ML20054E732
| ML20054E732 | |
| Person / Time | |
|---|---|
| Issue date: | 06/09/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-820604, NUDOCS 8206140116 | |
| Download: ML20054E732 (44) | |
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June 9, 1982 g
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For:
The Commissioners c /]Trfh@
JDD From:
T. A. Rehm, Assistant for Operations, Office of c
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 4, 1982 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Enclosure Contents Administration A
Nuclear Reactor Regulation B
Nuclear Materiai Safety and Safeguards C
D Inspection and Enforcement E
t!uclear Regulatory Research F*
Executive Legal Direct.or G
International Programs H
State Programs I*
Resource Management J
Analysis and Evaluation of Operational Data Small & Disadvantaged Business Utilization & Civil Rights K*
L Regional Offices M*
CRGR Monthly Report N*
Executive Director for Operations 0
l Items. Addressed by the Commission
- No input this week.
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T. A. R m, Assistant for Operations Office of he Executive Director for Operations FOR SUBSCRIBERS ONLY
Contact:
T. A. Rehm, EDO 492-7781 8206140116 820609 PDR COMMS NRCC WEEKLYINFOREPT PDR
fN HIGHLIGHTS OF WEEKLY INFORMATION REPORT Week Ending June 4,1982 WNP 3 The Washington Public Power Supply System (WPPSS) tendered an operating license application on June 2 for WNP Unit 3.
The unit is approximately 53% complete, with fuel loading currently scheduled for June 1985 San Onofre 1 On June 2, NRC discussed with the licensee the results of the steam generator debris inspection. Several broken wrapper support bars were found and removed from steam generators "A" and "B".
The licensee indicated that a report will follow.
TMI 2 Processing of the first batch of reactor coolant system water was completed on May 29,1982.
Access Authorization Rule Package The insider package, which consists of the proposed: access authorization, miscellaneous amendments, and pat-down search rules, is scheduled to reach the Commission by July 30, 1.982.
In the meanwhile, staff will re-examine the psychological testing requirement in the access autho'rization rule.
- Information TIansfer Operating Experience Paper An IAEA paper on "The Use of Operating Experience for Improving Nuclear Power Plant Safety in the United States" has been completed and will be presented at the IAEA International Conference on Nuclear. Powar Experience to be held in Vienna during September 1982.
Trojan On June 3, NRC notified Portland General Electric Company of the proposed imposition.of a $60,000 civil penalty for a Severity Level III violation resulting from the inoperability of an emergency diesel generator and failure to perform the required surveillance tests while it was out.of service.
LOFT Final preparations are being made for the L2-5 experiment, on schedule for June 16,1982.
- Not for PDR
T OFFICE OF ADMINISTRATION Week Ending June 4,1982 ADMINISTRATION OF THE F'REEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 288 9
Granted 207 0
Denied 32 6
Pending 49 3
ACTIONS THIS WEEK Received Philip N. Hamm esley, Requests, on behalf of hi.s client, film badge Trawick & Griffis, P.A.
records on his client.
(82-252)
(NRC employee)
Requests that copies of two computer printouts (82-253)
(051 and 052) regarding a particular Branch be sent to him beginning with March,1982 and to be continued indefinitely.
Leah Tremper, Requests all official charters for the Federal NTEU Steward Women's Program Advisory Committee and'the (82-254) charter referenced in a meeting on May 26, 1982.
Harold J. Spelman, Requests documents regarding any preliminary Harold J. Spelman draft Environmental Impact Statement for West and Associates Chicago, Illinoit Rare Earth facility prepared (82-255) by Argonne National Laboratory submitted in May 1981 to the NRC.
Harold J. Spelman, Requests documents regarding the preliminary Harold J. Spelman draft Environmental Impact Statement for West and Associates Chicago, Illinois Rare Earth facility prepared (82-256) by Argonne National Laboratory submitted subsequent to December 1981.
Harold' J. Spelman, Requests documents regarding the first prelimi. nary Harold J. Spelman draft Environmental Impact Statement for West and Associates Chicago, Illinois Rare Earth facility prepared (82-257) by Argonne National Laboratory submitted in December 1980.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A
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e Received, Cont'd Harold J. Spelman, Reque.sts documents regarding the Interagency Harold J. Spelman Agreement between the NRC and the DOE for the and Associates preparation of preliminary versions or drafts (82-258) of an Environmental Impact Statement covering decommissioning activities at the West Chicago, Illinois Rare Earth facility.
John W. Sullivan Requests a copy of seven listed NUREG reports.
(82-259)
Kathleen H. Shea, Requests a copy of the June 22, 1981 letter to Lowenstein, Newman, Self-Powered Lighting (SPL) from the Director, Reis & Axelrad Division of Fuel Cycle and Material Safety (82-260) informing them of the proposed denial of SPL's request for renewal of its license, SPL's subsequent request for a hearing, and all NRC or SPL documents relating to this issue after April 2,1982.
Granted David W. Meyer, In response to a request for a copy of SECY-82-86, Lowenstein, Newman, Nuclear Power Plant Staff Working' Hours, Memo Reis & Axelrad SECY to Dircks dated March 26, 1982, made available (82-188) a copy of the requested documents.
Katharine A. Watkins, In response to a request for a copy of SECY-82-72A, Lowenstein, Newman, made available a copy of this SECY paper.
Reis & Axelrad (82-212)
Ellyn R. Weiss, In response to a request for four categori.es of Union of Concerned documents regarding a meeting on or about March 12, Scientists 1982 between Chairman Palladino and Messrs. Dircks, (82-213)
Lafleur and England regarding safety issues likely to impact on the United Kingdom PWR inquiry, made available two documents, (NRCemployee)
In response to a request for three categories of (82-222) information pertaining to her EE0C complaint, made available 11 documents.
(NRCemployee)
In response to a request for a copy of the (82-237) selection certificate for vacancy announcement R 82-1318, specifically, the factor by factor rating between the requester and the selectee, made available a copy of this document.
Philip N. Hanniersley, In response to a request, on behalf of his client, Trawick & Griffis, P.A.
for his client's film badge records, informed the
{82-252) requester the NRC has no documents subject to his request.
ENCLOSURE A
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3 Denied _
Steven C. Sholly, In response to a request for documents regarding Union of Concerned failures of warning sirens or other devices used Scientists to notify the public in a radiological emergency; (82-152) any and all issues of a quarterly publication by the Office of Management and Program Analysis entitled, " Summary Information Report"; NRC's response and correspondence related to that response and to the GAO report "Do Nuclear Regulatory Commission' Plans Adequately Address Regulatory Deficiencies Highlighted by the Three Mile Island Accident?"; memorandum from SECY to EDO dated 5/1/80, "FY 1982-86 Policy, Planning and Program Guidance"; any documents related to NUREG-0839; and SECY papers,81-362, 81-422,81-509 and 81-454, made available 18 documents.
Denied one document in its entirety containing advice, analysis and opinions of the Offi_ce of the General Counsel regarding an ongoing deliberation. Also informed the requester additional documents subject to this request are already available at the PDR.
Dudley Thompson, In response to a request for 12 categories of Dudley Thompson documents regarding all NRC enforcement actions Associates involving civil penalties or orders on which (82-207)
NRC action was initiated or completed since January 1,1982, informed the requester the information he requested is already available at the PDR.
