ML20058N397
| ML20058N397 | |
| Person / Time | |
|---|---|
| Issue date: | 03/18/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20058M131 | List:
|
| References | |
| FOIA-92-436 SECY-82-123, WIR-820312, NUDOCS 9310140242 | |
| Download: ML20058N397 (42) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D C.20555 i
INFORMATION REPORT March 18, 1982 SECY-82-123 For:
The Commissioners Irom:
T. A. Rehm, Assistant for Operations, Office of the EDO Subiect:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 12, 1982 A summary of key events is included as a convenience to those Commissioners who nay prefer a condensed version of this report.
Enclosure Contents A
Administration B
Nuclear Reactor Regulation C
Nuclear Material Safety and Safeguards D
Inspection and Enforcenent E
Nuclear Regulatory Research F*
Executive Legal Director G
International Programs H
State Programs I
fianagement and Program Analysis J*
Controller K
Analysis and Evaluation of Operational Data Small & Disadvantaged Business Utilization & Civil Rights L
11 Regional Offices
~
N*
CRGR Monthly Report 0
Items Approved by the Comission T. A. Renm, Ais{stant for Operations 9310140242 930218 Office of the Executive Director r
bI$1N 9 -436 PDR for Operations b
- No input this week.
N D
'C
Contact:
D" T. A. Rehm, EDO m iss n ers FOR INTERNAL NRC 492-77EI Ccrrissicn staff offices DISTRIBUTION ONLY g
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SUMMARY
OF THE WEEKLY INFORMATION REPORT i
Week Ending March 12, 1982
]
5 R. E. Ginna Rochester Gas and Electric has removed the burst tube and the two tubes in front of it for metallurgical examination; they have also removed three other tube sections around the burst tube. RG&E plans to complete refueling
+
operations before performing further repairs to the "B" S/G.
l Seabrook On March 3,1982 the Appeal Board issued its " Decision on Remand" on the two seismic issues remanded by the Commission in the construction phase of l
l the Seabrook proceedings. The Appeal Board adopted the Staff position that the current seismic design is acceptable; that Dr. Chinnery's methodology has not been shown to be a credible means of predicting the intensity of l
seismic motion at a particular site; and the Staff's methodology for cor-relating vibratory ground motion was consistent with Appendix A to 10 CFR l
100.
CRBR i
A number of mee'.ings have been held with the applicant to discuss the follow-l ing topics: seismic and dynamic qualification of electrical and mechanical i
equipment, structural design, loose-parts-monitoring program, and applicant's analysis of accidents in Chapter 15 of the PSAR.
1 Spent Fuel Storage
)
NMSS Fuel Cycle and Safeguards staff met with Stone and Webster to discuss
.l S&W's design for a pool-type independent spent fuel storage installation to be located on the site of a reactor. The design was discussed in the context of the requirements of 10 CFR 72, " Licensing Requirements for the Storage of Spent Fuel in an ISFSI," and 10 CFR 73, " Physical Protection of Plants and Materials."
i i
f
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l 1
l 0FFICE OF ADMINISTRATION l
Week Ending March 12, 1982 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of l
Request Initial Decision l
l Received 164 6
Granted 107 0
Denied 12 4
Pendino 45 2
ACTIONS THIS WEEK Received Stephen A. Rondel, Requests information on the circuitry on Fyrenetics Advance Products and Travel Comander's applications submitted to (82-120) the NRC.
Katherine Hatton, Requests, on behalf of The Philadelphia Daily News, Kohn, Savett, Marion six categories of documents regarding the Hayward i
& Graf, P.C.
Tyler Pump Company of Burlington, Vermont.
(82-121) l l
Ellyn R. Weiss, Requests five categories of documents relating to a Union of Concerned report entitled " Recommendations of TMI-2 IE Scientists Investigation Team (Operational Aspects)" dated (82-122)
September 1979 (Martin Report).
Mark Wert, Requests all documents pertaining to a March 1,1982 Gannett Rochester meeting between the NRC and representatives of Newspapers Rochester Gas and Electric Corporation regarding l
(E2-123) the current status of steam generator inspections at the Ginna Nuclear Power Plant.
Mark Wert, Requests all documents pertaining to a March 2,1982 Gannett Rochester meeting between the NRC and representatives of the Newspapers Westinghouse Electric Corporation regarding (82-120)
Westinghouse's views with respect to steam generator tube degradation.
i CONTACT:
J. M. Felton l
492-7211 ENCLOSURE A l
l 1 l
l O
l 2
O Received, Cont'd Malcolm H. Philips, Jr.,
Requests specific information regarding test laboratory Debevoise & Liberman accreditation.
(82-125)
James R. Frankenberry Requests information on the siting of nuclear reactors (82-126) around federal prisons,. schools and hospitals.
Doulgas E. Lee, Ph.D.
Requests a copy of the transcripts of two closed i
(82-127) budget meetings held in 1981; a copy of the lawsuit that was filed in the U.S. District Federal Court pertaining to the above budget meetings, and a copy l
of the lawsuit which was handled in the U.S. Court of Appeals, District of Columbia pertaining to this matter as well as the Order and Decision of the i
three judges.
j Roger L. Boyer Requests copies of NUREG-0642, NUREG-0040, NUREG-51367 (82-128) and any other reports dealing with recomendations 1
for the present nuclear power plant licensing process i
and the evaluation of fault trees by the computer l
procram MOCUS.
(NRC employee)
Requests information on the costs of publishing and (82-129) distributing the NRC publication entitled "NRC Federal Women's Program News, Winter 1982."
Linda Weiss, Requests a list of awarded NRC contracts since Weiss & Associates October 1, 1980.
(82-130) i Rick Krainin, Requests copies of NUREG/CR-0743, SAND 79-0369, New York Public Interest NUREG/CR-0811, NUREG-0194, NUREG/CR-0742, PNL-2588, Research Group, Inc.
and the National Transportation Safety Board's (82-131)
Safety Effectiveness Evaluation 6 (NTSB SEE-81-2).
Lindsay Audin Requests a copy of SECY-81-498, " Routing Policy for (82-132)
Spent Fuel Shipments."
(NRC employee)
Requests three categories of information regarding (82-133)
Vacancy Announcement 82-0890.
Joseph Halapatz, Requests copies of all NRC position vacancy NTEU Steward announcements posted prior to July 14, 1981.
(82-134)
ENCLOSURE A I
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O l
Received, Cont'd J
Joseoh Halapatz, Requests a list of all applicant respondents to l
NTEU Steward Vacancy Announcements 82-1129 and R-82-ll29.
(82-135) 1 Requests four categories of information relating to j
William Fenton, telecommunication services obtained by the General l
Walter Hinchman Services Administration under provisions of the local l
Associates, Inc.
l (82-136) service tariffs of the C&P Telephone Companies.
Granted Lucian Kirby Paul, Jr.
In response to a request for a copy of the non-I (82-82) proprietary version of the technical proposal under Contract NRC-10-82-356, " Operation and Maintenance i
of the NRC Document Control System (DCS)", made available copies of the technical proposal and a revised technical proposal.
Nina Bell, In response to a request for information on all Coalition for nuclear projects which have been " mothballed" or Safe Power terminated and four categories of documents regarding (82-91) the Trojan Nuclear Power Plant, made available 38 documents.
David A. Simmes, In response to a request for a copy of Contract Raytheon Service NRC-10-82-356 with any amendments and a copy of the l
Company winning proposal with any amendments, made available (82-99) a copy of the non-proprietary versions of the technical proposal and a revised technical proposal.
Informed the requester the contract is already available at the PDR.
Nina Bell, In response to a request for documents regarding Coalition for Washington Public Power Supply System, Units 4 and Safe Power 5, made available five documents.
(82-104)
John W. Sullivan.
In response to a request for a microfiche copy of (82-108)
WASH 1520, made available the requested microfiche, l
1 Theresa Souza, In response to a request for a copy of Contract Frost & Sullivan, Inc.
NRC-10-82-356 with all modifications and a list of (82-115) respondees to the request for proposal, made available the list of respondees to RFP RS-ADM-82-356.
Informed the requester the contract has already been made available at the PDR.
ENCLOSURE A
4 i
Denied Ronald W. Drach, In response to a request, on behalf of a named Disabled American individual, for information pertaining to Vacancy Veterans Announcement 81-3586, made available two documents.
(81-507)
Denied portions of three documents, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
1 E
i ENCLOSURE A it
l i
I l
I I
o I
DIVISION OF TECHNICAL INFORMATION AND 1
DOCUMENT CONTROL
- Translations Completed for the Period Ending February 1982 Copies of these translations will be available in the Library on J
These translations Microfiche for internal NRC staff use only.
the foreien are derivative works created from foreign documents by J
author and are still the property of the foreign author or spon-sor1ng government.
i GERMAN Translation 951 PROPRIETARY PHDR REPORT 3.143/79.
