ML20140G730
| ML20140G730 | |
| Person / Time | |
|---|---|
| Issue date: | 03/27/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860321, NUDOCS 8604030274 | |
| Download: ML20140G730 (47) | |
Text
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90s s
March 27, 1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 21, 1986 A summary of key events is included as a convenience to those Commissioners 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
Executive Legal Director F*
International Programs G
State Programs H
Resource Manegement I
Analysis and Evaluation of Operational Data J
l Small & Disadvantaged Business Utilization & Civil Rights K*
Regionil Offices L
CRGR Monthly Reports M
Executive Director for Operations N*
Items Addressed by the Commission' 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution) s g,
- No input this week.
/
r 8604030274 e60327 T. A. Rehm, nt for Operations PDR COMMS NRCC Office of the Executive Director WEEKLYIN OREPT PDR for Operations
Contact:
T. A. Rehm, ED0 492-7781
HIGHLIGHTS OF WEEKLY INFORMATI0!1 REPORT WEEK ENDING MARCH 21, 1986 Vogtle Electric Generating Plant, Units 1 and 2 On Friday, March 14, 1986, the evidentiary hearing was conlcluded before the Atomic Safety and Licensing Board on safety issues (groundwater contamination, qualification of ASCO solenoid valves, and dose-rate effects of cable). A further hearing on emergency planning issues is contingent upon the Board's rulings on motions for sumary disposition.
Also on March 14, 1986, two ex-employees of Georgia Power Company appeared on the Phil Donohue Show complaining about improper urinalysis tests which resulted in their firing. The women stated that they were targeted for testing as a result of raising safety concerns at Vogtie and implied that the NRC violated its promise of confidentiality.to them.
Comanche Peak During a conversation with the staff on March 4, 1986, Billie Garde of the Government Accountability Project indicated that two more individuals (unidentified) had contacted her to assist in bringing additional allegations to the NRC concerning Comanche Peak. By letter dated March 5, 1986, the staff requested an opportunity to interview the two individuals on March 11, 1986, following an interview she had set up for the staff with another individual.
Following several phone conversations, by letter dated March 18, 1986, GAP responded that the two individuals will be made available to the staff only after they have been debriefed by GAP investigators and assigned an attorney or other representative who is able to represent them before the NRC, a process which will take an additional few weeks.
Following that time, GAP will set up the interviews.
The staff is preparing another letter to B. Garde again requesting the staff be provided with an interview schedule. The staff will consider further action (legal) if GAP continues 'to delay all staff efforts to contact the allegers.
DOE Satellite-Tracking for Department Shipments of Radioactive Material DOE Defense Programs is currently evaluating the use of a satellite-tracking system for large quantity radioactive material shipments.
The system would allow DOE to determine in " realtime" (instantaneously) a shipment's geographic j
position and other information. One system under consideration would consist
)
of three basic components:
(a) individual shipment " transceiver"; (2) three satellites in orbit above the United States; and (3) a powerful computer i
system at a ground location.
Every shipment transceiver would have a unique identifying code; the pulse emitted from the transceiver would be received by the satellites and relayed by microwave to the ground station, and on to I
monitoring stations. DOE plans to conduct a 6-month test of the satellite 1
tracking system beginning in late 1986.
The DOE's OCRWM will evaluate the possible application of the system to NWPA shipments.
Nuclear Fuel Services, Inc.
On March 18, 1986, members of the NRC staff met with Mr. John Kirk.III, of Bristol, Tennessee, to discuss what information a group of investors would need to supply NRC for review and approval of a change of ownership at a licensed facility. This group is considering the purchase of Nuclear fuel Services' Erwin, Tennessee facility.
MAR ! ; y
0FFICE OF ADMINISTRATION Week Ending March 21, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 198 32 Granted 134 11 Denied 39 2
Pending 206 34 ACTIONS THIS WEEK Received Stephanie Murphy, Requests records containing (1) allegations made by Nuclear Information Frank Pequese regarding construction defects, improper and Resource procedures, poor quality assurance or other complaints Service against the Shearon Harris nuclear power plant and (2)
(86-167) instances or allegations of water leakage in specified locations at the Shearon Harris plant.
William Greaney, Requests all records coretaining references to 17 named Covington &
persons, firms, or organizations.
Burling (86-168)
Art Kohn, Requests copies of records submitted by General Electric
' WWAY-TV ~
regarding a January 22, 1986, incident at its plant in (86-169)
Wilmington, North Carolina, and NRC's findings and citations.
Robert J. Sugarman, Requests a copy of Effluent Report No. 3 for Limerick Sugarman &
Unit 1 submitted by Philadelphia Electric Company by Hellegers letter dated February 28, 1986.
(86-170)
B.S. Dunn, Requests a list of fees charged for 1978 to date for six General Electric referenced 70 dockets.
(86-171)
Joan C. Bready, Requests all issues of the " Caseload Forecast Five-Year KMC, Inc.
Plan".
(86-172)
CONTACT:
Donnie H. Grimsley 492-7211 ENCLOSURE A
,,,3a
- ~:
m
2 Received, Cont'd Jin Harding, Requests copies of Caseload Forecast Review Panel records MHB Technical from January 1,1979, to December 31, 1981, re~garding the Associates Diablo Canyon nuclear power plant and the Diablo Canyon (86-173)
Project Manager's records from January 1,1979, to December 31, 1981, regarding the Caseload Forecast Review Panel.
Patty Day, Requests a copy of the procedure approved by Harold Denton NUS Corporation in mid-1985 allowing a 40-year license extension, (86-174) as mentioned on page 11 of the January 6,1986, issue of Inside NRC.
Jim Pedro, Requests a copy of report NED0-23566, " Structural NUS Corporation Analysis of Reactor Pressure Vessel and Internals for (86-175)
Vessel Head Drop."
Jim Pedro, Requests copies of the " Structural Integrity Test Reports" NUS Corporation for Shoreham, Limerick-1, Nine Mile Point, and Susquehanna.
(86-176)
Jim Pedro, Requests a copy of the February 4, 1986, memorandum for NUS Corporation Harold Denton from Victor Stello, subject: " Staff (86-177)
Actions Resulting from the Investigation of the November 21 San Onofre Nuclear Generating Station, Unit 1 Event (NUREG-1190)."
Billie P. Garde, Requests copies of two denied records regarding plans Government and proposals for 01 and OIA to be combined.
Accountability Project (86-178)
Billie P. Garde, Requests copies of one denied record regarding the
. Government June 29, 1984, meeting between TUECO officials and the Accountability NRC staff relating to the investigation concerning illegal Project use of drugs at the Comanche Peak site.
(86-179)
Billie P. Garde, Requests copies of all records regarding inspections by Government Region IV into allegations by current or fonner employees t
Accountability of the Comanche Peak Project about the stainless steel Project liner plates of the spent fuel pool, transfer canal, (86-180) refueling cavity, or any other facility at the site.
Billie P. Garde, Requests copies of the denied records regarding Board Government Notification 84-149 on the Comanche Peak nuclear power Accountability plant.
Project (86-181) l ENCLOSURE A MAR 211986 l
l
3 Received, Cont'd Billie P. Garde, Requests copies of six denied records regarding Government inspection report 50-445/84-32 and 50-446/84-11 on the Accountability Comanche Peak nuclear power plant.
Project (86-182)
Billie P. Garde Requests copies of the denied records regarding the Government September 19, 1984, proposed NRC Manual Chapter 0517, Accountability
" Management of Allegations."
Project (86-183)
Janet G. Aldrich, Requests, on behalf of an NRC employee, records provided Polydoroff and to the NRC concerning the employee.
Miller, P.C.
(86-184)
Marjorie M. Aamodt Requests copies of all correspondence between members (86-185) of the Special Inquiry Group (SIG) and SIG and NRC staff subsequent to R. DeYoung's October 3, 1979, memo on the subject of off-site iodine-131 air concentrations.
Charlie Barnes Requests copies of all NRC-741 forms from January 1975 to (86-186)
December 1978 for Docket 40-8027, SUB-1010, Kerr-McGee's Seluoyah facility in Gore, Oklahoma.
Jerral W. Patterson, Requests a list of Region II licensees currently engaging Radiological Health in industrial radiographic activities.
Services, Inc.