Denied 13 documents subject to item 2 of his request in their entirety containing advice, opinions and recommendations of the staff with respect to proposed enforcement actions by ccgnizant NRC Regional offices.
ENCLOSURE A
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.e DIVISION OF CONTRACTS ITEMS OF INTEREST WEEK ENDING June 4,1982 '
PROPOSALS UNDER EVALUATION RFP N0.: RS-NRR-82-ll8 Title : " Fire Protection Program Review" Casework Plants 1
==
Description:==
The contractor shall provide technical assistance in the review and evaluation of Final Safety Analysis Reports and Fire Hazards Analyses submitted by applicants for 2
the purpose of obtaining an operating license.
Period of Performance: 2 years and 5 months Sponsor: NRR Status: Proposals under evaluation 5-18 through 5-27 CONTRACTS CLOSED-00T NRC-19-81-495 Susan Wiltshire 6/2/82 NRC-10-81 -398 Wadlow Associates, Inc.
6/2/82 ADMINISTRATIVE MATTERS Contract No. NRC-04-76-242 with Daedalean Associates, Inc., was terminated for default on September 11, 1981. The contractor has exercised his right to appeal the default termination to the GSA Board of Contract Appeals. As part of the appeal process, the NRC has submitted to the GSA Board its official response to the contractor's appeal. The response is currently being examined by the GSA Board. Additionally, action has been taken to have the contractor's records regarding performance of the contract audited.
Finally, the contractor has requested that he and the NRC hold settlement discussions in order to resolve this matter prior to a decision by the GSA Board. The NRC is considering the contractor's request.
e ENCLOSURE A
DIVISION OF TECHNICAL INFORMATION AND.
DOCUMENT' CONTROL * -
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ENCLOSURE A i
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= =e OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending' June 4, 1982 San Onofre Unit No. I
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On June 2,1982 the staff and licensee representatives participated in a conference call to discuss the results of the San Onofre Unit No. I steam generator debris inspection. Three broken wrapper support bars approximately two inchas in diameter and six inches long were found by video inspection and r~emoved from steam generator "A".
There is one intact wrapper support bar in steam generator "A" and two bars which the licensee could not locate.
In addition, it appears that one of the welds attaching the upper portion of one of the intact wrapper support bars to the wrapper is broken. Steam Generator "B" had two broken wrapper support bars (removed), two intact support bars, one missing bar, and one location that could not be observed because of the difficulty of v. ideo scanning at the location.
No broken or intact wrapper support bars were found in l
steam generator "C"; however, upper sections of the support bars at the welds were there. The licensee has concluded that the missing bars were previously removed, most probably during manufacturing.
In addition to the wrapper support bars, detal shavings, and other miscellaneous pieces'of metal were located and removed from the steam generator.
The licensee indicated.that a report on the steam generator inspection results will be submitted next week for staff consideration.
WNP 3 The Washington Public Power Supply System (WPPSS) tendered an operating license application on June 2 for WNP Unit 3.
Unit 3 is now approximately 53% complete, with fuel loading currently scheduled for June,1985.
R. E. Ginna Rochester Gas & Electric (RG&E)is continuing to investigate the signals I
I received on its recently installed steam generator' Loose Parts Monitoring I
System (LPMS). ' Westinghouse technicians are-onsite and have two extra tranducers to use in determining the location of the source of the signals.
To date, they have been able to eliminate foreign objects in the primary side and noises in.the steam header as sources.
The investigation is-continuing to determine if the sou'rce 'is from the feed system, inside the steam. generator or from one of the snubbers that support the stemn generator.
ENCLOSURE B
o June 4, 1982 NRR MEETING NOTICES
- i ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT.
NRR CONTACT DOCKET 6/8/82 50-305 Kewaunee Plant Site Planning session to develop working Wisc. Public Service M. Grotenhuig schedules for completing licensing 10:00 am requirements 6/8/82 50-528 P-110 Arizona Public Service will make Arizona Public Service E. Licitra.
9:00 am 50-529 Bethesda a presentation on its emergency (PaloVerde) 50-530 procedures 6/8/82 50-322 P-118 Interaction of* staff and Long Long Island Lighting.
R. Gilbert' 10:00 am Bethesda Island Lighting Co. to discuss status of each open & confinnatory item on Shoreham 6/8-9/82 50-443 United Engineers &
Resolve open items related to the Public Service Co.~of L. Wheeler 9:00 am 50-444 Construction mechanical portion of the Power New Hampshire 30 S. 17th St.
Systems Branch (PSB) safety review Philadelphia, PA of the Seabrook OL application 6/8-9-10/82 Ft. Calhoun Site To audit the Station's procedures Omaha Public Power Dist.
E. Tourig; Pacific Northwest Lab.
8:30 am Washington Cty.,Nebr. and training as they relate to Pressurized Thermal Shock 6/9/82 50-285, Versailles Ballroom Discuss with the industry the Westinghouse Owners Grp., G. Vissin;-
9:00 am 261, 206,
. Holiday Inn NRC staff's positions and Combustion Eng. Owners 309, 251, Bethesda recommendations regarding the Grp... B&W Owners Grp, 317, 289, Pressurized Thennal Shock issue Omaha Public Power, 269 which wil1 be presented to the Maine Yankee Atomic, Commission Balt. Gas & Elec.,
Fla. P'ower & Light, 9
Carolina Power & Light, So. Cal.Edis:
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D. uke Power, GPU Nuclear SI PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166 A
co
- Copies of sumaries of these meetings will be made publicly available and placed in.the respective docket f the NRC and local public document rooms.
f
wt NRR MEETING NOTICESO s
ATTENDEES /
APPLICANT.
NRR CONTACT _-
DOCKET.
PURPOSE DATE/ TIME NUMBER LOCATION B&O Offices Discussion of issues raised
- ANL, B&W W. Jensen 6/9-10/82 Old Forest Rd.
by Argonne National Laboratory 8:30 am Lynchburg, Va.
in review of CADDS POWER TRAIN and TRAP-2 computer codes 6/10/82 50-275 Teledyne Offices Discuss status of the design Pacific G'as & Elec.
H. Schierling!
4 12:00 noon 130 Second Ave.
verification program efforts, (Dia.bloCanyon)
Waltham, Mass.
including schedules and QA program DiscussIPPRApiantanalysis Power Authority of J. Hannon 6/10-18/82 50-247' Pickard, Lowe &
50-286 Garrick Offices (internal and external events) the State of N.Y.,
Irvine, Calif.
and site visit by Sandia Consolidated Edison (6/10-15) regarding review of IP PRA Sandia Indian Point Site Buchanan, N. Y.
(6/17-18)
Utility briefs NRR on technical Washington Public Power L. Wheeler 6/11/82 50-508 P-ll4
- 9:00 am 50-509 Bethesda aspects of ITT - Grinnell Figure Supply System 215 Pipe Hanger Stiff Clamps Pacific Northwest Lab.
Ebasco ITT Discuss the identification and Baltimore Ga's & Elec.
D. Jaf,fe 6/14/82 50-317 P-110 9:00 am Bethesda repair of -steam generator tube damage at Calvert Cliffs 1 l'
m 492-7166 S
PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON g
tive docket file (s) in,
h 0 Copies of summaries of these meetings will be made publicly available and placed in,t e respec A
m the NRC and local public document rooms.