Data Compilation 43DR-Containment Prepara-M.
Schall.
tion of Input Data for Containment Pre-Calculations.
GRS Karlsruhe, Germany.
January 1981.
200 pages.
Requested by:
Tim Lee, RES.
Cost: 5900.
l Translation 964A l
GRS-A-532.
Determination of Characteristic Quantities of Opera-tional Reliability In Biblis B Nuclear Power Plant.
P.
Hoemke, H.
l W.
Krause, C. Verstgen, J. Hammel, H.
Loeffler.
Company of i'
Reec*cor Safety (GRS) mbH.
Cologne, Germany.
December 1980.
5 pages.
Requested by: F.
Rowsome, RES.
Translation 964P GRS-20.
Safe Operation of Nuclear Power Plants.
E. Lindauer and j
P.
Kafka.
Company of Reactor Safety (GRS) mbH.
Cologne, Germany.
l October 1980.
17 pages.
Requested by: F.
Rowsome, RES.
Translation 964C Reliability and Operational Experience.
E.
Lindauer.
Company of Reactor Safety (GF.S ) mbH.
Cologne, Germany.
December 1980.
24 pages.
Reques:ed by: F.
Rowsome, RES.
Total cost for 964A, 964B, and 964C: 5440.
Translation 965 PROPRIETARY GRS-A-588. Streusi - A Conouter Program to Determine the Disper-sion of Reliability Characteristics on the Basis of the Disper-sions of Input Data: Theoretical Fundamentals and Program Description.
Reactor Safety Company (GRS), Inc.
April 1981. 87 l
pages.
Requestes by: F. Rowsome, RES.
Cost: S1000.
Translation 995 Nuclear Technology in China.
K.
Becker.
DIN.
Berlin, Germany.
1981.
11 pages.
Requested by: J. Lafleur, OIP.
Cost: $118 Inis complete entry is celetea tram tne run copy.
j i
Enclosure A f
i l
~,. -
Translations (Continued)
?
GERMAN (continued)
Translation 1006 GRS-A-501, #73843.
Post-Calculation of the Tube Plastification Test R60 Using the Icepel Computer Program.
Dr.
B.
Baltes.
l GmbH.
Cologne, Germany.
September 1980.
43 pages.
Requested by:
A.
Summercur, RES.
Cost: S120.
i Translation 1009 PROPRIETARY GKN am 21.9. 1977 Subcooling Transient During The Accident At The
]
GKN (Neckar Community Nuclear Power Plant) on September 21, 1977.
j Bonn, Germany.
September 1977.
5 pages.
Requested bv:
J.
Lafleur, OIP.
Cost: S85.
Translation 1012 i
Reliability In Non-Destructive Evaluation.
R. Trumpfheller, Rhineland-Westfalian Technical Supervisory Association. Essen, Germany.
Undated.
11 pages.
Requested by: M.
Gaske, ACES.
Cost: S160.
Translation 1016 DIN 25435, Part 1.
Nuclear Facilities; Inservice Inspections; Remote Controlled Ultrasonic Inspection.
DIN.
Berlin, West Germany.
August 1979.
31 pages.
Requested by:
J. Muscara, RES.
Cost: S237.
Translation 1017 DIN 25 435, Part 2. Nuclear Facilities; Inservice Inspections; Magnetic Particle Method.
DIN.
Berlin, West Germany.
August 1979. 19 pages.
Requested by:
J.
Muscara, RES.
Cost: S262.
FRENCH Translation 969 Report #53.
Appendix 1 - Electric Power Supply.
EDF.
Ministry of Industry.
Paris, Franch.
1977.
20 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S200.
Translation 972 E-SE/FO 77-43.
PWR 1300-Behavior Of The Reactor In Case Of Total Loss Of Power Supplies (External and Internal)- Case Where The Reactor Is Initially At Power On In Hot Shutdown.
J. Montfort, EDF.
Ministry of Industry. Paris, France.
December 19, 1977.
20 pages.
Requested by:
J. Lafleur, OIP.
Cost: 5200.
Translation 973 E-SE/FO 78-26.
PWR 1300 - Behavior of the Unit in Case of Total Loss of Power Supply (External and Internal) - Case Where the Unit Is Initially In States of Intermediate or Cold Shutdown.
J.
Montfort, EDF.
Ministry of Industry. Paris, France.
May 3, 1978.
7 pages.
Requested by:
J.
Lafleur, OIP.
Cost: 575.
Enclosure A f
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1 Translations (Continued) 3 FRENCH (Continued)
Translation 974 E-SE/FO 78-29.
Guigonis 900 and 1300 MW PWR Units Main Results of Studies and Tests Concerning Removal of Residual Power From Reactor By Natural Circulation and Thermosiphon.
EDF.
Ministry of Industry.
Paris, France.
May 3, 1978.
7 pages.
Requested by:
J.
Lafleur, OIP.
Cost: 575.
Translation 975 FO 78-28 RO/SI.
Appendix X-900 NW and 1300 MW PWR Nuclear Power Plants Estimate of the Probability of Total Failure of the Power Supply of the 6.6 kV Safety Auxiliaries.
R. Orecchia and A.
Pages, EDF.
Ministry of Industry.
Paris, France.
May 3, 1978.
19 pages.
Requested by: J. Lafleur, OIP.
Cost: S180.
Translation 978 EdFE - SE/SN 78-26.
Basic Hypotheses For Evaluating Air Blast Waves Generated By Explosions Of Hazardous Products.
T.
- Gobert, EDF.
Ministry of Industry.
Paris, France.
November 2, 1976.
12 pages.
Requested by:
J.
Lafleur, OIP.
Cost: 5200.
Translation 980 EdF HP/219/79/79/.
Risks Due To Human Activity In The Vicinity Of A Nuclear Power Plant III - Railroad Traffic.
A.
Lannoy EDF.
Ministry of Industry.
Paris, France.
November 1979.
20 pages.
Requested by:
J.
Lafleur, OIP.
Cost S160.
l Translation 981 HP/219/79/47.
Risks Posed By Aviation With Respect To Nuclear Power Plants.
Evaluation of the Virtual Surfaces of Certain l
Buildings.
J.
- Dorey, EDF.
Ministry of Industry.
Paris, France.
June 1979.
24 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S75.
Translation 982 HP/219/79/18.
The Detonability of Methane.
A.
Lannoy, EDF.
l Ministry of Industry.
Paris, France.
Harda 1979.
11 pages.
Requ sted by:
J.
Lafleur, OIP.
Cost: S65.
l Translation 983 l
HP/219/80/46.
Realistic Hole Size in A Highway Unit Transporting A Liquefied Gas.
A.
Lannoy,
EDF.
Ministry of Industry.
- Paris, France.
July 1980.
11 pages.
Requested by: J. Lafleur, OIP.
Cost: $100.
Translation 985 HP/219/79/83.
Accidental Explosions of Empty Tanks.
A. Lannoy, EDF.
Ministry of Industry.
Paris France.
December 1979.
9 pages.
Requested by:
J. Lafleur, OIP.
Cost: S80.
Enclosure A I
Translations (continued) 4 FRENCH (Continued)
Translation 987 Dossier D3.
Basic Safety Options:
Failure of Ultimate Heat Sink.
EDF.
Ministry of Industry.
Paris, France.
June 1978.
24 pages.
Requested by:
J. Lafleur, OIP.
Cost: S242.
Translation 988 V-2, Dosser D3.
Loss of Ultimate Heat Sink.
EDF.
Ministry of Industry.
Paris, France.
July 1978.
19 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S194.
Translation 989 V-3, Dossier D4.
Loss of Electric Supply.
EDF.
Ministry of Industry.
Paris, France.
1978.
17 pages.
Requested by:
i J.
Lafleur, OIP.
Cost: $142.
Translation 990 Dossier D4.
Failure of Electrical Supply 1300 MWe Units.
EDF.
Ministry of Industry.
Paris, France.
April 1978.
14 pages.
Requested by:
J.
Lafleur, OIP.
Cost: $148.
Translation 991 FO 75-35 Unit Type PWR 900 (CP1) Functional Analysis of Systems Participating In Safety.
J.
J.
Joly, EDF.
Ministry of Industry.
Paris, France.
June 1976.
25 pages.
Requested by: J.
- Lafleur, OIP.
Cost: S256.
Translation 992
'FO-78-27A.
Electrical Feed of the Nuclear Center Auxiliaries
~
Estimation of the Reliability Data of External Feeds.
J.P.
Baboulin, EDF.
Ministry of industry.
Paris, France.
Mav 1978.
8 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S78.
Translation 993 199327 P/219/77/36.
Study of the Reliability of the System for i
the Production of Direct Current 125V (lines A and B) of 1
Fessenheim.
B.
Magnon, EDF.
Ministry of Industry.
- Paris, France.
