ML20215K192
| ML20215K192 | |
| Person / Time | |
|---|---|
| Issue date: | 04/29/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-870424, NUDOCS 8705110110 | |
| Download: ML20215K192 (32) | |
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April 29, 1987 -
For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
FEEKLY INFORMATION REPORT - WEEK ENDING APRIL 24, 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 and Resources Management A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Nuclear Regulatory Research D Governmental & Public Affairs E General Counsel F*
Personnel G*
Analysis and Evaluation of Operational Data H Small & Disadvantaged Business Utilization & Civil Rights I*
Special Projects J*
Regional Offices K*
CRGR Monthly Reports L Executive Director for Operations M*
Items Addressed by the Connission N Meeting Notices 0 Proprietary or Other Sensitive Information (Not for P external distribution) r
- No input this week.
/ - /]
T. A. RshnC Assistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781 8705110110 PDR 870429 COMMS NRCC WEEKLYINFOREPT PDR
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING APRIL 24, 1987
Perry Unit 1 - Steam Drain Line Break / Loss of Condenser Vacuum On April 14, 1987, at approximately 6:15 p.m., while at 9% power, operattft noted a decreasing main condenser vacuum coupled with an increased offgas system flowrate. Attempts to restore vacuum were unsuccessful and at 6:17 p.m., the unit was manually scramed and MSIV's manually closed. The loss of condenser vacuum resulted from a guillotine break of a 3-inch drain line from the "before seat" drains of the turbine stop valves. This drain line j expands to six inches and ultimately connects to a 24-inch manifold leading to the high pressure condenser. The break occurred at a weld point in the drain line. No injuries or contaminated personnel resulted from the event.
Magnetic particle inspections of six similar drain lines leading to the
. manifold revealed cracks in at least four other lines. The licensee intends t
to replace damaged piping and will be shutdown for at least ten days. The licensee suspects vibration induced cracking (caused by condensate flashing) as the cause. The resident inspector is monitoring the repair effort. i Seabrook Unit No. 1 On April 22, 1987, the offsite emergency planning Atomic Safety and Licensing Board (Hoyt Board) concluded that the applicant's petition for a one mile emergency planning zone under 10 CFR 2.758 and 10 CFR - - .
50.47(c) does not provide a 3 rima facie showing on its technical '
merits; therefore, the Hoyt 30ard will not be recommending to the Comission, at this time, that further consideration should be given to the applicant's motion.
The Hoyt Board noted "We do not take a position that a one mile PEPZ for the Seabrook Station is unjustifiable; only that Applicants and Staff need more time to determine more convincingly whether it is".
Explosive Detectors Using Neutron Sources An April 18, 1987 article in "The New York Times" stated that the Federal Aviation Administration (FAA) plans to install explosives detectors utilizing californium-252 neutron sources at major airports within two years.
Activation of baggage, food and medicine appear to be the items of most concern. Based on the information available to us, the amount of radioactivity in these items appears to be very small. An Agreement State licensee is authorized to develop these devices. 0GC's opinion has been solicited on what, regulatory jurisdiction NRC has over activation products produced by the ;
californium-252. NRC has not received a license application for this activity' .
i Cracked Stiffening Rings on UFe Cylinders-Update l
g cylinders have The NRCrings stiffening has fabricated information that from some which material 48-inch maydiameter no UF,t meet ASME and ANSI Standards. Up to 352 cylinders may be affected. Radial cracks have been detected on some of these stiffeni.ng rings. DOT regulations which become effective on June 30, 1987, will require UF cylinders g to meet ASME and ANSI Standards. To avoid unnecessary site operations to remove UF from cylinders which cannot be transported, an orderisbeingpreparedtophecludeloading of affected cylinders until it is clear that the cylinders can be transported under the new 00T rules.
OFFICE OF ADMINISTRATION AND RESOURCES MANAGEMENT For 5-Day Period of April 17,1987 - April 23,1987 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS - 1987 Initial Appeal of Request Initial Decision Received This Week 15 2 Completed This Week 7 2 Carryovers From 1986 170 53 Received In 1987 233 21 Granted In 1987 160 7 Denied In 1987 64 19
> Pending -
179 48 ACTIONS THIS WEEK Received 1
l (NRC enployee) Requests records concerning the evaluation, certification, (87-219) and selection under Vacancy Announcement No. 87-0147-6.
, Lynn Connor, Requests a copy of the scope of work for Mitre Corporation's
! Doc-Search task on the extension of operating licenses.
Associates (87-220)
Lynn Connor, Requests copies of Probabilistic Risk Assessments for the i Doc-Search following plants: Susquehanna 1 McGuire 1, Oyster Creek, Associates Bellefonte 1, and GASSAR (50-535).-
(87-221)
Stewart Wetzel, Requests a copy of a January 6, 1983 transcript of an
- NUS Corporation NRC staff meeting with an individual regarding alleged
, (87-222) deficiencies in the Diablo Canyon component cooling water system.
Stephen Giles, Requests copies of depositions or investigative interviews 3
Thompson, Mann of two named individuals relating to the NRC's investigation and Hutson of alleged civil quality control inspection deficiencies (87-223) or harassment of these two individuals while performing quality control inspections at Wolf Creek.
Bruce Maxwell, Requests copies of all records concerning an alleged 4 WTOL-TV Toledo incident of intoxication of an employee of the Davis i
(87-224) Besse nuclear power plant on December 31, 1986, or January 1, l 1987. l CONTACT: Donnie H. Grimsley ,
492-7211 j i APRIL 24, 1987 ENCLOSURE A
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. Received, Cont'd.
Linca Bauman, Requests copies of all records related to the March 11, Government 1987 mock disaster arill at the South Texas' plant.
Accountability Project -
(87-225)
David Rubinton, Requests copies of all records of investigations of Government kickbacks or other improprieties regarding ex-NRC Accountability employees now working for TERA, including an October 1986 Project incident at the Crystal River nuclear power plant.
(87-226)
David Rubinton, Requests copies of all records developed by the License Government . Fee Management Branch about the cost of the operating Accountability license review for the Comanche Peak nuclear power plant ,
Project from December 3, 1985, to the present.
(87-227)
David Rubinton, Requests copies of all records related to the dismissal Government of a health physicist at the Peach Bottom nuclear power Accountability plant for whistleblowing on a March 1985 incident of Project equipment malfunction.