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UPDATED JUNE 8, 1982 NRR MEETING NOTICESO ATTENUEES/
a DOCKET DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT.
NRR CONTACT 6/9/82 50-395 P-118 To review applicant's modification South Carolina Elec. &
W. Kane 8:30 am Bethesda to the control room ventilation Gas system described in the June 3, 1982 (Virgil C. Sunner) i letter from T. Nichols to H. Denton 6/15/82 50-341 P-110 Discuss proposed changes to the Detroit Edison Co.
L. Kintner 1:30 pm Bethesda composition of the Fermi.2 Safety and Performance Engineering Group 6/15/82 50-389 P-110 Discuss the following' items per-Florida Power & Light V. Nerses 1:00 pm Bethesda taining to St. Lucie 2 Technical Specifications: 1) Format,
- 2) Implementation, 3) Changes and
- 4) Philosophy 6/15-16/82 50-447 GE Offices Technical update meeting on General Electric H. Faulkner 9:00 am Landow Bldg.
GESSAR II PRA Room 203 Bethesda 6/16/82 50-261 Center Plaza Bldg. Discussion of NRC's need for infor-Carolina Power & Light G. Requa 1:00 pm Room 3Cl mation for pursuing studies con-(H. B. Robinson 2)
Raleigh, N.C.
cerning USI A-47, Safety Implication of Control Systems, USI A-49, Pressurized Thermal Shock 6/17/82 50-341 Detroit Edison Discuss status of items identified Detroit Edison Co.
L. Kintner 9:00 am 3331 W. Big in the Safety Evaluation Report and (Fermi 2)
El Beaver Rd.
its supplements to be verified by n,
{j Troy, Mich.
NRC staff when completed.
E PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166
- Copies of summaries of these meetings will be made publicly available and placed inJthe respective docket file j
the NRC and local public document rooms.
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NRR MEETING NOTICES?
i ATTENDEES /
APPLICANT.
NRR CONTACT _
DOCKET-PURPOSE _
DATE/ TIME NUMBER LOCATION To discuss applicant's QA program Louisiana Power & Light S. Black 6/15/82 50-382 P-422
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(Waterford'3) 9:00 am Bethesda 1
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M r-E 492-7166 PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON w*
docket file (s) in.
ocopies of sumaries of these meetings will be made publicly available and placed in.'the respe the NRC and local public document rooms.
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NRC TMI PROGRAM 0FFICE' WEEKLY STATUS REPORT May 29, 1982 - June 5, 1982 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
Available Core Cooling Modes:
Decay heat removal (DHR) systems, Mini DHR (MDHR) system.
RCS Pressure Control Mode:
Standby pressure control (SPC) system.
t NOTE:
During Reactor Coolant Syrtem feed and bleed, pressure will be maintained with a Reactor Coolant Bleed Tank Pump. Automatic back up pressure control will be provided by the standby pressure control system.
Backup Pressure Control Modes:
MDHR and DHR system.
Major Parameters (as of 0500, June 4, 1982) (approxidate values)
Average Incore Thermocouples:
97*F Maximum Incore Thermocouple:
125 F RCS Loop Temperatures:
"A B
Hot Leg 94"F 96*F Cold Leg (1) 88*F 80*F (2) 90*F 83*F Pressure: 69 psig NOTE:
During reactor coolant system feed and bleed, pressure is maintained at approximately 70 psig.
. Reactor Building:
Temperature:
70*F Pressure:
-0.8 psig Airborne Radionuclide Concentrations:
3 9.7 E-8 uCi/cc H (sampletaken6/1/82) 85 6.0 E-6 uCi/cc Kr (sample taken 6/1/82)
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l.6 E-9 uCi/cc particulates (sample taken 6/3/82)
ENCLOSURE B
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Effluent and Environmenta1 (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the' period May 28, 1982, through June 3, 1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained small amounts of radioactivity.
Calculations indicate that less than seven-hundredths (0.07)ofacurieoftritiumwasdischarged.
2.
Environmental Protection Agency (EPA) Environmental Data i
The EPA Middletown Office has not received the environmental Kr-85 l
analytical results for the samples which were taken April 16, 1982, through May 21, 1982, from the EPA's Counting Laboratory at Las Vegas, Nevada. These results will be included in a subsequent report.
No radiation above,normally occurring background levels was detected l
in any of the samples collected from the EPA's air and gamma rate networks during the period from May 26, 1982 through June 3, 1982.
NRC Environmental Data 3.
l Results from NRC monitoring of the environment around the TMI ' site were as follows:
I The following are the NRC air sample analytical results for the l
onsite continuous air sampler:
l I-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-321 May 26, 1982 - June 2, 1982
<6.6 E-14
<6.6 E-14 4.
Licensee Radioactive Material and Radwaste Shipment On Tuesday, June 1,1982, two drums containing samples of Unit 1 steam generator tubes were shipped to Babcock and Wilcox, Lynchburg, Virginia.
On Tuesday, June 1, 1982, one drum containing samples of Unit 1 l
i steam generator tubes was shipped to the Battelle Columbus l
Laboratory, West Jefferson, Ohio.
l ENCLOSURE B l
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Major Activities Submerged Demineralizer System (SDS).
Processing of the first batch 1.
(approximately 50,000 gallons) of reactor coolant system (RCS) water was 1
completed on May 29, 1982.
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EPICOR II. ' The EPICOR II system is shutdown because no water is ready 2.
for processing.
Reactor Coolant System (RCS) Feed and Bleed. The second feed and bleed 3.
cycle of the RCS commenced on June 1, 1982, and was completed on
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June 4, 1982._
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Weekly reactor building entries are coritinuing Reactor Building Entry.
4.
to support the scheduled Axial Power Shaping Rod (APSR) insertion and the The APSR insertion is scheduled
. control rod drive lead screw removal.
for late June 1982 and the lead screw removal and closed circuit I
television inspection of the upper reactor vessel internals is scheduled F
I for mid July 1982.
l There are eight APSR's ii) the TMI-2 core.
The APSR's have the same-i physical appearance and dimensions as the 61 control rods in _.
l However, the neutron absorption section in the the core.
APSR's is only 36 inches long and is used to_ regulate power distribution L.
in the core during power operation. During an automatic reactor shutdown,.the eight APSR's are designed to remain in position while the 61 control rods (134 inch.
neutron absorption section) are inserted into the core to stop the nuclear chain reaction.
Following the automatic reactor shutdown on March 28, 1979, the APSR's remained withdrawn about 35 inches from the. bottom.of the core.
The scheduled APSR insertion in June is a prerequisite for normal APSR uncoupling from the rod drive mechanisms. ~ The uncoupling of.all rods is Following uncoupling, the reactor necessary.for reactor head removal.
vessel head can be removed along with the control rod drive. mechanisms while the control rods remain inserted in the core. During the scheduled APSR insertions, sonic and electronic monitors will be used to evaluate l
l the resistance to the movement of the APSR's.
The resu.lts will be used as preliminary data to determine the physical condition of 1!he TMI 2
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Core.
Water samples taken in April 1982 from Groundwater Monitoring.
5.
