operate by preventing unit or reactor trips during the other transients.
MARCH 20, 1987 ENCLOSURE B
~
o l
The staff's review of the SONGS-1 electrical system design (one immediate access offsite circuit and a second offsite circuit available after several minutes) concluded that it did meet regulatory requirements regarding offsite power availability. Although an additional effsite circuit in excess of the GDC-17 requirements would have been beneficial during the November 21, 1985 event, the staff does not have a basis for requiring this modification.
Shoreham Nuclear Plant The Shoreham Station experienced a loss-of-offsite power at 0146 hours0.00169 days <br />0.0406 hours <br />2.414021e-4 weeks <br />5.5553e-5 months <br /> on March 18, 1987 when a condensate pump was energized for testing. Exact cause of the event is still Jnder investigation, but based on a preliminary licensee analysis, the root cause was a procedural error during earlier work on the electrical relays for the Colt EDGs.
(At Shoreham, the Colt EDGs are not yet tied into the facility. The facility uses the TDI EDGs for emergency power).
In order to deenergize the Colt EDG cabinets for the bifurcation work, the workers had shorted out the Current Transformers (cts). The cts are part of the Differential Current Protection Circuity (DCPC) for the protection of the Normal Station Supply Transformer (NSST) and the Reserve Station Supply Trmsformer (RSST). Apparently, the procedure did not take into account that th6 short-circuited cts were in parallel with all other cts, in effect shorting out all the cts. However, prior to the condensate pump start-up, the load was not large enough to reach the DCPC set-points..Those set-points were reached when the breakers for the condensate pump was closed, tripping the NSST. Station load was automatically transferred to the RSST. The DCPC again tripped the RSST as the condensate pump breaker was still closed, resulting in a loss-of-offsite power. Two TDI EDGs started within 10 seconds to restore emergency a/c power.
(The TDI EDGs service only essential po er i
which does not include the DCPC). Power from the RSST was restored at 0E05 hours by which time the condensate pump breaker had been opened. The licensee i
declared an Unusual Event (UE) at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> and terminated the UE at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.
The resident inspector is following the investigation and corrective actionc.
MARCH 20, 1987 ENCLOSURE B
NRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MARCH 16 - 22, 1987 1.
DEFUELING Two standing peripherial fuel assemblies, A-6 and A-7, were removed essentially intact. They were cut and placed in fuel canisters.
(The intact assemblies are approximately 1 ft. longer than the available space in the canisters.)
Removal of these two assemblies greatly improves access to the core support assembly-and potential access to the lower head.
It will allow increased flexibility in approaches to defueling those areas.
It also allows an additional access to adjacent fuel assemblies.
The licensee is preparing a jacking tool to exploit the new access to adjacent assemblies.
2.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water effluents are sampled from the station (Units 1 and 2) discharge and analyzed by EPA. Gamma spectrum analyses of the seven daily composited samples for February 28 - March 7,1987 indicated no TMI-2 related radioactivity.
EPA's gamma spectrum analysis of the NRC's THI outdoor air sample for the period March 12 - 19, 1987 showed no reactor related radioactivity.
The Lancaster water works intake composited seven daily samples March 1 - 7, 1987. The gamma spectrum analyzed by EPA showed no reactor related radioactivity.
3.
DECONTAMINATION ACTIVITIES Remote robotic scabbling of the seal injection valve room continued during the week as well as scabbling of the floor beneath the B and C bleed tanks.
Desludging of the auxiliary buildfrg sump continued.
4.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request numbers 49 and 51 and the associated Recovery Operations Plan Change Pequests 31 and 33.
Technical Specification Change Request 52, 55 and 56.
Solid Waste Facility Technical Evtluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
iiARCH 20, 1987 ENCLOSURE B
Processed L'ater Disposition Proposal.
Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Additional questions on the ese of the Plasma Arc Cutting Torch were subritted to GPUN on March 20, 1987.
Temporary Peactor Vessel Filtration System Safety Evaluation Report, Revision 3.
Pressurizer Defueling Safety Evaluation Report.