August 1977 31 pages.
Requested by:
J. Lafleur, OIP.
Cost: S236.
Translation 996 Analysis Of The Incident Of 16 September 1981 On The Center Of Tricastin-Unit 1 Drop In The Level Of The Spent Fuels Pool By Loss of Compressed Air.
Ministry of Industry.
Paris, Franec.
1981.
14 pages.
Requested by:
J.
Lafleur, OIP.
Cost: 5212.
Translation 1000 78H314384 Probabilistic Analysis of Safety Systems In Nuclear Centers.
M.
Llory and B.
Gachot, EDF.
Ministry of Industry.
Paris, France.
February 27, 1978.
63 pages.
Requested by:
J.
Lafleur, OIP.
Cost:$450.
Enclosure A I
4 i
Translations (Continued) 5 r
FRENCH (Continued)
Translation 1001 HT-13/17/78.
Utilization of Reliability Analysis.
R.
Portal and A. Villemeur, EDF.
Ministry of Industry.
Paris, France.
March 14, 1978.
22 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S149.
Translation 1002 PROPRIETARY HT-13/45/80.
Application of Analysis of Failure Modes and Their Effects to Nuclear Power Plant Systems.
J.
F.
Barbet, M. Llory, A.
Villemeur, EDF.
Ministry of Industry. Paris, France.
June 26, 1980.
23 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S402.50.
Translation 1003 PROPRIETARY EdF HT-13/43/8.
Methods of Analyzing the Reliability of Safety Systems of Nuclear Power Plants.
M.
Llory and A.
Villemeur, EDF.
Ministry of Industry.
Paris, France.
June 24, 1980.
14 pages.
Requested by:
J.
Lafleur, OIP.
Cost: S326.
Translation 1004 PROPRIETARY 79H323760 HT-13/30/79.
Apache-Code for Automa t a Generation of Failures in Hydraulic and Thermohydraulic Circuits.
J.
F.
- Barbet, E. Vielleville, EDF.
Ministry of Industry.
Paris, France.
August 20, 1979.
22 pages.
Requested by:
J. Lafleur, OIP.
Cost: S377.50.
Unavailable in microfiche. Available from requesting office.
Translation 1005 U
SA/GCA/BC DB/EP n 81/2676.
Agreement for Participation in Research and Technical Exchange Between U.S.
NRC and C.E.A.
in the LOFT Research Program Since September 12, 1980.
D.
Belley, Frend)
Atomic Energy Commission.
Fontenoy-Aux-Roses, France.
December 2,
1981.
Requested by:
J.
Lafleur, OIP.
Cost: In-House Translation.
One page letter.
Translation 1010A ISSN 0029 3997.
Reprocessing of Irradiated Fuel. M. Megy, CEA.
Paris, France.
October 1981.
D pages.
Requested by:
J.
Lafleur, OIP.
Cost: 5200.
Translation 1010B Standardization of Protective Equipment for Nuclear Installations.
CEA.
Paris, France.
Undated.
8 pages.
Requested by:
J. Lafleur, OIP.
Cost: 570.
Translation 1013 PROPRIETARY l
l TA/DE 79/670.
Incident Report.
Reactor: Advanced Prototype l
Nuclear Boiler (CAP), Center: Cadarache, Date: 6/4/79, Time: 1500 l
hrs.
Technicatome.
Ministry of Industry.
Paris, France.
l September 17, 1979.
22 pages.
Requested by:
J.
Lafleur,,OIP.,
Cost: S55.
Unavailable in ::icrofiche. Available only from requesting office.
Fmelosure A f
Translations (Continued) 6 FRENCH (Continued)
Translation 1028 No. 23.
Bulletin on the Safety of Nuclear. Installations.
Ministry of Industry.
Paris, France.
September-October, 1981.
28 pages.
Requested by:
J.
Lafleur, OIP.
Cost: $400.
Translation 1034 SIN no. 400/82.
Draft NUREG on Operating Qualifications.
A.
Messiah, Office of Industrial Safety and Security.
Ministry of Industry. Paris, France.
January 26, 1982.
10 pages.
Requested by:
J. Lafleur, OIP.
Cost: In-House Translation.
?
Translation 1042 PROPRIETARY Notice on the Incident at Gravelines Unit 1 Nuclear Power Plant.
Ministry of Industry.
Paris, France.
February 5, 1982.
3 pages.
l Requested by:
J.
Lafleur, OIP.
Cost: In-House Translation, i
Unavailable in microfiche. Available only from requesting office.
i I
JAPANESE i
Translation 952 l
Performance Evaluation Guide for ECC Systems.
Nuclear Energy Safety Commission, Nuclear Reactor Safety Commission, Nuclear Reactor Safety Standards Specialists Subcommittee.
July 20, 1981.
'l 55 pages.
Requested by:
M. Gaske, ACRS.
Cost:.S385.
Translation 953 Manual on the Inspection of Plans for an Earthquake Proof Nuclear Power Reactor Facility.
Special Commitee on Nuclear Reactor Safety.
June 1981.
24 pages.
Requested by:
M.
Gaske, ACRS.
Cost: S280.
Translation 954 Objectives for Supply of Petroleum-Substitute Energy.
Cabinet I
Decision.
November 28, 1980.
5 pages.
Requested by:
M. Gaske, ACRS.
Cost: $70.
Translation 955 19120.
In Search of the Ideal Atomic Power.
Tokyo Electric Power.
August 1981.
27 pages.
Requested by:
M. Gaske, ACRS.
Cost: $300.
Translation 1007 Nuclear Safety Commission : Monthly Report for April.
April 1981.
6] pages.
Requested by: J. Lafleur, OIP.
Cost 5770.
Translation 1008 Vol.
4, No.
5.
Nuclear Safety Commission Monthly Report For May.
Nuclear Safety Camdssbn. Tokyo, Japan.
May 6, 1981.
66 pages.
Requested by:
J. Lafleur, OIP.
Cost: $962.
Enclosure A
_ _ ~.
Translations (Cont'd) 7 Translation 1027 Aire Press Release. Cuerseas Electrical Industry Survey Institute.
Washington, D. C.
Septe=ber 24, 1981. 3 pages. Requested by:
C. Michelson, AEOD. Cost: $50.
SPANISH Translation 1011 17-00 Al-C-CSN-108. Report on Situation of Stea:n Generators of Unit One of Almaraz Nuclear Power Plant. Almaraz Nuclear Power Plant.
Madrid, Spain. November 12, 1981. 5 pages. Requested by:
J. Lafleur, OIP. Cost: $70.
Documents Processed By Policy and Publications Management Branch Division of Technical Information and Document Control Number of NUREG reports printed and/or distributed by TIDC in February 1982.
Number Processed Tvoe of Reoort in February
,4g Draft Environmental Statement 2
Final Environmental Statement 1
8 Safety Evaluation Repcrt Environmental Standard Review Plan 0
1 NRCI's Staff Reports (total combined figure) 39 37 Contractor Report 0
Conference Proceeding Brochures
_i TOTAL = 76 A listing of these NUREG reports is contained in " Regulatory and Technical Reports Compilation" (NUREG-0304), issued quarterly and available from TIDC.
1 ENCLOSURE A f
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DIVISION OF CONTRACTS Week Ending March 12, 1982 CONTRACTS AWARDED i
1.
RS-NRR-82-113 Title
" State of Knowledge on Psychological Stress And Its Applicability to Three Mile Island Unit I Restart" Description - The contractor is to conduct a workshop to discuss the state of knowledge on psychological stress and its applicability to Three Mile Island Unit I restart.
Period of Performance - January 14 - March 31,1982 Sponsor - NRR Status - Initial letter contract awarded on January 14,1982 to i
Mitre Corporation in the amount of NTE $15,000.00.
Contract was definitized on a cost-plus-fixed fee basis in the amount of $58,041.00 on March 5,1982.
2.
NRC-10-82-392 Title
" Photographic Reproduction Services" Description - Furnishing all labor, material, and equipment in connection with processing and printing of negative, and production of slides.
Period of Performance - One year from date of award Contractor - Chromacolour Lab, Inc.
117 N. Frederick Avenue Gaithersburg, Md. 20877 Amount - $28,495.15 Sponsor - Office of Administration Status - Awarded Marcn 5,1982 i
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ENCLOSURE A
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OFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING MARCH 12, 1982 R. E. GI t:NR Cn ". arch E,1952, Recnester Gas and Electric Corp: ration (RGLE) cce?leted cuttir.c a 3 inch hele in the side of the "E" Stea-Ger.erator (5/G) at the UpOn completion of the hole, the burst i
R. E. @inna I;uclear Fower Plant.
tube end the two tubes in front of it were removed for metalurgical exami-The licensee had identified two other tubes in the vicin.ity of
~
natien.
the burst tube which they hao planned to remove. Hoviever, further inspection inrouch the hele showed these tubes (R45C54 anc R44C55) had only fragments remai5inc and tneref ore would yield cnly limited-metalurgical. gata...In-
~
crder :c'er ain sufficient netallurgical data the licensee has removed 3 c;ner uce sections (RLAC54',443:54mA43C55% arosc.4he.-burst -tebe Ccmpiete removal Cf.the peripheral tube (E45C47) witti ECI indicatiCns at 24 inches from the U-bend area is.ex;ected to be accceplished today.