(86-187)
Billie P. Garde, Requests copies of all records related to Information Government Notice 85-97, " Jail Term for Contractor Employee Who
~ Accountibility Intentionally Falsified Welding Inspection Records,"
Project dated December 26, 1985.
(86-188)
Billie P. Garde, Requests copies of all records related to Information Government Notice 85-101, " Applicability of 10 CFR 21 to Consulting Accountability Firms Providing Training," dated December 31, 1985.
Project (86-189)
Billie P. Garde, Requests copies af NRC's February 27, 1986, letter to Government Congress regarding the January 4,1986, accident at Accountability Kerr-McGee's Sequoyah facility, Gore, Oklahoma, and all Project records related to that letter.
(86-190)
Billie P. Garde, Requests all records related to 01 Report A4-85-020 Government regarding an OI investigation of the Comanche Peak Accountability SAFETEAM concern files.
Project (86-191)
ENCLOSURE A rear :: 11986
4 Received, Cont'd Billie P. Garde, Requests all records related to Inspection Report 50-Government 445/85-07,50-446/85-05 regarding an inspection of Accountability the Comanche Peak nuclear power plant during April-June Project 1985.
(86-192)
Billie P. Garde, Requests copies of all records related to Inspection Government Report 84-16 regarding an inspection at the Comanche Accountability Peak nuclear power plant.
Project (86-193)
Malcolm H. Philips, Requests copies of SECY-85-306A, SECY-85-306B, and Bishop, Liberman, records related to those SECY papers.
Cook, Purcell &
Reynolds (86-194)
(NRCemployee)
Requests copies of noncritical and critical elements (86-195) and standards for NRR bargaining unit employees.
Joel Levin, Requests records relating to any radiation exposure Nurenberg, Plevin, of a deceased person while employed at the Pilgrim and Heller & McCarthy Perry nuclear power plants beginning in 1983.
Co., L.P.A.
(86-196)
Gregory A. Holmes, Requests copies of records in Mr. Hans Schierling's chron MHB Technical and reading files, from January 1, 1984, to the present Associates concerning Diablo Canyon.
(86-197)
Melvin S. Day, Requests a copy of the technical proposal submitted by
'Herner &~
Technassociates, Inc., for operation and maintenance of Company the NRC's document control system.
(86-198)
Granted Myron L. Scott, In response to a request for records related to allegations Coalition for made by workers at the Palo Verde nuclear power plant Responsible Energy between April and October of 1985, made available 29 Education records.
(86-46)
Susan L. Hiatt, In response to a request for nine categories of records OCRE Representative relating to damages occurring to nuclear power plants (86-91) following an earthquake exceeding the operating basis earthquake and the January 3, 1986, earthquake near the Perry nuclear power plant, made available 66 records.
Informed the requester that eight additional records subject to this request are a'iready available at the PDR.
MAR 211986 ENCLOSURE A
5 Granted, Cont'd Kay L. Dove In response to a request for a copy of the nonproprietary (86-111) version of the successful proposal in response to the FY 1985 Small Business Innovative Research Program by Expert-EASE Systems, Inc., entitled, "Use of Workstation and Expert Systems Technologies to Facilita1;e Development and Evaluation of Fault Trees," made available a copy of the requested record.
Joseph M. Varela In response to a request for copies of Mr. Wallace Swan's (86-114) reports during his residency at the Watts Bar nuclear power plant, informed the requester that records subject to this request are already available at the PDR.
Shao-Chih Way, In response to a request for a copy of the technical In-Situ, Inc.
proposal submitted to the NRC by the University of Arizona (86-120) in response to Request for Proposal No. RS-RES-85-114, informed the requester that the NRC was unable to locate the requested record.
Katina Cummings, In response to a request for copies of monthly and/or McIntyre, Haviland weekly reports showing deliveries to and consumption of
& Jordan nuclear power by Toledo Edison of Ohio and Consumers (86-137)
Power of Michigan for July 1980 through December 1981, and monthly inventory figures of nuclear power held by both utilities, informed the requester that one record subject to this request is already available at the PDR.
Gregory A. Holmes, In response to requests for copies of records from Mr. James MHB Technical Knight's chron and reading files from September 1, 1981, Associates through December 31, 1983, and January 1,1984, to the (86-145) present, concerning the Diablo Canyon nuclear power plant, and informed the requester that the NRC has no records (86-14.7) subject to these requests.
D.G. Swanson, In response to a request for the identity of the firm Applied Science receiving the contract for solicitation number RS-NRR-Associates, Inc.86-055 and the contract price, informed the requester that (86-161) the requestec' contract is already available ~at the PDR.
Robert J. Sugarman, In response to a request for a copy of Effluent Report Sugarman &
No. 3 tor Limerick No 1 submitted by Philadelphia Electric Hellegers Company by letter dated February 28, 1986, made available (86-170) a copy of the requested record.
Jim Pedro, In response to a request for a copy of a February 4,1986, NUS Corporation memorandum for Harold Denton from Victor Stello, subject:
(86-177)
" Staff Actions Resulting from the Investigation of the November 21 San Onofre Nuclear Generating Station, Unit 1 Event (NUREG-1190)," made available a copy of the requested record.
ENCLOSURE A MAP. 21 1986
6 Denied Marya C. Young, In response to an APPEAL TO THE COMMISSION for the Government release of eight denied records regarding the Wolf Accountability Creek nuclear generating station, made available one Project record. Denied five records in their entirety, the (85-A-42-85-101) release of which would inhibit the open and-frank exchange of ideas, views, advice and recommendations between the Office of Investigations, the Office of the General Counsel, and the Commission. Denied portions of two records, the release of which would inhibit the open and frank exchange of ideas, views, advice and recommendations between the Office of Investigations, the Office of the General Counsel, and the Commission and release of which would be an unwarranted invasion of personal privacy.
l ENCLOSURE A 2 1 1986
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MARCH 21, 1986 IFB ISSUED IFB No.: RS-0RM-86-276
Title:
" Maintenance of Data General Computer Equipment"
==
Description:==
Contractor shall provide preventative, remedial and on-call maintenance for NRC computers and peripheral equipment located in the Washington, D.C.
area.
Period of Performance: 24 months Spor.sor: Office of Resource Management Status:
IFB issued on March 18, 1986.
Bids due on April 17, 1986.
RFP ISSUED RFP No.: RS-NMS-86-005
Title:
" Technical Assistance in Geophysical Methods for Site Characterization"
==
Description:==
The contractor shall assist the NRC on a task order basis, assessing the adequacy of currently available surveying methods and data analysis techniques applicable to site screening and site characterization investigations.
Period of Performance:
Three years Sponsor: Office of Nuclesr Material Safety and Safeguards Status: RFP issued on March 10, 1986. Proposals due April 10, 1986.
I PROPOSALS UNDER EVALUATION 1
RFP No.: RS-0IE-85-156
Title:
" Technical Assistance in Developing and Implementing Programs and Procedures
~
for Reactors Requiring Special Inspection Resources"
==
Description:==
" The objective of this project is to provide technical assistance to the NRC for activities pertaining to problem reactors during construction and operation, including development of an NRC program that standardizes inspection procedures for significant problem areas and emergency outages, and assisting in inspections.
Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: Final Evaluation Report received on March 18, 1986.
RFP No.: RS-01E-85-158
Title:
" Technical Assistance in Developing and Implementing Programs and Procedures for Inspection of Operating Reactors During Major Outages"
==
Description:==
The objective of this project is to provide technical assistance to the NRC for activities pertaining to planned outages of operating reactors. This includes the development of standardized inspection procedures as well as providing assistance to the regional offices for conducting inspections.
Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: Final Evaluation Report received March 18, 1986.
ENCLOSURE A
,J.a.i a 1 1566
o Weekly Information Report Division of Contracts CONTRACT AWARDED RFP No.: RS-01E-85-167
Title:
" General Course in Non-Destructive Examination Technology and Codes"
==
Description:==
The purpose of this course is to provide NRC personnel detailed technical training in nondestructive examination and the applicable codes necessary to enable them to conduct in-depth inspections of NRC licensed facilities under construction or modification to determine whether or not such facilities and components are constructed properly in accordance with applicable codes and standards.
Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: A Firm-Fixed-Price type Contract No. NRC-05-86-167 was awarded to Biand Examination Services & Testing Company in the amount of $63,000.00, effective March 19, 1986.