(87-228)
Michael Knapik, Requests copies of all correspondence between Victor Stello McGraw-Hill ard persons outside NRC from January 1, 1987 to the present. ;
(87-229)
Michael Knapik, Requests copies of a report entitled, "Information McGraw-Hill Regarding South African-origin Material Importeo and (87-230) Exported from the U.S. 1981-1986," and the most recently filed 742 forms.
Michael Knapik, Requests copies of all records generated in the last three McGraw-Hill years concerning uranium " flag swaps" or substitutions.
(87-231)
Lynn Connor, Requests copies of monthly reports, progress reports, Doc-Scarch and/or milestone reports for contracts NRC-04-86-125 and Associates RS-RES-86-128 plus the final report for RS-RES-86-128.
(87-232)
Mike Johnson, Requests 4 copy of proposed Reg Guide 1.XYZ referenced in NUS Corporation NUREG/CR-4678.
(87-233)
Linoa Bauman, APPEAL TO THE COMMISSION for the release of six denied Government records regarding a request for records concerning NRC Accountability Announcement No. 197 dated December 19, 1986, subject:
Project Reorganization.
(87-A-20-87-86)
APRIL 24, 1987
3 4 . Received, Cont'd Linda Bauman, APPEAL TO THE ED0 for the release of two denied records Government regarding a request for records concerning a letter Accountability dated December 23, 1986, from Victor Stello regarding Project Rockbestos.
(87-A-21-87-93)
Granted
, Diane Curran, In response to a request for five categories of records Harmon & Weiss related to research matters discussed on page 36 of the (86-849) April 30, 1986 memorandum by V. Stello, made available 31 records. Informed the requester that additional records subject to this request are already available at the PDR.
Steven Sholly, In response to a request for two categories of records MHB Technical related to tests and analyses on high pressure melt Associates ejection, made available 41 records. Informed the requester (87-8) that one additional record subject to this request is already available at the PDR.
Riad Ahmed, In response to a request for a list of users of low-level California carbon-14 and hydrogen-3 radioactive isotopes, made i Bionuclear Corp. available the requested list.
(87-212)
Denied .
Stephanie Murphy, In response to a request for nine categories of records Nuclear regarding electrical cables at the Shearon Harris Information and nuclear pcwer plant, made available 10 records. Informed Resource Service the requester that additional records subject to this (86-760) request are already available at the PDR. Denied 11 records in their entirety, disclosure of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Lyle Graber, In response to a request for copies of (1) enclosures to
> NUS Corporation an NRC letter dated November 19, 1986, to Carolina Power and
-(87-52) Light regarding calibration of test equipment allegation; (2) enclosures to Duke Power Company letter to NRC dated November 10, 1986, regarding the 1986 Inservice Inspection Report; (3) enclosures to Virginia Power Company letter to NRC dated November 14, 1986 regarding the Inservice Inspection Report; and (4) NRC SALP report dated March 7, 1983, on Nine Mile Point Unit 2, made available copies of items 2, 3, and 4 Denied item 1 in its entirety, disclosure of which would ir.terfere with an enforcement proceeding. -
Billie Garde, In response to an APPEAL TO THE COMMISSION AND THE EDO Government for the release of 13 records denied in their entirety Accountability regarding a request for records relating to the proposed Project NRC Manual Chapter 0517, continued to deny these records, (87-A-4-66-215) release of which could stifle honest and frank communications within the agency.
l APRIL 24, 1987 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING APRIL 24, 1987 RFP ISSUED
- RFP No.: RS-ADM-87-211
Title:
" Audiovisual Equipment, Purchase and Installation at One White Flint North"
Description:
The contractor shall provide all equipment, labor and materials necessary for the installation and acceptance of the audiovisual systems at NRC's hearing and conference room facilities located at One White Flint North.
Period of Performance: 18 months Sponsor: Office of Administration and Resources Management Status: Closing date has been extended to April 29, 1987.
PROPOSALS UNDER EVALUATION RFP No.: RS-0RM-87-216
Title:
" Systems Management / Program Support"
Description:
The contractor shall provide, on a task order basis, systems programming support for all NRC in-house computers which presently consist of Data General (DG) and Hewelett-Packard (HP) 16 and 32 Bit CPU's and associated peripherals.
Period of Performance: Three years Sponsor: Office of Administration and Resources Management Status: The competitive range has been established and negotiations are scneduled for the week of April 27, 1987.
RFP No.: RS-RG1-87-271
Title:
" Purchase of Nondestructive Examination (NDE) Materials Testing System"
Description:
The contractor shall provide a system including both equipment and software with the ability to abstract data from various ultrasonic test systems and format the data for presentation on an existing PC. This system will enable the use of data generated during ultrasonic testing (UT) by other automatic or manual, analog or digital data based UT systems to provide independent UT analysis capability to the NRC.
Period of Performance: Delivery within 3 months of contract award.
Sponsor: Region I Status: Negotiations have been completed. Best and Final offers are due on April 28, 1987.
APRIL 24, 1987 ENCLOSURE A
Weekly Information Report Division of Contracts CONTRACTS AWARDED RFP No.: RS-0RM-87-223
Title:
" Cost Analyses of Proposed Changes in NRC Requirements Having Economic Impact"
Description:
The contractor shall provide services for cost analyses to identify, derive and analyze the economic impact of proposed changes in regulatory requirements and the costs to licensees of replacement power when a plant is shutdown.
Period of Performance: 30 months Sponsor: Office of Nuclear Regulatory Research Status: A cost-plus-fixed-fee task order type Contract No. NRC-04-87-086 was awarded to Science and Engineering Associates, Inc., in the ceiling amount of $604,807.00 effective April 24, 1987.
RFP No.: RS-NRR-87-028
Title:
" Operating Reactor Plant Specific Reviews"
Description:
The contractor shall perform, on a task order basis, specific reviews of nuclear power plants.
Period of Performance: 36 months Sponsor: Office of Nuclear Reactor Regulation Status: A cost-plus-fixed-fee indefinite task order type Contract No. NRC-03-87-028 was awarded to SBA/ Viking Systems International in the ceiling amount of $326,290.00 effective April 20, 1987.
This firm has been certified by the SBA as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.
APRIL 24, 1987 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending April 24, 1987
- Susquehanna Units land 2 On April 16.-1987, at about 8:30 a.m., Susquehanna, Unit 2 experienced a Group 1 isolation while the unit was at 100% power. The control room operator observed the successive closure of the MSIVs followed by HPCI start and shutdown, and RCIC start. All safety systems operated as expected. The Pennsylvania Power
& Light Company (licensee) has decided to keep the unit down for at least five days to: (1) repair a defective vacuum breaker solenoid test circuit; and (2) investigate and correct a problem of unidentified coolant leakage in the con -
tainment. A pending emergency change to the Technical Specifications is obviated by this protracted shutdown.