RGLE row plans tc comoiste refueling cperations prict to perforbine further j
re: airs to the."5" 5/G.
A meeting with the NRC staff to presect the licensee's 1
fir.aii:ed recovery program is tentatively scheduled for the week cf "aren 22, 1952.
Oconee Nuclear Station, Unit 1 Oconee I shutdown to repair a steam generator tube leak on Saturday, March 6,1982. The leakage rate at the time of shutdown was approximately 0.1 ppm in the B steam generator. Upon placing the unit. in a cold shutdown condition, the steam generator will be inspected and repaired.
In addition, Ine HP1/ Makeup no::le may be examined for cracks.
\\
SEA 5 ROCK On March 3,1982, the Appeal Board issued its " Decision on Remand", ALAB-667, en the two seismic issues remanded by the Commission in the construction permit phase of the Seabrook proceedings. The two reopened seismic issues were:
(1) the validity of *he methodology developed by Dr. Michael Chinnery (intervenor expert witness) for relating earthquake intensity and recurrence time, so as to cuestien the adequacy of the Seabrook seismic design, and (2) whether the Staff's
.ethodolocy for ccrrelating vibratory ground motion is censistent'with Appehdix A
.to 10 C.F.R. P art 100.
After an evicentiary bearing, the Appeal Board adopted the Staff position that l
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the current seismic design for Seabrook is acceptable, and that Dr. Chinnery'~s I
rethodolcgy has not been sho6:n to be a creditable means of predicting the intensity of seismic. motion at a particular site. The Appeal Scard also held that the Staff's methedolocy for correlating vibratory ground motion was c:nsistent with Appencix A to 10 C.F.R. Par 100.
ENCLOSURE B I
, Sum arv of Februarv 17, 1982 CRBR Review Meeting A meeting was held on February 17, 1982 in Bethesda, Maryland to discuss the structural design of the Clinch River Breeder Reactor. The applicants stated that the Category I structures for CRBR include: the reactor containment building; the steam generator building; the reactor service building; the control building; the diesel generator building; the emergency cooling tower; the buried diesel generator fuel oil tanks; and the class 1E underground cable ducts and manholes. The applicants then discussed the current codes, standards and regulations for the Category I This discussion included the seismic design modeling and the structures.
seismic method of analysis.
In addition, the containment vessel buckling criteria were discussed.
s The NRC staff requested a future meeting to discuss the safety functions and requirements of the emergency cooling tower. The NRC staff also finalized their structural review questions which were sent to the applicant on February 26,1982 (CS220 series questions).
Summary of February 25 and 26, 1982 CRBR Review Meeting A meeting was held on February 25 and 26,1982 in Bethesda, Maryland to discuss Chapter 15 of The Clinch River Breeder Reactor PSAR. The applicant presented an overview of the accidents analyzed in Chapter 15 and followed with detailed presentations of Sections 15.1 through 15.4.
Detailed discussions included: fuel and blanket design criteria, plant protection system trip '
function design, reactivity insertion events, undercooling events, the sodium water reaction event and local failure events.
1 Sections 15.5 through 15.7 were not discussed and will be the subject of a future meeting. The applicant will also provide additional information on the sodium water interaction event with assumed single failures in the associated water systems.
l Su arv of February 24. 1982 CRER Review Meetinc A meeting was held on February 24, 1982 in Bethesda, Maryland to discuss the Loose Parts Monitoring Program for the Clinch River Breeder Reactor.
The applicants described CRER design features which preclude or minimize the consecuences of loose parts in the CRBR primary loops. The features include debris barriers in the reactor vessel inlet plenum along with a large plenum volume and low plenum coolant velocities. The applicants also described an ongoing experimental program which is evaluating acoustic microphones, accelerometers, and the use of coolant pipes as-waveguides in order to detect loose parts in the reactor primary loop.
The NRC staff requested a future meeting to discuss loose parts monitoring in otner safety related systems such as the intermediate heat transfer system; the direct heat removal system; and, the steam generator hea removal system.
In addition, the NRC staff recuested a discussion of the experimental procram results and future activities.
ENCLCSURE B i
i
s I
i 4 '
Sumary of January 25, 1982 CRBR Review Meeting A meeting was held on January 25, 1982 in Bethesda, Maryland to discuss the seismic and dynamic qualification of electrical and mechanical equipment for the Clinch River Breeder Reactor. The applicant described the applicable codes, standards and regulatory guides for CRBR equipment qualification.
l The CRBR equipment qualification program and results are documented in PSAR i
Sections 2.5, 3.2, 3.6, 3.7, 3.9, 3.10, 3.11 and 3. A.O.
In addition, three '
l 4
reports also sumarize the program and results. These reports are: (1)
WARD-D-165, " Requirements for Environmental Qualification of Class 1E Equipment;" (2) WARD-D-0037, " Seismic Design Criteria for the Clinch River Breeder Reactor Plant;".and (3) WARD-D-0174, " Active Pump and Valve l
Operability Verification Plan." The applicant also described the filing of equipment data packages for each piece of equipment or system.
l The staff results of this meeting and subsequent review of the PSAR are documented in two sets of review questions which were sent to the applicant's l
on March 9 and 11, 1982.
1 Meeting Notices:
l l
1.
Subject:
Clinch River Breeder Reactor SMBDB Review i
Date/ Time:
March 25, 1982, at 8:30 a.m.
1 Location:
Air Rights Building, Room 5033, Bethesda, Md Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
C. Allen, R. Stark, et. al. (NRC) 2.
Subject:
Review of CRER Reactor Design in PSAR Chapter 4 Date/ Time:
March 23-24, 1982, at 8:30 a.m.
Location:
Air Rights Building, Room 5033. Bethesda, Md Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
T. Wehner, R. Stark, et. al. (NRC)
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ENCLOSURE B I
I
NRC TM1 PROGRAM OFFICE WEEKLY STATUS REPORT March 6,1982 - Ma'rch 13,1982 i
Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
i Available Core Cooling Modes: Decay heat removal systems.
Long term j
cooling "B" (once through steam generator-B).
j RCS Pressure Control Mode: Standby pressure control ('SPC) system.
l Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
l Major Parameters (as of 0500, March 12,1982) (approximate values)
Average Incore Thermocouples: 103*F I
Maximum Incore Thermocouple:
133*F RCS Loop Temperatures:
A 8
94*F 97*F Hot Leg Cold Leg (1) 77*F 80*F (2) 81 *F 85"F j
i RCS Pressure: 95 psig t
Reactor Building: Temperature:
60*F Water level:
Elevation 283.1 ft. (0.4 ft. from floor)-
l Pressure:
-0.2 psig
}
Airborne Radionuclide Concentrations -
2.1 E-7 uti/cc H3 (sample taken 3/8/82)
I 1.5 E-6 uC1/cc Kr85 (sample taken 3/1/82)
Effluent and__ Environmental (Radiolocical) Information l
1.
Liquid effluents from the TM1 site released to the Susquehanna l
River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement I
dated February 27, 1980.
During the period March 5,1982, through March 11,1982, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, contained no detectable radioactivity.
ENCLOSURE B r
l t
1
- -.. J
4 2.
Environmental Protection Acency (EPA) Environmental Data.
The EPA Middletown Office has not received the analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada. When these results become available, they will be included in a subsequent repo rt.
No radiation above normally occurring background levels was detected in any of the samples collected from EPA's air and l
l gamma rate networks during the period from March 3,1982 l
through March 11, 1982.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment arounc tne TM1 site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-1 31 Cs-137 Samol e Period (uCi/cc) (uCi/ct)
H P-310 March 3,1982 - March 10,1982
<6.2 E-14 <6.2 E-14 4
License Radioactive Material and Radwaste Shipments.
On Friday, March 5, 1982, 45 drums containing contaminated laundry from Unit 1 and Unit 2 were shipped to Tri-State Industrial Laundries, Utica, New York.
On Tuesday, March 9,19S2, fourteen liquid samples from Unit 2 (various plant locations) were shipped to the Westinghouse Electric Corp. Laboratory, Waltz Mills Site, Madison, Pennsylvania.
On Thursday, March 9,1982, one package (Unit 2 air sample HPR 221 B) was mailed to Science Applications Inc., Pockville, Maryl and.
On Thursday, March 9,1982, two liquid samples from Unit 1 (precoat A) were shipped to the Westinghouse Electric Corp.