ADMINISTRATIVE MATTER LNR Associates (LNR) filed a protest with the General Accounting Office (GAO) on March 19, 1986, under Solicitation No. RS-NMS-86-001 for " Technical Assistance in Environmental and Socioeconomic Assessments." The protest disputes the basis for excluding LNR from the competitive range.
The protester requests that his proposal be reconsidered and that award be delayed pending resolution of the protest.
NRC's response to the protest is due to GA0 by April 24, 1986.
O EPCLOSURE A IZA' 2 1 ES3
0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending March 21, 1986 Diablo Canyon Unit 2 The Diablo Canyon Unit 2 completed its low power testing program. The Unit 2 reactor reached 100% power at 12:45 a.m. (PST) on March 13, 1986. The licensee declared the Unit in commercial operation at 3:00 a.m.
on March 13, 1986. At the time the Unit 2 was generating 1079 MWe.
Unit 1 has been in commercial operation since May 7, 1985.
River Bend Station On March 12, 1986, at approximately 11:40 a.m. (CST), River Bend Station experienced a reactor scram. When the scram occurred, the reactor was at 42% rated power; all control rods inserted and all systems appeared to respond as expected.
At the time of the scram, the licensee was conducting surveillance tests on the main steam isolation valves (MSIV) as well as calibrating the jet pump instrumentation. The immediate cause of the scram was a pressure spike associated with the calibration of the jet pump instrumentation.
River Bend Station received its full power operating license November 20, 1985. This is the sixth unplanned scram in 1986.
Pilgrim Station At 8:28 a.m. on Saturday, March 15, 1986, shutdown of the Pilgrim Station was commenced after growth of unidentified reactor coolant leakage 1.1 qpm in the previous 24-hour period. The plant was in cold shutdown at 3:50 a.m. on Sunday, March 16.
Inspection indicated that a fillet weld in a 2-inch instrument line was leaking at approximateli 1 quart / minute with the plant in depressurized, cold shutdown condition.
The leak is aoout 18 inches outside the reactor vessel well at a level about 70 inches above the top of the active fuel.
General Electric Company consultants arrived late yesterday, March 17, to investigate and recommend methods of repair.
Boston Edison proposes a meeting with NRC later this week to discuss the status.
Pilgrim Station is expected to remain shut down for a least 2 weeks.
Vogtle Electric Generating Plant, Units 1 and 2 On Friday, March 14, 1986, the evidentiary hearing was conlcluded before the Atomic Safety and Licensing Board on safety issue contamination, qualification of ASCO solenoid valves,,s (groundwater and dose-rate effects of cable). A further hearing on emergency planning issues is contingent upon the Board's rulings on motions for summary disposition.
MAR.01 1986 l
i
Also on March 14, 1986, two ex-employees of Georgia Power Company appeared on the Phil Donohue Show complaining about improper urinalysis tests which resulted in their firing. The women stated that they were targeted for testing as a result of raising safety concerns at Vogtle and implied that the NRC violated its promise of confidentiality to them.
Millstone 3 Millstone 3 is currently operating at 50% power with continuous blowdown to reduce SG sulfate concentration. The licensee is attempting to achieve the WOG recommended sulfate concentration of less than 20 ppb.
Sulfate is now being recorded at about 30-65 ppb in the SGs.
NNECO is performing a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> test run at the 50% power level to observe SG chemistry conditions; specifically sulfate concentration and cation conductivity.
The licensee is also running tests that are performed at steady state operation including RCS flow measurement.
Limerick On March 13, 1986, the Licensing Soard appointed to consider Mr. R. Anthony's request for a hearing on License Amendments Nos. I and 2 scheduled a Prehearing Conference in Philadelphia for March 27, 1986. The Board also directed that the licensee and the staff should file any answers it may have to Mr. Anthony's " contentions" by March 17, 1986.
Palo Verde Units 1 and 2 The licensee notified Region V on March 17, 1986 that an engineering analytical review for Palo Verde has revealed that supports for the main steam lines on the #1 steam generators for Units 1 and 2 are of inadequate strength and could fail during plant operation.
Currently Unit 1 is shut down for scheduled surveillances and Unit 2 is in Mode 4 (Hot Shutdown). At this time, we do not know how this finding will affect the projected date of April 8,1986 for initial criticality of Unit 2.
Catawba Unit 2 Activities performed at Catawba Unit 2 following entry in Mode 5 on March 7, 1986, are proceeding on schedule.
Filling and venting of the reactor coolant system (RCS) completed March 16, 1986.
Venting of control rod drive mechanisms completed March 17, 1986.
M 211986 EflCLOSURE B l
T
. Currently, licensee's personel are heating up the RCS to 165 F using the reactor coolant pumps.
The next activity is to establish RCS chemistry.
Subsequent activities are:
(a) drawing of the pressurizer bubble, (b) rod drive timing test, and (c) rod drop time measurement.
Entry in Mode 4, Hot Shutdown, is expected about April 9, 1986.
The critical path for this entry is the Auxiliary Building Ventilation System flow balance.
The schedule for initial criticality and operation above 5% power remains unchanged (i.e., April 27, 1986, and May 6, 1986, respectively).
Perry Nuclear Power Plant A low power operating (CEI) on March license was issued to the Cleveland Electric Illuminating Company 18, 1986 for Perry Unit 1.
CEI expects to begin loading fuel on/or about March 19, 1986, and be ready to go critical on/or about April 9,1986.
Comanche Peak During a conversation with the staff on March 4, 1986, Billie Garde of the Government Accountability Project indicated that two more individuals (unidentified) had contacted her to assist in bringing additional allegations to the NRC concerning Comanche Peak.
By letter dated March 5, 1986, the staff requested an opportunity to interview the two individuals on March 11, 1986, following an interview she had set up for the staff with another individual.
Following several phone conversations, by letter dated March 18, 1986, GAP responded that the two individuals will be made available to the staff only after they have been debriefed by GAP investigators and assigned an attorney or other representative who is able to represent them before the NRC, a process which will take an additional few weeks.
Following that time, GAP will set up the interviews.
The staff is preparing another letter to B. Garde again requesting the staff be provided with an interview schedule. The staff will consider further action (legal) if GAP continues to delay all staff efforts to contact the allegers.
Turkey Point Units 3 and 4 The staff have been informed by the Office of the General Counsel that the U.S. District Court of Appeals (District of Columbia) has rendered a decision in the action initiated by Joette Lorian and the Center for Nuclear Responsibility in relation to Pressurized Thermal Shock (PTS) affects on the Turkey Point-Plant reactor vessels.
ENCLOSURE B The court affirmed the NRC decision not to institute a proceeding per g gh 2 06 request of lis. Lorian.
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MARCH 21, 1986 1.
DEFUELING As of March 23, 1986, 28 debris canisters have been transferred from the reactor vessel to pre-shipment storage. These cans h' ave a total net weight of 30,678 lbs. which is about 10% of the estimated core material originally in the reactor vessel.
2.
PLAN'T STATUS The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The incore thermocouple average is 80*F.
The airborne radioactivity on the defueling platform is about 7.1 E-7 uCf/cc Tritium and 3.0 E-11 uCi/cc particulates, predominately Cesium-137. The platform is mounted above the modified internals indexing fixture which is mounted on the reactor vessel flange.
These provide water coverage of 151 feet over the core region.
This water level is about 5 feet over the top of any debris canisters in the reactor vessel.
3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) continued processing batch 130 from the "C" Reactor Coolant Bleed Tank (RCBT) to the monitor tanks then to the "A" RCBT. SDS total processed to date is 3,842,869 gallons.
EPICOR II was in temporary shutdown this week. EPICOR II total processed to date is 2,854,371.
4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge (includes TMI-1 and TMI-2) to the river consisted of seven daily composite samples taken from March 1 through March 8, 1986. A gamma scan detected no reactor related activity.
These EPA samples are then sent to Pennsylvania - Department of Environmental Resources (PA-DER) for determination of Tritium, gross Alpha emitters and gross beta emitters. These data are normally available about two months from sampling. Unit l's resumed operation is accompanied by normal releases of fission and activation products, which are allowed by Technical Specifications. Tritium is the only isotope released in detectable quantities. The average concentrations reported in the THI-1 Effluent Summary for October - December 1985 (244 pCi/1, 350 pCi/1, 1700 pCi/1) were consistent with the PA-DER Tritium values as detected in 20 of 92 daily outfall samples. These Tritium values are much less than 1/1,000 of the limit of 3,000,000 pCi/1.