! The cause of Group 1 isolation is unknown at this time. The Resident Inspector is following the licensee's post-trip investigations.
. In addition, en April 15, 1987, Unit I was manually shutdown as a result of an inability to maintain containment integrity during a surveillance test of the containment purge. exhaust valve.
Turkey Point Units 3 and 4 The licensee for Turkey Point has advised Region II that a number of deficiencies have been identified in the load sequencing system of the emergency power electrical system. The deficiencies included jumpers and lifted leads which could have affected the operation of some safety-related power. The information was preliminary and the licensee will continue his investigation through the weekend with the resident inspector and PM monitor-ing their actions. Both units are currently shut down.
Perry Unit 1 - Steam Drain Line Break / Loss of Condenser Vacuum
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On April 14, 1987, at approximately 6:15 p.m., while at 9% power, operatbri noted a decreasing main condenser vacuum coupled with an increased offgas system flowrate. Attempts to restore vacuum were unsuccessful and at 6:17 p.m., the unit was manually scrammed and MSIV's manually closed. The loss of condenser vacuum resulted from a guillotine break of a 3-inch drain line from the "before seat" drains of the turbine stop valves. This drain line expands to six inches and ultimately connects to a 24-inch manifold leading to the high pressure condenser. The break occurred at a weld point in the drain line. No injuries or contaminated personnel resulted from the event.
Magnetic particle inspections of six similar drain lines leading to the manifold revealed cracks in at least four other lines. The licensee intends I
APRIL 24, 1987 ENCLOSURE B
l to replace damaged piping and will be shutdown for at least tendays. The licensee suspects vibration induced cracking (caused by condensate flashing) as the cause. The resident inspector is monitoring the repair effort.
Big Rock Point On April 15, 1987, Region III issued a Confirmatory Action Letter (CAL) regarding the environmental qualification (EQ) of certain electrical cables at the Big Rock Point Plant. Deficiencies in the qualification of certain Butyl rubber and Polyethylene insulated cables needed for post-accident shutdown were identified during a September 1986 Region III EQ inspection. The licensee maintains that the existing test data and analysis in the EQ files for the cables in question provide reasonable assurance that the cables will perform their intended post-accident safety functions. However, in order to achieve prompt resolution of this issue, Consumers Power Company has committed to replace the in-containment cable in question and to provide acceptable written technical justification to support the qualification of the relevant cable located outside the containment. The licensee has scheduled an outage to begin May 31, 1987, for cable replacement and their written justification is to be provided at least two weeks prior to startup from that outage.
Clinton Power Station On April 17, 1987, Illinois Power Company received a full power operating license for Clinton Power Station. On April 10, 1987, the USNRC Commissioners voted 5 to 0 in favor of NRR's issuance of the license when the licensee had resolved the few remaining issues. The facility is located in Harp Township, DeWitt County, approximately six miles east of Clinton in east-central Illinois.
Clinton is the fourth General Electric BWR 6 reactor with a Mark III containment to receive an operating license. The other three reactors are Grand Gulf, Unit 1, River Bend and Perry, Unit 1.
Illirlois Power Company is planning to evaluate its performance against previously prepared perfonnance standards after completion of the power ~ ~
ascension test programs through Test Condition 2 (55% of rated power) before .
proceeding. This performance will be reviewed by the staff before the !
licensee proceeds in the test programs.
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Turkey Point Units 3 and 4 As previously reported, deficiencies were identified by the licensee in the EDG load sequencers at the Turkey Point Site.
The initial findings by the licensee identified wiring discrepancies (i.e.,
l' lifted leads, crossed wires, etc.) which could potentially negate some safety components from being energized during specific sequences. Initially, i the licensee's engineering staff proposed to check all the sequencers (Unit 3 and 4) for the previously identified errors. Based on discussions with the Regional staff, the licensee's operational staff requested that a complete check of the sequencers be performed. The licensee's staff has completed a wire-by-wire check of three of the four sequencers,(several hundred wires) over the weekend. None of the previously identified discrepancies nor any similar wiring problems were identified as the result of the effort to date.
The fourth sequencer cannot be checked until Thursday of this week (4/23/87) due to the Technical Specification requirements for one operable train for Unit 4. The licensee is completing a major overhaul'on one of the two EDG
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4 Region II is sending an electrical inspector to the site. Unit 3 is still in its refueling outage and Unit 4 is completing its clean up and corrective
- actions necessary due to the RCS leakage.
Shearon Harris, Unit 1 i Shearon Harris, Unit 1 achieved the initial 100 percent power plateau at !
12:15 a.m. April 21, 1987. As a result of loss of feedwater, the plant was i manually tripped at approximately 4:50 a.m.' April 21.
Seabrook Unit No. 1 1
On April 22, 1987, the offsite emergency planning Atomic Safety and Licensing Board (Hoyt Board) concluded that the applicant's petition i for a' one mile emergency planning zone under 10 CFR 2.758 and 10 CFR --
! 50.47(c) does not provide a ) rima facie showing on its technical merits; therefore, the Hoyt 30ard will not be recomending to the Comission, at this time, that further consideration should be given to the applicant's motion.
4 The Hoyt Board noted "We do not take a position that a one mile PEPZ for the Seabrook Station is unjustifiable; only that Applicants and j Staff need more time to determine more convincingly whether it is".
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! APRIL 24, 1987 ENCLOSURE B
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR APRIL 20 - 26, 1987 1.- DEFUELING Pick and place fuel removal operations continued. Damaged fuel assembly B-6 was removed using a hook tool. It was subsequently loaded into a canister. The extractor screw tool broke in its initial use while attempting to remove damaged fuel assembly B-7.
One canister was filled and two were partially filled with core material. Two full canisters were transferred to the full spent i fuel pool (one.had been filled the previous week).
- 2. ENVIRONMENTAL MONITORING j -
US Environmental Protection Agency (EPA) sample analysis results
! show that TMI site liquid effluents are in accordance with j regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water effluents are sampled from the station (Units I and 2) discharge and analyzed by EPA.' Gamma spectrum analyses of the seven daily composited samples for April 4 - 11, 1987 indicated no TMI-2 I related radioactivity.
EPA's gamma spectrum analysis of the NRC's TMI outdoor air sample i -
i for April 16 - 24, 1987 showed no reactor related radioactivity.