Safety Evaluation Report for Defueling of the Core Support Assembly.
Containment Air Control Envelope Technical Evaluation Report, Revision 7 was approved on March 19, 1987.
Coanulant Criticality Safety Evaluation Report.
Revision 2 to the Sediment Transfer and Processing Safety Evaluation Report.
Seismic Evaluation for Modified Containment Penetration.
5.
MEETIhG The Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled to meet on March 25, 1987 from 6:00 PM to 10:00 PM at the Holiday Inn, 23 S. Second Street, Harrisburg, PA. The meeting will include further discussion of the proposed disposition of the accident-generated water and the NRC's Draft EIS and will include an opportunity for public comment.
Persons desiring to speak before the Panel are requested to contact Mr.
Thomas Smithgall at 717-291-1042, or write to him at 2123 Marietta Avenue, Lancaster, PA 17603, so that they may be placed on the meeting
- agenda, fMRCH 20,1987 ENCL 63URE B
l OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Endino Parch 20, 1987 Narrative Explanantion of Table S-3 of 10 CFR Part 51 W. E. Thompson '(NMSS) and W. R. Pearson (RES) met on March 12, 1987, to review drafts of portions of the Table S-3 narrative explanation and to discuss plans for revising the remaining portions of the narrative.
In revising the explana-tion of the values given in Table S-3, more errphasis will be placed on describing how the estimates were developed and on discussing the sensitivity of estimates
,to changes in assumptions or other parameters, including higher burnup.
In the discussion of population dose commitments and potential health effects, a com-parisen of the health effects of the uranium fuel cycle with those of the coal fuel cycle will be introduced to support the conclusion that the environmental impacts of the uranium fuel cycle do not significantly increase the total impacts of producing electric power.
Ifpdate of NUREG/CR-1620 The r'equest for proposal deadline for a project to update ?!UREG/CR-1620,
" Survey of State and Tribal Emergency Response Capabilities to Respond to Radiological Transportation Incidents," was March 17, 1987, at 2 p.m.
On March 19, 1987, a representative of the Division of Contracts will distribute technical proposals received prior to the deadline to members of the source evaluation panel for review and evaluation.
Following completion of the procurement process, the contract is tentatively scheduled for award in early June 1987.
Combustion Engineering (Windsor, Connecticut, Facility, Docket 70-1100)
Representatives of Cembustion Engineering (CE) and NRC met on March 18, 1987, to discuss the CE revised application requesting authorization to base nuclear criticality safety on the maximum mist density of water from a sprinkler system in a particular area of the facility. The application will be reviewed to determine whether the NRC comments discussed in a February 19, 1987, meeting have been adequately addressed, t1 ARCH 20, 1987 ENCLOSURE C
2 HIOSH Study of NFS Workers' Health Effects The NRC has received an interim report from the National Institute for Occupational Safety and Fealth (NIOSH) describing the results of a pilot study on health effects experienced by workers at Nuclear Fuel Services (NFS). The pilot study consisted of a questionnaire given to male workers with at least 20 years of employment et NFS and to guards and security workers with no production experience. The questionnaire consisted of five cuestions about kidney disease, including kidney stones, kidney or bladder infections, blood or protein in the urine, and other kidney problems. Both production and non-production workers reported more frequent kidney stones, urinary tract infections, and blood in the urine than did the guards. The interin report recommends that a more definitive medical study be conducted to clarify the nature and probable cause of the kidney problems observed. NIOSH is currently planning to convene a peer review group to evaluate the findings and make recomendations for further action. NRC P,egion II is arranging for a briefing of NRC staff on the pilot study by the NIOSH principal investigator.
West Valley Demonstration Project Lawsuit A letter submitted to the NRC on January 26, 1987, by the law office of Terranova, Seeger and Galeziowski has notified the NRC of the possibility of its being named in the current West Valley lawsuit. The basis for NP.C's being named in the lawsuit is the definition of the term " transuranic waste" as used in the West Valley Demonstration Project Act (P.L.96-368).