Laboratory, Waltz Mills Site, Madison, Pennsylvania.
Major Activities 1.
Submerced Demineralizer System (SDS).
Processing of batch 22 was completed on Marcn 6,1982 The Datch 22 process parameters are included in.
Processing of batch 23 (bleed tank water) continued throughout the week. After batch 23 is processed, the SDS will be secured for minor maintenance.
Reactor coolant system water processing through the SDS is scheduled to commente in May.
ENCLOSURE B f
i t
2.
EPICOR II.
The EPICOR II system continued to process SDS effluents curing the week.
Perfomance parameters are included in Attachment 1.
3.
Reactor Building Entries _. The gross decontamination experiment has
(
proceecea on senecule curing the past week.
The following surfaces.
l have been flushed with water in various combinations of pressure 305 ft. elevation floors, 347 ft. elevation-floors, polar crane surfaces and the refueling pool.
Approximately ~
j and temperature:
l 6,000 gallons of processed water have been used for the flushes.
The effectiveness of the flushes in removing surface contamination and decreasing ambient radiation levels will be evaluated after the j
post decontamination surveys are completed.
The flushing and data gathering phase of the experiment is scheduled to be completed during four reactor building entries next week.
Groundwater Monitoring program. Based on the most recent test j
i 4.
boring samples, tritium concentrations in the ground water have.
l remained essentially in the same range as reported in previous Weekly Status Reports.Except for tritium, there have been no other radioisotopes detected in the latest water samples.
Control Red Drive Removal Practig. A proposed technique for 5.
inspecting tne interior of tne Unit 2 reactor vessel with a television camera will be practiced on Monday and Tuesday, March 15 and 16,1982, in the Unit 1 reactor building.
The technique was proposed by the l
Technical Assistance and Advisory Group (TAAG) and involves removing a control rod drive lead screw to make an opening in the top of the reactor vessel head for television camera insertion.
It is expected that this technique will permit a visual inspection of the top of several fuel assemblies.
Tne entire procedure will be implemented on the Unit I reactor in conjunction with the Unit 1 examination of primary system components for signs of possible deterioration.
The Unit 1 lead screw removal, visual inspection of the reactor vessel interior, and lead screw replacement is scheduled to be performed over the two day period.-
l Past Meeting On Saturday, March 13, 1982, Lake Barrett addressed the Society of Manufacturing Engineers in Williamsport, PA. The major topics of discussion were nuclear power, the accident at TMI, TMI cleanup, waste management, risks of alternate energy production and public confidence in nuclear energy.
Future Meetings On Wednesday, April 14, 1982, Lake Barrett will be the' keynote speaker for the Southern Pennsylvania Association Occupational Health Nurses, to be held at the Holiday Inn in York.
ENCLOSURE B f
i ATTACHMENT 1 i
SDS Performance for Batch Number 22 i
Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml) t 5
Cesium 137 1.2 x 102 5.4 x 10-4 2.3 x 10 Strontium 90 4.7 5.7 x 10-3 8.3 x 102 EPICOR II Performance March 2,1982 to March 8,1982 Average Average Average Radionuclide In fl uent Ef fluent DF (uc/mi )
(uc/ml)
Cesium 137 4.8 x 10 4 1.8 x 10-7 2.7 x 103 Strontium 90 5.4 x 10-3
<1.3 x 10- 5
>4.2 x 102 Antimony 125 5.0 x 10-3
<2.8 x 10-7
>1.8 x 104 l
l l
ENCLOSURE B i
i I
OFFICE OF NUCLEAR 11ATER/AL SAFETY AMD SAFEGUARDS l
Items of Interest Week Endina March 12, 1982 Letters to Catecory I Licensees Letters were sent to Category I licensees reminding them that interim Physical Protection Upgrade Rule measures must be provided if construction, modifcation and installation cannot be completed within 180 days after plan approval.
CRBR Fuel Cycle Environmental Review i
A list of persons who might be involved in CRBR fuel cycle testimony has been j
j The designated individuals will be responsible for updating NRC's prepared.
i responses to the 1976-77 intervenor interrogatories in their respective areas.
Spent Fuel Storace i
On March 3,1982 NMSS Fuel Cycle and Safeguards Divisions' staff members met S&W's l
with Stone and Webster Engineering Corporation (S&W) representatives.
)
design for a pool type independent spent fuel storage installation (ISFSI) l to be located on the site of a reactor was discussed in the context of the requirements of 10 CFR Part 72, " Licensing Requirements for the Storage of l
Spent Fuel in an Independent Spent Fuel Storage Installation," and 10 CFR Part 73, " Physical Protection of Plants and Materials." Some discussion of-
{
dry storage cask design requirements followed, also in the context of an at-reactor site ISFSI.
l Combustion Encineerina. Inc. (CE)
On March 3,1982, members of HMSS met with representatives of Combustion Engineering to discuss the unresolved items related to the Combustion Engi-l neering, Inc. (Windsor) SNM-1067 license renewal application.
l Although most of the items were resolved, there are several unresolved issues relating to nuclear criticality and radiation safety. CE responses to the nuclear criticality safety comments require analytical work to justify some of the criteria they propose in their license.
It is hoped that all out-standing issues can be resolved within six weeks.
l ENCLOSURE C i
l e.
l
~
Feetinds - Division of Fuel Cycle and Material Safety To discuss amendment applicatinn for fibs.
1.
Subject:
Date/ Time:
March 18 - 1:30 Gaithersburg, MD Location:
W. T. Crow (FC)
A. L. Soong (FC), Representatives Attendees:
from fibs To attend symposium on ground, vater transport 2.
Subject:
modeling for near-surface disposal of nuclear wastes and on-site visit of licensed facilities at University of Seattle, WA.
Date/ Time:
March 22-26 Location:
Seattle, WA E. Y. Shum (FC)
Attendees:
Pre-licensing site visit (Kasecki Berylco, Inc.)
3.
Subject:
March 24-26 Date/ Time:
Reading, Boyertown and Revere, PA Location:
A. L. Scong (FC)
Attendees:
Meetines
~' fision of Safeguards I!W.M Technical Workshop on Physical Protection.
1.
Subject:
Date/ Time: March 15-19, 1982 Location:
Osage Beach. Missouri Attendees:
R. F. Burnett - Invited Speaker L. Quinn - Workshop coordinator To review proposed changes to security plan at request of licensee 2.
Subject:
Trojan Date:
March 15-17, 1982 Location:
Prescott, Oregon Attendees:
D. Kunze Licensee Personnel Region V Personnel Confirmatory s'te vitis to Susquehanna re 73.55 plan 3.
Subject:
Date:
March 24-25, 1382 Location Pennsylvania Attendees:
C. Gaskin Licensee Personnel j
Region I personnel ENCLOSURE C f
l Meetings - Division of Waste Management i
1.
Subject:
Plateau Resources Limited Shootering Canyon Uranium Mill Date/ Time:
March 12,1982; 9:30 a.m.
Location:
Willste Building, 4th Floor Conference Room.
Attendees:
U. K. Gupta, F. Gerdamen, PRL D. Martin, T. Fleming, K. Hamill, WMUR/NRC Discussion on proposed mill and mining facilities 2.
Subject:
in the State of Virginia - Marline Corporation Date/ Time:
March 16,'1982 Willste Building, Mr. Scarano's office Location:
Attendees:
Mr. Glasspiegel of Marline Mr. R. Scarano, WMUR/NRC i
i 3.
Subject:
Discussion on CFR Part 60
)
Date/ Time:
March 15-17,1982 Locaticn:
Albuquerque, NM (Sandia' Labs)
Attendees:
M. Bell, M. Knapp, WMHL/NRC Sandia Personnel 4.
Subject:
NRC sponsored symposium on Unsaturated Flow. and.
l
~
Transport Date/ Time:
March 23-24,1982 Locaticn:
Seattle, Washington Attendees:
D. L. Siefken, R. J. Starmer, WMLL/NRC l
Meeting with representatives of Pacific Northwest Labs 5.
Subject:
and visit to US Ecology low-level waste disposal site Date/ Time:
March 25, 1982 Location:
Seattle, Washington Attendees:
D. L. Siefken, R. J. Starmer, WMLL/NRC l
Meeting with IDNS, ISGS, IAG, US.GS on Sheffield 6.
Subject:
tritium migration in Urbana, Illinois Date/ Time:
March 26,1982 Location:
Urbana, Illinois Attendees:
D. L. Siefken, WMLL/NRC 1
l ENCLOSURE C 1
0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest i
March 8,1982 - March 12,1982 i
i 1.
There were no Significant Enforcement Actions imposed during the past i
week.
{
2.
The following Preliminary Notifications were dispatched during the week:
a.
PNO-II-82-24c, Duke Power Company (Oconee Unit 2) - Makeup Line Thermal Cracking.
l b.