The water works for the City of Lancaster composited seven daily l samples from April 5 - 11, 1987. EPA's gamma spectrum analysis of .
the composite sample showed no reactor related radioactivity. l
- 3. DECONTAMINATION ACTIVITIES The top flight of the three flight stairwell from the reactor
.! building 305' elevation to the basement was removed. The removal was to allow access with a robot to the basement for examination of the area outside of the west D-ring. Very little is presently known about the conditions in this area.
Auxiliary building sump desludging continues. Thus far, three 160
, cubic foot solidified containers have been generated. The project-
) is expected to generate four containers.
Robot desludging in the reactor building basement continues. The dewatered sludge is being held in the modified spent resin storace
- tanks in the auxiliary building basement.
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Robot scabbling in the seal injection valve room continued.
- 4. NRC EVALUATIONS IN PROGRESS i
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- a. Completed i
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Temporary Reactor Vessel Filtration System Safety Evaluation Report, j Revision 3, was issued on April 21, 1987.
l l APRIL 24, 1987 ENCLOSURE B l
- b. In Progress Technical Specification Change Requests 52, 55 and 56. "
Solid Waste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Processed Water Df: position Proposal.
Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Pressurizer Defueling Safety Evaluation Report.
- Safety Evaluation Report for Defueling of the Core Support Assembly.
' - Canister Handling and Preparation for Shipment Safety Evaluation l Report, Revision 4.
- 5. MEETING The Advisory Panel for the Decontamination of Three Mile Island Unit 2 has not set a meeting date. Future meetings will be announced.
Persons desiring to speak before the Advisory Panel are asked to contact Mr. Thomas Smithgall at 2122 Marietta Avenue, Lancaster, PA 17603 (telephone 717-291-1041). Persons desiring to submit topics or questions for the Advisory Panel to consider are asked to contact the Chairman, Mayor Arthur Morris,120 North Duke Street, Lancaster, PA 17602.
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APRIL 24, 1987 ENCLOSURE B
0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS ..
Items of Interest Week Ending April 24, 1987 URENCO NRC staff members (SEC, IP, FC) met with URENC0 representatives to discuss forthcoming security procedures for handling sensitive and classified information on uranium centrifuge enrichment, as marked and controlled by European governments. The Division of Security is now in a position to grant clearances to four individuals associated with URENC0 for access to certain limited information. Subsequent discussions with the FRG (German), Dutch, and British embassies and the Department of State will be arranged and coordinated by IP and URENCO.
Explosive Detectors Using Neutron Sources An April 18, 1987 article in "The New York Times stated that the Federal Aviation Administration (FAA) plans to install explosives detectors utilizing californium-252 neutron sources at major airports within two years.
Activation of baggage, food and medicine appear to be the items of most concern. Based on the information available to us, the amount of radioactivity in these items appears to be very small. An Agreement State licensee is
- authorized to develop these devices. 0GC's opinion has been solicited on what regulatory jurisdiction NRC has over activation products produced by the californium-252. NRC has not received a license application for this activity.
Meeting on Bi-lateral Agreement The Department of State requested a meeting with NRC and 00T staff to discuss US decisions on authorizing the shipment of plutonium by air. The meeting took place on April 22, and representatives from Safeguards and Transportation, International Programs, and the General Counsel attended.
Issues discussed included US certification for air transport containers, transient shipment requirements, and establishment of air routes.
APRIL 24, 1987 ENCLOSURE C
2 Cracked Stiffening Rings on UFg Cylinders-Update ,
The NRC has information that some 48-inch diameter UF g cylinders have stiffening rings fabricated from material which may n5t meet ASME and ANSI Standards. Up to 352 cylinders may be affected. Radial cracks have been detected on some of these stiffening rings. 00T regulations which become effective on June 30, 1987, will require UF cylinders g to meet ASME and ANSI Standards. To avoid unnecessary site operations to remove UF g from cylinders which cannot be transported, an order is being prepared to preclude loading of affected cylinders until it is clear that the cylinders can be transported under the new DOT rules.
LEU Reform Rule Plan Approved The 10 CFR 74.31 Fundamental Nuclear Material Control Plan (as revised) submitted by Advanced Nuclear Fuel Corporation. (ANF), formerly Exxon Nuclear Company has been found acceptable. ANF's Plan is the second to be approved of the six Plans submitted pursuant to the 74.31 LEU Reform Rule. The four remaining Plans are all in need of further revision before being deemed acceptable. Westinghouse-Columbia is the other licensee having an approved j 74.31 Plan.
Shipment of Spent Fuel from the National Bureau of Standards A representative'of the Division of Safeguards and Transportation visited the National Bureau of Standards (NBS) Research Reactor facility on April 20, 1987. This visit was to observe the loading of a spent fuel shipment into the General Electric Model 700, NRC-Certified cask. It was the first such
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shipment by NBS in over nine years, and was the first of a campaign of some seven expected shipments to DOE at Savannah River which are planned over the next two months.
West Valley Modeling Needs The staff has developed an approach to assessing hydrogeologic modeling needs for the West Valley Nuclear Services Site in Cattaraugus County, New York. The approach was developed in support of ongoing discussions with the Department of Ener'gy and contractors regarding environmental impact and safety assessments.
This approach, which compares alternate radionuclide transport pathways using the dose limit performance objective in 10 CFR Part 61, will be refined through discussions within NMSS and with RES prior to meeting with DCE.
Alternate Concentration Limits In support of NRC's ongoing licensing of uranium mills and efforts to conform 10 CFR Part 40, Appendix A with EPA's September 1983 uranium mill tailings !
regulations, NRC staff consulted with EPA in developing joint guidance on a j methodology to establish Alternate Concentration Limits (ACLs) for contaminants ;
in groundwater. The NRC staff has learned of recent EPA policy decisions re-l garding ACLs that could significantly restrict the flexibility of the ACL methodology. J The methodology will be needed by NRC for licensing new uranium 1 l
APRIL 24, 1987 ENCLOSURE C
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mills. In' addition, the methodology is a key component in support of NRC's
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current rulemaking to conform 10 CFR Part 40 with 40 CFR Part 192. NRC and EPA staff are meeting to develop a mutually acceptable approach for establishing
- Alternate Concentration Limits.