13 groundwater monitoring locations (test borings) indicate that tritium concentrations in the TMI groundwater have remained in the same range as The monitoring locations in reported in previous Weekly Status Reports.
the vicinity of the borated water storage tank (BWST) continue to show the increased tritium levels which were first identified in January 1982 after a leak was discovered from the BWST.
Based on samples taken in l
April 1982, test boring 16 and 17 contained the highest tritium concentrations, 670,000 pCi/L and 824,000 pCi/L, respectively.
l ENCLOSURE B
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' Gamma scans on samples taken in February and March 1982 have not identified any gamma emitting isotopes in the groundwater. Composite samples taken during the last quarter of 1981 from test borings and the east dike catch basin were analyzed for strontium 89 and 90. The analyses indicated that the strontium isotopes were below the lower limit of detection.
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Purification Demineralizer Disposal.
Preparations are being made by GPU and DOE for the eventual removal and disposal of two reactor coolant system letdown purification demineralizers. The 4 ft. diameter, 7 ft.
high, stainless steel vessels contain up to 50,000 curies of mixed fission products which were deposited on the organic ion-exchange resins during the March 29, 1979 accident.
Initially, characterization work will be performed to determine both the external conditions in the auxiliary building demineralizer cubicles and the internal conditions of the ion exchange vessels. The characterization will include analyses of gases, liquids and analyses of the resins. Potential methods being considered for removing these waste materials include:
(1)sluicingthe resins into a special shipping container, (2) chemically dissolving the ion exchange media followed by sluicing and solidification, and (3) removal of the intact demineralizer vessel and ' placement into a special shipping cask. The removal method selected will be based on the amount of radiation and thermal degradation that the resins experienced. The actual shipment of these two purification demineralizers to a DOE facility is anticipated to occur in 1983.
7.
EPICOR II Prefilter Inerting Tool Status.
s previously highl.ighted in the February 1,1982 Weekly Status Report, a remotely operated inerting tool was delivered to GPU for functional testing in preparation for shipment of the 49 EPICOR II prefilters (PF). This special TV monitored inerting tool, which was designed and built by the DOE (Idaho National Engineering Laboratory, INEL) to remotely sample and purge the EPICOR II PF's is currently being tested at TMI with a simulated EPICOR PF liner.
The functional test integrates the inerting tool with the support systems and hardware including the concrete blockhouse, remote support facility, ventilation system and effluent monitors.
For actual EPICOR PF shipment preparations, the licensee plans to perform all inerting operations at the solid waste storage facility (SWSF) in the individual cells where the PF liners are presently stored.
The inerting tool will be used; (1) to remove and insert the threaded vent plug on liner process parts, (2) to draw samples of the gases contained in the liners, (3) to purge the liner of contained gases, and (4) to inert the liners with nitrogen gas..All operations will be done remotely under a concrete blockhouse which will replace the existing cell shielding lid.
The first EPICOR II prefilter inerting is tentatively scheduled to begin in early July. After inerting and leak testing, the liners will be shipped to INEL in standard type "B" shipping casks which are designed to withstand transportation accidents.
ENCLOSURE B
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Past Meetings On May 28, 1982, Lake Barrett met with the Concerned Mothers group to discuss various TMI related issues.
On June 4, 1982, a meeting was held with 1,ake,,Barrett, NRC; Messrs.
Robert Arnold., President of GPU Nuclear; Bill Gifford, Vice President of Communications, GPU Nuclear; and a group of Concerned Mothers to discuss the financial difficulties that are hindering the progress of the Unit 2 cleanup.
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l ENCLOSURE B
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.a OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Itemsofinterest Week Ending June 4, 1982 CRBR Environmental Review Another version of the updated CRBR Environmental Statement was received 'from the contractors at the Pacific. Northwest Laboratories. This version has incorporated the previous comments made by staff members.
Value Impact Analysis of Statistical Deficiencies PNL is initiating a value impact analysis of the alternatives available to remedy the 13 statistical deficiencies identified in the " Report on the Statistical Treatment of Inventory Differences." A panel of six.to ten recognized experts in the field will be assembled to aid in the assessment.
Access Authorization Rule Package The insider package, which consists of the proposed access authorization, miscellaneous amendments, and pat-down search rules, is now scheduled to reach
- the Commission by July 30, 1982. The thirty.-day delay from June 30,1982 is to allow staff time to re-examine the psychological testing requirement in the access authorization rule.
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e ENCLOSURE C v
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HMSS MEETING NOTICES June 4. 1982 Division of Waste Management DOCKET ATTENDEES /
l DATE/TIhE NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT June 8,1982 Lincoln, Nebraska To formulate coordination of Nebraska State Officials; J. Linehan, NRC licensing review of proposed Reg. IV State Liaison WMUR R&D solution mining in Nebraska Office; J. Linehan, WMUR with tlose performed by the State under the UIC permit program June 10, 1982 Denver, Colorado To develop coordinated and timely UMTRAP State Reps; DOE; H. Pettengill, approacii for DOE action on vicinity EPA; H. Pettengill and WMUR properties, and to review roles in K. Hamill, WMUR standards development and concurrence process June 11, 1982 Denver, Colorado To review the NRC pending action on Union Carbide Reps and H. Pettengill, the reclamation plan for the inactive their contractors; WMUR tailings impoundment H. Pettengill, WMUR June 15, 1982 Germantown, MD Interagency Meeting on LLW Modeling D0E, EPA, USGS, NRC E. F. Hawkins, 9:00 a.m.
Room C-337 WMLL June 15, 1982 Willste Building, DOE /NRC Information Meeting on Data Tina Jouse and Cheryl Ken Jackson, 9:00 a.m.
4th Floor Conf. Rm.
System for tracking waste' generation Coppin, EG&G; Ken WMLL and di,sposal Jackson, WMLL June 16-17, 1982 Arlington Hyatt Symposium on LLW Disposal: Site NRC; other Federal M. Dunkelman, Arlington, Virginia Characterization and Monitoring, agencies; private ind.
WMLL June l'.
1982 Moran, Wyoming Roundtable Open Discussion of Reps. of Uranium R. A. Scarano, Current NRC Mill and Mill Tailings Milling Industry; WMUR Licensing Requirements and Methods R. A. Scarano, WMUR g
by which the Licensing Staff 72 Proposes to Implement the Tailings St Regulations in 10 CFR 40 App. A.
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"' June 18, 1982 USGS, Reston, VA USGS Contract with NRC on Ground-J. Robertson, USGS; E. F. Hawkins, c'
water Waste Disposal in Sheffield, E. Hawkins, D. Siefken, WMLL Illinois and J. Shaffner, WMLL
June 4,1982 NMSS MEETING NOTICES Division of Fuel Cycle and Material Safety _
ATTENDEES /
DOCKET APPLICANT _
NRC CONTACT
) ATE / TIME NUMBER _
LOCATION PURPOSE June 3 Project Willste To discuss West Valley Demonstration Marcy Williamson, A. T. Clark etal.,(D0E) 9:00-11:30 M-32 Room 106 Project A. T. Clark (FC)
L. C. Rouse (FC).
N. Ketzlach June 3 70-27 Willste Discuss B&W amendment application W. T. Crow (FC))
9:30 Room 548 for fabrication of test reactor N. Ketzlach (FC fuel assemblies B. Kosla (FC)
R. A. Cordani (B&W)
J. W. Kelly (B&W)
H. H. McClanahan (B&W)
June 4-21 70-734 Los Angeles, Participate in American Nuclear N. Ketzlach (FC)
N. Ketzlach j
San Diego, CA Society Standards Committee Meetings and Technical Sessions on Nuclear Criticality Safety and a site visit to General Atomic Co.