If NRC has redefined " transuranic waste," then NRC will be named in the lawsuit.
Revision to Regulatory Guide On March 10, 1987, the staff issued Revision I to Regulatory Guide 4.17,
" Standard Format and Content of Site Characterization Plans for High-Level Waste Geologic Repositories." Regulatory Guide 4.17 presents up-to-date guidance to the U.S. Department of Energy (DOE) on the types of information that should be included in a site characterization plan (SCP) that will be submitted to the NRC for review.
The guide also presents a format for presenting this informa-tion. This revision makes the Guide consistent with the provisions of the Nuclear Waste Policy Act and formalizes guidance provided to DOE in public meetings.
Public notice of this issuance will be made in the _ Federal Register.
Exploratory Shaft Meeting An NRC/ DOE technical meeting on Exploratory Shaft at the Yucca Mountain site is scheduled for April 14-15, 1987.
This meeting will focus on exploratory
.chaft facility design and construction with emphasis on discussing and reaching agreement on DOE changes to the shaft location and diameter as well as the extent of drifting.
f1 ARCH 20, 1987 ENCLOSURE C
3 IAEA Verification of Westinghouse Physical Security Westinghouse, Columbia, is a fuel cycle facility currently under IAEA safeguards.
IAEA inspectors verified on-site an inventory conducted by Westinghouse in January 1987.
Concerns with respect to the acceptability of the Westinghouse physical inventory were tentatively resolved during a phone call on March 17 with IAEA and NRC. The IAEA will finalize this conclusion by examiration of the Westinghouse books at the IAEA/ Westinghouse /NRC review meeting the week of April 27, 1987.
Policy Statement an'd NUMARC Guidelines on Access Authorization The NUMARC response to staff questions on use of temporary workers in the nuclear industry was received March 12, 1987, and is undergoing staff analysis to determine measures to be applied in granting unescorted access to temporary workers at nuclear power plants.
10 CFR 73.71, Reporting Requirements for Safeguards Events CRGR comments on 10 CFR 73.71, Reporting Requirements for Safeguards Events, were received March 6, 1987, and are being incorporated into the rule package. The CRGR requested the rule be forwarded to the CRGR Chairman prior to forwarding to the ED0 for signature and publication as a final rule.
Accordingly, the anticipated publication date for the final rule will probably slip from March 1987 to April 1987, which will still be within the 2-year time limit.
I MARCH 20, 1987 ENCLOSURE C
ABSENCE OF Tile DIRECTOR / DEPUTY DIRECTOR Division of Fuel Cycle and Material Safety None Division of Waste itanagement None Division of Safeguards Robert Burnett - March 24-26,1987(Travel)
MARCH 20, 1987 ENCLOSURE C
Office of Inspection and Enforcement Items of Interest Week Ending March 20, 1987 1.
Items of Interest 2.
Civil Penalties Paid 3.
The following Significant Enforcement Actions were taken during the past week:
4.
The following IE Information Notices and Bulletins were issued during the past week:
5.
The following IE Prelinirarv Notifications were issued during the past week:
PN0-II-P7-20, Virginia Electric & Power Company (Surry Unit 2) - Unit Returning to Service.
PNO-III-87-41, Commonwealth Edison Company (LaSalle Unit 1) - Reactor Trip; Arcing in Buss Bars from Unit Auxiliary Transformer.
PNO-V-87-22, Washington Public Power Supply System (WNP-2) - ECCS System Partially Disabled.
MARCH 20, 1987 ENCLOSURE D
OFFICE OF NUCLEAR EEGULATORY RESEARCH Items of Interest Week Ending March 20, 1987 Hot Particles at Nuclear Power Plants Several nuclear power plants have recently made reports of very small radioactive particles that cling to the clothing or skin of plant workers.
Most of these particles cannot be seen with.the naked eye and are detected using radiation instruments. There have been a few instances where particles of this type were reported to have been inadvertently carried home on the skin and clothing of some workers. They come from fuel cladding leakage or from activated corrosion products and apparently are deposited by cooling water or water in the spent fuel pool on tne surfaces of components and systems maintained by the workers.