MAR 211986
. The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from March 2 through March 8, 1986. A gamma scan detected no reactor related radio-activity. No Tritium was detected during October - December 1985.
The NRC outdoor airborne particulate sampler at the TMI s-ite collected a sample between March 13, and 20, 1986.
No reactor related radio-activity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of Defueling Water Cleanup System (DWCS) continued.
The Kelly vacuuming decontamination in the 281' elevation of the fuel handling building has resulted in the release of 75% of the general access areas from loose contamination controls.
The initial Seal Injection Valve Room (281' Auxiliary Building) entries on March 17 and 21 were judged to be successful in removing boron which built up on rubber and lead shielding installed in 1980-1981. The low pressure water flush proved the floor drain is operating.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
TMI-2 Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 1.
7.
PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for April 10, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.
j Persons desiring the opportunity to speak before the Advisory Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, PA 17603.
ENCLOSURE B
0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending March 21, 1986 Near-Term NRC Actions Under the NWPA Section:
121(a) of NWPA:
EPA Final HLW Standards Status:
Staff briefed the ACRS on January 15, 1986, and the Director, NMSS, on February 21, 1986 on proposed revisions to 10 CFR Part 60 for conformance to EPA HLW standards (40 CFR Part 191).
Action:
The proposed Federal Register notice of revisions to Part 60 is scheduled to be submitted to the Commission in late March 1986, for approval and publication.
Section:
114(e) of NWPA:
Project Decision Schedule Status:
DOE issued the draft Project Decision Schedule (PDS) on July 18, 1985 for comment.
NRC transmitted formal comments to DOE on October 24, 1985.
Action:
NRC and DOE staff have been meeting to resolve NRC comments on the draft PDS.
DOE is now scheduled to issue the final PDS in late March 1986.
Section:
141(d) of NWPA:
Licensing of MRS Status:
NRC has developed revisions to 10 CFR Part 72 to provide the licensing framework for the MRS if it is authorized by Congress.
i Action:
The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1985 and is awaiting Commission approval.
Section:
223 of NWPA:
Joint Notice of Technical Assistance Status:
NRC and DOE must annually update a joint notice in the Federal Register stating that the United States is prepared to cooperate and provide technical assistance to non-nuclear weapon states in the field of spent fuel storage and disposal.
Action:
The third annual joint update is currently being prepared for publication in early April 1986.
ENCLOSURE C f.'T3 21236
Section:
306 of NWPA:
Regulations for Training of Power Plant Personnel.
Status:
The final rulemaking on Part 55 and three associated regulatory guides received ACRS approval in December 1985.
Final office review has been completed.
Action:
The final rule was submitted to CRGR for review on February 26, 1986.
The edited final rule was resubmitted to the CRGR on March 19, 1986.
Pending CRGR approval, the final rulemaking package is expected to go to the Commission in April 1986.
Near-Term DOE Actions of Interest March 1986 - DOE to submit Fee Adequacy Report to Congress (Section 302)
March 1986 - DOE to issue Final Project Decision Schedule (PDS)
(Section 114(d))
April 1986 - DOE to submit Annual Report to Congress (Section 304)
April 1986 - DOE to issue final five Environmental Assessments for first repositocy April 1986 - DOE to nominate and recommend candidate sites for site characterization April 1986 - DOE to issue Final Transportation Institutional Plan April 1986 - Secretary makes Preliminary Determination on site suitability for a repository 4
April 1986 - Issue Notice of' Proposed Rulemaking for Defense Waste fee EPA Proposed Rule For Mill Tailings under the Clean Air Act The EPA proposed standard for radon emissions from licensed uranium mill tailings was signed by the Administrator on February 14, 1986.
A public hearing is scheduled for March 25-26 in Denver, Colorado.
A 30-day comment period will follow.
EPA and the Sierra Club have agreed to postponing promulgation of the court ordered final standards until August 15, 1986, pending court approval.
The proposed rule package is presently under NRC staff review.
The staff plans to attend the public hearing to observe and is preparing written comment on the proposed rule.
- 4A3 211986 ENCLOSURE C i
Ogle Petroleun.. Inc. Insolvency The State of Wyoming is proceeding in calling in two surety bonds following the announcement of Ogle Petroleum's insolvency in November 1985. Western Fuel, Ogle Petroleum's joint venture partner, is providing funding'to maintain their solution mining site in a standby status.
Western Fuel has provided a letter of credit in the amount of $500,000 in addition to the Ogle surety bonds to pay half of all additional costs over and above those covered by the Ogle sureties.
The Wyoming Environmental Quality Council held a meeting on January 10, 1986 to decide whether to grant Allied Fidelity Insurance Company a hearing.
Allied Fidelity and Travelers Indemnity each have bonds in the amount of
$448,000 and $598,000, respectively.
At tha January 10 meeting, the Council denied Allied the hearing request.
On January 22, 1986, the Attorney General of Wyoming issued an order for both Allied and Travelers to forfeit their bonds by February 14, 1986.
Travelers forfeited their bond the week of February 10, 1986, and Allied filed in the First Circuit Court requesting judicial review of the order.
The Attorney General of Wyoming has filed a counter motion alleging Allied has no valid reason to not forfeit their bond.
The State of Wyoming and the Uranium Recovery Field Office are working with Western Fuel to develop an acceptable restoration and decommissioning plan.
The current schedule is to have a contractor on site and beginning restoration by July 1, 1986.
RER (Regulatory Effectiveness Review) at Power Reactor The next RER is scheduled for the week of March 31, 1986 at Duane Arnold (Iowa).
Nuclear Materials Management and Safeguards System (NMMSS)
On March 11, 1986 the E00 approved for publication in final form amendments to 10 CFR Parts 40, 51, 74, and 150, Material Balance Reports.
The final rule removes the requirement for reporting material balances of U.S. origin source material and the requirement to report composition of ending inventories for all except nuclear reactor licensees and licensees reporting under the US/IAEA Safeguards Agreement.
The final rule package has been transmitted to ADM for submission to the Federal Register.
Implementation is anticipated in April 1986.
Institute of Nuclear Materials Management (INMM) Workshop on Security Forces Mr. Nulsen, a member of the Safeguards staff, is making a presentation in Albuquerque (March 17-20, 1986) at the INMM Workshop on Security Forces.
The workshop focuses on the qualifications, training, operations, and evaluation of security forces for Federal and commercial nuclear facilities.
Mr. Nulsen is presenting the NRC perspective on security force matters.
MAR 211986 ENCLOSURE C
NFS-Erwin, Tennessee Strike by OCAW members continues.
There has been no progress made in resolving differences between the Union and NFS.
A recent proposal by the OCAW Union to return to work for a "90 day cooling-off period" was rejected by NFS.
Nothing less than a 1 year contract without the return of the seven fired union members would be considered by NFS.
NFS continues to conduct limited operations of the HEU production and scrap recovery operations.
On March 12, 1986, a grass fire was discovered outside the protected area at the NFS facility.
The blaze was apparently caused by a flare.
The Erwin Volunteer Fire Department was harassed by the Union pickets and was delayed in reaching the fire.
No damage was experienced by the facility due to this delay.
On March 19, 1986, another grass fire occurred outside the protected area.
On March 20, 1986, a building on the site, also outside the protected area, suf-fered fire damage.
In the last two cases, the Erwin Volunteer Fire Department and local law enforcement personnel responded in a timely manner with no harass-ment encountered from the striking Union pickets.
All three fires are of a suspicious origin and are currently under investigation.
Meeting with ACRS Members of the SG and FC staff met with an ACRS subcommittee on March 12, 1986 to answer the subcommittee's concerns about safeguards for ISFSIs (10 CFR Part 72).
International Shipments of Research Reactor Fuel DOE is attempting to arrange for shipments of research reactor fuel from Taiwan to the U.S. West Coast, and on to DOE's Savannah River facility.
Although similar shipments have been completed in the past without incident, i
the three Fort cities most suitable to receive the shipments have objected.
Governor Gardner of Washington has written to DOE Secretary Herrington concerning the shipments.