! Status of Maxey Flats CERCLA Activities
^
The inactive low-level radioactive waste disposal facility at Maxey Flats,
. Kentucky, has been identified on the National Priorities List fo'r remedial action under CERCLA (Comprehensive Environmental Response, Compensation, and i Liability Act of 1980). EPA has identified potentially responsible parties l (PRPs), including D00, DOE, and EPA, and encouraged PRPs to agree to conduct i the remedial actions. Concurrent with the identification of PRPs, EPA is conducting a Remedial Investigation / Feasibility Study (RI/FS) with PRP
- oversight to determine the extent of contamination and feasible . remedial
] actions to mitigate potent'ial hazards. NRC staff will continue to observe the progress of the CERCLA activities at the Maxey Flats site to assess their potential implications for existing and future low-level radioactive waste disposal facilities.
Radioactive Biohazardous Wastes On Wednesday, April 15, 1987, NRC staff met with representatives from the '
George Washington University (GWU) Medical Center to discuss the generation, storage, and disposal of radioactive wastes containing biological, pathogenic or infectious material.
The GWU staff described its practices for handling infectious, radioactive, infectious / radioactive chemical, and non-hazardous wastes. The NRC was provided i
with a tour of the facilities at the hospital and university which included steam sterilization autoclaves, nuclear research laboratories, P-3 (biohazardous) 3 laboratory, and a waste incinerator.
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. APRIL 24, 1987 ENCLOSURE C
OFFICE OF NUCLEAR REGULATORY RESEARCH l Items of Interest -
Week Ending April 24, 1987 i
License Renewal Policy j AIF presented the results of their study of license renewal issues, :
" Regulatory Considerations for Extending the Life of Nuclear Power Plants,"
at a meeting with the staff and our contractor, MITRE.
Chernobyl Implications Report A Staff Requirements Memo is expected that directs the staff to have draft NUREG-1251, " Assessment of the Implications of the Accident at Chernobyl for Nuclear Safety Regulation in the United States," professionally edited and resubmitted to the Commission by June 1, 1987, prior to issuance for public comments.
Spent Fuel Pool Accidents The staff met with BNL to discuss comments on and revisions to their report on the risk of spent fuel storage pools. The comments and revisions primarily address the proper characterization and qualification of the various factors that are combined to make the risk estimate. A DOE representative, who is participating in the IAEA workshops on spent fuel pool safety and monitoring this generic issue, attended.
ECCS Rule A notice of the availability of NUREG-1230, "A Compendium of ECCS Research for Realistic LOCA Analysis," is being published in the Federal Register for public comment.
B&W T-H Experimental Program RPSB will mtet with the B&W Owners Group on May 29, 1987, to continue the discussion of the need for industry support of the B&W Thermal-Hydraulic Experimental Program.
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NUREG-1150 Workshop The NRC Sponsored a seminar during April 21-22, 1987 to explain the methodology for calculating reactor risk to recipients of NUREG-1150. The researchers who did much of the risk calculations gave presentations and answered a limited number of questions about the methodology. The meeting was attended by about 160 people representing several branches of the NRC, utilities, architect / engineering fims, contractors, industry groups, national laboratories and public interest groups. HUREG-1150, " Reactor Risk Reference Document," is currently in its public comment period which ends August 21, 1987. . ..
Expert Review of NUREG-1150 Methodology for Uncertainty Analysis A meeting was held by the BNL Review Committee for NUREG-1150 Uncertainty Methodology (H. Kouts, chaiman; R. Farmer, S. Hanauer, A. Cornell and N.
Rasmussen, members) during April 20-22, 1987 at the Holiday Inn-Crown Plaza Hotel in Rockville. The committee was briefed by the NRC contractors on the methodologies used in NUREG-1150, with emphasis on approaches to address issues related to uncertainty. In addition, industry representatives (EPRI, IDCOR, NUS, PL&G, and Stone and Webster) presented their views on the subject. The review committee is currently in the process of completing their final report to the staff.
Piping Erosion / Corrosion Meeting A meeting was held on April 16 to review research related activities underway on erosion / corrosion, and to hear a brief report on the previous two day meeting held by EPPI wherein the industry reviewed its own actfvities. NRC was represented by NP,R and RES personnel, while the presenters included three French researchers who attended the EPRI meeting, an EPRI representative, and RES contractors from BNL, ANL, MIT and a private consultant. The meeting included presentation of the failure analysis of the Surry pipe, a review of erosion / corrosion including an overview of the significant amount of work done in France, the U.K. and Germany that sets the basis for an excellent understanding of the factors affecting the pftenomenon, a presentation by the French on more detailed aspects of their work, a review of past industrial practice regarding inspection and experience on erosion / corrosion, and a summary of the future industry program for action. The industry reportedly is working to set up a 4
procedure for selection of locations for inspection to reveal the presence of wall thinning. EPRI intends to help implementation of this by writing a program that can be run en a PC type of computer for identification of the locations. The exact pinpointing of locations for inspection is very important because removal of insulation or other activities to gain access for inspection can be exceptionally expensive and can incur APRIL 24, 1987 ENCLOSURE D
1 A
.3-significant man / rem costs, whereas the ultrasonic test inspection itself was claimed to have a cost on the order of one hundred dollars. EPRI hopes to e
have its program ready for use during the summer of 1987. RES will complete its report on a summarization of the factors affecting erosion / corrosion, as derived primarily from foreign research findings, a summary of industry experience and practice, and the failure analysis of the Surry pipe, all by mid-June 1987.
NRC Management Meeting With Utility Worker Unions At the request of the Utility Workers Union of America (UMUA), RES hosted a meeting with representatives of UWUA, the International Brotherhood of Electrical Workers (IBEW) and managers of other NRC offices on April 20, 1987. The purpose of the meeting was to discuss utility worker concerns about how NRC regulatory decisions are made and implemented, and ways to get worker input into regulatory decisions that affect them.
- The union representatives complained that' issues such as overtime limitations, hands-on-search, fitness-for-duty and operating room-professionalism are decided and imposed without any effective dialogue with l workers. Often the new restrictions conflict with bargaining agreements t established under DOL regulations, and in several cases union legal action j has resulted in injunctions or reversals.
Suggestions for establishing a communication link with the unions were discussed. RES and OGC are preparing joint recommendations to the EDO
- regarding reso'lution of this issue.
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APRIL 24, 1987 ENCLOSURE D
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RES RULEMAKING ACTIVITIES ..
l Elimination of Inconsistencies Between Part 60 and EPA HLW Standard (Part 60) .
- The Nuclear Waste Policy Act of 1982 directs NRC to. promulgate criteria for the -licensing of HLW geologic' repositories. Section 121 (c) of this act i states that these criteria must be consistent with standards to be developed by EPA for the disposal of HLW in deep geologic repositories. The proposed 4
rule is needed in order to eliminate several. inconsistencies with the EPA standards, thus. fulfilling the statutory requirement.