Very sensitive instruments, that have recently become commercially available and are being installed at nuclear power plants,.have been primarily responsible for the detection of these particles. Generally, detection has involved only one, isolated particle at a time, a situation much different than skin contamination incidents that have occurred in the past. While most contamination incidents normally cause only small radiation doses (millirems) over relatively large skin areas (tens of square centimeters),
the single particles can cause much larger doses to very small areas of skin (1 square centimeter and less).
Limited surveys conducted to date indicate that the particles may not have become airborne; they are believed to be sufficiently insoluble that ingestion would not result in significant uptake of radioactive material by the gastrointestinal tract. Highly localized irradiation of the skin appears tentatively to be the primary radiobiological problem.
Current radiobiological literature indicates that a highly localized radiation dose is less efficient in causing cancer than the same dose distributed over a large volume of tissue. The NRC regulatory dose limit for the skin is 7.5 rems per calendar quarter, with the exception that the linit for the skin of the hands, forearms, feet and ankles is 18.75 rems per calendar quarter. The depth and area of skin over which these dose limits are intended to apply is not specified in the regulations.
It is the present position of the NRC staff that these skin-dese limits apply at a tissue depth of 0.007 centimeters averaged over an area of I square centineter.
Compliance with these regulations in this manner is believed to provide adequate protection for workers under all conditions of irradiation.
MARCH 20, 1987 ENCLOSURE E
~.
2 If regulatory skin dose limits are greatly exceeded, effects sinflar to thermal burns may be expected. These are reversible unless deep tissue layers receive very large doses (thousands of rads), in which case grafting may be required. To date, localized skin doses caused by such particles and reported to the NRC have not exceeded a few hundred rads.
The regions and headquarters offices are coordinating efforts to ensure that practical methods of prevention and control are instituted by licensees.
The National Council on Radiation Protection and Measurements (NCRP) is being requested by RES to investigate the health significance of this issue and to make necessary recomendations based on their findings.
R.E. Alexander. RES -
443-7976 Radiation Damage Mec_hanisms Seminar l
The Materials Branch of DES held a seminar on Radiation Damage Mechanisms on February 16, 1987, to review cooperative work underway between NRC contractors at Oak Ridge National Laboratory and the University of California at Santa Barbara, and foreign researchers from the CEN/SCK Laboratory at Mol, Belgium and the KFA Juelich Laboratory in Germany.
Reviewed was the current effort.to apply the German-derived radiation damage model to the NRC-Engineering Data Base of reactor surveillance embrittlement and dosimetry data that has been under development for several years. The German damage model has been evolved based on a large number of irradiations of both redel alloys and of steel compositions under a variety of critical conditions or irradiation temperature, fluence, flux rate and neutron spectrum. The NRC-Engineering Data Base contains all the surveillance data from US power reactors, and has been carefully evaluated to assure that the data are up to the current, best standards for accuracy. The German damage 4
model is currently seen to predict the damage rather well, although the work 4
is not complete.
Implicaticns of the cooperative work are large because such a prediction method for radiation damage are needed to assure adequate safety as plants age. A clear action evolving from the meeting was to assure that experts in radiation damage mechanisms studies meet on a regular basis to exchange their current results, and provide critical review of each other's work.
It was noted that a tentative data of Spring 1988 has been identified for such a gathering in Oxford, England, as a follow up to an initial meeting held in Monterey, California in Septenber 1985.
1 4
MARCH 20, 1987 ENCLOSURE E U
3 2D/3D All the degraded U. S.-supplied instruments in the Upper Plenum Test Facility (UPTF) have been completely refurbished, and the work is ahead of schedule. The upper plenum internals were inserted in the vessel on March 16, 1987, and the entire facility will be checked cut for the remainder of March 1987. Testing will resume in April 1987.
RES is negotiating with the Germans to have an upper plenum injection (UPI) test conducted shortly after the facility is brought up to a ready condition. NRR wants to heve a UPI test conducted at UPTF in order to expand the relatively small data base for UPI geometry.