June 7-9 40-8406 Pulaski,PA Pre-licensing site visit to B. Kosla (FC)
B. Kosla Pessess Co. at the Metcoa site June 7-11 Project West Valley, To observe and consult with' A. T. Clark (FC)
A. T. Clark-M-32 New York Rockwell Hanford on High Level Rockwell Hanford Waste. Tank Inspection at West Project Manager 00E-West Valley Valley, New York Site Rep June 9 71-9132 Willste Sodium Contaminated Fuel in C. E. MacDonald (FC)
R. H. Odegaarden R. H. Odegaarden (FC) 9:00-11:00 Room 517 T-3 Cask W. Lake (FC)
P Dick Helsig (Nuclear Packaging) n, Fi Joe Gofford (Westinghouse)
G tew
.1 O
Paga 2 June 4, 1982 NMSS MEETING NOTICES Division of Fuel Cycle and Material Safety ATTENDEES /
DOCKET APPLICANT NRC CONTACT
] ATE / TIME NUMBER LOCATION PURPOSE June 11 71-5450 Willste RCC Series Package R. H. Odegaarden (FC)
R. H. Odegaarden 9:00-10:00 Room 517 Increased Fuel Enrichment C. Marotta (FC)
Joseph Nardi (Westinghouse
+3)
June 14-16 Albuquerque, To work with Sandia Lab on the D. Chapell (FC)
D. Chapell New Mexico Material Licensing Study J. Cook (FC)
Rep. from IEAL Rep. from SANDIA June 16-18
- Miami, To speak at Annual Meeting on R. E. Cunningham (FC)
R. E. Cunningham Florida ALARA in the context of nuclear
^
medicine and discuss how an ALARA program can be organized in a nuclear medicine facility
- June 17 Willste Meet with GNS Company for Nuclear C. E. MacDonald (FC)
C. E. MacDonald Room 517
. Services, Ltd.
Pre application C. Marotta (FC) (RES) meeting for cast modular iron J. Weidenhammer Jack Rollins (GNS) shipping cask Rep. from LLL OTentative schedule P85 m
.1
~
~
l OFFICE OF INSPECTION AND ENFORCEMENT l
Items of Interest Week Ending June 4,1982 1.
No Significant Enforcement Actions were taken during the past week.
2.
The following Prelimiaary Notifications were dispatched during the past week:
a.
PH0-HQ-82-01, Sardia Laboratories (Albuquerque, NM) - Fire in a Test Facility Containing Uranium 0xide, b.
PN0-I-82-40, Pilgrim Nuclear Power Station - Stuck Traversing In-Core Probe (TIP): High Local Radiation on Reactor Suilding (Ground Elevation).
PN0-II-82-60, Carolina Power and Light Company (Brunswick Unit 2) -
c.
Pinhole Leak Identified in Reactor Coolant Pressure Boundary, d.
PN0-II-82-61, Carolina Power and Light Comp'any (Brunswick Unit 2) -
Licensee Report of Potential Sabotage, e.
PN0-III-82-50, Cincfnnati Gas and Electric Company (William H. Zimmer Nuclear Power Plant) - Quality Control Inspector Killed in Auto Accident.
f.
PN0 III-82-51, Cincinnati Gas and Electric Company (William H. Zimer Nuclear Power Station) - Work, Halted by Licensee followl.ng Dousing of Quality Control Inspectors.
g.
PNO-IV-82-23, Arkansas Power and Light Company (Arkansas Nuclear One -
Unit 2), Outage Greater Than Two Days, 1
3.
The following IE Bulletin was dispatched during the past week:
IE Bulletin No. 82-02:
Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants.
4.
Other Items l
Division of Emergency Preparedness 1.
On June 2,1982, IRDB staff members participated in a meeting on NRC/ FEMA l
incident response. Also involved are Regional Emergency Planning l
Coordinators and their FEMA Regional counterparts.
ENCLOSURE D
/
s 2-4 i
2.
On June 3,1982, the Director,'DEP, made a presentation to the ACPs,(Dr. Moeller) on emergency planning related to earthquakes.
3.
On June 3,1982, the Director, DEP, participated in a meeting with General Lewis (FEMA) to discuss emergency planning requirements for low power operation.
Division of Reactor Programs 1.
Larry Cohen conducted a meeting in Region IV on June 3 to discuss state contracts for environmental monitoring.
2.
John Buchanan and Fred Anderson will visit RI June 9-11 to review the Region's Health Physics Appraisal followup.
1
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I I
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1 ENCLOSURE D y
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l June 4, 1982
~IE MEETING NOTICES DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION
~ PURPOSE APPLICANT NRC CONTACT June 7; 8:00AM 50-528 Palo Verde Site Tour and Orientation Richard DeYoung Richard DeYoung 50-529 Robert Engelken 50-530 June 8; 8:00AM San Diego, CA-Discuss Techniques for Richard DeYoung Richard DeYoung Management Management Assistance Robert Engelken Analysis Corp.
Ronald Haynes June 8 Los Angeles CA Presentation on Emergency Frank Pagano Frank Pagano Preparedness Appraisal Brian Grimes Program at Annual ANS Conference June 9 Richland/
Participate in a Mid-Year Frank Pagano Frank Pagano Seattle Review of the PNL l
Contract June 10 Los Angeles CA Orientation Visit to Frank Pagano Frank Pagano Training Reactor at University of. California at Los Angeles F2 i.
8 si m
C3 i
l.
CFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending June 4, 1982 NRU The NRU LOCA heatup and clad ballooning test MT-4 was successfully completed on Thursday, May 27. The center 12 rods of a full-length, commercial enrichment, 32-rod bundle were pressurized to extreme high burnup conditions (4.6 MPa = 670 PSIA 9 300K) and the bundle was nuclear heated to provide a peak clad heatup rate of about 8K (15'F) per second, and pressurized rod clad rupture temperatures of 1080K-1100K (1480*F-This is the high clad distortion range. The reflood rate was 1520*F).
then controlled for 20 minutes to keep the upper regions of the fuel rod bundle uncovered, but at safe peak clad temperatures. The whole bundle was then recovered with water and the nuclear heating was stopped. The measured clad temperatures during and after test showed that the bundle was coolable at all times and that the post-ballooning local heat transfer coefficients at all measured points on the bundle were effectively as good as or better than the pre-ballooning heat transfer coefficients.
The results to date indicate that, under best estimate large break loss of coolant accident conditions, the cladding of the average 17 x 17 type fuel rod with Sandvik cladding will not be heated hot enough to balloon and the few if any extreme condition fuel rods will not balloon enough to ' threaten local fuel bundle coolability.