! A Commission paper transmitting the final rule was forwarded for OGC and NMSS review and concurrence on February 12, 1987. To date, NMSS.has concurred. Staff is currently awaiting OGC response.
Production and Utilization Facilities: Timing Requirements for Full i Participation Emergency Preparedness Exercises for Power Reactors Prior to Receipt of an Operating License (Part 50)
~
I The proposed rulemaking would relax the timing requirements for a full participation emergency preparedness exercise for power reactors prior to receipt of an operating license. The Commission believes that adoption of the proposed rule would more effectively focus available resources on the pertinent issues and problems in establishing'and maintaining an upgraded and effective day-to-day status of emergency preparedness.
l The final rule was signed by the EDO and forwarded to the Commission for approval on April 6, 1987 (SECY-87-92).
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l APRIL 24, 1987 ENCLOSURE D i
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! GOVERNMENTAL & PUBLTC AFFAIRS WEEK ENDING APRIL 24, 1987 State, Local and Indian Tribe Programs Weekly Highlights - April 24, 1987 Interagency Res)onse Video On Apr'1 21, 1937, Sheldon Schwartz met with the Illinois Department of Nuclear Safety (IDNC) in Springfield, Illinois and Comonwealth Edison Comonwealth Edison Company (CECO) in Chicago, Illinois to discuss Video Taping of the Dry Run Drill and the Federal Field Exercise. IDNS representatives are supportive of the project and will cooperate in the project. CECO indicates that they were not planning to do any " Broadcast Quality" taping however, they would now consider taping activities at the joint public information center.
! Additionally, they have 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of tape that was professionally taken during a 1984 Dresdon Exercise and never used. CECO is considering providing this tape for use in the interagency video. Funding for this project is being provided by AEOD and FEMA.
4 Low-Level Radioactive Waste Forum As part of NRC's effort to support the national policy of reliance on States to provide disposal capacity for all low-level radioactive waste (LLW) by providing information to States and interstate compacts, Frank Young, State, Local and Indian Tribe Programs, will attend the Low-Level Radioactive Waste Forum, Las Vegas, Nevada, April 27-30, 1987. The LLW Forum is an association of representatives of States and interstate compacts established to facilitate-State and compact commission implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of LLW regional compacts. The Forum provides an opportunity for States and compacts to share
, information with one another and to exchange views with officials of Federal agencies.
Topics that Frank Young will discuss from the NRC perspective include LLW below
- regulatory concern, mixed LLW, emergency access to operating sites, storage and disposal at nuclear power plants, and source term estimates. Also, financial assurances and liability, a topic of major concern to the States and compacts will be a subject of one full day of the meeting. Other agenda items include LLW data collection, storage, maintenance and distribution; volume reduction, l economic modeling, the 1988 milestone, and DOE technical assistance.
Agreement State Program Review l The radiation control program of Oregon and North Dakota will be reviewed the l week of April 27, 1987. ;
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4 APRIL 24, 1987 EhCLOSURE E
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Office for Analysis and Evaluation of Operational Data Items of Interest '
Week Ending April 24, 1987
- 1. Incident Response ..
A staff representative participated at an International Atomic Energy Agency (IAEA) Advisory Group meeting on April 6-10, 1987 to develop methods for the early monitoring of the accident release source ~at a nuclear installation and means of event classification. The IAEA Group adopted most of the material from draft NUREG-1210, Vol. 6 on " Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents." It also appears.that the IAEA Group will adopt a method of event classification that parallels that used in NUREG-0654 and that a draft will be available for agency review in 6-8 weeks.
An upgraded version of the computer code IDAS used in the Operations Center for dose profections was installed during the week of April 20, 1987. The new computer model provides for a more rapid easy to use display system.
FFE preparations continued and included training for the Executive Team on April 22, discussions with RIII management on April .23, and the final meeting of the scenario work group in Chicago on April 24.
A meeting between participants of the Institute of. Nuclear Power Operations (INP0) Senior Nuclear Plant Management Course and the Chairman / Commissioners,
, the EDO and other senior NRC managers was conducted in the Operations Center on April 24, 1987. This meeting, which is part of the course curriculum, provided the participants an opportunity to obtain NRC views regarding matters that help assure safe nuclear power plant operations, to ask questions regarding NRC policies and practices, and to tour the Operations Center and discuss NRC response activities.
Two members of the Technical Training Center (TTC) staff observed and evaluated the operational response and potential NRC training capability of the Babcock and Wilcox (B&W) simulator for the WPN-1 plant in Richland, Washington on April 21-22, 1987. The evaluation ~ indicated that the
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simulator would be acceptable for NRC training purposes. Based on this evaluation and a similar evaluation of a B&W simulator associated with the cancelled Midland plant, TTC plans to develop a request for proposal to initiate the competitive procurement process to see if a B&W simulator can be relocated to the TTC within the existing TTC budget.
The following Preliminary Notifications were issued during the past week.
- a. PNS-I-87-06, Rochester Gas & Electric Company (Ginna Station), Bomb Threat.
- b. PNO-I-87-33, Polyclinic Medical Center, Malfunction of Teletherapy Unit. i APRIL 24, 1987 ENCLOSURE H l
- c. PN0-III-87-57, Illinois Power Company (Clinton Nuclear Plant),
Issuance of Full Power Operating License.
- d. PNO-III-87-58, Toledo Edison Company (Davis-Besse Nuclear Plant),
Decision Issued on Burial of Radioactive Waste Material.
- e. PN0-III-87-59, Illinois Department of Nuclear Safety, Alleged Misidentification of Low-Level Waste Shipments.
- f. PNO-IV-87-18, Public Service Company of Colorado (Fort St. Vrain Nuclear), Reactor Startup after Prolonged Shutdown.
- g. PN0-IV-87-19, Public Service Company of Colorado (Fort St. Vrain),
Conviction of Former Manager of Nuclear Production.
- h. PNO-V-87-30-A, Pacific Gas & Electric Company (Diablo Canyon Unit 2), '
Loss of Suction to Residual Heat Removal System While at Half-Loop.
- i. PN0-V-87-32, Arizona Nuclear Power Project (Palo Verde Unit 3),
Foreign Material Found in Steam Generator.