Thermal Hydraulic Technical Integration Center (TIC)
One of tne functions of the TIC is to resolve priority issues. One such i'; sue is to establish the differences in demands on plant safety systems and on operating personnel for three comparable abncrmal transients in representative plants for each PWR vendor. The results of these comparisons will be integrated with other study results to develop NRC's reevaluation of B&W plant performance which should be completed during June 1987. The CE plant chosen for this study is Calvert Cliffs, the Westinghouse plant chosen was H. B. Robinson and the B&W plant chosen was Oconee-3.
In order to assure the quality of plant modeling for these analyses, the contractor (INEL) must visit each plant and discuss the planned analyses with plant staff.
INEL previously visited Calvert Cliffs and H. B. Robinson and during the week of March 16, 1987 is visiting the Oconee plant.
National Academy of Sciences Workshop on High Temperature Chenistry On March 1, 1987 the NRC awarded a grant to the National Academy of Sciences (NAS) to conduct a workshop on high-temperature and nuclear chemical processes in severe reactor accidents.
Following the workshop, NAS will also provide a report on the subject to the NRC. This activity was suggested by Comissioner Bernthal and stems from some of the limitations in severe accident technology identified in NUREG-0956, " Reassessment of the Technical Bases for Estimating Source Terms." An NAS steering committee, composed of about 14 natforally known scientists met on March 18, 1987 to discuss the scope of their activities and to make plans for the workshop.
Staff from Comissioner Bernthal's office and from RES participated in this meeting. The three-day workshop will be held in August 1987 and will include presentations and discussions by renowned scientists both within and outside of the nuclear comunity.
International participation is expected.
MARCH 20, 1987 ENCLOSURE E
9-Recently Issued Publications Draft Regulatory Guide and Value/ Impact Statement: Guidance for Selecting Sites for Near-Surface Disposal of Low-Level Radioctive Waste, Task WM 408-4. Comments requested by May 29, 1987.
Contact:
Jchn C. Stewart (301) 443-7980 Regulatory Guide 10.10," Guide for the Preparation of Applications for Radiation Safety Evaluation and Registration of Devices Containing Byproduct Material", Task FC 601-4. Ccntact: S. Baggett (?! MSS)
(301)427-9005 i
MARCH 20, 1987 ENCLOSURE E
i 5
RES Rl!LEMAKIhG ACTIVITIES 4
Licenses and Radiation Safety Requirements for Well Logging (10 CFR 39)
The rule establishes a new Part 39 in NRC regulations. The new part contains specific radiation safety requirements applicable to licensees who perform operations such as well logging and subsurface use of radioactive materiels in tracer studies. The rule was necessary to provide the specific e
requirements necessary to ensure that these operations are performed safely.
i' On March 17, 1987, the final rule was published in the Federal Register (52 FR 8225). The rule will be effective on July 14, 1987. Copies are being sent to all well logging licensees and to Agreement States.
Acceptance Criteria for Emergency Core Cooling Systems (ECCS) for Light Water Nuclear Power Reactors (10 CFR 50)
The proposed rule would amend regulations concerning acceptance criteria for j
emergency core cooling systems (ECCS) by changing the methods used to demonstrate that an ECCS would protect the nuclear reactor core during a 1
loss-of-coolant accident.
t On March 3, 1987, the proposed Emergency Core Cooling System (ECCS) Rule was published in the Federal Register for public comment (52 FR 6334). A 120-day public comment period is provided to allow coincident publication of the draft regulatory guide, "Best Estimate Calculations of ECCS Performance," and the draft " Compendium of ECCS Research for LOCA Analyses."
The public comment period for all three documents will end on July 1,1987.
i h
t MARCH 20, 1987 ENCLOSURE E i
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGPAMS WEEK ENDING MARCH 20, 1987 Discussions with National Academy of Sciences on USSR Topics of Interest Glenn Schweitzer, Director, Soviet and Eastern European Affairs, National Academy of Sciences (NAS), met with Robert Wood of DOE and J. Shea and H. Faulkner of IP/NRC on Wednesday, March 18. Schweitzer is travelling to Moscow on March 23 for discussions with the Soviet Academy of Science. Schweitzer was briefed on the recent U.S. team visit to the USSR. Discussions followed relevant to NAS plans regarding their interest in (1) nuclear safety and (2) research on effects of radiation.