2D/3D Analysis Support The TRAC analysis support for the 2D/3D program at Los Alamos is now playing a major role in the overall program. Blind predictions have been provided for the CCTF and SCTF tests and TRAC has been shown to be a reliable analysis tool. The most significant role of the analyses to date has been the recent TRAC predictions confirming the importance of multidimensional flows in these large scale test facilities. Such multidimensional flows are shown to be responsible for rritigating the effects of large nonunifonn local power distributions, which cannot be represented by simple one-dimensional computer codas. LANL is preparing a computer-generated movie illustrating this flow redistribution for the power effects tests in the Slab Core Test Facility. The flow re-distribution could not be detected by the instrumentation (radial ap gauges).
ENCLOSURE E
.a
' Midland BE LOCA Analyses A letter report was received from LANL on their large-break LOCA analysis for the Midland plant (B&W) with a coarse-node input deck using TRAC-PD2.
This calculation was requested by NRR and several copies were transmitted to them.
The main results were:
(1)amaximumhot-rodcladdingtemperature of 962'K was predicted to occur at about 35 seconds with all rods quenched by 123 seconds; (2) most of the liquid supplied by the pressurizer and half that supplied by the accumulators was forced out of the break; core refilling was accomplished mostly by the LPIS.
Large Melt Facility The first large scale test of UO2 (273 kg. charge) in the large melt facility was terminated by a water leak in the RF coil. The futnace had reached the design temperature level in the graphite susceptor of 2700'C and the charge was being heated to melt temperature (2550'C) when the leak occurred. The leak was first indicated by pressure surging in the RF coil cooling water. The furnace tripped shortly thereafter on an overpressure signal from the furnace shell. The water failed the melt crucible instrumentation but the late readings indicated that some melting may have occurred and an attempt was made to tap the charge without success.
Inspection of the facility on June 1,1982 indicates that the furnace shell is undamaged. The " water gas," produced by the water / hot graphite reaction, exited from the pyrometer port and burned in the atmosphere. The pyrometer was destroyed and the furnace lid handling crane is considered unsafe to operatee Except for the glass, the ports did not appear damaged.
The charge for the second test is being pressed at LANL and a second melt crucible is on hand.
It is currently estimated that the lid. handling crane, the new charge crucible, instrumentation replacement and new RF coil installation can be accomplished to permit Test #2 to proceed in August 1982 as previously scheduled.
LOFT Final preparaticns are being made for the L2-5 experiment, on schedule for June 16, 1982. All necessary plant modifications have been made and plant fill has begun in preparation for a plant leak test. L2-5 will be a double-ended cold leg break with an assumed loss of offsite power. The consequent rundown of primary pumps and delay in pumped ECC injection is predicted to lead to a maximum peak clad temperature 0
of 1489 F.
A report on the defective internal fuel clad thennoccuples has been delayed pending the completion of autoclave tests. All surface mounted thermocouples are still operative.
ENCLOSURE E
BWR FIST The FIST vessel has been delivered to the GE Test Site in San Jose, California. The vessel delivery was delayed approximately 2 months due to fabrication difficulties. Of the 2 month delay, GE can recover about one month during construction. Some additional.Mco.ygrX may.. result.
during shaked6M ~ f now iir'ofic~t'itait 'of' tesfin'g in' Hovember or December 1982 if_no further delays are encountered.
Northwestern University NWU has submitted two reports for publication. They highlight experimental results in the following areas:
(a) Countercurrent Steam-Water Flow in Flat Plate Geometries, and (b) The Behavior of Water Sprays Injected Into An Air / Steam Environment.
Data Bank Data from three reflood runs in the FEBA (Flow Effects Blockage Apparatus) facility were added to the data bank. Runs numbered 4261, 4262 and 4263 were input and resulted from Test Number 3211, Series 4 which is a 62 percent blockage test series Semiscale The first 100 percent main steam line break experiment which was run on semi-scale last week was initiated from hot standby conditions. The steam flow rate was higher than the condenser could handled resulting ir. high back pressure in the main steam line. This prevented establishing chocked flow and thus reduced the primary side cooldown rate. Pump seal leakage prevented a successful feed / bleed add-on test. Hardware repairs are in progress, after which a 50 percent steam line break test will be run.
Plans call for adding-on' a feed / bleed test again.
USNRC/CEA Cooperative Research The agreement between the USNRC and CEA for a 3-year program of cooperative research on the nuclear qualification of polymer base materials has been Specimens of gasket, seals, cables and officially signed by both parties.
electrical insulation materials are to be aged in the LICA facility at Sandia National Laboratories and be sent to Saclay in France for LOCA qualification in the CESAR facility.
The initial batch of specimen materials from Saclay has been received at Sandia.
Publications Issued During the Neek of May 31-June 4,1982 Draft Regulatory Guide and Value/ Impact Statement: Second Proposed Revision 4 to Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (ALARA)". Task OP 618-4.
Coments requested by August 10, 1982.
ENCLOSURE E
RES MEETING NOTICES
.inna 4-10M ATTENDEES /
DOCKET DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT _
i (If Applicable)
- 6/1-3 Paris, France Attend special international DFRoss DFRoss, RES Meeting on LOFT Consortium.
16/14-15 Oak Ridge, Tennessee Attend workshop on Novel Design Concepts for LSTong, RES Light Water Reactors 6/28229 Oak Ridge, Tennessee Research program management ORNL review.
Dross /RBHinogue t
Brookings Institution Invited Speaker on Participant in P. A. Comella 6/3/82 6:30 p.m.
HLW Disposal Brookings Conference-Federal Gov't Ops-A seminar in Public
~
Policy ANS Meeting, LA Invited Papers on 1982 Annual P. A. Comella 6/8/82 AM & PM "NRC Regulations Meeting F. J. Arsenault for HLW Disposal" i.
E and
~P
" Licensing: Techno-
.8 logical Implications
'E for Geologic Disposal of High-Level Radio-active Wastes"
s_,
June 4. 1982 RES MEETING NOTICES ATTENDEES /
DOCKET DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT (If Applicable)
$/2 Willste Bldg.
Contractor Visit L. Beratan T. Nicholson Dr. D. Evans, U.of AZ:
T. Nicholson Unsaturated Flow & Transport R. Kraus Through Fractured Rock Related to High-Level Repositories Semi-Annual Program Review for L. Beratan L. Beratan 6'/4 USGS Reston, VA Office of Earthquake Studies-A. Murphy USGS Arlington Hyatt Symposium on LLW Disposal:
L. Brown E. Hawkins 6/16-17 Site Characterization and T. Nicholson Monitoring T. Schmitt E. Zurflueh R. Kraus sne 14-16 Counsel Room To conduct a critical Cognizant NRC staff C. Jup' iter Sheraton Inn technical review of contractors, and 8727 Colesville Rd the hydrological and consultants Silver Spring, MD geochemical modeling aspects of the RES waste management research rg c3 program.
5 15 m
A
I RES MEETING NOTICES June 4, 1982
+
~
I ATTENDEES /
i DOCKET APPLICANT NRC CONTACT _
I DATE/ TIME NUMBER LOCATION PURPOSE (If Applicable)
June 12-18 Miami Beach
- Society of Nuclear Medicine Deborah A. Bozik Annual Meeting
\\'
Attendee is going for.th.e following reasons:
0 (1) To take part in, a Discussion / Commentary of which she will discuss " Guidelines afor Patients at Home following Treatment with Radioiodine*
There has been press intere'st in this topic.
(2) To respond to an invitation from the SNM's Committee on Government Relations to discuss the proposed revision to Part 35.