- 2. Trends and Patterns The AE00 Annual Report covering AE00 activities for January through Deceber 1986 was distributed this week. The report provides selected comments and observations resulting from the review of operational data and AEOD trends and pattern program studies. A brief summary of the Office's activities and accomplishments during this period is included.
The technical evaluation program results are highlighted and a number of the program activities are discussed including ongoing studies and available reports. Also included are a status and summary of the AE00 recommendations that are new or that remained outstanding from the last report.
l APRIL 24, 1987 ENCLOSURE H
CRGR f10fiTHLY REPORTS Week Ending April 24, 1987 ,.
CRGR Attached is a summary of the CRGR activities for the period January 1 through March 31, 1987. Background material on topics reviewed by the Committee and the minutes of CRGR meetings is sent to the Commission. Copies are provided to the Public Document Room after the NRC has considered (in a public forum) or decided the matter addressed by th'e documents. Questions concerning this monthly report should be referred to Tom Cox (492-9855).
APRIL 24, 1987 EllCLOSURE L
i 2 Page'1 of 3 Date: April 20, 1987
- 8
SUMMARY
OF CRGR ACTIVITIES i ;: (January 1 through March 31, 1987)
- Meeting No. CRGR CRGR Recommendation g Meeting Date Agenda Status to EDO EDO ction 111 Review, Proposed 50.54(f) Complete CRGR recommended that the pro- No action required 3/11/87 Letter concerning Mark I posed letter be issued after Drywell Corrosion Problems modification to reflect
.; CRGR comments
! -Sponsoring Office - NRR
-Category 2 Item
-Issue #162 1
110 Review, Proposed 50.54(f) Complete CRGR recommended that the pro- No action required 2/25/87 Generic Letter Concerning posed generic letter be issued Integrity Verification for after modification to reflect Pressure Isolation Valves recommended language revisions in the Reactor Coolant j System i -Sponsoring Office - NRR
-Category 2 Item
-Issue #123 109 Review, Proposed new SRP Complete CRGR recommended that the staff No action required 2/9/87 Section 6.5.5, " Pressure issue the proposed SRP for
, Suppression Pools as Fission comment after appropriate
. 02 Product Cleanup Systems" revisions to reflect CRGR .
E comments h -Sponsoring Office (NRR) g -Category 2 Item j
m- -Issue #161 r-i
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3 Page 2 of 3 Date: April 20,19%
- g
SUMMARY
OF CRGR ACTIVITIES p: (January 1 through March 31, 1987)
- Meeting No. CRGR CRGR Recommendation
@ Meeting Date Agenda Status to EDO EDO Action 108 Review, Proposed Final Complete CRGR recommended that the pro- Approved by the EDO 2/5/87 Rule Concerning Rqts. posed final rule be issued and forwarded to the for Criminal History after modified as agreed by Commission Checks CRGR and NMSS
-Sponsoring Office - NMSS
-Category 2 Item
-Issue #144 107 Review, Proposed Rule Complete CRGR recommended that the Proposed Approved and forwarded 1/20/87 Changes to Deal with Lack Rule be approved by the EDO after of Governmental Cooperation to the Commission.
modifications to reflect CRGR Proposed rule has been <
in Offsite Emergency Planning concerns. published in the 8 for public comment.
-Sponsoring Office - OGC
-Category 2 Item
-Issue #160 106 Review, Final Rule Entitled Pending CRGR recommended that the proposal No action required at 1/28/87 Reporting Requirements for be modified to incorporate CRGR Safeguards Events this time comments and then be rereviewed by the CRGR Chairman to determine
-Sponsoring Office - NMSS if additional CRGR action is m -Category 2 Item required.
M -Issue #159 g __________________________________________________________________________________________________________
E Review, Final Property Complete CRGR recommended that the rule No action required at M Insurance Rule be forwarded to the EDO for this time.
r_ approval after modification
-Sponsoring Office - SP to reflect CRGR comments.
-Category 2 Item
-Issue #33
3 Page 3 of 3 Date: April 20, 1987
- g
SUMMARY
OF CRGR ACTIVITIES
- (January 1 through March 31, 1987) 2 o
Meeting No. CRGR CRGR Recommendation g Meeting Date Agenda Status to EDO EDO Action 105 Review, Proposed Licensing Pending CRGR recommended that the proposed No action required at 1/15/87 Guidance on New Rules guidance-be issued via generic this time (Search Requirements and letter after modifications to Miscellaneous Amendments) reflect CRGR comments. However, prior to issuance a copy should be
-Sponsoring Office - NMSS forwarded to the CRGR Chairman
-Category 2 Item to assure that no further CRGR
-Issue #158 consideration is necessary.
Briefing, NRC's Request to Complete No CRGR recommendation necessary No action required OMB to Continue the Reporting and Recordkeeping Burden of 10 CFR Part 50
-Sponsoring Office - IRM
-Category 2 Item
-Issue #122 Review, Proposed Rev. 2 of Complete CRGR recommended that the proposed No action required.
SRP 6.5.2, " Containment Spray revision be issued for public as a Fission Product clean-Up comment after modification to System" reflect CRGR comments
-Sponsoring Office - NRR
-Category 2 Item E -Issue #157
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ITEMS ADDRESSED BY THE COMMISSION WEEK ENDING APRIL 24, 1987 A. STAFF REQUIP.EMENTS - BRIEFING ON STATUS OF PEACH BOTTOM, 3:45 P.M., FRIDAY, APRIL 10, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo J. C. Hoyle, Asst. SECY to V. Stello, ED0 dated 4/21/87 The. Commission was briefed by the staff on the status of the Peach Bottom nuclear power plants, which were shut down as a result of the reactor operators sleeping in the control room.
The staff committed to provide the Commission a comparative analysis of the frequency of shift rotation at all commercial nuclear facilities and their associated human factors on operator alertness.
B. STAFFREQUIREMENTS-PERIODICMEETINGWITHADVISORYCOMMITTEEONREACTOR SAFEGUARDS (ACRS), 10:00 A.M., FRIDAY, APRIL 10, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo J. C. Hoyle Asst. SECY to R. Fraley, ACRS dated 4/22/87 The Commission was briefed by the ACRS on its recommendations for further consideration of desired features in advanced nuclear reactors for electric power generation.
Chairman Zech recommended that the ACRS pursue its review of
- the experience and design features of some of the European plants. In addition, Chairman Zech recommended that the ACRS address the feasibility, benefit, and cost effectiveness of selected and combined systems recommended in the Kerr to Chairman Zech letter dated January 15, 1987. The review should include plant reliability, challenges, complexity, and burden on plant and maintenance personnel. The ACRS.should also provide the name(s) of an existing plant (s) which incorporates the desirable features recommended in the January 15, 1987 letter.