In addition, the Northwest Inland Water Coalition, a group of environmental interest organizations, has filed suit to block the shipments. 00E is at present trying to route the shipments through Long Beach, California.
Long Beach officials have raised numerous questions, including questions on NRC's Final Environmental Statement on Transportation (NUREG-0170), which DOE is using as its basis for responding to concerns on environmental impact of the shipments.
DOE has requested NRC review of Long Beach questions and DOE answers pertaining to NUREG-0170; FC is providing coordination of NRC response.
Nuclear Fuel Services, Inc.
On March 18, 1986, members of the NRC staff met with Mr. John Kirk III, of l
Bristol, Tennessee, to discuss what information a group of investors would need to supply NRC for review and approval of a change of ownership at a licensed facility.
This group is considering the purchase of Nuclear Fuel Services' Erwin, Tennessee facility.
OSURE C f.iAR 211986 i
. DOE Satellite-Tracking for Department Shipments of Radioactive Material DOE Defense Programs is currently evaluating the use of a satellite-tracking system for large quantity radioactive material shipments.
The system would allow DOE to determine in " realtime" (instantaneously) a shipment's geographic position and other information.
One system under consideration would consist of three basic components:
(a) individual shipment " transceiver"; (2) three satellites in orbit above the United States; and (3) a powerful computer system at a ground location.
Every shipment transceiver would have a unique identifying code; the pulse emitted from the transceiver would be received by the satellites and relayed by microwave to the ground station, and on to monitoring stations.
DOE plans to conduct a 6-month test of the satellite tracking system beginning in late 1986.
The DOE's OCRWM will evaluate the possible application of the system to NWPA shipments.
Babcock & Wilcox Site Visits During the week of March 10, 1986, members of the NMSS visited the three Babcock & Wilcox SNM licensed facilities in Lynchburg, Virginia.
The Naval Nuclear Fuel Division (SNM-42) was visited to review its operations related to the license and to discuss controls to ensure nuclear criticality safety.
The Commercial Nuclear Fuel Plant (SNM-1168) was visited to review its operations related to the license and to discuss its license amendment application requesting authorization for organizational changes as well as for an additional fuel handling operation.
The Lynchburg Research Center (LRC, SNM-778) was visited to review its operations related to the license, the status of the program to decontaminate Building C to limits acceptable for release to unrestricted use, and to discuss NRC comments on the LRC license renewal application.
e 0
0 ENCLOSURE C MAR 211986
Office of Inspection and Enforcement Items of Interest Week Ending March 21, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
a.
EN 86-11A, an Order Suspending License, Fffective Immediately had been issued to Radiation Technology, Inc. (Rockaway, NJ) on March 3, 1986. In consideration of the licensee's responses, plans, and corrective actions, an adequate basis has been provided for lifting the suspension Order subject to certain conditions.
b.
EN 86-12, a Notice of Violation and Proposed Imposition of Civil Penalty was issued on March 19, 1986 to Professional Services Industries, Inc. (0ak Brook, IL) in the amount of $500. This action is based on improper storage and accompaniment of shipping papers.
c.
EN 86-13, a Notice of Violation and Proposed Imposition of Civil Penalty was issued on March 19, 1986 to Commonwealth Edison Company (LaSalle) in the amount of $50,000. This action is based on the failure to evaluate the operability of the emergency core cooling system during a preventative maintenance activity.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PN0-II-86-22A, Nuclear Fuel Services, Inc. (Erwin, TN), Second Grass Fire on Plant Property, b.
PNO-III-86-22A, Union Electric Company (Callaway), Communicated Threat,(Update).
c.
PNO-III-86-23, Cleveland Electric Illuminating (Perry), Mispositioned Instrument Valves.
d.
PNO-III-86-24, Detroit Edison Company (Fermi 2), Failure of Backup Reactor Protection System Trip Breaker.
e.
PNO-III-86-25, Toledo Edison Company (Davis-Besse), Apparent Crack Indications in Reactor Coolant Pump Shafts.
f.
PNO-III-86-25A,ToledoEdisonCompany(DavisBesse),ApparentCrack IndicationsinReactorCoolantPumpShafts(Update).
g.
PNO-III-86-26, Ferris State College (Big Rapids, MI), Apparent Tritium Overexposure.
h.
PN0 111-86-27, SchlumbergerCorporation(Mt. Pleasant,MI), Erroneous Pr urt of " Leaking" Radioactive Shipment, i.
NO-III-86-28, Cleveland Electric Illuminating (Perry), Perry Unit 1 g.gp, g i gg3 Receives Operating License.
ENCLOSURE D
2 j.
PN0-IV-86-09, Sequoyah Fuels Corporation (Gore, OK), Overfill of Uranium Hexafluoride (UF6) Cylinder.
k.
PN0-IV-86-09A, Sequoyah Fuels Corporation (Sequoyah Facilfty),
Overfill of UF6 Cylinder (Update).
1.
PNO-V-86-11, Pacific Gas and Electric (Diablo Canyon Unit 1), Safety Injection During a Turbine Test.
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
None.
4.
Other Items a.
Civil Penalties Paid Pacific Gas and Electric Company (Diablo Canyon) in the amount of
$50,000 for violations involving partial failure of automatic isola-tion capability to an MSIV.
b.
Operations Center The Chief, Incident Response Branch, Division of Emergency Prepared-ness and Engineering Response conducted the following briefings on the agency's incident response program and tour of the NRC Operations Center:
(1) March 18, 1986 - management representatives from Turkey Point
- emergency preparedness representative from Maine Yankee (2) March 19, 1986 - visitors from Indonesia (3) March 20, 1986 - representatives from U.S. Air Force, Nuclear Assurety c.
Vendor Program Staff members of the Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs partici-l pated in the following inspections:
i (1) San Onofre Unit 1, San Clemente, CA - to inspect San Onofre Unit 1 for check valve problems.
(2) Patel Engineering, Inc., Huntsville AL - to review LOCA test evaluations of Buchanan terminal blocks and Raychem splices for Cooper nuclear plant.
ENCLOSURE D f'AR 311986311986(3) Automatic Electric Products, Parsipanny, NJ - to obtain additional information on the RPS transfer panels supplied to Peach Bottom and Limerick nuclear power plants.
3 d.
Allegation Followup A staff member of the Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs conducted an inspection at Standard Environmental Products (Cherry Hill, NJ) this week.
e.
Generic Issues A staff member of the Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response parti-pated in the requalification of KWU (UTL) and CE UT personnel for dett:ction of IGSCC using automatic UT systems at the EPRI-NDE Center, Charlotte, North Carolina, March 18-21, 1986.
ENCLOSURE D EAP 2 1 USS 1
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending March 21, 1986 Multiloop Integral System Test (MIST) Program The MIST facility is an integral test facility designed to simulate hydraulic aspects of transients in reactors of the Babcock and Wilcox (B&W) design.
Characterization testing to understand the performance of various systems related to the MIST facility comenced in January 1986. These include the auxiliary feedwater system which controls the flow into the steam generator, the guard heaters which are used to compensate for heat loss during testing, and the steam pressure control system which controls the steam generator secondary pressure. Simulation of reactor transients will begin at the end of May and will be used for reactor safety code assessment. The data will be used in assessing code capability for licensing application.
Natural Circulation in Severe Accidents A meeting was held on March 17, 1986 in Bethesda, Maryland to discuss the NRC-sponsored studies on " Reactor Coolant System Natural Circulation During PWR Station Blackout Accidents." This is an important issue currently being addressed in the severe accident risk rebaselining document to be published as NUREG-1150. Results will also have direct impact on other NUREG-1150 issues including Direct Containment Heating, Hydrogen Generation, Fission Product Reevaporation, and Melt Progression. The meeting was attended by representatives from NRR, RES, and national laboratories.
Highlights of the meeting were:
(1) a RES presentation on the scope, status, and review of NRC and industry work on natural circulation; (2) introduction to the MELPROG code, which is being developed for detailed mechanistic analysis of severe accident progression in a reactor vessel; and (3) preliminary results of a MELPROG calculation for a TMLB' (station blackout) accident in the Surry Plant.
The MELPROG code predicts the vessel temperature distributions, core geometry and status, and hydrogen generation rate as a function of time during the course of the accident from initiation to core melt and to vessel failure. Based on this preliminary calculation, the onset of core melt and the timing of vessel bottom head failure are delayed by about 10 to 40 minutes respectively due to the presence of in-vessel naturel circulation.