PNO-II-82-26, Nuclear Fuel Services, Inc. (Erwin) - Reported i
Inventory Difference.
c.
PNO-II-82-27, Duke Power Company (0conee Unit 1) - Outage Greater Than Two Days.
d.
PNO-II-82-28, Duke Power Company (Oconee Unit 3) - Emergency Drill Exercise.
e.
PNO-IV-82-08, Public Service Company of Colorado (Fort St. Vrain) -
Contamination of Two Plant Workers.
f.
PNG-IV-82-09, Arkansas Power and Light Company (Arkansas Nuclear One, Unit 2) - Reactor Trip With Safety Injaction System Activation.
3.
IE Information Notices No. 82 Potential Deficiency of Certain AGASTAT E-7000 Series Time Delay Relays and No. 82 Increasing Frequency of i
Drug-Related Incidents were issued on March 10,1982-to all power reactor facilities holding an operating license or construction permit.
4.
Other Items:
a.
Division of Emeraency Preparedness Chief. EPLB, participated in a TRIGA User's Conference on March 9, 1982 and presented a paper on overview of the emergency preparedness upgrade for research and test reactors.
The Headquarters Operations Center participated with Region II and Oconee Nuclear Station Unit 3 in an emergency exercise. The initiating event for the exercise concerned a reactor trip and tube leak in the steam generator. The Headquarters response was limited to activa-tion of the Reactor Safety Analysis and Protective Measures Teams.
The exercise included transmission via the Duke Power Company l
transmittal system of plant parameters for the first time.
ENCLOSURE D i
i I
2 b.
Division of Fuel Facilities, Materials and Safeouards The staff survey of utility drug and alcohol awareness programs is continuing. To date, the subject has been discussed with eight utilities - discussions with four more utilities are planned. Although varying in detail, each utility has invested significant resources in their screening programs for detection of alcohol and drug abuse.
c.
Division of Reactor Procrams The Director and staff met with officials of IEEE on March 9,1982 l
to discuss the laboratory accreditation program.
d.
Enforcement Staff The NRC enforcement policy was published in the Federal Register on March 9,1982.
l l
1 l
i l
l i
ENCLO5URE D I
t OFFICE OF NUCLEAR REGULATORY RESEARCH t
IMPORTANT EVENTS FOR THE WEEK ENDING MARCH 12, 1982 l
i Analytical Models Branch l
1.
Pressurized Thermal Shock Analysis Meetino A Pressurized Thermal Shock Analysis Coordination Meeting was held in Silver Spring on March 3,1982 with representatives of NRC, ORNL, LANL, INEL, and BNL. The status and schedules of coordinated activities for calculation of the B&W plant were discussed.
ORNL will supply scenarios in March to be calculated by LANL (TRAC-PWR) and INEL (RELAP-5). SAI will supply recommendations for secondary-side modelling by April.
LANL and INEL are developing and refining input decks for PTS calculations to be performed in June / July (LANL) and August / September (INEL). The source of all numbers in the input decks wiii be documented so the Q/A function (BNL) can be performed efficiently. For selected times in selected transients (those expected to exhibit multi-D flow in the downcomer) LANL (50LA-3D) will supply local downcomer fluid tem-l Presentation peratures for the fracture mechanics calculations to be performed by ORNL.
l l
of status and plans for these calculations to the Advanced Code Review Group (ACRG) will be held April 21-22, 1982.
2.
Calculations Beino Performed at LANL for NRR NRR request of October 27, 1981 for re-calculation of Semiscale test S-07-6: this study is proceeding and is scheduled to be completed by April 15, 1982.
Status of repcrts on completed calculations: Preliminary results on all of these calculations have already been transmitted to NRR.
The CE pumps on/off study has not started yet. Calculations could start in April 1982 if this study is still of interest to NRR.
I Status cf Five Calculation Studies requested on October 23, 1981:
The Aoki data is still being analyzed by LANL and 11. appears that the pressure dropIn caused by accumulator injection is more caused by momentum than by condensation.The fact, it appears that as condensation increases, the pressure drop decreases.
analysis of the Aoki data will be completed, and the results scaled to full-size by the calculations, by July 1982.
2 Midland SE LOCA Analyses: The SB (0.075 ft ) run is finished and the LB run is proceeding. Difficulties of calculating the accumulator injection into the downtoe.er will delay the completion of this study until April 1982.
Pressurizer Emptying: LANL sent a draft letter (2/26/82) to NRC/RES that attributes the increase in slope of system pressure, once the pressurizer empties, to a change in system-average enthalpy and density after the pressurizer stops supplying hot fluid to the system. RES is reviewing this with LANL to see if additional data and analyses can support this hypothesis, which is based primarily on calculations and data from test S-07-6.
i Break Isolation in B&W Plants: LANL sent a draft letter (2/26/82) to NRC/RES that mported on a calculation for a 1.75 in, diameter CL break that was run out to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> until the pressurizer emptied and the candy-canes voided. The break was then isolated and the system refilled with HPIS in about 1500 seconds. Natural circulation started at this point and was fully established by 2500 seconds after the break was isolated. A final letter reported on the details of this calculation will be received ENCLOSURE E t
j' l
l I l I
i sol ate d.
A final letter reported on the details of this calculation will be received by RES in April 1982.
SBLOCA Recovery in E&W Plants: Very interesting results are being.obtained and RES suggested that the calculations be stopped and the results documented. A base case i
l was run until the pressurizer emptied and the candy-canes voided, effectively termi-Four actions were then independently investigatec:
nating natural circulation.
(a) Start secondary cooling. (b) Start secondary cooling + " bump" primary pumps, (c)
Start secondary cooling + open candy-cane high-point vent-valves, and (d) Start secondary cooling + spray into candy-cane None of the four actions were effective in re-starting natural circulation, for the one base case sesncric investigated. However, the core was effectively cooled by a flow path, internal to the vessel, from core to upper plenum, through vent-valve to downtomer and up through the core again. This phenomena may be a function of the break-sin and scenario assumed, because LANL feels that if the vessel void fraction were lower, natural circulation might have been re-established.
i Experimental Procrans Branch 1.
Data Bank Four PSF / Irradiation Effects Tests (PBF/IE-1,2,3, and E) were added to the data bank.
These tests evaluate the influence of simulated fission products, cladding irradiation damage and fuel rod internal pressure on pellet-clad interaction during a power ramp and on fuel rod behavior during film boiling operation.
Four PBF Power Coolant Mismatch (PCM) Tests were also added to the bank: PCP-2,3,4 and B.
Finally, a combination of PCM (25 tests) and Reactivity Initiated Accident (RIA) Tests l
(3 tests) were entered and are identified under Fuel Behaviors Tests as PR31.
2.
FLECHT SEASET A PMG meeting, review of the technical and financial status of the FLECHT SEASET was held at Monroeville, Pennsylvania on February 25-26, 1982. A Status Report on the Shakedown Tests, Test Matrix, Mass / Energy Program and the proposed analytical model of natural circulation for the SET / Natural Circulation was presented by Westinghouse.
In addition,153 Blocked Bundle Status was discussed and Westinghouse proposed some changes to the workscope in order to incorporate blockage analysis method using COBRA-TF which Westinghouse will utilize the expertise at PNL. A PMG agreement was not reached on the accounting procedure to be used at the conclusion of the whole program. EPRI, NRC and Westinghouse will resolve this in the near future.
i 3
LOFT Plant refill and cold testing will begin this week. The new test PORY for the ATWS test will be installed later in the week or perhaps next week, after which the plant will be hydro tested. All documents from this are expected to be completed in another week for the L9-3 ATWS test. A group from RES will visit INEL March 24-25, 1982 to review preparations and mechanical components design for the ATHS test. The test is currently scheduled for April 7,1982.
l 4
Thermal Mixine Procram A joint EPRI/NRC/CREARE Program to evaluate the degree of thermal fluid mixing in the downtorer and cold leg regions is currently being considered. The dtta resulting from this program would be useful to determining the effects of pressurized thermal stock on a reactor vessel.
rm narer r
! Safecuerds Branch l
1.
" Physical Protection of Plants and Materials: Reportino I
of Physical Security Events" A minor rule change amending 10 CFR 73.71 was signed by the EDO on January 20, 1982 The amendments being made include: updating and is being published as a final rule.
the notification procedure for reporting of unusual physical security events; revising Appendix A of Part 73 to include the commercial telephone number needed to contact the NRC Operations Center, Regional FTS numbers, and a change of address for Region V; and correcting a footnote to a table contained in 10 CFR 73.71(c).