(3) To respond to an invitation from the SNM's Publications Committee to be present for questions regarding the I-131 pamphlet mentioned in (1) which is being considered for publication by SNM.
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RES t' _ TING NOTICES June 4. 19R7 1
ATTENDEES /
DOCKET DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT (If Applicable)
June 7,1982 Room 1148-5S
!!eeting with R. Klersy and C. Kelber/D. Ross C. Kelber 10:00 am H. Holtbecker, Ispra, Italy June 7, 1982 Bonaventure Hotel ANS Ad Hoc Committee on " Source Committee members R. Minogue/
5:00 pm Los Angeles, CA Terms" being appointed W. Pasedag June 15, 1982 Culcheth,UK UKAEA-USNRC Research Coordinators R. Minogue/
'R. Minogue Meeting Jose Cortez June 16, 1982 Springfields, UK Discuss fuel-related work and R. Itinogue/ Jose Cortez/
R.Pitnogue Springfields Nuclear tour facility
- 0. E. Bassett Power Development Laboratories June 17,1982 Bournemouth, UK Discuss LOCA topics and tour R. Minogue/ Jose Cortez/
R. Minogue l
UKAEA Atomic Energy facility O. E. Bassett Establishment June 18, 1982 London, UK Discuss radiological protection R. Minogue R. Minogue Health & Safety standards and applications of 9
Executive rish assessment to the " inquiry".
,j2 Nuclear Installations l5!
Inspectorate l E, n
'm
June 4, 1982 RES MEETING NOTICES ATTENDEES /
DOCKET APPLICANT NRC CONTACT DATE/ TIME NUMBER LOCATION PURPOSE (If Applicable)
J. Jones-PUBLIC MEETINGS ON THE ADVANCE NOTICE OF PROPOSED RULEMAKING ON CERTIFICATION OF INDUSTRIAL R June 8, 1982 Atlanta, Georgia 9:00 am Colony Square Hotel June 10,1982 Houston, Texas 9:00 am University of Texas School of Public Health Auditorium June 15, 1982 Oakland, California 8
9:00 am Hyatt Oakland Hotel' June 17,1982 Chicago, Illinois 9:00 am Americana Congress Hotel June 23, 1982 Washington, DC 9:00 am GSA Auditorium l
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June 4. 198?
RES MEETING NOTICES f
I ATTENDEES /
DATE/ TIME NUMBER.
LOCATION PURPOSE APPLICANT NRC CONTACT DOCKET (If Applicable)
June 15, 1982 Room 2318 RH0S Bouguard Hearing 1:00 pm CSNI Senior droup of Possibly D. Ross R. Minogue.
June 16-18,1982 Paris, France Experts on Severe Accidents
[
June 16, 1982 NBS Interagency Comittee Committee members E. Oklesson 10:00 am Gaithersburg, MD on Standards Policy l
l June 7,1982 Bonaventure Hotel ANS 9 Standards Subcomittee Subc. members E. L. Hill 9:00 am Los Angeles, CA E
m I
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 4,:1982 NRC Training for Short-Term Foreign Assignees
- Cesar Cruz from the liexican National Nuclear Safety and Safeguards Commission (CNSNS) will participate in a BWR Technology Course (R-106B) at the Reactor
, Training Center from June 7-11.
Carlos Arredondo and Ruben Ramirez (CNSNS) will be visiting the NRC June 7-11.
During that time they will meet with representatives from the Mechanical Engineering Branch and the Operating Reactors Assessment Branch to discuss equipment qualification.
' FOREIGN VISITOR TO NRC On Thursday Mr. Santiago Valverde, Chief of the Data Processing Center of Brazil's Institute of Energy and Nuclear Research (IPEN), met with H. Sullivan, Chief of the RES Separate Effects Research Branch, to discuss the development and utilization of reactor safety computer codes, and with R. Senseney, IP, for an overview of NRC and its cooperative program with the Brazilian regulatory authority.
- INFORMATION TRANSFER Renewal of NRC-Swiss F0E Arrangement IP appears to have reached agreement with the: Swiss Federal Office of Energy (F0E) on the renewal text of the "NRC-F0E Arrangement for the Exchange of Technical Information and-Cooperation in Nuclear Safety fiatters." The Swiss, since December 1979, had raised several questions about NRC's ability to protect information provided in confidence and about their ability to give us such utility-owned information in the first place. We have agreed to modify Section III.1 of the Arrangement (which had called for the " widest possible dissemination of information," regardless of intended use) as follows:
"The parties support dissemination of information provided or exchanged under this Arrangement, as far as the safety of nuclear installations may be increased by such dissemination, subject both to the need to protect proprietary or other confidential or privileged information as may be exchanged heraunder, and to the provisions of the Patent Addendum."
- Not for PDR ENCLOSURE G
2 Renewal of NRC-Swiss F0E Arrangemen'; (continued) '
The letter agreeing to this change is'now in NRC concurrence channels. The full package for the ED0's signature and Executive Branch clearance will be.
prepared within the next two weeks.
Foreign Report
- Not for PDR.
ENCLOSURE G
e sO OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING. JUNE 4,1982 New Mexico Draft Proposal for Amended Agreement On June 3 the staff received New Mexico's final draft proposal for an amended agreement to continue to regulate uranium mill tailings. New Mexico is requesting review of the final draft prior to the Governor formally submitting the proposal.
Follow-up Review of Kansas Program A follow-up review will be performed June 7-8, 1982 of the Kansas radiation control program.
i e
1 l
l I
l ENCLOSURE H
- i..
o o
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF' INTEREST WEEK ENDING JUNE 4, 1982 Engineering Evaluation on Degradation of BWR Scram Pilot Solenoid Valves Due to Abnormal Power Supply Voltage AEOD has completed an engineering evaluation of an August 1981 event at Grand Gulf Nuclear Station where, during CRD checkout testing during' construction, several scram pilot valves were found stuck in the energized position when the solenoids were de-energized. This prevented the proper actuation of the affected scram inlet and outlet valves. The licensee has determined that the valves were damaged by being operated with insufficient voltage being supplied to the solenoid coils by the power supply for the reactor protection system due to insufficient cable size.
A number of suggestions resulted from this eva?uation. These items have been forwarded to NRR and IE for appropriate action.
IAEA Paper on "The Use of Operating Experience for Improving Nuclear Power Plant Safety in the United States A paper on the above subject has been completed and forwarded to IAEA. The paper will be presented by Carl Michelson at the IAEA International Conference on Nuclear Power Experience to be held in Vienna during September 1982.
The paper presents an overview and status of NRC's recent experience with the operational experience assessment program, and describes the approach and various activities of AE00. The results of several AE0D studies are discussed as examples of the lessons learned from operating experience.
ENCLOSURE J
June 4,1982 AEOD MEETIriG NOTICES I
1 l
OATE/ TIME LOCATI0il PURPOSE ATTEt4 DEES NRC CONTACT June 9-10,1982 If4P0 Offices Informal discussions on BWR fiRC Stuart Rubin Atlanta, GA related operational data.
S. Rubin E. Brown M. Chiramal IttP0 R. Baker, et al G
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REGI'ON I MEETING NOTICES aim,a_ long
~'
OATE ATTENbEES/
DOCKET DATE/ TIME NUMBER LOCATI0l_
PURPOSE APPLICANT.