If failures in other parts of the reactor coolant system should result in sufficient depressurization prior to this high pressure ejection of molten fuel, the consequent direct heating loads on containment may be avoided.
ENCLOSURE E MAR 21192S
l -
GDC-4 Presentation at ACRS Meeting 311 on March 14, 1986 The staff bas developed an expanded proposed rulemaking package to modify General Design Criterion 4.
The proposed acdification, known as the broad scope GDC-4 rule, would eliminate the need to consider the dynamic effects associated with postulated rupture of piping provided certain rigorous acceptance criteria are met. The effect of this modification will permit the use of " leak-before-break" if the criteria are met and allow the removal of certain massive pipe whip restraints. This results in lower radiation cyposure to plant workers and, at the same time, enhancing overall safety by avoiding inadvertent restraints to thermal growth during normal operation. This modification expands the modification to GDC-4 (recently affirred as an effective rule by the Commission) that is limited to the primary piping of PWR's. The staff presented this proposed broad scope rule modification to the ACRS on Merch 14, 1986. While various differing views were expressed, the ACRS generally supported this modification.
It is anticipated that the proposed rule will be reviceo to reflect the ACRS cortments and will be forwarded to the Comissiun in the near future for consideration and approval to publish in the r
Federal Register.
Georgia Earthquake on March 12, 1986 A small earthquake, magnitude of about 2.4 on the Richter scale, occurred in central Georgia near Lake Sinclair on March 12, 1986. The closest nuclear plant to the epicenter of this earthquake is the Vogtle plant, which is about 100 miles to the west. The earthquake was not detected and had no impact on the Vogtle plant. The event was felt and heard only by residents close to the epicentral area.
It was preceded by a small swann of earthquakes approximately~ 2 weeks before. These events were not felt or heard but were recorded by the sensitive seismographs of the NRC Georgia-Alabama Seismographic Network. All of these earthquakes are probably reservoir induced seismicity as was a magnitude 3.5 earthquake on February 13, 1986, in South Carolina.
Reservoir induced seismicity is a phenomena associated with a number of man-made reservoirs, including Monticello Reservoir, a cooling water source for the V.C. Summer NPP. Reservoir induced seismicity is a reasonably well understcod phenomena in which the reservoir affects the tectonic stresses acting on a fault by either retarding or advancing the stress regime toward failure. There are two principal effects: one associated with the load of the reservoir water and a second associated with pore pressure variations at hypocentral depths. Depending on fault orientation and type, the two effects can work in combination or in opposition.
Fluid injection wells are special cases of reservoir induced seismicity in that there is no load effect.
While the phenomena is understood, there is currently no technique to predict in advance which reservoirs will experience reservoir induced seismicity or, once reservoir induced seismicity is initiated, when or if it will occur again or stop.
UAP 2 1 1333 ENCLOSURE E
RES RULEMAKING ACTIVITIES Emergency Core Cooling Systems; Revisions to Acceptance Criteria (Part 50)
(Appendix K)
The proposed rule would amend regulations concerning acceptance criteria for emergency core cooling systems (ECCS) by changing the methods used to demonstrate that an ECCS would protect the nuclear reactor core during a loss-of-coolant accident.
Because the proposed rule represents a significant change in a regulatory requirement, the staff is currently preparing a summary of ECCS research performed over the last 10 years which will serve as the technical basis for the proposed rule and a regulatory guide which will provide definition of what constitutes an acceptable best estimate model and acceptable methods of performing the uncertainty evaluation.
Comments have been received from NRR on the draft Comission paper. NRR indicated that they support the rule and find the Comission paper generally acceptable. They did provide numerous comments and, in particular, had coments on the Regulatory Analysis.
RES staff met with NRR staff on March 18, 1986, to discuss the concerns and RES is now in the process of revising the Comission paper and the Regulatory Analysis.
A study has been initiated at SNL to evaluate the effect of the proposed rule on plant risk. These results are expected to be available within 2 months.
The staff has been requested by the Acting EDO to prepare the paper for submittal to the Comission in the near future. The regulatory guide is to accompany the paper to the Comission.
NRR provided criteria for the models to 4
be used in the guide and requested that RES review and approve the models.
This review will proceed in parallel with the preparation of the rulemaking package for,CRGR review.
The technical basis document supporting the proposed rule will be vol'uminous (more than 1000 pages). A draft of the technical basis' document will be available for review when the Commission paper is sent to the Comission.
Severe Accident Risk Assessment The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being used to support NRR's review of IDCOR submittals.
In addition, it will support the staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.
A meeting to discuss the range of uncertainties associated with the Grand Gulf and Sequoyah analyses will be held at Sandia National Laboratories from April 2-4, 1986.
Remaining items still unresolved on the treatment of uncer-tainties for the Surry and Peach Bottom analyses wil,1 also be addressed.
ENCLOSURE E I.ma 211986
t l
4,,
Publication to be Issued in the Near Future
Title:
Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants (Draft Reg. Guide, R. G.1.63, Proposed Rev. 3)
==
Description:==
This guide describes a method acceptable to the NRC staff i
for complying with the Commission's regulations for the design, construction, testing, qualification, installation and external circuit protection of electric penetration assemblies in containment structures of nuclear power plants.
i
Contact:
S. K. Aggarwal 443-7668 2
1 I
i 4
9 i
i i
i li.;.R 211986 i
i
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MARCH 21, 1986 Foreign Visitors A three-member team from Taiwan representing the Atomic Energy Council, the Institute of Nuclear Energy Research (INER), and the National Tsing Hau University held a series of meetings throughout the week with NRR and NMSS staff as part of an examination of the licensing issues and technical procedures associated with spent fuel storage and the installation of high-density spent fuel racks at operating reactors in the US. Their one-week program at NRC is to be followed by a tour and discussion with the engineering and licensing staff of the Grand Gulf Nuclear Plant and a tour of General Electric's BWR maintenance facility.
Foreign Trip Reports Shlomo S. Yaniv, RRAMB/RES September 15-17, 1985; Visited the FRG:
Mr. Yaniv participated in the Workshop on Harmonization of Modeling in Nuclear Accident Consequence Codes held at the Nuclear Research Center in Karlsruhe (KfK) on September 15-17, 1985. The objectives of the Workshop were to (1) exchange information on the current status of modeling for nuclear accident consequence analysis in Gemany, Great Britain, snd the U.S.; (2) discuss ongoing and planned activities in these countries; and (3) identify areas suited for international harmonization.
Herbert Knuts, Department of Nuclear Energy, BNL December 7-13, 1985; Visited the FRG and Austria:
This trip was taken in connection with Mr. Kouts' membership on the International Nuclear Safety Advisory Group (INSAG). He chairs a two-man subconnittee of INSAG to report on the source tem for severe accidents. He prepared a first draft of a report on the source term and took it to Garching, FRG, for coordination with Prof. Dr. A. Birkhofer.
In Vienna, Austria, Mr. Kouts reviewed the draft report with IAEA staff members.
Frank H. Rowsome. Chief, Human Factors Issues Branch, DHFT/NRR January 5-17, 1986; fisited the PRC:
Mr. Rowsome was one of two instructors sent to Beijing by the IAEA to conduct a two-week workshop on PRA. The workshop had from 30-40 attendees who were all eager to learn about our practical experiences with PRA and better methods for use of PRA.
ENCLOSURE G l#A 2 ". O
2' Foreign Trip Reports continued Jerry B. Fussell, JBF Associates, Inc, President-Senior Engineer, ORNL January 24-31, 1986; Visited Italy and Austria:
The purpose of this trip was to participate in discussions at the EEC/ EURATOM Joint Research Centre, Ispra, Italy, and present a paper on the PRISM computer program at IAEA Headquarters in Vienna, Austria.