I
?
l Ef; CLOSURE E l
t
~
I I
ITEMS OF INTEREST i
OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MARCH 12, 1982 r
l Foreien Visits to NRC On Monday Mr. Pietro Milella, Head of the Materials Branch of the Italian National Commission for Nuclear Energy (CNEN), met with W. Hazelton and i
C. Y. Cheng of the NRR Materials Engineering Branch to discuss several i
aspects of ISCC on piping and safe ends sensitized by welding in BWRs.
l On Tuesday fir. Milella met with C. Z. Serpan, Chief, and M. Vagins, J. Muscara and J. Strosnider
- of the RES Materials Engineering Branch to discuss possible cooperative efforts between NRC and the CNEN in the research fields of elastic plastic fracture mechanics and crack arrest.
On Thursday fir. Hans Peter Ryder, Head of Danish nuclear emergency plan-l ning, and Mr. Johannes Jensen of the Danish Environmental Protection j
began a one-week program to participate in the tiRC observation Agency of the emergency preparedness exercise at the Oconee nuclear facility.
l Messrs. Ryder and Jensen are among several foreign regulatory personnel with immediate responsibility for emergency preparedness activities in who are being selectively scheduled to participate.
their own countries as a part of the NRC observation team in emergency preparedness exercises l
at U.S. facilities.
On Thursday a five-member Japanese team met with W. Mills, R. Baker and M. Cool of the RES Health Effects Branch to discuss ICRP recommendations.
l l
On Thursday Dr. Hans Gruemm, IAEA Deputy Director General for Safeguards, met j
~
i with Commissioners' staff and representatives from International Programs, the Safeguards Division of Nuclear Material Safety and Safeguards, the i
Office of the General Counsel and the Executive Legal Director to discuss l
the current IAEA safeguards system.
f On Friday Mr. Kuroi Chief of the Fast Reactor Physics Laboratory of the l
Japan Atomic Energy Research Laboratory, met with SG Director Robert 1
l Burnett to discuss programs for the safe transport of nuclear fuel.
i
)
On Friday the new Economic Minister of the Korean Embassy in Washington.
j Mr. Chong Sang Park, accompanied by First Secretary Dong Chul Chang and Science Attache Shiyohl Park of the Korean Embassy, made a courtesy call on Chairman Palladino.
J. D. Lafleur. IP Deputy Director, also attended the meeting.
l On Friday Chairman Palladino, Executive Director Dircks and IP Deputy Director Lafleur met with Mr. Glyn England, Chairman of the U.K. Central Electricity Generating Board, to discuss safety issues likely to impact on the U.K. PWR inquiry.
Dr. John Gaunt, Atomic Energy Attache at the British Embassy, also attended the meeting.
i ENCLOSURE G
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- Foreien Reports The following foreign reports were r!ceived in IP March 8-12:
(For further information contact Eva Szent-Ivany, IP, X277BS.)
From France:
CSN - Suiletin of Incidents - Third Quarter 1981 (Sent for translation)
From the FRG:
GRS-5 Transport of Radioactive Materials in Nuclear Fuel Cycle From S. Korea:
KEC - Electric Power in Korea (1981)**
Fror,the U.K.:
PROPRIETARY NII - Eesearch and Support Programme - January 1982**
Deleted from PDR Copy
- Indicates the reports are in English ENCLOSURE G f
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MARCH 12. 1982 e
NRC representatives attended the meeting of the negotiators of the Rocky Mountain Low-level Waste Compact in Reno on Monday, March 8.
Cclorado expects the Compact to be adopted by its legislature this year; it is not expected to be adopted in New Mexico, Arizona, Nevada or Wyoming until next year.
1 The revisions agreed to at this meeting are expected to be submitted to NRC in two weeks.
The NRC has completed comments on the January 11, 1982 working draft " Midwest Interstate Compact on Low-Level Radioactive Waste." This compact has 16 l
eligible party States. In a letter dated March 12, 1982 to Professor Taylor, of Michigan Governor Milliken's office, we discuss four major areas of concern:
l (1) the scope of the compact goes beyond disposal to all aspects of wa:te l
management; (2) the restriction on the export of waste; (3) State inspecticn and enforcement of NRC licensees; and (4) the settlement of disputes. The compact group will be meeting in July to negotiate additional changes in the compact.
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ENCLOSURE H f
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OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING - MARCH 12, 1982
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l Br iefing Papers (1) For Commissioner Ahearne, produced information on plants in operation, under construction, and cancelled. Paper also included estimates on numbers of operating licenses and con-struction permits expected and projections of generating capacity; (2) for Commissioner Gilinsky, prepared a back-grounder for his visit to Arizona and the Palo Verde site.
Publication Distributed " Unresolved Safety Issues" (Aqua Book), NUREG-0606, Vol. 4, No. 1, dated 2/19/82.
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1 0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING MARCH 12, 1982 i
i Meetino with INPO A semi-annual progress meeting was held at INPO on March 9, 1982 between AE00 (Michelson and Heltemes) and INP0 (Wilkinson, Zebroski, Rosen, and others). This meeting covered: the status of the revised Memorandum of Agreement; the anticipated trial use program for the Sequence 1
Coding System; the INPO program for achieving enhanced reporting of I
human error; cooperative activities on foreign data; and the establishment of sessions on individual technical subjects.
The revised Memorandum of Agreement (MOA) was reviewed in detail. Final word changes will be coordinated within the next week and the overall agreement and Appendix 1 dealing with operational data activities should be ready for signature. All NRC offices have agreed to the revised overall MOA.
INPO has agreed to participate in the trial use of the Sequence Coding System.
It is planned to hold a workshop now scheduled for this summer, possibly at INP0, in order to provide the details and documentation related to the system's use.
AEOD and INP0 have agreed to a number of informal technical exchanges on specific subjects and events of mutual interest. The first meeting will be scheduled in the near future.
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ENCLOSURE K
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1' 0FFICE OF SMALL AND DISADVANTAGED BUSINESS UTILIZATION / CIVIL RIGHTS Items of Interest Week Endino March 12, 1982 l
On March 10, 19S2 the Federal Women's Program presented a workshop in P-il8 from 9:00 AM to 12:00 Noon at which 75 NRC women employees participated. This sensitivity training involved stress reduction, self-esteem and critical issues facing women today acd in the future and was conducted by Judith Mueller and Ruth Dehart of the Northern Virginia Center for Women, both of whom are conseling p.ychologists, s
l A National Women's History Week display was set up in the Lobby of the Phillips Building in recognition of this special week including a video tape on the history of women and women in non-traditional jobs.
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ENCLOSURE L I
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l REG 10f! III ITEMS OF INTEREST WEEK ENDING !! ARCH 12, 1982 The Regional State Liaison Officer served as the Team Leader of eight federal observers at the Wisconsin State E0C in Madison during the Point Beach Radiological Energency Response exercise on March 9,1982. During the exercise he met with the Conmissioners of the Wisconsin Public Service Commission in Madison to discuss NRC emergency preparedness regulations, the Point Beach exercise, need for power considerations, and the Wisconsin mer:torium on nuclear plant construction.
Planned Meetinas
Subject:
Commonwealth Edison Company Program for Drug Abuse Control Date:
fla rch 18, 1982 Location:
Region III Office Attendees:
J. G. Keppler and Staff Peter Bensinger, licensee consultant
Subject:
Regionali:ation of fiaterials Licensing & Safeguards Date:
March 19,1982 Location:
Headquarters Attendees:
A. B. Davis, G. W. Roy (Region III)
D. B. Mausshardt (fl MSS)
Subject:
Systematic Appraisal of Licensee Performance - Fermi 2 Date:
March 16,1982 Location:
Detroit, MI Attendees:
A. E. Davis and Region III Staff Detroit Edisen Company (licensee)
Subject:
Licensee Proaran for Improved Regulatory Performance (D.C. Cook){FollowuptopreviousEnforcementConferences)
Date:
March 16,1982 Location:
flew York, N.Y.
Attendees:
J. G. Keppler and Region III Staff American Electric Power Service Corp. (licensee) l l
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N REGION V ITEl15 0F INTEREST WEEK ENDING I4 ARCH 12.1982 Portland General Electric Co.
Trojan - DN 50-344 The latest analytical results of primary coolant activity indicate the dose i
ecuivelent iodine concentration is 82 to 86 percent of the Technical Specification (TS) limit and the gross specific activity 45 to 50 percent of U,c TS linit. Steam generator leakace continues at less than five gallons per day.
A least-scuares fit of the dose ecuivalent iodine data extrapolates to the TS lini: about May 1 - which corresponds to the scheduled date for shut down for refueling.
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ENCLOSURE fi i
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 12, 1982 STAFF 9EOUIREMENTS - DISCUSSION AND POSSIBLE V0TE ON STAFF A.
DIABLOICANYON PROGRAM PLAN AND INDEPENDENCE OF AUDIT, 10:00 A.M., THURSDAY MARCH 4, 1952, COMMISSIONERS' CONFERENCE ROOM, DC OFFICE (OPEN TO PUBLIC XTilhDANCE), Memo Secy to Dircks, 3/8/82 The Co=ission was brief ed on staff 's conclusions and recommenda resulting frem their review of the adequacy of the proposed seismic verification program and the qualifications and (Staf f recommendations independence of the proposed contractors.
are contained in SECY-S2-89).