I C. STAFF REQUIREMENTS - BRIEFING BY THE OFFICE OF SPECIAL PROJECTS,10:00 A.M., l WEDNESDAY, APRIL 15, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN i TO PUBLIC AFFAIRS) - Memo J. C. Hoyle, Asst. SECY to Memo for the Record dated 4/23/87 The Commission
- was briefed by the staff from the Office of Special Projects on activities relating to the review of the Comanche Peak and TVA plants.
'l There were no requirements placed on the staff at this meeting.
- Commissioner Carr was not present.
APRIL 24, 1987 ENCLOSURE N
D. STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 4:00 P.M., THURSDAY, APRIL 16, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE LOPEN TO PUBLIC ATTENDANCE) - Memo J. C. Hoyle to W. C. Parler, GC dated 4/24/87 2
I. SECY-87 Exemptions from 18 USC 208(a) (Financial Interest Posing Conflict of Interest) for NRC Employees The Commission,* by a 5-0 vote, approved revisions to 10 CFR 0.735-21 which are intended to clarify the standards and procedures for the granting of exemptions from the prohibition
, against an employee's personal and substantial participation in a particular matter the outcome of which would have a direct and predictable effect on the financial interest of the employee or certain related persons.
Following approval by the Office of Government Ethics, the Federal Register Notice should be forwarded to SECY for signature and publication.
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- Section 201 of the Energy Reorganization Act, 42 U.S.C.
S5841, provides that action of'the Commission shall be deter-mined by a " majority vote of the members present." Commissioner Carr was not present when this item was affirmed. Accordingly, the formal vote of the Commission was 4-0 in favor of the i decision. Commissioner Carr, however, had previously indicated that he would approve this paper and had he been present he j would have affirmed his prior vote.
i APRIL 24, 1987 ENCLOSURE N l
3 l E NRR MEETING NOTICES
- i g . APRIL 24, 1987
- ts
, Q3 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/28/87 50-424 Vogtle Site To discuss in detail the Vogtle NRC/GPCo M. A. Miller 9:00 a.m. Waynesboro, GA Unit I startup history.
5/5/87 50-443 Room P-118 To discuss technical issues that NRC/PSNH-NHY S. Long 1:00 p.m. Phillips Building have developed during the course '
of the NRC staff's review of the applicant's 10 CFR 2.758 petition.
5/8/87 -
Room P-114 To review River Bend Station (RBS) NRC/GSU S. M. Stern 10:00 a.m. Phillips Building plans for fuel reload. ,
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- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms A summary of these meeting notices can be obtained by calling 492-7424 EE .
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3 p: NMSS MEETING NOTICES h0 DIV!sION OF FUEL CYCLE, MEDICAL, ACADEMIC AND COMPERCIAL USE SAFETY hh y
FOR WEEK ENDING DOCKET ATTENDEES /
April 24,1987 DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 4/28/87 Senate-Dirckson Johnson /McClure HLW H. Thompson, PIMSS Browning 9:30 a.m. Bldg., Room 366 Hearings R. Cunningham, NMSS R. Browning, NMSS 4/29/87 Project M-40 Silver Spring, MD To discuss submittal J. Roberts, NMSS J. Roberts of topical report for a A. Wells, Nuclear new dry spent fuel storage Assurance Corporation cask design (NAC) (NAC) 4/29-30/87 70-143 Erwin, Tf! To attend Quarterly Program L. Rouse L. Rouse Review Meeting at Nuclear Region II Fuel Services, Inc. (NFS) 8. Knight, NFS 5/4/-8/87 Dak Ridge, TN To meet with DOE contractors T. Clark, NRC T. Clark to discuss safety analyses E. McKenna, NRC of. existing gaseous diffusion plants DIVISION OF SAFEGUARUS AND TRANSPORTAIION None E2 .
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NMSS MLETING NOTICES FOR WELK ENDING: 4/24/87 DIVISION OF LOW-LEVEL WASTE MANAGEMENT AND DECOMMISSIONING
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DOCKET ATTENDEES / NRC NUMBER LOCATION PURPOSE APPLICANT CONTACT g DATE/ TIME t
m .
J 4/28-5/1/87 Grand Attend Remedial Action Annual Meeting H. Thompson (NMSS) Knapp
C0; Las chemical waste disposal site (Nevada) D. Sollenberger (LLWM)
Vegas, NV and tour mill tailings sites (Colorado).
1 DIVISION OF HIGH-LEVEL WASTE MANAGEMENT To attend the Defense Waste Processing RBallard EAWick 4 April 21-24 Savannah River Plant CPeterson Aiken, SC Facility Technology Exchange and Site
- EAWick Visit i TCJohnson To attend meetings and make presentation RLJohnson RLJohnson May 5-7 Hyatt Regency Hotel 13210 Katy Freeway (I-10) on Exploratory Shaft Facility Design (ESF) NTanious Houston, Texas 77079 .to give overview of past NRC issues and MNataraja i
comments. JPearring ;
i DOE contractors States and Indian tribes Meetings to discuss various activities PAltomare PAltomare June 9-10 Embassy Square Suites m 2000 N Street, NW underway in HLW program, including NRC's ABender i
' approach to identification and resolution BChampion ?
f Washington, DC o -
of issues, status of NRC rulemakings, HLWM staff j
States and demonstration of the pilot program m associated with the Licensing Support Indian tribes-System DOE o -
Federal agencies 1
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. April 24,1987 4 > RII MEETING NOTICE I
N
- P DOCKET ATTENDEES /
j DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT i - 4/28/87 Miami, FL Turkey Point AIT exit Licensee representatives, Grace
] $
1:00 p.m. J. Sniezek, J. Grace and-selected RII. staff members 1
~
5/7/87 RII Office Meeting with 0. Kingsley, Licensee representatives Grace 4 10:00 a.m. W. Cavanaugh, and and Regional ~ Administrator 1
T. Cloninger, System Energy Resources. Inc. to discuss items of mutual i interest 5/13/87 RII Office Enforcement Conference - Licensee, Regional Admini- Grace -
! 10:00 a.m. Oconee Facility stator, and selected RII staff members 5/14/87 RII Office Management Meeting Same as above -Grace 10:00 a.m. Florida Power and Light Company i 5/28/87 Hartsville, SC Presentation of Operator Licensee management and Grace p.m. Certificates at Robinson operators, and Regional '
Administrator I
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