1 i
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ENCLOSURE G laiQ 21 ;S86
0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MARCH 21, 1986 Low-Level Radioactive Waste Transportation Plan for the State of Maryland The NRC commented en a draft document, " Low-Level Radioactive Waste Transportation Plan for the State of Maryland," that was submitted by the Maryland Department of Health and Mental Hygiene. The purpose of the document is to prepare a recommended transportation plan that will outline specific procedures for monitoring and regulating low-level radioactive waste transport in Maryland consistent with Federal law and party State requirements under low-level radioactive waste compact conditions.
l 1
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f MER 211986 ENCLOSURE H
o 0FFICE OF RESOURCE MANAGEMENT Items Of Interest Week Ending March 21, 1986 Travel Workshops The Division of Accounting and Finance is conducting Travel Workshops for Headquarters personnel responsible for preparing travel authorizations and vouchers.
In response to a memorandum sent to office directors on February 7, 1986, approximately 150 persons requested training.
Five workshops have been scheduled through mid-April. Similar travel workshops will be scheduled for Regional Offices during the upcoming months.
New Per Diem Regulations Public Law 99-234 eliminates the statutory ceilings on reimbursements for civilian employees on domestic travel and authorizes the General Services Administration to establish appropriate maximums administrative 1y. Effective July 1, 1986, domestic travel reimbursements will be based on the amount a traveler pays for lodging plus a fixed amount for meals and miscellaneous expenses, the total not to exceed a maximum rate set by locality. Appropriate announcements will be prepared to advise NRC staff of these changes.
ENCLOSURE I
!;AP,111986
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM 0F INTEREST Week Ending March 21, 1986 AE0D Engineering Evaluation Report, E604, " Spurious System Isolations Caused by the Panalarm Model 86 Thermocouple Monitor," has been issued. The report evaluated a number of High Pressure Coolant Injection, Reactor Core Isolation Cooling and Reactor Water Cleanup System isolations caused by a spurious trip of a Panalarm Model 86 thermocouple monitor. The study found that the elevated sensitivity of the Panalarm thermocouple monitor makes the instrument highly susceptible to spurious trips caused by momentary electrical disturbances.
The spurious system isolations caused by the instrument are undesirable because of the potentially adverse impacts on system reliability, isolation valve opera-bility, and the distractions presented to the plant operating personnel. The study found that a modification to the leak detection system trip circuitry at Duane Arnold appears to have proven successful in significantly reducing spurious system isolations caused by the thermocouple monitor.
The study has been forwarded to IE with the suggestion that they issue an Information Notice which discusses the spurious system isolations caused by the Model 86 thermocouple monitor and describes the modification implemented at Duane Arnold as a possible corrective action.
4 U.AR 211986211986ENCLOSURE J
J REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT March 21, 1986 Plant Status The plant remains in cold shutdown.
Restart Activities A NRR maintenance survey inspection team will be on site March 24-28 to follow up on previous findings and to evaluate the licensee's actions concerning management practices as they relate to the maintenance area.
MOVATS testing, environmental qualification work and other maintenance
++
activities continue on the 167 safety-related motor-operated valves onsite.
The licensee has completed all planned work on eighty five valves and returned them to service. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The NRC test review team continues to provide weekly coverage of licensee
++
testing activities. The licensee has completed their review of the systems important to safe plant operations and the testing requirements associated with each. This review has identified a test program consisting of 274 tests of which 28 will be performed following criticality. This program consists of 174 existing or modified surveillance tests and 101 new test procedures. Four tests were performed last week and 57 tests have been performed to date.
Other Activities Inspections of safety system piping supports in the auxiliary building are
++
continuing. Evaluation of the nonconformances (NCR) found on supports in containment is in progress. Of the support NCRs requiring disposition prior to restart, one remains to be dispositioned.
The licensee's repair, replacement and engineering review of items requiring environmental qualification (EQ) is continuing. While no significant deficiencies were identified, a subsequent inspection is planned prior to restart.
ENCLOSURE L ETR 2 1 '986
The licensee has written a work request to disassemble the No.1 Service
++
Water Pump as part of their investigation into the cause of a suspected sheared pump shaft or dropped impeller. This event was mentioned in the Region III Daily Report dated March 11, 1986.
Ultrasonic Testing (UT) of the four Reactor Coolant Pumps (RCPs) is in
++
progress. Review of the UT traces by a licensee contractor has revealed areas of concern on all four RCPs. Additional angled (70 ) UT performed on the shafts for RCP's 2-2 and 1-1 confirmed crack indications at the 52 inch region of the shafts (measured from the top of the shaft). Angled UT is planned on shafts for RCP's 2-1 and 1-2.
The spare RCP shaft has been sent to the pump manufacturer Byron Jackson for inspections and balancing. The licensee is developing schedules for repairs of the RCPs and for continuation of the System Review and Test Program.
l l
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EllCLOSURE L MAP. 21 '986
l
\\
DEPUTY EXECUTIVE DIRECTOR FOR REGIONAL OPERATIONS AND GENERIC REQUIREMENTS (DEDR0GR)
Week Ending March 21, 1986 CRGR Attached is a summary of the CRGR activities for the period February 1 through February 28, 1986. Background material on topics reviewed by the Committee and the minutes of CRGR meetings are sint 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 the documents. Questions concerning this monthly report should be referred to Walt Schwink (492-8639).
MAR 211936 ENCLOSURE M
f Page 1 of 1 Date: March 21, 1986,
a
SUMMARY
OF CRGR ACTIVITIES E
(February 1 through February 28,1986) s, rA Mtoting No.
l',Heeting Date (Announcement CRGR CRGR Recommendation Date)
Agenda Status to ED0 EDO Action 1
86 Review, Final Rulemaking Pending No CRGR recommendation at this No action necessary at 2/26/86 Package to Revise the time. This review was continued this time because Regulations for Operator at Meeting No. 87 on March 19.
review of this item is Licensing, 10 CFR Part 55, incomplete.
Conforming Amendments and Three Associated RGs
-Sponsoring Office - NRR
-Category 2 Item
-Issue #125 85 Review, Proposed Broad Pending Ho CRGR recomendations at this None required at this 2/5/86 Scope Rule to Modify General time. Minutes in preparation, time.
Design Criterion 4 of 10 CFR Part 50
-Sponsoring Office - RES
-Category 2 Item
-Issue #135 1
i
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1 1
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o m
3
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MARCH 21, 1986 A.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE,11:30 A.M.,- THURSDAY, MARCH 13, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello and H. E. Plaine dated 3/19/86 I.
SECY-86-57A - Extension of the Comanche Peak Construction Permit The Commission, by a 4-1 vote, approved an order responding to a request filed on January 31, 1986 by the Citizens Association for Sound Energy, which sought Commission action in connection with the extension of the Comanche Peak construction permit.
The order (1) denies both CASE's request for a halt to con-struction and its request for the institution of a new con-struction permit proceeding; (2) denies CASE's request for a stay of staff's extension of CPPR-126; (3) rejects CASE's view that significant hazards considerations are involved in the extension of CPPR-126; (4) refers CASE's request for enforcement action to the staff for consideration under 10 CFR 2.206; and (5) refers CASE's request for a hearing to the Chairman of the g
Atomic Safety ar.d Licensing Board Panel for appointment of a hearing board to rule on the hearing request and to conduct any necessary hearings in accordance with Subpart G of 10 CFR Part 2.
Commissioner Asselstine disapproved the order, preferring an alternative approach, and provide separate views.
(Subsequently, on March 13, 1986 the Secretary signed the Order.)
II.
SECY-85-333 - Procedural Amendments to 10 CFR 60 Dealing with Site Characterization and the Participation of States and Indian Tribes The Commission (with Chairman Palladino and Commissioners Roberts, Bernthal and Zech agreeing) approved the procedural amendments to 10 CFR Part 60 dealing with site characterization and the participation of states and Indian tribes subject to:
(1) incorporating the following additional provisions into Part 60:
(a)
Host states and affected Indian tribes have an unquestionable legal right to full party status.
(b)
The NRC will review and concur in the necessity for the use of all radicactive materials, including radioactive tracers, on a case-by-case basis.
(c)
The NWPA requirements that DOE defer the sinking of shafts at least until such time as there has been an opportunity for pertinent comments on shaft sinking to have been solicited and considered by DOE.
ENCLOSURE O MAR 211986 i
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COTTINUED (2)
Thedefinitionof"Indiantribe"and"tribalorganidtion" should remain as they are defined in Part 60 and not be changed as proposed.
(3)
The attached changes should be incorporated.
(4) on page 6, line 4 of the first complete paragraph of the rule change "new statute" to "NWPA".