The Commission:
by a vote of 4-1, with Cc=missioner Ahearne in the minority, disapproved a motion by Commissioner a.
Ahearne (1) to reject the proposal of pG&E to retain Cloud Associates as the independent auditor to perform the proposed seismic design verification program; and (2) to accept a prorosal frcm PG&E, if submitted, to retain Teledyne Engineering Services in that capacity; with Commissioner Roberts abstaining by a vote of 4-0, b.
approved Commissioner Sradford's motion directing the staff (1) to make a concerted effort for one week to obtain an agreement among the parties (FG&E, State of California, Joint intervencrs) for a proposed independent auditor or a list of auditors frcm which NRC would make a selection; (2) if this is not accomplished within the time period prescribed, the staff should proceed as otherwise directed; unanimously approved the following additions to, c.
the recommendations contained in SECY-82-59:
"The contractor's role should include the following items, to be defined in the program plan and implementing procedures:
l (7)
Scope and technical approach should be enlarged to include analysis of NSS vendors design; I
censideration of statistics in the sanpling plan; and, inclusion of a sample of structural elements (see staff Conclusions chart presented at the Commission meeting).
ENCLOSURE O
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ITEMS APPROVED BY THE COM'41SSION - WEEK ENDING MARCH 12, 1982 A.
STAFF REQUIREMENTS (cont'd) by a vote of 4-1, with Commissicner Roberts dissenting d.
approved the recommendations of the staff as contained in SECY-E2-89 as amended by b and c above (one week effort to obtain agreement among the parties on an auditor or a list of auditors; modifications to the program plan).
~he Commission instructed the staff that:
if the efforts to agree on a jointly approved contractor were successful, the staff could proceed with that selection; if the parties agreed on a short list, the staff could pick a ecmpany (such as Teledyne);
if efforts above were unsuccessful, the staff should proceed with the recommenfations contained in SECY-82-89 as revised and voted upon by the Cec. mis sion.
(NRR) (SECY SUSPESE:
3/12/82) 8.
STAFF REOUIREMENTS - AFFIRMATION SESSION 82-7, 4:00 P.M., THURSDAY, MARCH 4, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PU5LIC ATTENDANCE),
Memo Chilk to Dircks and Kammerer, 3/9/82 l
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SECY-82 Re'cuest for Directed Certification of ASLB Order in Diablo Canyon Proceedinc l
1 The Comission, by a vote of 4-1, approved a proposed order dismissing Governor Brown's petition for certification of an ASLB order in the Diablo Canyon proceeding. Chairman Palladino and Comissioners Gilinsky, Ahearne and Roberts approved the order; Comissioner Bradford disapproved the order.
(OGC)
(Subsequently, the order was signed by the Secretary on March' 5,1982.)
i II. SECY-81-672 - Proposed Rule Chance on Technical Specifications 2
The Comission, by a vote of 5-0, approved a proposed rule revising present technical specifications into two categories and revising the present procedures for amending the technical specifications.
(Footnotes follow at end of this entry on page 4)
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f ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 12, 1982 B.
STAFF REQUIREMENTS (cont'd)
{
The Comission:
a.
approved publication in the Federal Register of the proposed rule, as l
circulated in a modified version on March 3,1982, for 60-day public comment; (NRR)
(SECY Suspense: 3/23/82)
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b.
requested that appropriate Congressional comittees be advised (Enclosure 2 of the staff paper); and (OCA/NRR)
(SECYSuspense: 3/23/82)
.i c.
requested that copit.s of the proposed rule be sent to licensees and
{
other interested persons after publication.
(NRR)
(SECY Suspense: 4/2/82) l r
Comissioner Ahearne requested that during the coment period, staff should
{
prepare a report which would
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1.
take a typical " tech spec" and show how it would be separated (and added to) under the proposed rule; and l
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describe NRC experience with the use of the current 50.59 procedure.
1 III. SECY-82-8/8A - Final Rule for Eliminatina Need for Power and Alternative Enercy Sources as issues in OL Proceedings l
The Comission, by a vote of 4-13 (Comissioner Bradford disapp' roving),
approved for publication in the Federal Register a final rule, as circulated March 4,1932, amending 10 CFR Part 51 to provide that, for NEPA purposes, need for power and alternative energy sources will not be considered in OL proceedings for nuclear power plants and need not be addressed in environ-mental reports at the OL stage, in the absence of a showing of special circumstance.
(SP)
(SECYSuspense: 3/23/82)
The Comission:
a.
requested that appropriate Congressional comittees be notified (Enclosure D of the staff paper); and (SP/0CA)
(SECYSuspense: 3/23/82) b.
requested that the notice be distributed to affected licensees, OL applicants, public interest groups and other interested persons.
(SP) (SECYSuspense: 4/2/82)
(Footnotes follow at end of this entry on page 4) l ENCLOSURE O
_4 ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 12, 1982 B.
STAFF REOUIREMENTS (cont'd)
ISection 201 of the Energy Reorganization Act, 42 U.S.C. 55841, provides that action of the Commission shall be determined by a " majority vote of the members present." Comissioner Roberts was not present when this item was affirmed, but had previously indicated his approval of the order. Had Comissioner Roberts been present, he would have affirmed his prior vote. Accordingly, the formal vote of the Comission was 3-1 in favor of the decision.
2 ection 201 of the Energy Reorganization Act 42 U.S.C. 55841, provides that S
action of the Comission shall be determined by a " majority vote of the members present." Comissioner Roberts was not present when this item was affirmed, but had previously indicated his approval of the item. Had Comissioner Roberts been present, he would have affirmed his prior vote. Accordingly, the formal vote of the Comission was 4-0 in favor of the decision.
Section 201 of the Energy Reorganization Act 42 U.S.C. 55841, provides that action of the Comission shall be determined by a " majority vote of the members present." Commissioner Roberts was not present when this item was affirmed, but had previously indicated his approval of the item. Had Comissioner Roberts been present, he would have affirmed his prior vote. Accordingly, the formal vote of the Comission was 3-1 in favor of the decision.
C.
STAFF REQUIREMENTS - BRIEFING AND POSSIBLE VOTE ON DRAFT FINAL RULE REQUIRING DOCUMENTATION OF DEVIATIONS FROM THE REVISED STANDARD REVIEH PLAN, 9:10 A.M.,
KEDNESDAY, MARCH 10, 1982, COMMISSIONERS' CONFERENCE ROO", DC OFFICE (OPEN TO PUBLIC ATTENDANCE), Meno Secv to Dircks. 3/11/82 The Cornission continued discussion of a rule to recuire acclicants to evaluate differences from the Standard Review (S RP).
The Co=ission unanimously approved the attached P'1'an final rule for publication f or a 60 day coment period.in the Federal Recister.
(
) (SECY SUSPENSE:
3/26/82)
Attachment:
Not Included D.
SECY-82 PROPOSED RETRANSFER FOR REPROCESSING (SPAIN TO THE U.K.'), memo Se:v to Dircks, 3/11/82 This is to advise you that the Cornission (with Chairman Palladino and Cormissioners Ahearne and Roberts agreeing) has approved the proposed response to the Department of Energy (DOE), subject to the modifications contained in the attached final draft.
Cermissioner Bradford indicated that he preferred the letter proposed by the staff in SECY-81-677.
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ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 12 1982 1
D.
SECY-82-69 (cont'd)
Commissioner Gilinsky disapproved, indicating that the Comission should make reference to its finding on the ineffectiveness of international safeguarding of plutonium.
The office of International Programs was informed of this action on March 11, 1982.
It is requested that you forward a copy of the letter to DOE to the Office of the Secretary when signed.
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Attachment:
Not Included s
E.
SECY-82 PROPOSED RETRANSFERS FOR REPROCESSING (JAPAN TO THE U.K. AND FRANCE), Memo Secy to Dircks, 3/11/82 This is to advise you that the Commission (with Chairman Palladino and Commissioners Ahearne and Roberts agreeing) has approved the proposed response to the Department of i
Energy (DOE), subject to the modifications contained in the attached final draft.
Cc=missioner Bradford indicated that he preferred the letter proposed by the staff in SECY-81-677.
Cc=missioner Gilinsky disapproved, indicating that the 1
Conmission should make reference to its finding on the ineffectiveness of international safeguarding of plutonium.
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Cc=missioner Ahearne asked that the staff provide the current status of their addressal of transient shipments of spent fuel (reference SECY-80-533).
The Office of International Programs was informed of this action on March 11, 1982.
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It is requested that you forward a copy of the letter to DOE to the Office of the Secretary whe,n signed.
Attachment:
Not Included l
ENCLOSURE O i
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