NAS recognizes the corltinuing U.S. Government dialogue on the same topics with various organizations in the USSR, and they will structure the Academy's role to complement these interests.
Small Fire at Lucas Heights, Australia The Australian Embassy advised IP on Thursday that a fire had occurred at the Lucas Heights Nuclear Research Laboratory near Sydney, resulting in the release of a small amount of radioactivity into the air.
(The amount was one-fourth of the approved weekly limit.) The fire occurred in a plastic filter in an area used to process medical isotopes (apart from the research reactor).
It burned itself out in less than one hour after workers sealed off the chamber. Although eight fire brigades responded, none were needed.
Foreign Visitors On Monday a technical team from the Chinese Bureau of Safety, Protection and Health, Ministry of Nuclear Industry, met with staff members from RES, the Incident Response Center, and NMSS to discuss topics including source term analysis, emergency response, and low-level waste disposal.
On Monday a technical team from the West German Federal Ministry for Environment, Nature Conservation and Nuclear Safety (BMU) and the Reactor Safety Company (GRS) held discussions with hMSS and RES on several topics related to the backerd of the fuel cycle and implementation of the U.S. Vaste Policy Act.
On Thursday Dr. Kenneth Hare of the Ontario Nuclear Safety Review (NSR) in Canada, accompanied by Ms. Margaret Grisdale, Project Manager, NSR, net with Chairman Zech and R. Hauber of IP to discuss the public inquiry into the safety of CANDU reactors operating in Ontario.
MARCH 20, 1987 ENCLOSURE G
ITEMS ADDRESSED BY THE COMMISSION - Week Ending March 20, 1987 A.
STAFF REQUIREMENTS - DISCUSSION /POSSIBLE V0TE ON FULL POWER nPERATING LICENSE FOR V0GTLE-1, 2:00 P.M., THURSDAY, MARCH 12, 1987, CCN.f SSILAERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo SECY to V. Stello dated 3/20/87 The Commission was briefed by the licensee (Georgia Power Company) and the staff on the readiness of Vogtle Unit I for a full power operating license.
Presentations by the licensee were made by the following:
- Robert Scherer, CEO and Chairman of the Board
- James Miller, Jr., President
- George Bockhold, Jr., General Manager The Commission, by a vote of 4-0,* approved immediate effective-ness of the Vogtle Licensing Board's decision and authorized the Director of the Office of Nuclear Reactor Regulation to issue, after the staff makes the appropriate findings, a full power license to Georgia Power Company for Vogtle Unit 1.
4 MARCH 20, 1987 EUCLOSUP.E P
5
- o EE NRR MEETING NOTICES
- MARCH 20, 1987
- g IE i 03 i '"
DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT l
3/23/87 50-259/
Suite 204/TVA To discuss open items on NRC NRC/TVA J. F. Stang 8:00 a.m.
260/295 Fairmount Ave.
draft safety evaluation on safe shutdown.
3/23/87 50-352 Room 6110 To discuss implementation of the NRC/PECo R. E. Martin 10:30 a.m.
Mary.Nat. Bank Build.
SGTS modifications proposed in the licensee's January 12, 1987 letter.
3/24/87 50-259/
Suite 204/TVA To discuss open items on NRC NRC/TVA J. F. Stang 8:00 a.m.
260/295 Fairmount Ave.
draft safety evaluation on safe shutdown.
3/25/87 50-443 Room P-110 To discuss the Brookhaven NRC/BNL/ MASS A.G.
"V. Nerses 8:00 a.m.
Phillips Building National Laboratory (BNL) report on their technical review of the Seabrook Emergency Planning Sensitivity Study.