(5) on page 9, line 1 of the rule change "the responsibilities" to "its obligations".
j (6)
The Commission has agreed that this rulemaking should not be held up to tie it in with the Part 51 changes.
Accord-ingly the last paragraph on page 9 should be edited to read:
e "It is important to proceed with the present actions without awaiting other changes to Part 51 that will be prepared in the light of the NWPA.
This would allow for ~
changes related to...."
(7)
The rulemaking package should also be reviewed to assure that additional modifications needed for consistency with the above changes are incorporated.
Commissioner Asselstine approved in part and disapproved in part, he disapproved in that he would also have retained the present requirements to issue the draft site characte'rization
-analysis for public comment and staff analysis of those comments as well as-the requirement for NRC review of DOE's site screening and selection process.
His separate views are attached and should be published with the Federal Register Notice.
The final rule should be revised as noted and returned for signature and publication in the Federal Register.
(EDO)
(SECY Suspense:
4/18/86)
Attachments: hy aggej As stated ENCLOSURE 0 BR 211986 l
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STAFF REQUIREMENTS - BRIEFING BY DOE ON R&D RESULTS FROM TMI-2 CLEANUP, 2:00 P.M.,
TUESDAY, MARCH 11, 1986, COMMISSIONERS' CONFERNECE ROOM, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 3/20/86 The Commission met with representatives of the Department of Energy (DOE) to be briefed on results to date of research and development efforts involving the Three Mile Islan'd Unit 2 reactor.
l The following persons participated in this briefing:
Jim Vaughan Acting Assistant Secretary for Nuclear Energy i
DOE Don McPherson
- TMI-2 Accident Evaluation Program Manager Light Water Reactor Safety and Technology Office DOE Dave McGoff, Director Office of LWR Safety and Technology DOE Jim Broughton, Manager TMI Accident Evaluation Program EG&G Idaho, Inc.
Chairman Palladino asked for more information from DOE con-cerning the effects of loss-of-coolant environment in the TMI-2 accident on instrumentation and electrical equipment.
(Subsequently, DOE provided this informatkon in report GEND-05.0.)
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STAFF REQUIREMENTS - BRIEFING BY TVA ON STATUS, PLANS AND SCHEDULES, 9:30 A.M.,
TUESDAY, MARCH 11, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE - Memo SECY to RECORD dated 3/21/86 The Commission met with representatives of the Tennessee Valley Authority (TVA) to discuss the status of TVA activities in the areas of management and operations of TVA nuclear power plants.
The following representatives of TVA were in attendance at the meeting:
i Charles H. Dean, Jr.
l Chairman, Board of Directors 1
John B. Waters Corporate Director Steve White MAR 211986 Manager Nuclear Power ENCLOSURE 0 l
. C.
CONTINUED The representatives of TVA promised to provide the Commission a plan outlining the methods by which TVA, subsequent to its reorganization, would prevent the reoccurrence of the problems in its nuclear operations that it is presently attempting to resolve.
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fGR 21 IEE6 ENCLOSURE 0 l
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$i NRR MEETING NOTICES
- rd MARCH 21, 1986 ER D0CKET
_ APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/24-25/86 50-312 Rancho Seco Site Brief senior NRC staff NRC, IE, S. Miner B:30 a.m.
Herald, CA.
regarding SMUD's proposed Region V plans for recovery from 12/26/85 incident and plant trip.
3/25-26/86 50-266 Point Beach Site Visit and meeting at WEPC0 T. Colburn 11:15 a.m.
50-301 Nuclear Plant WEPC0 Corporate Offices.
3/26/86 50-267 Fort St. Vrain Forthcoming meeting with PSC K. Heitner 1:00 p.m.
Site Public Service Co. of Colorado Platteville, C0.
to discuss Fort St. Vrain Equipment Qualification Program.
3/26/86 50-219 Room P-110 Present the up-to-date status of GPUN J. Donohew 9:30 a.m.
Phillips Bldg.
the licensee station betterment, the Expanded Safety System Facility, and February 1986 Progress Review Summary Meeting.
3/27/86 50-219 Room P-114 Discuss the licensee's requested GPUN J. Donohew
):30 a.m.
Phillips Bldg.
cancellation of the upgrade of the nitrogen purge / vent system in the Cycle 11R outage dated 9/24/85.
3/27/86 50-445 Room P-114 Discuss qualifications of the Texas A. Vietti-Cook L:00 p.m.
50-446 Phillips Bldg.
Radiation Protection Manager.
Utilities n
$ Copics of sumaries of these meetings will be made publicly available and placed in the respective docket file (s) j in the NRC and local public document rooms a
m m
w NRR MEETING NOTICES
- n$
MARCH 21, 1986 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/27/86 50-410 Room P-110 Discuss the NMPC design NMPC M. Haughey i
10:00 a.m.
Phillips Bldg.
verification program for the NMP-2 FSAR.
3/28/86 50-219 Room P-114 Discuss staff's Safety State J. Donohew 4
10:00 a.m.
Phillips Bldg.
Evaluation dated January 26, of N.J.
1984, to defer replacement of the existing core spray sparger in the Cycle 11R outage.
4/1/86 50-313 Room P-114 Discuss the ANO-1 concern Arkansas G. Vissing 9:00 a.m.
Phillips Bldg.
regarding the design of seismic Power & Light category II system equipment and structures.
4/1/86 Room P-114 Hear and discuss licensee's MP&L L. Kintner 1:30 p.m.
Phillips Bldg.
plans for the first refuel.ing outage.
4/1/86 Room P-118 Discuss topical report on EPRI R. Emch 1:00 p.m.
Phillips Bldg.
seismic hazard analysis planned for submittal by EPRI in mid-July.
4/1/86 50-219 Room P-110 Discuss the draft Technical GPUN J. D'onohew 9:30 a.m.
Phillips Bldg.
Evaluation Report on IPSAR E
Section 4.11 issued by the staff on January 9, 1986.
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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
55 vo b)
NRR MEETING NOTICES *
[(j MARCH 21, 1986 c.
DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/2/86 50-219 Room P-110 Discuss the post-accident GPUN J. Donohew i
9:30 a.m.
Phillips Bldg.
NUREG-0737 Items II.F.1.1/2 design criteria for the Radioactive Gaseous Effluents Monitoring System (RAGEMS).
4/8/86 Room P-118 Discuss the draft plant being B&W Owners W. Paulson 9:30 a.m.
Phillips Bldg.
developed by the B&W Owners Group Group to address the NRC staff's concerns relative to the frequency of reacto- *-ips.
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NMSS MEETING NOTICES FOR WEEK ENDING:
3/21/86 co Division of Fuel Cycle and Material Safety s
rd 12 DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 3/19-20/86 40-3392 Glen Ellyn.
To attend enforcement conference W. Pennington (FC)
Cool Il for Allied Chemical.
D. Cool (FC)
Regional Reps 3/23-27/86
- Richmond, To attend DOE seminar on trans-M. Lauer (FC)
Lauer VA portation regulation review.
3/27/86 Project
- Willste, To discuss NAC/ Storage Transport Reps of Nuclear Roberts 9:00 am M-40 5th floor Cask.
Assurance Corp.
conf room J. Roberts (FC)
F. Sturz (FC)
J. Schneider (FC)
Division of Waste Management None Division of Safeguards None I
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RES MEETING NOTICES March 21,1986
[
DOCKET ATTENDEES /
12 DATE/ TIME NUleER LOCATION PURPOSE APPLICANT NRC CONTACT C) 3/26-27/86 Atlanta, GA ANSI /NSB (Nuclear Standards Board)
ANSI /NSB Arlotto Executive Committee Meeting Members ANSI /NSB Meeting 3/26-27/86 ORNL HSST Program Review (informal)
Vagins Vagins d
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j 57 OSP MEETING NOTICES March 21, 1986 x
em m
DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 8?
4/3-4/86 New Orleans, LA Participate in DOE /LLW W. Kerr, OSP WKerr Meeting on Public State / Local 8:30AM Sheraton Involvement Officials r
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- u RII MEETING NOTICE s
is DOCKET ATTENDEES /
o' DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 03/18/86 50-395 Columbia, SC Summer SALP Meeting Regional Administrator, Walker 10:30 am Deputy RA, Selected Regional and Resident Staff Members, and Licensee Representatives e
9 P
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