NRC 0NTACT Public Meeting concerning the FEMA-Robert. Bores Hiantic, CT Edward. Wojnas 6/7 AM March 20, 1982 Millstone Exercise Arlingto, VA Symposium on Low-Level Waste State Officials Faith E Brenneman 6/16-17 Disposal: Site Characterization 8:00 AM and Monitoring ORNL/NRC e
e P
o C
A r
4 I
^
.e REGION V ITEMS OF INTEREST
- WEEK ENDING JtJNE 4,1982 Portland General Electric Company TROJAN - DN 50-344 On June 3,1982, the Region V Administrator notified the licensee of the proposed imposition of a $60,000 civil penalty for a Severity Level III violation resulting from the inoperability of an emergency diesel generator and failure to perform the required surveillance tests when one of the diesels was out of service. A press release was issued June 3,1982 by Region V.
e ENCLOSURE L
I
. e f!EGI0tl V f1EET1tJG NOTICES WEEK ENDING 6/4/82 DATE/ TIME DOCKET HO.
LOCATION PURPOSE ATTENDEES /
NRC CONTACT APPLICANT USAF Hospital (MAC),
The NRC will discuss the
- Hospital, Mr. R. Thomas 6/8/82 03001225 Travis AFB, CA enforcement options available Director, and to the NRC as a result of
- Staff, findings from a recent inspection.
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_.g._._..._..__._..._.-___..__
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1
ITEMS ADDRESSED BY THE COMMI.SSION - WEEK ENDING JUNE 4, 1982 A.
BRIEFING BY DOE ON TMI-2 CLEAN UP, 1:30 P.M., WEDNESDAY, MAY 26, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE, (PUBLIC MEETING),. Memo Secy for the Record, 5/27/82 The Comission* was briefed by the following representatives of.the Department of Energy on their, activities associated with the clean-up of TMI-2.
Mr. Ben Rusche, Special Assistant to Secretary Edwards Dr. Franklin E. Coffman, Deputy Assistant Secretary for Nuclear Waste Management and Fuel Cycle Programs Mr. Herbert Feinroth, Acting Deputy Director, Office of Coordination and Special Projects The Commission took no action and made no requests of staff.
B.
STAFF REQUIREMENTS - AFFIRMATION OF SECY-82-208 - APPROVAL UNDER SECTION 145B 0F THE ATOMIC ENERGY ACT OF 1954, AS AMENDED, FOR THE EMPLOYMENT OF MS. SAUNDRA R. FRAGER AS A SECRETARY TO COMMISSIONER JAMES K. ASSELSTINE AND FOR ACCESS TO NATIONAL SECURITY INFORMATION AND RESTRICTED DATA, 12:05 P.M.,
FRIDAY, MAY 28, 1982, COMMISSIONERS' CONFERENCE ROOM (OPEN TO PUBLIC ATTENDANCE),
Memo Secy to Dircks, 5/28/82 The Commission
- by a vote of 4-0:
(Commissioner Gilin 9 r not' participating) 1.
Approved, pursuant to Section 145b of the Atomic Energy Act 1954, as amended, employment.of Ms. Saundra R.
Frager as a Secretary to Commissioner Asselstine and granted her access to National Security Information and Restricted Data; and 2.
Granted Ms. Frager an NRC "Q" access authorization.
(ADM)
C.
STAFF REQUIREMENTS - BRIEFING ON GENERIC EVALUATION OF FIRST-ROUND EXERCISES AND APPRAISALS (NT0L'S AND OR'S), 2:00 P.M., THURSDAY, MAY 20, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE),
Memo Secy to Dircks, 6/3/82 The Commission
- was briefed.by I&E on the results of the recently completed emergency preparedness on-site appraisals as described in SECY-82 -199.
The Commission:
1.
Requested staff to provide a few examples of the cost per booklet of public information brochures; (IE)
(SECY Suspense:
6/30/82)
- Commissioner Gilinsky was not present.
ENCLOSURE O
5
~~ '
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 4, 1982 C.
STAFF REQUIREMENTS - CONT'D 2.
Requested a status report on those plants that are in the 120-day period, particularly those that are past or at the end of the 120-day period, whether there were any cases where the 120-day clock expired without staff action and what actions staff is contemplating; (IE)'
(SECY Suspense:
6/30/82) 3.
Noted that a FEMA report is due the end of June 1982, covering the review of state and local emergency plans and the results of offsite exercises.
The' Chairman asked staff to develop a briefing or review of the program of off-site appraisals.
(IE)
(SECY Suspense:
8/30/82)
L STAFF REQUIREMENTS - BRIEFING 0N SECY-82-178 - HUMAN FACTORS SOCIETY REPORT 10:00 a.m., TUESDAY, MAY 25, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C.
OFFICE (OPEN TO PUBLIC AT.TENDANCE), Memo Secy to Dircks, 6/4/82 The Commission
- was briefed on the draft report of the Human Factors Society on their project to develop a comprehensive Human Factors Plan.
Members of the Human Factors Society Study Group present were:
l 1
1.
Dr. Harry Snyder, Chairman l
2.
Dr. Charles Hopkins 3.
Mr. H.E. Price 4.
Dr. Richard Hornick, and 5.
Dr. Robert Smillie The Commission was informed by staff that the staff's " Human Factors Program Plan" is scheduled to be submitted July 1,1982.
The Commission:
1.
Requested that the final report include a total of the resources required by the recommendations; 2.
Requested a staff estimate of the program's implementation cost -
to nuclear power plant owners; 3.
Directed staff to interact with the Society on estimating the cost of the research program; l
4.
Asked that the schedule entries (table 4) include high-medium-low l
markings.
(RES)
(SECYSuspense:
7/1/82)
ENCLOSURE 0
- Commissioner Gilinsky was not present
,3 ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 4, 1982
~
E.
STAFF REQUIREMENTS - BRIEFING ON MID-YEAR RESOURCE AND PROGRAM REVIEW, 10:00 A.M., TUESDAY, JUNE 1, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy to Dircks, 6/4/82 The Commission was briefed on the status of program performance and resource expenditures for the first half of Fiscal Year 1982.
The Commission requested a briefing on the Systematic Evaluation Program and its relationship with IREP/NREP before the start of Phase III.
(NRR) (SECY SUSPENSE:
8/27/82)
F.
SECY-82-137 - ABNORMAL OCCURRENCE RECOMMENDATION - MAJOR DEFICIENCIES IN.
MANAGEMENT, Memo Secy to Dircks, 6/3/82 This is to advise you that the Commission (with Chairman Palladino and Commissioners Gilinsky and Roberts agreeing and Commissioner Ahear'ne disagreeing) has approved the proposed Abnormal Occurrence as modified in the attachment.
Commissioner Asselstihe did not participate i'n.this action.
Commissioner Ahearne believes that removal of two paragraphs (which describe the nature of management deficiencies) have
. mischaracterized the nature of the occurrences that were intended to be reported as an Abnormal Occurrence.
The Federal Register notice should be prepared and forwarded for publication.
(AEOD) (SECY SUSPENSE:
6/14/82)
The Office of Analysis and Evaluation of Operational Data' was informed of this d,ecision on June 3, 1982.
6 ENCLOSURE 0