3/25/87 50-412 Room 6110 To discuss with applicant NRC/DLC P. S. Tam 10:00 a.m.
Mary.Nat. Bank. Build.
personnel issues uncovered by the Seismic Qualification Review m
Team.
i2i E>
E El
- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s)
, c3 in the NRC and local public document rooms t summary of these meeting notices can be obtained by calling 492-7424
)
bh E!
NRR MEETING NOTICES
- MARCH 20, 1987 m?
co i"
DOCVET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/25/87 50-443 Room P-110 To discuss the Brookhaven NRC/BNL/PSNH-NHY V. Nerses 1:15 p.m.
Phillips Building National Laboratory (BNL) report on their technical review of the Seabrook Emergency Planning Sensitivity Study.
3/26/87 50-369/
P-110 To discuss tentative requests for NRC/ DUKE POWER CO.
D. Hood l
8:30 a.m.
370/413/ Phillips Building additional information regarding 414 proposed removal of the RTD bypass manifold.
a 3/27/87 50-247 Poem P-110 To discuss Consolidated Edison's NRC/ Con-Ed M. Slosson 9:30 a.m.
Phillips Build, iluly 24, 1986 amendment applica-tion concerning nurrican alert.
3/27/87 Room P-118 To discuss Technical Exchange on NRC/ Industry R. M. Bernero 1:00 p.m.
Phillips Build.
Mark I Containment Improvements.
3/30/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ante with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
9 Pgg o Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) gg in the NRC and local public document rooms
'm j es A suneary of these meeting notices can be obtained by calling 492-7424 i
3
- o E2 NRR MEETING NOTICES
- MARCH 20, 1987 no G
03 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/31/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.n.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
4/1/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
4/2/87 50-498/
Scuth Texas Project To discuss the South Texas compli-NRC/ Licensee H. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-
- manCP, 4/3/87 50-498/
South Texas Project To discuss the South Texas compli-NRC/ Licensee N. P. Kadambi 8:00 a.m.
499 Site ance with Appendix R and to conduct Matagerda County, TX a site audit to review the confor-mance.
Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) g in the NRC and local public document rooms P
cg A summary of these meeting notices can be obtained by calling 492-7424 m
x2
- j.
Y
+
i :o i E NRR MEETING NOTICES
- MARCH 20, 1987 jp G
co DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/9/87 R.B. Russell Fed.
To provide information about the NRC/0L3/
W. T. Russell 8:00 a.m.
Build. Atlanta, GA final revisions to 10 CFR Part 55 Reg. Reps./
" Operators' Licenses," and their Utility Reps./
implementation.
Public Members 4/14/87 Steuffer Concourse To provide information about the NRC/0LB/
W. T. Russell 8:00 a.m.
Hotel Denver, C0 final revisions to 10 CFR Part 55 Reg. Reps./
" Operators' Licenses," and their Utility Reps./
implementation.
Public Members I
Rarada Hotel O' Hare To provide information about the NRC/0LB/
W. T. Russell 4/16/87 8:00 a.m.
Rosemont, Il final revisions to 10 CFR Part 55 Reg. Reps./
" Operators' Licenses," and their Utility Reps./
implementation.
Public Members 4/20/87 Hilton Hotel Valley To provide information about the NRC/0LB/
W. T. Russell l
8:00 a.m.
Forge final revisions to 10 CFR Part 55 Reg. Reps./
King of Prussia, PA
" Operators' Licanses," and their Utility Reps./
l implementation.
Public Members Copics of summaries of these meetings will be made publicly available and placed in the respective docket file (s) g in the NRC and local public document rooms g
A summary of these meeting notices can be obtained by calling 492-7424 E
m bQ 1
REGION III MEETING NOTICES g
I E
^
WEEK ENDING: April 4, 1987 5
t i
9 G
m DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT
- NRC CONTACT April 1 50-295 Illinois Beach SALP Commonwealth Edison A. B. Davis 7:00 -
50-304 Resort Hotel, Company 10:00 p.m.
Zion, Illinois l
w-d' I
=
P St
!5 m
,O
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -