ML20058N357
| ML20058N357 | |
| Person / Time | |
|---|---|
| Issue date: | 12/02/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20058M131 | List:
|
| References | |
| FOIA-92-436 SECY-80-528, WIR-801128, NUDOCS 9310140197 | |
| Download: ML20058N357 (23) | |
Text
{{#Wiki_filter:- - _. k. w UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 December 2, 1980 . INFORMATION REPORT S For: The Comissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 28, 1980 A sumary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report. Contents Enclosure Administration Nuclear Reactor Regulation B Stant'ards Development C Eclear Material Safety and Safeguards 0 Inspection and Enforcement E Nuclear Regulatory Research F* Executive Legal Director G International Programs H State Programs Management and Program Analysis J Controller K" Analysis and Evaluation of Operational Data L Small and Disadvantaged Business Utilization M* Items Approved by the Comission N Calendar of Speaking Engagements O Connissioners Commission Staff Offices Exec Dir for Operations ACRS Secretariat c= 2 'y i. A. Re m., m istant for Operatio Office of the Executive Director _ g hO for Operations 'No input this week. 7 930218 gO1 GILINSK92-436 PDR
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s' O.AN & ~ 5 5M )b d J% ~ Summary of Weekly Information Report Week Ending November 28, 1980 I LER Secuence Coding and Search Procedure The status and features of the LER Sequence Coding and Search Procedure (SCS), under development by AEOD and the Nuclear Safety Infomation Center, were presented at an industry-wide workshop in Oak Ridge. TN. When fully operational, the SCS procedure is expected to be a more versatile and effective tool than that presently available to search and evaluate historical and current reactor operating data. Annual Occupational Dose Limit EPA has reconsidered its orevious decision to propose an annual occupational dose limit range of 0.5 to 12 rems /yr in its new guidance to Federal agencies. EPA guidance will propose a limit of 5 rems /yr, and, in addition, the preamble to the Federal Register notice will reouest infomation on the impact of establishing a limit at 0.5, 1.0, or 3.0 rems /yr. Proposed guidance may be published before the end of the year; joint EPA / OSHA /NRC hearing could be held in the spring of 1981. Lacrosse Boiling Water Reactor The full LACBWR core (72 fuel assemblies) has been offloaded into the newly installed double-tier spent fuel pool racks. The 14 oldest fuel assemblies (the remainder of the Allis Chalmers-manufactured fuel) were wet sipped. No leakers were found -- a sharp contrast to previous fuel examinations which revealed significant fuel damage. When the core is reloaded during this outage, all but two of the fuel assemblies will be Exxan; the remaining two will be from the Allis Chalmers Core 1. LACBWR is expected to return to power production around December 23, 1980. Reoort of Incidents Involving Padioactive Materials As a result of a 6-month trial arrangement between DOE and NRC (NMSS/FC and AEOD). DOE will furnish to NRC a monthly report of serious incidents involving handling of radioactive materials and a quarterly report of the less serious incidents. Details of any specific incident may be obtained from DOE. IE Enforcement Actior. acainst Niagara Mohawk IE issued a Notice of Violation and an Notice of Proposed Imposition of Civil Penalties ($225,000) to the Niagara Mohawk Power Corp. (Nine Mile Point, Unit 1). NRC also issued a license modification removing the former Nine Mile Point Site Superintendent from involvement in nuclear activities, and, to the coproration, an Order to Show Cause why the Executive Vice President should not be removed from involvement in nuclear activities as well. Tripartite Research Agreement EURATOM, the Power and Nuclear Fuel-Development Corporation of Japan, and NRC began a tripartite research agreement to test the limits of coolability of UO2 fuel debris beds in sodium at the Annular Core Research Reactor at Sandia Lab. Coast Guard Infomation Recuest NMSS met with Cdr. Adess, US Coast Guard, to clarify Coast Guard information needs regarding a study involving m3vement of radioactive materials through ports under the responsibility of the Coast Guard. NRC will provide a series of reports from the NMSS system. GAO Reviews Regarding Nuclear Non-Proliferation Act NMSS and IP staffs met with GAO representative to comment on GAO draft report, " International Nuclear Safeguards Need Further Improvement." Target date for completion of NNPA report has been moved from March to January 1981.
OFFICE OF ADMINISTRATION Week Ending November 28, 1980 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REOUESTS Initial Appeal of Recuest Initial Decision Received 658 38 Granted 51 0 14 Denied 100 18 Pending 48 6 ACTIONS THIS WEEK Received (Individuals requesting Requests information on their Senior Reactor Operator infomation about themselves) License exam results. (80-570 & 80-571) Burt Hubbard, Requests all documents pertaining to the storage of The Albuquerque Tribune nuclear, radioactive or any other hazardous waste (80-572) in the State of New Mexico. (NRC employee) Requests a copy of two documents pertaining t'o (80-573) hers elf. Marilyn Shineflug, Requests four categories of documents relating to Illinois Safe Energy cracks in the containment of at least one of the Zion Alliance reactors. (80-574) McNeill Watkins, II, -Requests nine categories of documents relating to the Debevoise & Liberman final rule on " Fire Protection Program for Operating (80-575) Nuclear Power Plants, Appendix R." W. T. Crawford, Requests information on uranium shipments for the General Electric period FY 1976 through FY 1980. (80-576) John R. Stover, Requests a copy of the technical proposal under contrac Franklin Research Center, RFP RS-ADM-BD-381 entitled " Conference Program for the (80-577) Nuclear Regulatory Commission's Atomic Safety and Licensing Board Panel Members." CONTACT: J. M. Felton 492-7211 ENCLOSURE A I
2 Received, Cont'd Robert R. Holt, Requests all documents relating to the report of the New York University " Task Force on Interim Operation of Indian Point," (80-578) submitted to the Commissioners in June,1980, and any subsequent documents. (Individuals requesting Requests information on their Senior Reactor Operator inforration about themselves) License exam results. (80-579, 80-580, 80-581) Linda Weiss, Requests a list of NRC contractors. Paul /Howard Associates (80-582) James R. Kahn, Requests, on behalf of his client, three categories Blank, Rome, Comisky of information relating to the use of cobalt for & McCauley X-ray purposes at the Sun Ship Dry Dock and (80-583) Shipbuilding Company in Chester, Pennsylvania between 1946 and 1958. Granted David G. Swartzlander, In response to a request for information on routes The Sun-Bulletin and quantities of 14 shipments of spent fuel passing (80-373) through the Binghamton, New 2%rk area from an experimental reactor at the i.ialk River Nuclear Laboratories in Ontario, Canada to Savannah River, South Carolina, made available two documents. William Reynolds. In response to a request for information on specific American Friends routes and number of shipments which have taken place Service Committee and are scheduled to take place for shipments of (80-369) spent nuclear fuel, made available two documents. Jay E. Silberg, In response to a request for nine categories of Shaw, Pittman, Potts records relating to fees in connection with withdrawn, & Trowbridge suspended, or postponed applications, made available (80-536) 54 documents. Informed the requester additional records subject to this request are already available at the PDR. Lilias Jones, In response to a request for a copy of NUREG/CR-1056, Black Hills Alliance NUREG/CR-0628, NUREG/CR-0758 and NUREG/CR-ll55, made (80-538) available these documents. Lucille Sadwith, In response to a request for a list of all reports, Center for Farm & Food studies, etc. within the last five years on Research, Inc. radionuclides in milk, leafy vegetables, root (80-541) vegetables, grains and meat, made available a list of pertinent documents. ENCLOSURE A ~ f
~ 3 Granted, Cont'd Charles P. Mooney, In response to a request for copies of abstracts of Engineering Design NRC computer programs which are available to the Concepts, Inc. public, informed the requester the NRC does not (80-547) maintain any fully documented records which would be subject to his request. Robert Goldsmith, In response to a request for copies of four categories Citizens for a of documents pertaining to the decontamination of Better Environment Dresden Unit 1, made available 22 documents. Informed (80-550) the requester additional documents subject to the request are already available at the PDR. Theresa M. Watson, In response to a request for copies of all the comment! FOI Services, Inc. on the final rule, " Deletion of Source Material (80-552) Medicinals from the General License of Small Quantities of Source Material," made available eight documents. Alletta d'A. Belin, In response to a request for all documents relating to Center for Law in the organization Armadillo Coalition of Texas or any the Public Interest of its affiliate organizations, made available 13 (80-553) documents. Whitney S. Minkler. In response to a request for information pertaining to MSTC, Inc. contract NRC-10-80-708, informed the requester the (80-559) requested information is already available at the PDR. (Individuals requesting Made available copies of their Senior Reactor Operator information about themselves) License exam results. (80-570 & 80-571) Denied Robert L. P1emmons In response to a request for information on spent fuel (80-439) routes through and around Asheville, North Carolina, made available one document. Denied portions of six documents containing safeguards infonnation. ENCU)SURE A f
DIVISION OF CONTRACTS Week Ending November 28, 1980 IFB'S ISSUED IFB RS-ADM-81-370 Title - Preventive Maintenance for Micrographic Equipment Description - Monthly preventive and remedial maintenance services for NRC-owned micrographic equipment. Period of Performance - One year Sponsor - Office of Administration Status - IFB issued on November 28, 1980 j l i 1 l l l i ENCLOSURE A f
DIVISION OF SECURITY WEEK ENDING NOVEMBER 21, 1980 NRC Appendix 2101, Part XVI - Proprietary Information NRC Appendix 2101 Part XVI, " Proprietary Information," has been forwarded to the Office of Management and Program Analysis for coordination with the Execu-tive Director for Operations and publication. Concurrence of the Offices of the Executive Legal Director and Nuclear Material Safety and Safeguards was obtained prior to transmission. Pertinent connents received from other Head-quarters offices and divisions were incorporated. Information Security Oversicht Office (1500) Conference On November 19, and 20,1980, representatives of the Division of Security. Division of Technical Information and Document Control. Division of Rules and Records, as well as of the Office of the Executive Legal Director and Office of the General Counsel, attended a symposium conducted by 1500. Among the topics covered by the guest speakers were: "The Balancing Test," " Historian's Perspective," "On the First Amendment," " Intelligence Community Perspectives," and " Defense Contractor's Perspective." ENCLOSURE A I .~.
OFFICE OF NUCLEAR REACTOR REGULATION l r WEEKLY ITEMS OF INTEREST (Week Ending November 28,1980) Lacrosse Boiling Water Reactor The full LACBWR core (72 fuel assemblies) has been offloaded into the newly installed double tier spent fuel pool racks. The spent fuel rack storage capacity was increased by the recent completion of this modifi-The old spent fuel storage racks have already been. removed cation. from the site. The 14 oldest fuel assemblies, the remainder of the Allis Chalmers manufactured fuel, have been wet sipped. No lenkers have been found. This is in sharp contrast to previous fuel examinations where signiff-cant fuel damage has been observed. the core is reloaded during the current outage, all except two of When the fuel assemblies will be Exxon assemblies. The remaining two will be from the Allis Chalmers Core 1; not Core 2 that has been plagued with fuel failures during the exposure period in LACBWR. It is expected that LACBWR will return to power production about December 23, 1980. 9 ENCLOSURE B
OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING NOVEMBER 28, 1980 1. At its request, the ACRS Class 9 Accidents Subcommittee was briefed by G. A. Arlotto on the charter and progress of the Degraded Cooling Steering Group. The purpose of the Group and Group membership were discussed; rulemaking to be coordinated was outlined; and the Group's charter was discussed in detail. A preferred sequence of rulemaking was contrasted with the rulemaking sequence actually underway; progress ] to date was reviewed in terms of both the immediate technical issues being discussed by the Group,'such as hydrogen combustion control and fission product chemistry, and procedural issues being discussed, such as the lead vs. follow relationship of licensing and rulemaking decisions. A rough schedule leading to identification of key elements for a degraded cooling proposed rule was reviewed and the ACRS' advice was solicited concerning bases for proposed rules and tireliness of necessary supporting activity, such as research. The meeting lasted approximately one hour. 2. For the week ending November 21, 1980, it was reported that EPA management had decided that EPA's new guidance to Federal agencies would not propose an annual occupational dose limit of 5 rems, as originally) planned, but would propose instead a range of values (0.5 to 12 rems /yr for comment. NRC staff members have since been advised by EPA staff members that this decision has been reconsidered. According to Dresent plans, 5 rems per year will be proposed in the guidance, and, in addition, the preamble to the Federal Register notice will request information on the impact of establishing a limit at 0.5,1.0 or 3.0 rems per year. It now appears that the proposed guidance may be published before the end of the year and that the joint EPA / OSHA /NP.C hearing could be held in the spring of 1 981. l 3. COMMISSION BRIEFING ON RADIATION HEALTH EFFECTS AND RESEARCH On November 21, 1980 Drs. Marvin Goldman, University of California, Davis; K. 2. Morgan, Georgia Institute of Technology; Harold Rossi, Columbia University; Henry Kohn, Shields Warren Dadiation Laboratory; and Alice Stewart, University of Birmingham, England, briefed the Commission on the health effects of ionizing radiation and research ther eon. The subject areas covered were the extrapolation of animal data to man, the extrapolation of health e'fects from medium and high dose and dose rate experiments to low dose and dose rate situations, and the relative merits of future research in the area of large scale epidemiologic and animal studies and cel. lular and animal experiments on the mechanisms of radiation action. ENCLOSURE C
i i i 1 1 e The participants held no uniform view on the usefulness of extrapolation of animal data to man. However, there was general consensus that if any tuman studies were to be performed, the best populations would be in the medium dose range. Dr. Stewart concentrated her presentation on her l analysis of the Japanese atomic bomb survivor data, which she maintains l indicates that previous analyses of these data are not representative of i low-level radiation effects. j A transcript of the briefing was made. This briefing was particularly timely because the Commission currently hasunder consideration an NRC/ EPA joint report to the Congress on the i feasibility of conducting human epidemiologic studies of the effects l of low-level ionizing radiation. The staff will be analyzing papers which Dr. Stewart distributed to j l support her presentation on the A-Bomb survivor's and an updated analy-sis by George Neale of the Hanford Worker population. The results of this analysis will be published as a Radiological Health Standards Branch Information Report, copies of which are routinely sent to the Commission. 1 ~ ENCLOSURE C l
l -{ i t publications to be Issued in the Near Future
Title:
Guidance on the License Application to Store Spent Fuel in an i Independent Spent Fuel Storage Installation j Expected Issuance Date: March 1981 j t
== Description:== The proposed regulatory guide is on updating material on the license application to store spent fuel in an ISFSI. l
Contact:
M. W. Jankowski l 443-5910 i 9 t Publication Issued During the Week of November 24-28, 1980 l Reg. Guide 3.45 - Nuclear Criticality Safety for Pipe Intersections i Containing Aqueous Solutions of Enriched Uranyl Nitrate I I i l l l i i l i ENCLOSURE C l
1 ) i l 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS l Items of Interest Week Ending November 28, 1980 ~ Report of Incidents Involving Radioactive Materials Representatives of HMSS/FC and AE00 worted out an arrangemerrt with DOE whereby DOE will furnish NRC with a monthly report of serious incidents involving handling of radioactive naterials and a quarterly report of l the less serious incidents. Detailed information on arty particular incident can be obtained on a case-by-case basis from DOE. This is a trial arrangement for a six month period and will be reevaluated at that time. Coast Guard Information Request A meeting was held on Novenber 25 with Corsnander Adess to clarify the information neads of the Coast Guard regarding a study involving movement of radioactive materials through ports under the responsibility of the Coast Guard. Arrangements were made to provide a series of outputs from the NtHSS system. GAO Reviews Regarding NNpA NMSS and IP staff met on November 19 and 24 with a representative of the GAO ] to provide specific connents on the GAO draft report " International Nuclear Safeguards Need Further Improvement." A discussion on the NRC role in the implefnentation of Title II, " United States Initiatives to Strengthen the International Safeguards System," of the Nuclear Non-Proliferation Act of 1978 was also conducted. The GAO target date for coupletion of the NNPA report has been moved from harch to Janur.ry 1981. I l i ENCLOSURE D -e-
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending November 28, 1980 1. The following Notification of Significant Enforcement Action was dispatched during this week: a. EN-80-52 Niagara Mohawk Power Corporation (Nine Mile Point Unit 1) - On November 26, 1980, a Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $225,000 were issued to the subject licensee. Also issued were an immediately effective license modification removing the fonner Nine Mile Point Site Superintendent from involvement in nuclear activities for the Corporation and an Order to Show Cause why the Executive Vice President should not also be removed from involvement in nuclear activites. These actions were based on material false statements submitted by the licensee under oath on January 22, 1980 in response to the NRC Order of January 2,1980 regarding short-term recommendations from the TMI-2 Lessons Learned Task Force. 2. Preliminary Notifications relating to the following actions were dispatched during the week: a. PNO-I-80-169 Oyster Creek - Unscheduled Plant Shutdown b. PNO-I-80-170 Soils Engineering Services, Inc., Wayne, NJ - Vehicular Accident During Transportation of a Troxler Density Gauge c. PNO-I-80-171 and 171 A U.S. Testing Company, Reading, PA - Theft'of Truck Containing Radiographic Exposure Device d. PNO-II-80-162 Farley Unit 2 - Fuel Loading Delay e. PNO-II-80-163 Sequoyah Unit 1 - Release of Radioactive Gas to Auxiliary Building f. PNO-II-80-164 Sequoyah Unit 1 - Safety Injection During Loss of Site Power Test g. PNO-II-80-165 North Anna Units 3 and 4 - Restart of Construction of Unit 3; Cancellation of Unit 4 h. PNO-II-80-166 Turkey Foint Unit 3 - Steam Generator Tube Leak 1. PNO-IV-80-34B South Texas Project Units 1 and 2 (HP&L) - Update - Resumption of Currently Halted Construction at South Texas Project
- j. PNO-V-78 Nuclear Engineeering Co. (NECO), Richland, Washington Burial Site - Banning of Nuclear Metals, Inc., Concord, Massachusetts (NRC Licensee) for Radioactive Waste Shipments k.
PNO-V-80-79 San Onofre Units 2 and 3 - Fatality at Construction Site 1. PNS-II-80-31 Sequoyah, Daisy, TN - Bomb Threat ENCLOSURE E I
r ~. 2. The following IE Bulletin was issued: a. IE Bulletin 80-24 " Prevention of Damage Due to Water Leakage Inside Containment (October 17, 1980 Indian Point 2 Event)," was issued on November 21, 1980 to licensed power reactors for action and to construction permit holders for information. 4. The following IE Information Notice was issued:
- a. ' IE Information Notice 80-42, "Effect of Radiation on Hydraulic Snubber Fluid," was issued on November 24, 1980 to all power reactor facilities with an operating license or construction permit.
I i e l l ENCLOSURE E j 1 ^
l ITEMS OF INTEREST i 0FFICE OF INTERNATIONAL PROGRAMS l WEEK ENDINFs NOVEMBER 28, 1980 Advisory Mission to Korea Dr. Kyo Kim, Division of Safeguards, Fuel Cycle and Environmental Research, RES, will depart NRC on Friday, November 28, for a one-month advisory mission to the Korean Atomic Energy Research Institute (KAERI) in Seoul, Korea. During his one-month stay in Korea, Dr. Kim will advise KAERI on their waste cisposal program as well as conduct short seminars on nuclear waste management. Initiation of Tricartite Research Agreement On November 14. EURATOM, the Power and Nuclear Fuel Development Corporation of Japan (PNC) and NRC commenced a tripartite research agreement. The Agreement fuel debris provides for a program of testing the limits of coolability of UO2 beds in sodium at the Annular Core Research Reactor at Sandia Laboratory in return for monetary payments from the two foreign parties. Over the four year period of the Acreement, EURATOM will contribute $3,160,000 and PNC will orovide $1,800,000 j to NRC. Foreign Safety Data Discussions On Monday and Tuesday J. D. Lafleur, IP Deputy Director,and M. W. Mallory, IP, met in Oak Ridge, Tennessee with W. B. Cottrell, J. Buchanan, and H. Bertini of the Nuclear Safety Information Center and with C. Michelson, AE00 Director and F. Hebdon, AE00 to discuss the Foreign Operating and Incident Data evaluation project under contract to NSIC. On Tuesday J. D. Lafleur, M. W. Mallory, and C. Michelson, met with Klaus Kottoff l and Otto Duner of the Federal Republic of Germany to discuss Licensee Event Reporting in the U.S. and FRG. Foreign Reports The followino foreign reports were received at IP during the period of November 24 to 28. The ** indicates the reports are in English. For further infomation contact Eva Szent-Ivany (49-27788) IP. i From Denmark: Report on Radioactive Waste from the Working Group Set Up by the Danish National Agency of Environmental Protection ** From Greece: GAEC - Hazards Evaluation Report, Athens 1970** Safety Analysis Report of the Greek Research Reactor 1, September 1980**
- Deleted from PDR copy ENCLOSURE H
'l
1. 1 1 Foreign Reports Cont'd From Italy: CNEN - The Static-Dynamic Verification of an Emergency Sodium-Air Exchanger for the Super-Phenix Reactor From Japan: 1 Annual Program of Safety Research on Nuclear Power Plants and Related Facilities, May 28, 1980** From S. Korea: Monthly Operating Data for October 1980 Ko-Ri Nuclear Power Plant Unit 1** l l l l l l l ENCLOSURE H
- Deleted from PDR copy f
l l OFFICE OF STA"'E PROGRAMS ITEMS OF INTEREST WEEK ENDING NOVEMBER 28, 1980 I The Conference of Radiation Control Program Directors Task Force on Suggested State Regulations, Part C for Licensing of Radioactive l Materials, will meet in Bethesda, Maryland, December 1 and 2, 1980, to revise and update this part. l 1 l l l ENCLOSURE I
l j 1 l I j q i i 0FFICE OF MANAGEE.NT AND PROGRAM ANALYSIS 1 Items of Interest l WEEK ENDING NOVE!SER 28. 1980 l l l t i Infomation for Transition Group J Forwarded information requesteid by Mr. Kennedy for the incoming Administration's Transition Group. He asked for background infor-l mation on a variety of subjects that covered practically every l aspect of NRC's activities, i l l i 1 ) l I i l i ENCLOSURE J l 1 i i
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA i ITEMS OF INTEREST WEEK ENDING NOVEMBER 28, 1980 l An industry-wide workshop was held in Oak Ridge, Tennessee on November 24, 1980 on the status and features of the LER Sequence Coding and Search Procedure (SCS). This procedure is being developed by the Nuclear Safety Information Center and AEOD. The SCS procedure, when-fully developed and verified, is expected to provide a significantly more versatile and effec-tive tool than presently available for the searching and evaluation of historical and current reactor operating data. The workshop was attended by over 100 individuals from approximately 50 organizations. AEOD also provided presentations on the status of other AE00 activities and on the recent AEOD and SD recommendations for revising the reporting of opera-tional events and f ailures. There was considerable interest in and discussion on the subjects presented. 1 ENCLOSURE L
I I ITEMS APPROVED BY THE COMMISSION - WEEK ENDING NOVEMBER 28, 1980 A. STAFF REOUIREMENTS - BRIEFING ON INCLUSION OF STEAM GENERATOR TRANSIENTS AS A l US1, 2:00 P.M., MONDAY, NOVEMBER 10, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks, dtd 11/21/80. 1 I The Commission
- was briefed by Staff on the status of the inclusion of steam generator transients as an unresolved safety issue.
NRR and AEOD agreed that steam generator and reactor overfill transients should be treated as part of the proposed new unresolved safety issue on safety implications of control systems, with priority being. given to the B&W plants. The issue of whether the steamline break with small LOCA (Para. 2.E.2. Action Plan) should be designated as a separate unresolved safety issue or whether the issue should be considered as part of the proposed new unresolved safety issues on Training and Oualifications of Operating Personnel or Operating Procedures, was not resolved. By this memorandum EDO is requested to resolve the differing views of NRR and AEOD. (These issues are contained in SECY-80-325 which is presently before the Comission. ) 1 B. SECY-80-416A - PUBLICATION OF NUREG-0689, " POTENTIAL IMPACT OF LICENSEE DEFAULT DN CLEANUP OF TMI-2" (COMMISSIONER ACTION ITEM). Memo SECY to Dircks, dtd 11/24/80. This is to advise you that the Comission (with all Comissioners approving) has l approved publication and distribution of NUREG-0689, " Potential Impact of Licensee Default on Cleanup of TMI-2", subject to the following condition. I The report should include a disclaimer to the effect that it is a staff report l which has not been reviewed by the Comission. i The Office of Nuclear Reactor Regulation was informed of this action by telephone on November 24, 1980. C. STAFF REOUIREMENTS - COMMISSION MEETING ON IODINE RELEASE FROM ACCIDENTS; AND ESTIMATES FOR CONSEQUENCES OF NUCLEAR ACCIDENTS (SEE SECY-80-504),10:00 A.M., TUESDAY, NOVEMBER 18, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks, dtd 11/25/80. The Comission was briefed on iodine release from accidents and estimates of consecuences of nuclear accidents by the following individuals: W. R. Stratton, Los Alamos Scientific Laboratory; A. P. Malinauskas & D.O. Camobell, Oak Ridge National Laboratory; Frank von Hippel, School of Engineering, Princeton University; C. Starr, Milton Levenson & Ian Wall, Electric Power Research Institute; W. Schikarski, Nuclear Research Center, Karlsruhe, W. Gemany; j H.J.C. Kouts, Bronkhaven National Laboratory; ENCLOSURE N I The Director, Research and NRC Staff members. I
1 o . C. (continued) 1 The Comission requested that the Directors of Nuclear Regulatory Research, Standards Development and Nuclear Reactor Regulation discuss how best to deal wi+h the information presented at the briefing. The Director of Nuclear Regulatory Research advised they would analyze the infomation presented at the briefinp and at other meetings during the week, and report to the Comission on their findings in about a month on what, if anything, ought to be done. (RES/SD/NRR) (SECY Suspense: 12/26/80) D. STAFF REOUIREMENTS - BRIEFING ON ENVIRONMENTAL IMPACT STATEMENT FOR THE SUMMER NUCLEAR PLANTS, 2:00 P.M., MONDAY, NOVEMBER 17, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks, dtd 11/25/80. j l The Comission* was briefed on the draft Environmental Statement supplement 1 on the Sumer nuclear power plant. The Comission requested an infomation report on the 25 letters received comenting on the interim policy statement. (NRR) (SECY Suspense: 12/5/80) l Comissioner Hendrie requested clarification in the final text of the FES on l the assumptions contained in the probability consequence distributions, including changed results due to reasonable protective measures. (NRR) (SECY Suspense: 2/23/81) l Commissioner Bradford requested a review of letters citing increases in leukemia rates around power plants. (NRR) (SECY Suspense: 1/26/81) E. STAFF REOUIREMENTS - BRIEFING BY IE ON CURRENT STATUS OF INDIAN POINT-2 INVESTIGA-TION OF THE CONTAINMENT FLOODING EVENT S AND BASIS FOR ALLOWING RESTART OF INDIAN i P0lNT-3; AND DISCUSSION OF INSTRUCTIONS TO BOARD ON INDIAN POINT PROCEEDING, I 10:00 A.M., FRIDAY, NOVEMBER 14, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE i l (OPEN TO PUBLIC ATTENDANCE) (CONTINUED AT 2:00 P.M.). Memo SECY to Dircks/Bickwit/ Hanrahan, dtd 11/26/80. l The Comission was briefed on the status of the IE investigation of the Indian Point-2 containment flooding. The Comission discussed with staff the proposed Order on Indian Point, contained in SECY-A-80-179A/1793. l The Commission directed that the General Counsel revise the draft Order as l discussec at the neeting, with the inclusion of a paragraph, to be drafted by l OPE, that would serve as an alternative to paracraphs 17 and 18. (It was l retoonized that the language of that paragraoh might affect the wording of other portions of the Order. (OGC/0PE) (SECY Suspense: 11/24/80) l ENCLOSURE N ~ l 1
l i . F. STAFF REOUIREMENTS - DISCUSSION AND VOTE ON SECY-80-486, RESOLUTION OF THE PAT-DOWN SEARCH ISSUE AT POWER REACTORS AND STATUS OF RELATED SAFEGUARDS ACTIVITIES, 10:00 AM, MONDAY, NOVEMBER 17, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Mema SECY to Dircks/Fouchard/Kammerer, dtd 11/26/80. The Commission discussed staff's proposed set of search procedures and related safeguards-for use at nuclear facilities. I Chairnan Ahearne noted that the relationship between future screening-procrams and pat-cown searches was not completely clear. Along this line, he indicated potential problems in the handling of contractor personnel, such as those used during refueling operations. The staff should examine j j comoensatory measures to be used in the absence of a complete screenino process. l l Conmissioner Hendrie expressed a concern that certain longer tern actions i listed in the paper might be counter to reactor safety and suggested that l the staff balance safeguards measures with any potential adverse effects to safety. l The Commission recuested that the lanounce of the proposed rule be changed l to read "has cause to suspect." (N"SS) The Connission by a vote of 3-0* approved the proposed rule (enclosures A and B of the staff paper) as amended. The Commission requested that: 1. the proposed rule as amended be published in the Federal Register; (NMSS) (SECY Suspense: 12/12/80) 2. a public announcement be issued when the amendments are filed with the Office of the Federal Register; (OPA) (SECY Suspense: 12/17/80) 3. the aopropriate Congressional committees be notified. (OCA) (SECY Suspense: 12/17/80) l ENCLOSURE N l
l I P SCilEDULED SPEAKING ENGAGEMENTS i Date Organization location Subject Speaker 12/2/80 Lion's Club Newtown Square PA NRC Activities Since TMI K. Abraham, R0 I 3/26/81 22nd.9nnual Quality Clinic Knoxville, TN What the NRC Regulations W. Ruhlman, RO II Require from a QA Program 3/31/81 American Chemical Society Atlanta, GA Regulatory Implications of H. Peterson, SD Radiation-Dose Effect Relationships 4/1/81 Spouses of Operating Staff Education Center Qualit, assurance Requirements A. Cerne, R0 I at Seabrook Station Seabrook, Nil and Licensing Procedures Related. to Seabrook Station n i 4 0 ENCLOSURE O 4i
U t'l L M r .y~ %. W UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INFORMATION REPORT Sacy-ao-sn cece*er n.1980 cor: ine Cormiissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO Subiect: WEErd.Y INFORMATION REPORT - WEEK ENDING DECEMBER 5,1980 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report. Contents Enclosure Administration A Nuclear Reactor Regulation 3 Stancards Development Nuclear Material Safety and Safeguards D Inspection and Enforcement i Nuclear Regulatory Researen F* Executive Legal Director G International Programs H State Programs I Management and Program Analysis J Controll er ) Analysis and Evaluation of Operational Cata L Small and Disadvantaged Susiness Utilization M* Items Aporoved by the Commission N E I E" "" DISTRIBLITION Commissioners Comission Staff Offices Exec Dir for Operatiens // [ ]OgqolS ACRS Secretariat T. A. Renm, Assistant for Ooerations N-Office of the Executive Director for Operations RO*r -
- No inout this week. / k
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l i ig l Cd k vo-ssw s. Summary of Weekly Information Report g l[ j l Week Ending December 5, 1980 l 1 i i North Anna, Unit 2 i During the weekend, the Unit 2 main generator step up transformer had a fault which caused damage to the bus duct system between the generator bus terminal and the transformer. There were minor fires in the area which were caused i by the hot metal. The reactor tripped and all shutdown systems responded satisfactorily. I Davis-Besse, Unit No. 1 On December 3, 1980, the reactor tripped due to a reactor coolant pump trip. i Following the reactor trip, the main steam isolation valve' closed. The i s operators then manually actuated the Steam and Feed Line Rupture Control System (SFRCS), which then allows steam generator level to be controlled automatically by the auxiliary feedwater system. -Actuation of SFRCS should start both auxiliary feedwater pumps; however, one of the pumps did not start automatically and required separate operator action to start. IE is l reviewing the event. 'I TMI Reactor Building Entry The fifth entry into the Unit 2 reactor building is scheduled for Thursday, December 11, 1980. The planned tasks include replacement of the neutron I source range, amplifier, decontamination experiments and additional radiation-i mapping. i ] Contamination of TMI Building Expansion Joints During a radiological survey of the 281 elevation of the Unit 2 auxiliary building on November 27, 1980, contamination was found in two expansion joints. l The licensee has implemented a plan to determine the source and extent of l the contamination. Wood River Junction Public Meeting On December 2, 1980, at the request of the State of Rhode Island, a public meeting was held in Wood River Junction to inform the public of the progress of the decontamination effort at the United Nuclear facility. Also of concern was 1) the status of the waste shipments to Nevada, which received a consider-able amount of publicity recently when the State of Nevada returned six truck-loads of waste to UNC which had been destined for burial; 2) issues that were discussed in meetings held in July of this year; and 3) recent stories in the press concerning the disposal of liquid wastes from lagoons to the environs by. i UNC. I Licensee Transoortation Activities in Possible Non-Compliance with Part 71 On November 26, 1980, a notice was mailed to approximately 170 NRC radiography licensees stating that all their transportation activities may not be conducted
in accordance with 10 CFR Part 71. The letter noted that they neither were registered with NRC for any shipping packages nor had an NRC approved quality assurance program. Licensees who fail to respond to the letter will be referred to IE for followup action at a later date. O \\ l i t I
l 0FFICE OF ADMINISTRATION Week Ending December 5,1980 l ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT j STATUS OF REQUESTS Initial Appeal of { Request Initial Decision Received 668 38 Granted 520 14 Denied 102 19 Pending 46 5 ACTIONS THIS WEEK Received (An individual requesting Requests a copy of his Official Performance information about himself) Appraisals. (80-584) Linda A. Sanders, Requests all correspondence between the NRC Johnson City Press-Chronicle and the Nuclear Fuel Services Plant in Erwin, i (80-585) Tennessee from June,1980 through September,1980. Charles A. Green, Requests a copy of a staff study on the potential Knight-Ridder Newspapers of presently licensed sites to cause significant (80-586) radiation exposure to surrounding populations l in the event of a severe accident. Anthony F. Earley, Jr., Requests, on behalf of the Utility Group on Hutton & Williams ATWS, 51 categories of documents relating to (80-587) " Proposed Rulemaking to Amend 10 CFR Part 50 i Concerning Anticipated Transients Without Scram (ATWS) Events." i Michele McCarthy Requests information on the Windscale nuclear (80-588) reactor accident in Cumberland, England in i i October,1957. f John Vail, Attorney-At-Law Requests information indicating the whereabouts (80-589) of plutoniJm or other radioactive substances unaccounted for by Nuclear Fuel Services of 3 Erwin, Tennessee. CONTACT: J. M. Felton 492-7211 I ENCLOSURE A I i
l Received, Cont'd Stephan C. Volker, Requests a copy of " Guidelines for Decontamina-Sierra Club Legal Defense tion of Facilities and Equipment Prior to Release Fund, Inc. for Unrestricted Use or Termination of Licenses (80-590) for By-product. Source or Special huclear Material" dated November 1976. l Lilias Jones, Requests a copy of NUREG/CR-ll38, NUREG/CR-l Black Hills Alliance 1273, and " Investigation of Radon-222 Emissions (80-591) from Underground Uranium Mines, Progress Report 1. R. B. Borsum, Requests a copy of " Summary of Meeting Held on Babcock & Wilcox June 5,1978"; referenced in a June 23, 1978 l (80-592) Memorandum for: Faast Rosa from R. Fitzpatrick. l Lilias Jones, Requests a copy of ten listed documents. Black Hills Alliance (80-593) Granted Jeffrey D. Littlejohn, In response to a request for information LAND Minnesota Chapter relating to the transportation and inspection (80-E37) of eight shipments of radioactive waste from the Dairyland Power Cooperative, Lacrosse ) Boiling Water Reactor in Wisconsin, and nine categories of documents regarding cask model NFS-4, made available 10 documents. Al Stern, In response to a request for a list of firms that Al Stern Associates responded to a specific NRC announcement in (80-557) the Commerce Business Daily, made available a copy of this list. Joseph Halapatz, In response to a request, on behalf of an NRC (Representing an NRC employee for a copy of NRC Form 50 regarding that employee) employee, made available two documents. (80-558) Richard Shaikewitz, In response to a request, on behalf of his Wiseman, Shaikewitz, client, for information concerning her deceased McGivern & Wahl husband and information on the incidence of l (30-561) carcinoma in uranium workers, made available one document. ENCLOSURE A I
- Granted, Cont'd McNeill Watkins, II, In response to a request for records of NRC Debevoise & Liberman staff opposition to making the fire protection (80-564) rule applicable to future plants or licenses and records related to such future application of the rule on which NRC staff relied in analyzing the question, made available three documents. Informed the requester additional documents subject to the request are already available at the PDR. I McNeill Watkins, II, In response to a request for six categories of Debevoise & Liberman information relating to fire protection require-(80-566) ments in Appendix R to 10 CFR Part 50 under the Commission's final rule on " Fire Protection i Program for Operating Nuclear Power Plants," I made available one document. (Individuals requesting In response to requests for copies of the information about themselves) transcript of their Senior Reactor Operator (80-579,80-580,80-581) License exam results, made available this information. j Denied Charles W. Elliott In response to a request for documents pertaining (80-544) to five categories of information regarding spent fuel shipments traveling on certain routes in the Comonwealth of Pennsylvania, made available 12 documents. Denied portions of five documents containing safeguards information. (NRC employee) In response to a request for documents pertaining (80-567) to the selection for Vacancy Announcement 80-3428, i made available three documents. Denied portions of two documents, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy. Martin Levy, In response to an appeal, on behalf of an NRC NTEU Steward employee, for a copy of the Personnel Performance (80-A-30-80-492) Appraisals for three named individuals, continue'd i to deny this information, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy. l ENCLOSURE A I
DIVISION OF CONTRACTS Week Ending December 5,1980 RFP'S ISSUED 1. RFP RS-RES-8i-235 Title - Seismic History of the Eastern Seaboard from New York to Norfolk, Va. Description - The work to be accomplished under this contract comprises a comprehensive search of all available records in major repositories throughout the northeastern United Stated for the purpose of discoverino new information on earthquake occurrence and effects. The region to be surveyed extends from New York City to Norfolk, Virginia, and includes the Appalachian tiountains within its western boundary. The historical period to be covered extends from the earliest records available up to 1930. The results of this search is to be published in a catalog, suitable for interfiling with existing catalogs. Period of Performance - One year Sponsor - Office of Nuclear Regulatory Research Status - RFP issued November 26, 1980. Proposals are due January 5,1980. l 2. RFP RS-ADM-81-389 Title - Holding Public Meetings Amid Conflict Description - To develop and conduct a course on planning and conducting meetings where conflict is anticipated in public comment. Period of Performance - Ten weeks Sponsor - Office of Administration Status - Letter RFP issued December 1, 1980 to USDA, Graduate School. Proposal due December 12, 1980 PROPOSALS UNDER EVALUATION RFP RS-NRR-81-138 Title - Technical Assistance in Support of NRC's Reactor Licensing Actions (Program II) Description - The purpose of the proposed contract is to provide support to NRR for the management and review of 300 backlog operating reactor licensing actions. Ultimate decisions regarding the acceptability of the proposed licensing actions will be made by NRR after review of the contractor's evaluation and recommendation. Period of Performance - Two years Sponsor - Office of Nuclear Reactor Regulation Status - Best and Final offers due on December 8,1980. ENCLOSURE A i
2 CONTRACTS CLOSED OUT (All administrative action completed and final payment made) Contract No. Contractor Close-Out Date AT(49-24)-0033 Thorion Industries 12/1/80 AT'49-24)-0287 Price Waterhouse 11/28/80 AT(49-24)-0173 Project Software &,0evelopment 11/28/80 AT(49-24)-0306 Edwards Trucking 12/4/80 AT(49-24)-0257 Sport Chevrolet Co. 11/26/80 NRC-10-79-398 Dictaphone Corp. 11/26/80 l 0 i ENCLOSURE A I l
DIVISION OF TECHNICAL INFORMATION AND DOCU"ENT CONTROL' WEEK ENDING DECEMBER 5,1980 TRANSLATIONS The following translations were received by the Division of Technical Information and Document Control during the month of November 1980. Copies of these transla-tions will be available in the Library. " GERMAN Design of Operations Manuals for Nuclear Power Plants. Technical Control Union l Rhineland (Institute for Accident Research) cologne, F.R. Germany. March 1977. 265 pages. NRC Translation 791. Cost of translation: $2055.00. l Requested by: RES. l GRS-A-417. Studies of the effect of Neutron Flux Density and Irradiation Time (Dose Rate Effect) on the Embrittlement of RPV Steels. G. Nagel. Gesellschaft fur Reaktorsicherheit (GRS) mbH, Cologne, F.R. Germany. February 1980. 57 pages. NRC Translation 792. Cost of translation: $280.00. Requested by: ACRS. GRS-A-443. Test and Structural Dynamic Analysis Methods for Applicability in Licensing Procedure. (Part I) Deterministic and Stochastic Computer Methods for Vibration Analyses. J. Jonczyk. Gesellschaft fur Reaktorsicherheit (GRS) mbH, Cologne, F.R. Germany. March 1980. 96 pages. NRC Translation: 793. Cost of translation: $1,100.00. Requested by: ACRS. GRS-5-31. Policy Statements on Problems of Nuclear Power Decommissioning of Nuclear Power Plants-Safety Aspects. H. Heller, H. May. Gesellschaft fur Reaktorsicherheit (GRS) mbH, Cologne, F.R. Germany. December 1979. 25 pages. NRC translation: 794. Cost of translation: $350.00. Requested by: ACRS. EUR 5476 d. Nuclear Research and Technology-Use of Personnel in Inspection, Maintenance and Repair in Controlled Areas of Nuclear Power Plants. Kommis-sion Der Europaischen Gemeinschaften. Frankfurt, Germany. 1976. 43 pages. NRC translation. 795. Cost of translation: 5250.00. Requested by: ACRS. i GRS-A-333. Status Report on the Hydrogen Distribution Following a Coolant Loss i Accident. H.L. John. Gesellschaft fur Reaktorsicherheit (GRS) mbH, Garching, Germany. August 1979. NRC translation: 796. Cost of translation: $1,500.00. Requested by: RES. BF-F-63-363.3. Experimental Investigation of the Hydrogen Distribution in the Containment of A Light Water Reactor Following a Coolant Loss Accident. G. Langer, R. Jeniar, H. G. Wentlandt. Battelle Institute. e.v. Frankfort, F.R. Germany. May 1979. NRC translation: 801. Cost of translation: 5315.00. Requested by: ADB. t
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ENCLOSURE A i H
DIVISION OF TECHNICAL INFORMATION AND DOCUMENT CONTROL continued...* Guidelines for Waste Management for Nuclear Power Plants. Bundesmenisterium des Innern, Conn, Germany. March 1933. 9 cages. MRC translation: 802. Cost of i translation: 550.00. Requested by: ACRS. Japanese Emission of Radioactivity Accompanying Power Plant Accident and Evaluation of Exposure -- Power Plant Accident at Three Mile Island, USA. S. Seo, Kyoto Univer-r perimental Station. 14 pages. NRC translation: 800. Cost sity, Atomic Pile s of translation:
- 5.00.
Requested by: I.P. Russian UDC 621.311.25:621.039. A System for Damage Control After Rupture of Main Pipelines in Nuclear Power Plants with VVER a40. A.M. Bukrinskity, Yu. V. Rzdreznikov. All - Union Heat Engineering Institute, Russia. 6 pages. NRC translation: B04. Cost of translation: 550.00. Requested by: I.P. DOCUMENTS PROCESSED BY TIDC Number of NUREG reports printed and/or distributed by TIDC in November i l' Number processed Average Number l Type of Report in November Processed per month Draft Environmental Statement 0.0 0.5 Final Environmental Statement 0.0 1.6 Safety Evaluation Report 1.0 1.0 Standard Review Plan Revision 0.0 0.0 i Environmental Standard Review Plan 0.0 0.0 Staff Report 22.0 28.0 Contractor Report 74.0 68.8 Conference Proceeding 0.0 0.8 l Board Notification 0.0 2.8 i Total 96.0 TU353I
- This entry is deleted from the PDR copy.
ENCLOSURE A i i l
t DIVISION OF SECURITY i WEEKLY INFORMATION REPORT i WEEK ENDING DECEMBER 5,1980 l The draft of a Comprehensive Automated Information System Security Plan (AISSP) to meet the requirements of 0MB Circular A-71, Transmittal Memorandum Number 1, was issued and distributed to all Directors of Offices and Divisions for comment on November 24, 1980. Comments are requested to be returned to the Division of Security by January 2,1981. i The Facilities and Systems Security Branch (FSSB) conducted a periodic security survey at Region II, Atlanta, Georgia, on December 4-5, 1980. It resulted in the assignment of a satisfactory rating. The Division of Security received comments from the Office of Inspection and Enforcement (0IE) on all security plans previously submitted by licensee facilities under 10 CFR Parts 25 and 95. The receipt of these ten plans completes inter-office coordination. l TYPEWRITER l TRACKS! RIBB0llS TilATTYPE l CLASSIFIED DOCUhlENTS X' i ARE CLASSIFIED TOB. _-w l 0 T A i ~ 1 l 1 1 i / j ENCLOSURE A t I i
+ NRR HIGHLIGHTS (December 1 - 5, 1980) North Anna Power Station, Unit 2 The resident inspector at North Anna Power Station advised that during the weekend the Unit 2 main generator step up transformer had a fault which caused damage to the bus duct system between the generator bus terminal and the transformer. There were minor fires in the area which were caused by the hot metal. The reactor tripped and all ' shutdown systems responded l satisf actorily. l I Dreis-Besse, Unit No.1 l At 9:23 am on December 3,1980, the reactor tripped due to a reactor coolant pump trip. Following the reactor trip, the main steam isolation valves closed. The operators then manually actuated the Steam and Feed Line Rupture Control System (SFRCS), which then allows steam generator level to be controlled automatically by the auxiliary feedwater system. Actuation of SFRCS should start both auxiliary feedwater pumps; however, j one of the pumps did not start automatically and required separate j operator action to start. The causes of the failures have not yet been identified.' The Office of Inspection and Enforcement is reviewing the event to ensure the causes of failures are identified and corrected prior to allowing the plant to again operate. ENCLOSURE B I
i i NRC TMI PROGRAM OFFICE WEEXLY STATUS REPORT j Week of November 23 - December 6,1980 J Plant Status 1 Core Cooling Mode: Reactor coolant System (RCS) heat transfer to reactor building ambient (air and sump water). Available Core Cooling Modes: OTSG "A" or "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal. RCS Pressure Control Mode: Standby Pressure Control (SPC) System. Backup Pressure Control Mode: One of two decay heat removal pumps to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST) to provide control of pressure. Major Parameters (As of 0500, December 5,1980) (approximate values) Average Incore Thermocouples: 1340F MaAimum Incore Thermocouple: 1680F RCS Loop Temperatures: A B ~ Hot Leg. 1290F 1320F 7. Cold Leg (1) 70 F 710F 0 0 0 (2) 70 F 70 F RCS Pressure: 97 psig (DVM) \\ Pressurizer Temperature: 720F 0 ~ Reactor Building: Temperature: 65 F Water level: Elevation 290.5 ft. (8.0 ft. from floor) via penetration 401 manometer Pressure: -0.5 psig (Heise) l Concentration: 1.4 x 10-4 uti/cc (Kr-85) (sample taken 12/4/80) Environmental & Effluent Infomation 1. Liquid effluents from TMI-1 released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications. 2. No licuid effluents were discharged from TMI-2. 3. EPA _ Environmental Data. Results from EPA monitoring of the environment around the THI site were as follows: ENCLOSURE B
2 3. EPA Environmental Data. Results from EPA monitoring of the environment around the TMI site were as follows: The EPA measured Krypton-85 (Kr-85) concentrations (pC1/m3) at several environmental monitoring stations and reported the following results: Location November 21 - December 1, 1980 3 (pCi/m ) Bainbridge 18 Goldsboro 22 Observation Center 22 Middletown 19 All of the above levels of Kr-85 are considered to be back-ground levels. No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and ganrna rate networks during the period from November 26 through December 4, 1980. 4. URC Environmental Data. Results from NRC wonitoring of the environment around tne TM1 site were as follows: The following are the NRC air sample analytical results for the onsite continuous air sampler: I-131 Cs-137 Sample Period (uCi/cc) (uC1/cc) HP-244 November 26 - December 3, 1980 <7 9 E-14 <7.4 E-14 5. Licensee Radioactive Material and Radwaste Shipments. The following shipment was made: On Monday, December 1,1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia. Major Activities 1 Reactor Decay Heat Cooling. The loss of Decay Heat to Ambient Test (transfer of reactor decay heat to the reactor building ambient) is continuing. A decrease in key plant temperatures is noted since the start of the test on November 6,1980. Short period review of thermocouple data indicated an apparent decrease of approximately f 60F for the average value of the incore thermocouples (1400F to j 1340F) and the hottest loop hot leg temperature' decreased approximately 60F (1380F to 1320F). ENCLOSURE B-I ---gW.-m--y-7 + a -*r: m--*-t r -a--de e-ee-mA -i- +tr-- ---W he4 4-'r+' -e-- +-e- ^=-?
\\ 3 The licensee will be submitting a proposal to the NRC to justify the shutdown of the secondary plant for long term layup based on j test data and this includes finalizing the special operating (test) procedure to a formal operating procedure. 2. Reactor Building Purge / Entry. The fifth entry into the Unit 2 reactor building is scheduled for Thursday, December 11, 1980. A pre-entry purge was conducted on Thursday, December 4,1980. An estimated six curies of Kr-85 was released during tnis period. A second purge is scheduled to commence Tuesday, December 9,1980. l This purge will continue thrnugh the entry. The objective of the i second purge is to minimize Kr-85 concentrations during operations inside the reactor building. The planned tasks inside the reactor building include replar.ement of the neutron source range preamplifier, decontamination experiments, and additional radiation mapping. The decontamination experiments are dcsigned to test the effectiveness of various decontamination j solutions. A detailed radiation map will be made on the 305' elevation and a three man team will climb into the refueling pool -(presently dry) to take radiation readings in the vicinity of the
- reactor head.
One of the entrants will climb a vertical ladder to the polar crane to assess the condition of the crane. ) i 3. Contamination of Building Exoansion Joints. During a radiological survey of the 281' elevation of the Unit 2 auxiliary building on November 27, 1980, contamination was found in an expansion joint. The expansion joint lies between the service building on one side and the auxiliary building and the air intake tunnel on the other side. Further licensee investigations revealed contamination in a second expansion joint which is contiguous to the first and which circles the reactor building. The expansion joints appear to be more highly contaminated towards the seal injection room which is adjacent to the reactor building and through which the second expansion joint runs. The seal injection room is currently inaccessable because of high radiation levels as a result of previous reactor coolant system leakage. The contamination has been identified as including CS-134, CS-137, Ru-106, Sb-125, Ce-144; and Sr-90. Water samples taken from the expansion joint by the licensee, showed cesium activity of 0.85 - 1.7 uC1/ml. The licensee has implemented a plan to determine the source and the extent of the contamination. The on site NRC staff will continue to closely monitor the licensee's actions in this area and licensee's plan. The plan includes taking core samples of the expansion joints and excavating to monitor the outside edges of the expansion joints. ENCLOSURE B 'l
i i* l l 1 4 4. Long Term Spent Resin Storage _F_acility. During tnis_reparting pertoa in D icensee received the analysis rasults from i, ontractor j laboratory on a water sample f rom the sump used to cnlleu-arainage j for the Long Term Spent Resin Storage Facility (Module A a.;:: P. ). J Gamma spectro:copic analyses indicated tru e emounts (1.2 x 10-8 uCi/ml) of Cs-137. Tritium analysis indicated 3 x 10-5 uCi/ml. The licensee strongly suspects that this activity is due to rain water inleakage picking up known liner loose surface contamination and tritium vapor offgassing througn liner fittincs-Module A has been in use as a repositor y for EPICOP-1 ano EPICOR-II spent resins since early 1980. The mocule nas 60 cells. Each cell i can acconcodate one 6' x 6' (nominal external dimensions) liner or i two 4' x3' liners. Presently the A module contains approximately j module is struturally con.Diete but is empty at 50 liners. The c tne present ticie. Water orains are provided at tne bottom af eech storage cell ine drains from both the A and B modules flow to a common sump. j i Csilected sumo water is being stored onsite for processing.ind l onsite storage flRC review of the licensee's surveillance program in tnis area continues. fleetino Attended On Friday, December 5.1980, L. Barrett attended a meeting with the Atomic Industrial Forum Working Comittee on THI-2 Recovery, to discuss the NRC's site office role in cleanup operations of Tr!I-2. Future Meetings 1. On Thursday, December 11, 1980, L. Barrett and R. Bellamy will attend a public briefing in Harrisburg sponsored by the Department of Environmental Resources on the status of decontamination at Three Mile Island. Representatives from General Public Utilities l (GPU) and the U.S. Environmental Protection Agency will also be j participating in the presentation. 2. On Friday, December 12, 1980, L. Barrett and R. Bellamy will attend a meeting in Parsippany, New Jersey, with GPU and _ Met-Ed to discuss proprietary information concerning EPICOR-II radwaste system. ENCLOSURE B
OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING DECEMBER 5,1980 1. Member State Comments on IAEA Draft Safety Guide SG-D7, " Emergency Power Systems at Nuclear Power Plants" By letter dated December 3,1980 from Joseph D. Lafleur, Jr. to John Trevithick of the Department of State, Member State comments are being transmitted to the IAEA on draft safety guide, SG-D7. We are strongly recommending that the IAEA incorporate the substance of certain U.S. comments into SG-D7; however we are not recommending that publication of the guide be delayed unduly because of differences over these items. In other words, the guide would be improved, in our view, and made more consistent with U.S. practice if the comments are incorporated, but the guide contains important provisions which should be published in any event without further delay. SG-D7 contains provisions intended to meet the objectives and minimum requirements cf Part 7 of the IAEA Code of Practice -Design for Safety of nuclear Power Plants. SG-D7 provides general guidance for all types of emergency power systems (EPS), and gives, in Appendix A, specific guidance on emergency electric power systems (EEPS). The contents of SG-D7 cover most of the same subjects as the relevant portions of 10 CFR Part 50, Appendix A, Criterion 17 (Electric Power Systems), and Regulatory Guides 1. 6, 1. 9, 1. 32, 1. 4 7, 1. 5 3,s'>. 75, 1. 81, 1.93,1.108,1.118,1.128 and 1.129. The goals of SG-D7 and applicable U.S. documents addressing emergency power systems are similar; however, there are differences between American practice and the provisions of SG-D7, Rev. 6. The most significant difference is the SG-D7, Sec. 3.1.2 recommendation that in evaluating power grid stability, the stability be considered when the second largest generating unit is forced off, when the largest unit is already disconnected, i.e. the two largest units are off. It is current U.S. practice to only consider grid stability when the largest generating unit is forced off. With respect to the remaining differences between SG-D7 and current U.S. practice, the recommendations of the safety guide are less demanding. Thus, U.S. practice requires at least two offsite transmission lines; SG-D7 permits one. SG-D7 implies that the nuclear plant capability to run back to house load, without tripping on loss of load is sufficient compensation for the use of a single offsite transmission line; the U.S. does not. SG-D7 permits qualification of emergency power system equipment by analysis alone; the U. S. does not. SG-07 allows automatic connections between independent EEPS safety divisions; the U. 5. does not. SG-D7 recommends that plant battery chargers have the capacity to recharge plant batteries in an acceptable time; U.S. practice limits acceptable time to eight hours. And finally, SG-07 requires a plant battery capacity of only thirty minutes at full load; the U.S. requires two hours for PWR's and four hours for BWR's. FNr.1 MilRF C I
i i 2-2. Degraded Cooling Steerino Group meeting: On November 26, 1980, the Degraded Cooling Steering Group met for approximately four hours to continue the coordination of staff efforts related to degra'ded cooling rulemaking. A main item of discussion concerned a draft document, presented at the meeting by RES, entitled " State of Technology Report on Release of Fission Product Iodine." The objective of the proposed report would be to provide the Commission with the best available technical information concerning accidental release of radioactive iodine. RES explained that such a document is necessary in view of facts and opinions being published by industry and Government laboratory representatives indicating that traditional assumptions concerning accidental iodine release may not only be overly conservative but simply wrong. The draft RES document goes on to explain that "This report is to be a dispassionate reporting of facts and available bases for informed judgment..." The Steering Group endors2s the RES proposal provided a parallel program goes forward "in-house" to put the RES proposal in proper perspective; the Group intends to make a recommendation to the EDO. Another item of discussion concerned the Severe Accident Sequence Analysis (SASA) program recently instituted by RES. RES explaincd the program in detail and requested that the Steering Group indicate whether or not it supports the program. The Steering Group concluded that the SASA program should be continued for another two months but that user office endorsement be required before the program goes forward on a full scale. The Group has forwarded its conclusion to Mr. Minogue by memo. Other subjects covered were a November 26, 1980 memo from Bernero to Arlotto entitled " Decisions for the DCC Rulemakings" and a presentation by Conti, SD, updating the rulemaking action plan. Both subjects will be discussed in more detail at subsequent meetings. 3. Training Course for Certified Health physicists: Thirty health physicists on tne NRC neadquarters staff am certified by the American Board of Health Physics. This relatively large number of Certified Health Physicists (CHP's) is a significant asset and resource to the Commission. CHP's must complete a prescribed number of continuing education units every four years to retain their certified status. To assist NRC CHP's in this regard, SD organized and presented a series of training courses designed to satisfy these education requirements. The courses involved 22 hours of instruction on five topics -- radiation epidemiology, respiratory protection, radiation genetics, environmental and internal dosimetry, and environmental aspects of nuclear reactors. Instructors were NRC staff personnel, NRC contractor personnel, and NRC consultants. In addition to NRC CHP's, the series was open to other NRC staff members and to other CHP's residing in this area. The first training session was held July 7,1980; the final one was held December 3,1980 The series of courses was approved by the American Board of Health Physics and will enable most of the NRC CHP's to retain their certification. (Contact: R. E. Alexander 443-5975) ENCLOSURE C I
4 . 4. Meetine with Dr. William Brandom, University of Denver, December 4,1980: A meeting was neld witn Dr. William Brandom, Professor of Biological Sciences at the University of Denver, to discuss the preliminary results of cytogenetic analyses done on residents of Grand Junction, Colorado (high radon environment due to mill tailings) and Greeley, Colorado (control population). The cytogenetic analyses were part of a feasibility study funded by the Environmental Protection Agency to determine the biological effects of exposure to radon and radon daughters. NRC is funding the second year of the cytogenetic portion of this study which will examine the use of cytogenetics as an indicator of low-level radiation exposure. Also discussed were the merits of: 1) having a baseline chromosome registry of nuclear workers in case of overexposures; and 2) establishing a system similar to the British National Radiological Protection Board system which utilizes cytogenetic analyses to estimate the dose received by individuals thought to have been overexposed to radiation when either their conventional physical dosimeter indicates an "off scale" exposure or when the worker was not wearing a dosimeter. (Contact: D. Flack 443-5860) Publications Issued During the Week of December 1-5, 1980 Draft Regulatory Guide and Value/ Impact Statement: Second Proposed Revision 3 to Reg. Guide 1.33, Quality Assurance Program Requirements (Operation), Task RS 902-4 (Comments requested by January 30, 1981) Reg. Guide 3.44, Rev.1: Standard Fonnat and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type) (Issued to reflect comments) ENCLOSURE C I
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending December 5,1980 i US/IAEA Safeguards Agreement 1 NMSS staff provided assistance to the State Department in finalizing the i initial U.S. eligible facilities list. The State Department has indicated they intend to deliver this list along with the written communication l required to put the agreement into force, to the IAEA on December 5,1980. Subgrouo on Nuclear Export Control Meeting (SNEC) During the November 20, 1980, SNEC meeting, NRC's proposed amendment to Part 110 l to permit export of small samples to IAEA labs under the U.S. Voluntary Offer was discussed. Concern was voiced by Executive Branch members in reference to l the NRC approach which considers such export transactions as having a non-nuclear end-use. No formal counter-proposal was offered, however, and the different agencies represented at this group will continue to review the matter. Concerce's drafting of changes to their pertinent export licensing regulations to control technology not on the " Nuclear Referral List" continues. A purpose of the proposed changes is to prevent certain technology and non-nuclear l equipment from going to unsafeguarded facilities. ISIS Source Evaluation Panel Meeting On December 2,1980, the ISIS Source Evaluation Panel held its first meeting to l discuss the Request for Proposals (RFP). The DOE representative on the panel i indicated that DOE requirements will not be available before the end of February 1981, and will then be subject to review. Specific changes will be made to the present RFP (originally prepared in February of this year) responsive to anticipated guidance from the Commission related to the OPE examination of ISIS. The Panel intends to prepare the RFP for release early in 1981. Advanced Material Accounting System Simulation (AMASS) On December 5,1980, the kickoff meeting will be held for the project, " Evaluation of Material Accounting Performance at Nuclear Fuel Cycle Facilities". NUSAC, Inc., was awarded the contract to assist the NRC in applying the Advanced Material Accounting System Simulation (AMASS) to six nuclear fuel cycle facilities over the next 24 months. The first facility to be evaluated is Nuclear Fuel Services, Erwin, Tennessee. The schedule for this evaluation will be established at this first meeting. ENCLOSURE D l I
Items of Interest 2 Wood River Junction public Meeting On December 2, at the request of the State of Rhode Island, a public meeting was held in Wood River Junction to inform the public of the progress of the decontamination effort at the United Nuclear facility. Also of concern was the status of the waste shipments to Nevada which received a considerable i amount of publicity recently when the State of Nevada returned six truckloads of waste to UNC which had been destined for burial. The meetino was chaired by state officials and tiu NRC was represented by members of IE, SP and NMSS staffs. A considerable amount of interest was centered around issues that were discussed in previous meetings held in July of this year. These items were as follows: 1. Status of a deep monitoring well, previously suggested by USGS, to evaluate the vertical extent of groundwater contamination under the UNC site. USGS, the state and NRC are working together to establish the optimum location of the well, plus the appropriate samples to be taken. 2. The public was triefec on tne status o' :ne inves: ga:icn :encerning the processing of zero-power fuel at the UNC. The main interest centered around the 1976 to 1980 period when this material was processed without license authorization. This is an ongoing investigation by IE. i 3. Status of IE's investigation into the allegations concerning burial of wastes on site. IE reported that two burials had been made in the early days of plant operations and that both had since been dug up and transferred to a licensed burial ground. Both burials were made in accordance with regulations existing at that time. ~ l 4. Status of IE',s' proposed domestic well sampling program to determine if tne contamination in the aquifer has not migrated offsite. Also discus:ed were recent stories in the press concerning the disposal of liquio wastes from lagoons to the environs by UNC. A former guard has alleged that UNC personnel had pumped liquid process waste containing radionuclides from the lagoons into a nearby ditch and that lagoon liners had been deliberately punctured to allow the liquid waste to migrate into the soil. IE stated that this would be the subject of a future investication. ENCL 6SURE D l \\
) i Items of Interest 3 j I The Governor has appointed a Citizens Advisory Council which is comprised of a member from each of four comunities surrounding the UNC facility. This Council will provide input to the State to assure public awareness of the actions taken by UNC, the State and NRC during the decommissioning process. Each Council member presented a list of concerns which will be subject to review by the staff. Several local citizens groups also presented a list of demands to be considered by the state, NRC and the licensee. The Concerned Citizens of Rhode Island (CCRI), which has been very vocal regarding alleged license violations at United Nuclear as well as the environmental effects of the acquifer contamination under the UNC property, demanded an opportunity for a hearing so that they could have input into the decommissioning process prior to any staff action. They were informed that the NRC's regulations provide any individual or group an opportunity to petition for a hearing and that CCRI's legal council, who is very familiar with these procedures, had been so informed. i Visit to Mallinckrodt Chemical Plant, St. Louis, Missouri i On Tuesday, December 2 two members of the Material Control and Accountability Licensing Branch visited the Mallinckrodt Chemical Plant in St. Louis, Missouri to obtain information on the measures employed by the facility to protect and account for controlled substances. Discussions were held with two accompanying DEA inspectors on their role in enforcing government regulations covering bulk manufacturing of controlled substances. i U.S.-Canadian Bilaterial Discussions Members of the Safeguard's staff participated in US-Canadian Bilateral Discussions on Nuclear Terrorism hosted by DOE, December 2-4, 1980. Included in the Agenda was a briefing by the NRC staff on the Insider Study (NUREG-0703). Proposed MC&A Upgrade Rule The proposed MC&A Upgrade Rule has been distributed for concurrence by the Offices of Inspection and Enforcement Standards Development, and the Executive Legal Director. It is anticipated that the rule will be forwarded to the Comission at the end of December, Licensee Transportation Activities in Possible Non-compliance with Part 71 On November 26, 1980, a notice was mailed to approximately 170 NRC radiography licensees stating that all their transportation activities may not be conducted in accordance with 10 CFR Part 71. The letter noted that they neither were registered with NRC for any shipping packages nor had an NRC approved quality assurance program. Licensees who fail to respond to the letter will be referred to IE for followup action at a later date. ENCLOSURE D 1
Items of Interest 4 West Valley Demonstration Project On December 3,1980, members of NMSS and ELD staffs met with DOE to hold i initial discussions concerning the interagency agreement required by the i West Valley Demonstration Project Act. This agreement will define the interrelationship between agencies necessary to accomplish NRC's role for review and consultation during the course of the activities conducted, by DOE under the project. During this first meeting a preliminary draft i of the interagency agreement prepared by DOE was reviewed and discussed, and general requirements to revise and expand several of the draft sections were identified. A second meeting has been tentatively scheduled for I December 17, 1980. b i i I ENCLOSURE D i
l OFFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST Week Ending December 5,1980 i 1. Preliminary Notifications relating to the following actions were dispatched during the week: a. PNO-I-80-167A Undeveloped Land, Rochelle Park, New Jersey - Radioactive Material in a Restricted Area (Update) b. PNO-I-80-172 Indian Point Unit 2 - Contamination of an Individual l l I PNO-II-80-167 H. B. Robinson 2 (CP&L) - Primary Coolant System Leak c. d. PNO-II-80-168 North Anna Unit No. 2 - Failure of Main Generator Output f Bus e. PNO-III-80-218 Clinton 1 - Slippage in Fuel Load Schedule f. PHO-III-80-219 Point Beach 1 - Reactor Trips Caused by Closure of the Main Feedwater Regulating Valve 9 PNO-III-80-220 Dresden Unit 2 - Reactor Trip and Scram Discharge Volume Level Monitoring System Malfunction h. PNO-III-80-221 Palisades Nuclear Power Plant - Equipment Problems Resulting in Extendir.g a Plant Shutdown for More Than Two Days l
- i. PNO-III-80-222 Davis Besse 1 - Reactor Shutdown Exceeding Two Days l
- j. PNO-III-80-223 Zion Station, Unit 1 - Equipment Problems Resulting in Plant Shutdown in Excess of Two Days k.
PNO-IV-80-39 Wolf Creek Generating Station (KG&E) - Work-hold Agreement Related to Safety-related Piping at the Wolf Creek Generating Station 1. FNO-TMI-80-52 Three Mile Island, Unit 2 - Contamination of Expansion Joints m. PNS-I-80-25 Millstone Nuclear Power Station, Unit II - Senior Reactor Operator Involved in Fatal Shooting n. PNS-II-80-32 and 32A Brunswick 1 and 2 (CP&L) - Bomb Threat 2. The following IE Circulars were issed: IE Circular 80-24, "AECL Teletherapy Unit Malfunction," was issed on a. Der. ember 2,1980 to all teletherapy licensees. b. IE Circular 80-25, " Case Histories of Radiography Events," was issued on December 5,1980 to all radiography licensees. I ENCLOSURE E i
_ 2_ i 3. The following Information Notice was issued: a. IE Information Notice 80-29 (Supplement No.1), " Broken Studs on Terry Turbine Steam Inlet Flange," was issued on November 26, 1980 to all Light Water Reactor Facilities holding power reactor Operating Licenses or Construction Permits. l i ENCLOSURE E l ~l
l L i l \\ l OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST i WEEK ENDING DECEMBER 5,1980 Davis-Besse Nuclear Power Station, Units 2 and 3 On December 1,1980, the Appeal Board issued a Memorandum and Order (ALAB-622) with respect to the applicants' request of November 17, 1980 to withdraw their applications for permits to construct Units 2 and 3. The Appeal Board struck from its docket two ASLB partial decisions relating to Units 2 and 3 which were subject to appellate review sua sponte and remov.ed this proceeding from the list of proceedings i.n which appeal boards are considering the generic issue of radon releases. The Appeal Board also stated that the applicants' request for full termination of this proceeding must be directed to the ASLB. 1 1 Three Mile Island Nuclear Station. Unit 1 (Restart) On December 5,1980, the Commission issued a Memorandum and Order (CLI-80-39) with respect to the question certified by the presiding ASLB as to whether the issue of psychological stress can be legally relevant to this proceeding. j By a divided vote of 2-2, the Commission directed the ASLB not to consider the j issue of psychological stress and to deny all contentions related thereto. The Commission also decided to reconsider the matter when a fifth Commissioner was 1 appointed and confirmed. l l i l ENCLOSURE G 1
i ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 5, 1980 Italian Earthouake Effect IP received notification from CHEN, Italy on December a, reportino on the effects of the recent earthouake on two Italian nuclear power plants Latina (a GCR) and Garigliano (a BWR). Garigliano is located about 150 km, l and Latina about 200 km, from the earthquake epicenter. Both plants were shut down at the time of the earthquake. Although both plants felt t.he earthauake, no known damage or abnormal consequences were sustained by either plant. Ground accelerations recorded at both plant sites have been forwarded to the appropriate staff offices. Notification of Korean Nuclear Officials of Lost Radioactive Material ] IP this week used the Department of State cable network to officially advise the Korean Administrator of the NRC-Korean Nuclear Regulatory Bureau (NRB) i infomation exchange arrangement of the apparent loss during 1970 of a package containing 10 medical applicators, containing a total of 125 MCI i Cesium 137, being shipped by the 3M Company to Seoul, National University j Hosoital (PNO-III-80-212). (Word over the loss had only recently reached NRC.) Although DOT had already notified the Ministry to which NRB reports, NRC repeated the message to assure delivery and to fulfill our obligation under the arrangement to notify the NRB when such potential safety problems are discovered. The staff is continuing to review circumstances surrounding the loss of the material and reporting of the loss to NRC. + Progress on Renewal of Arrangement with the British IP this week received Executive Branch clearance to transmit to the British a reauested clarification of the sentence on non-proliferation sensitivity of information to be exchanged which it now included in NRC's broad scope inter-national agreements. In giving NRC its clearance to proceed, the Executive Branch requested that we confirm in writing the following three understtndings: 1. That NRC will corsult with the Executive Branch should the U.K. wish to retransfer to other countries any infomation which falls under the category of " proprietary or other confidential or privi-leged infomation" within the proposed renewal arrangement. 2. That NRC will orovide no infomation under the Arrangement that pertains to the use of mixed oxide fuel in LWRs. l i 3. That neither this arrangement nor any current NRC arrangement covers cocoeration in the area of separating tritium from cooling l water and that MRC will seek Executive Branch concurrence should any cooperation in that area be proposed. l
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l ENCLOSURE H s
1 l 1 l l l l The staff plans to confirm these understandings soon. Meanwhile, we have sent the British the following explanation, which we hope will allow them to l accept the sentence as now included in the proposed renewal arrangement text: l "The language referring to " proliferation sensitive" information was inserted in the Arangement in recognition of the heightened awareness of the international community to the proliferation concerns that could be associated with peaceful nuclear cooperation. Inclusion of this language is part of a general policy, and is not meant to single out any particular country. Proliferation-sensitive l technologies include the sensitive nuclear technologies (non-public information on enrichment, D 0 production, and reprocessing) as 7 defined in the U.S. Nuclear Non-Proliferation Act of 1978, and referred to in the Nuclear Suppliers Guidelines, as well those covered by Part 810.7 of Title 10, Chanter 3, of the U.S. Code (attached). This provision, as applicable to our Arrangement, will not restrict any of the activities outlined in our scope and in no way is intended to frustrate the objectives of the agreement." Banoladesh Agreement for Cooperation IP received from State a copy of the U.S. - Bangladesh Agreement for l Cooperation and a reauest for formal NRC views. Staff is reviewing the agreement and plans to forward it to the Commission the week of December 8. Meeting with Monsanto Officials l l On November 3, IP representatives met with Messrs. Taylor and Schirwel from the Monsanto Corporation. Topics discussed included the status of Monsanto's pending export license application for 1 mg of Californium-252 for India and the status of the proposed amendments to NRC's export regulations regarding i byproduct material. I Foreign Visit to NRC On Tuesday Mr Antonio Carraninana of the Spanish Junta de Energia Nuclear c (JEN, NRC's rgulatory counterpart) met with D. Sells of LB-2/NRR to discuss technical issues related to a Spanish facility for which the South Texas Project is a reference plant.
- Foreign Reports The following foreign reports were received at IP during the period of December 1 to 5.
The ** indicates the reoorts are in English. For further information contact Eva Szent-Ivany (49-27788) IP. i' From Finland: IRP - Quarterly Report 1980/II, April - June **
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ENCLOSURE H I
i b I 3 i Foreign ReDorts Cont'd i i From FRG: ) GRS-A-451 - Environmental Safety Analysis for Recycling of Plutonium in LWRs
- 3. Partial Report - PROPRIETARY l
GRS-A-495 - Evaluation of the Mechanical Behavior of Irradiated Zircaioy Clad Fuel Rods During Reactor Transients and LOCA's - PROPRIETARY TUV-Stuttgart - Suggestion for the Determination of Allowable Repair Times From Italy: Technical Guide No. 20 - Quality Assurance. Documentation. Outline for the Operating Phase of. Nuclear Power Plants Technical Guide No. 21 - Operating Regulations of Article 45 of D.P.R.185/64. (Structure and content of applications for " Operating Regulations" for plants) q From Japan: i Atoms in Japan - October 1980** From Spain: JEN - Accident Reports of Vandellos Nuclear Power Plant - Clad Rupture of Fuel Element - Incident Report: Fuel Clad Failure in Pools From the U.K.: Health and Safety Research,1979** H&SE - Quarterly Statement on Nuclear Incidents - Third Ouarter 1980**- 1 i 4
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ENCLOSURE H l . ~.
= OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING DECEMBER 5, 1980 A meeting of the State Liaison Officers will be held at the H Street offices on December 9 and 10. Chairman Ahearne, Mr. Dircks and several NRC offices will make presentations to the S LO ' s. Governor Ella Grasso has written Chairman Ahearne indicating Connecticut is interested in becoming an Agreement State. The staff plans to arrange a meeting with Connecticut officials to t discuss the program. Joel Lubenau represented NRC at a planning meeting of the Radiation Policy Council's staff on Roles and Functions of Federal and State Relations. Bill Menczer, RSLO, Region III, met with the Regional Advisory Committee in Glen Ellyn, Illinois on December 2 ta plan future RAC activities and exercises. Bob Trojanowski, RSLO, Region II, participated in a number of emergency planning activities during the week of December 1 - 5. On December 2 and 3 he was in Columbia, S. C. with State officials and later that week he participated in the McGuire EP exercise in North Carolina. During the week he also met with the Tennessee State Liaison Officer, met with the Fairfield County (S.C.) Administrator to discuss EP matters relating to the Summer Facility and attended a public meeting to discuss a recent prchlem at the Nuclear Fuel Services facility in Irwin, Tennessee. On December 3, 1980, the Illinois State Legislature overrode Governor James Thompson's veto of a bill which bans the importation into the State of spent nuclear fuel from States that do not accept spent fuel from Illinois' power plants. The implication of this action is that spent fuel from the San Onofre Power Plant cannot be shipped to Illinois for l interim storage at the Morris Operations Facility in Morris, Illinois. San Onofre is currently the only power station that l ships spent fuel into Illinois. It is anticipated by State officials that the legislation will be challenged in court on the constitutional grounds of restricting interstate commerce. i ENCLOSURE I
0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING DECEMBER 5,1980 TMI Action Plan Tracking System Briefed the Chair an on the Action Plan Tracking System. i NFS Erwin Reoort Briefed EDO on report on inventory differences, concentrating particularly on statistical bounds on adjustments to the reported differences. l Information for Transition Grou,o i (1) At request of Mr. Kennedy updated the information in the Basic Facts i Book and Program Area Briefing Book given earlier to Mr. Carnesale. (2) Assembling response to additional request for information from the Group. Abnormal Occurrence Published 2nd Quarter CY-80 Report to Congress. WITS-II Briefed AEDO on basic reports for EDO segment of WITS-II. i Value-Impact Briefed EDO on status and problems associated with value-impact analyses. i ENCLOSURE J [ f I
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING DECEMBER 5,1980 An AE00 repert on the June 11, 1980 event at St. Lucie has been completed. This event involved a natural circulation cooldown following the simul-taneous loss of ccaponent cooling water to all reactor coolant pumps. During the natural circulation cooldown, a rapid depressurization of the Reactor Coolant System (RCS) caused the relatively stagnant reactor coolant in the upper head of the reactor vessel to flash creating a steam bubble. The presence of the steam bubble in the reactor vessel head resulted in large pressurizer level oscillations caused by alternately shifting the alignment of the charging pumps between the cold leg and the auxiliary spray connection in the pressurizer. Although the voiding of the reactor vessel head does not represent an immediate safety concern, this office has developed recommendations, based on our investigation of this event, that should be considered. Of the recommendations made, the most important concerns operator training and development of operating procedures. The rapid depressurization of the RCS during natural circula-l tion, for example, resulted in a plant condition that was not anticipated by the plant operators. The f act that the plant behavior did initially puzzle the operators clearly indicates that guidance needs to be developed such that operators are aware of what conditions will lead to voids in the primary system, other than the pressurizer, how to recognize the presence of voids, and how to either cooldown the RCS with voids or collapse the voids. The AEOD report contains a detailed description of the event, along with our findings, recommendations, and conclusions. Arrangements are in progress to have the report reviewed for factual content by NRR, IE, and the utility (plant management) prior to the formal issuance of the report. The formal l issuance is expected next month. A copy of the report is being placed in the PDR at the same time it is issued to other organizations. AEOD also issued a report on the AEOD Actions on the Crystal River 3 Loss of Non-Nuclear Instrumentation and Control Power Event. This report documents AEOD's involvement and conclusions regarding this event. AE00's recommenda-tions associated with the study of this event have been forwarded previously to NRR for appropriate action. Thus, this report contains no additional items warranting specific review or action. l l ENCLOSURE L 1
I ,. ITEMS ADPROVED BY THE COMMISSION - WEEK ENDING DECEMBER S,1980 l A. SECY-80-419 - NUCLEAR EXPORTS TO SWITZERLAND (COMMISSIONER ACTION ITEM). Memo l SECY to Dircks, dtd 12/4/SO. This is to advise you the: Me Commissien's action with restec: to a letter forwarded by Chairr.an Ahearne to Dr. 3r:erinski cf the White House on November 24, 1980 :,.s ~ considered to have completed action on the subject paper. The Office of International Programs was informed of this matteb by telephone on December 3, 1980. ~ ~ i B. SECY-80-505 - RESPONSE TO GAO RECOMMENDATIONS ON ELECTRICITY PLANNING (COMMISSIONER ACTION ITEM. Memo SECY to Dircks, dtd 12/4/80. 1 l This is to advise you that the Cc=ission (with all Cc=missioners i app cring) has approved the prcpesed NRC comments to Ccngress, as =cdified by the changes contained in the attached final draf: 1er er. The Office of Nuclear Reactor Regulation was informed of this action by telephone on December 4, 1980. It is recuested that you revise the letter per the attached draft and forward final versions for all Congressional addressees fer the signature of Chairman Ahearne to the i Office of the Secretary by c.o.b. December 8, 1980. C. SECY-80-356A - PROPOSED REPROCESSING RETRANSFER FROM SWITZERLAND (BEZNAU) TO U.K. (SECY-80-356) (COMMISSIONER ACTION ITEM). Memo SECY to Dircks, atd 12/4/80. This is to advise you that the Co =ission's action with respect to a letter forwarded by Chairman Ahearne to Dr. Er:erinski of the White House en November 24, 1980 is considered to have completed action en the subject paper. The Office of International Programs was informed of this matter by telephone on December 3, 1980. D. SECY-80 497 - RE'!IEW OF DELEGA~ IONS OF AUTHORITY AND OTHER DOCUMENTATION (C05?4ISSIONE: ACTID:. ITEM). Msmo SECY tc Eickwit/Kar.ranan, ctd 12/S/80. This is c advise you that the Cc=ission (with all Commissioners appreving) has appreved your rec==endation that no revisions cf the delegatien cf authcrity are rectired at this time as a result of implementation of Recrgami:ation plan No. 1 of i 1950. In connectien with his appreval, Chai=an Ahearne l provided the fellowing ce=ent: "Suggest issue be reexamined when new Chai=am is a:pcinted." The Cffices cf the General Counsel and poliev Ivaluation ~ were infc = ed =f this acticn by telechene en ;ecember 5. ._ I
E. STAFF REOUIREMENTS - DISCUSSION AND VOTE,11:00 A.'M., FRIDAY, NOVEMBER 21, 1980, COMISS13NERS' CCNFERENCE ROOM, D.C. OFFICE (OPEN TO FUBLIC ATTENDANCE). Memo i SECY to DircKs/Kammerer/Foucnaro, c:d 12/2/80. i I. SECY-BO 276 - Recortino of Physical Security Events-1 The Commission discussed the proposed final rule contained in the subject paper. I \\ The Comission by a vote of 4-0 approved the final rule as modified:
- to clearly state the relationship between the strategic significance of nuclear nsterial and the reporting requirements; (SD) f
'the definition cf the reporting time period be modified as in l (SD) The Commissicn noted that: 1. the a endments are to be published in final form in the Federal Register; (SD) (SECY Suspense: 12/22/S0) 2. upon publication of the amendments, the revised guide (Enclosure B of the subject paper) is to be published concurrently; (SD) (SECY Suspense: 12/22/80) 3. the appropriate Congressional comittees are to be notified; (SD) (SECY Suspense: 12/22/B0) 4. a public announcement (such as Enclosure H of the SECY paper) is to be j issued when the amendments are filed with the Office of the Federal Register; (OpA/SD) (SECY Suspense: 12/22/80) l 5. approval by the General Accounting Office of the report requirements in the proposed rule is to be obtained. (ADM/SD) (SECY Suspense: 2/10/81) II. SECY-80 LS7 - EDO Delecation of Authority The Commission discussed the EDO delegation of authority and approved several modifications. (See Attachment 2) The Comission requested that: 1. OGC draft a separate subsection to 0103.02 to cover budget control's execution l 2. OGC draf t languace as proposed in Attachment 2, p.3; 3. OGC draf t alternative language to 0103-031 (See Attachment 2, p.3) (Subsequently the Office of the General Counsel has indicated.that 1 hey will be preparing a memo succesting alternative language for all items i: t c.wh the Co =ission was unable to acree.) ENCLOSURE N
o t SCllEDULED SPEAKING ENGAGEMENTS Date Organiza tiorg Location Subject Speaker 12/12/80 ORNL Conference on Leach-Gatlinburg, TN Leachability as an Element in John D. Randall ability of Radioactive Regulatory Strategy (co-authored Solids by D. M. Sollenberger). Aspects of leachability are discussed in contexts of IILW, LLW, and leach tests. 3/26/01 22nd Annual Quality Clinic / Knoxville, TN What the NRC Regulations W. Ruhlman, R011 Require from a QA Program j 3/31/81 American Chemical Society Atlant. r,A Regulatory implications of II. Peterson, SD { Radiation-Dose Effect Relationships 4/1/01 Spouses of Operating Staff Education Center Quality Assurance. Requirements A. Cerne, R0 I at Seabrook Station Seabrook, Nil and licensing Procedures Related to Seabrook Station = l i ENCLOSURE O i r .s--ev+i..- -_m,,-,m_... ---.s-,-m#_..--4---,,_m _w__,_____________
., u.ar.o sr = /
- NUCLEAR REGULATORY COMMISSION
.:WAsHUGGrON,D.C.2eee5 i . ~, o'e=*ar 29 198o .lNFORMATION REPORT SECv-so-ss4 f_or.,: The Commissioners From: T. A. Rehm. Assistant for Operations. Office of the EDO Sub.iect: WEEELY INFORMATIGt REPORT - WEEK ENDING DECDRER 19, 1980 A summary of key events is included as a convenience to those Consissioners who prefer a condensed version of this report. Administration A Nuclear Reactor Regulation 8 Standards Development C Nuclear Materi,a1 Safety and Safeguards D Inspection and Enforcement E Nuclear Regulatory Research F* Executive Legal Director G* International hwy-H State Programs I Management and Program Analysis J Contr1311er K* a ! a \\ Analysis and Evaluation of Operational Data L k Small..and Disadvantiged Business Utilization M* l It'eas Approved by the Commission i N Calendar of Speaking Engagements O' DISTRIBUTION: Casaissioners Canaission~ Staff Offices j E90 / T. A. ehe, L...et for Operations ( ACRS agil0014Q i Office of the Executive Director SECY u Mff'
- No input this week.
~ ~~ for Operations / d; k hon -- A f"T. - lkl
Cd.U b~ scy bb,2 30 o s Sumary of Weekly Infomation Report Week Ending December 19, 1980 Salem Unit 2 The licensee has notified us that them will be a significant delay in the conduct of an emergency drill, which was originally scheduled for January 26, 1981. FEMA infomed the licensee that their review of the scenario to be exerciied will mquire about three weeks longer than the licensee had anticipated. The licensee expects that an emergency drill would not be conducted before April 1981. Reouests for Hearino Maine Yankee Atomic Power Plant and Pilgrim Unit 1 have requested a hearing regarding the Environmental Qualification of Safety-Related Electrical Equipment. Public Meetino The Office of Standards Development is planning to hold a public meeting to discuss Section 50.55a, the Comission's regulation on Codes and Standards. This regula-tion incorporates by mfemnce, with some modifications, national codes for the construction and inservice inspection of components for nuclear power reactors. The meeting is intended to provide an opportunity for the NRC staff and other interested parties to discuss coments and suggestions for impmving the regulation. The meeting will be held in Room P-114/118, Phillips Bldg., Bethesda, on January 30, 1981, from 9:00 a.m. to 4:00 p.m. I ] Radon Value for Table S-3 I The staff is making preparations to publish a technical report giving the latest t data on radon releases from uranium mining and milling operations. This report provides the technical basis for a rulemaking to amend Table S-3 by adding the new radon-222 data. IE Bulletin On December 2,1980, at Dresden Unit 2, the centinuous monitoring system (CMS) on the scram discharge volume (SDV) failed to respond as expected following a nomal reactor scram. The CMS was recently installed to detect the presence of water in the SDV in accordance with a confirmatory order issued as a result of the Browns Ferry 3 partial scram on June 28, 1980. IE supplement 4 to Bulletin 80-17, " Failure of Control Rods to Insert During a Scram at a BWR " was issued December 18, 1980, requiring that testing be perfomed within 14 days to denenstrate CMS operability and that manual surveillance of the SDV be resumed in the interim. Licensee actions will be verified by IE inspections. Transfer of Depleted Uranium Export Licensing Authority On December 16 the President signed legislation (H.R. 6942) which transfers export licensing authority for certain foms of depleted uranium from NRC to the Executive Branch.
i l' i l \\ OFFICE OF ADMINISTRATION l Week Ending December 19, 1980 t ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS l Initial Appeal of Request Initial Decision Received 703 38 6 ranted 550 16 Dented 105 19 Pending 48 3 ACTIONS THIS WEEK Received Jay Gary Finkelstein, Requests, on behalf of American Broadcasting Companies. Bergson, Borkland, Inc. and Charles C. Thompson, II, six categories of Margolis & Adler information relating to the Lifespring Corporation or (80-612) Foundation and Human Factors Research. Inc. John W. Pestle, Requests a copy of the damage claim filed against the Varnum, Riddering, NRC on December 8,1980 by General Public Utilities Wierengo & Christenson Corporation relating to the Three Mile Island Nuclear (80-613) Power Plant accident. (An individual requesting Requests information on his Reactor Operator License infomation about himself) exam results. (80-614) i Allan Mazur, Requests the enclosures to a letter dated December 1 j Syracuse University 1978 to Connonwealth Edison Company from James Keppler (80-615) and any subsequent correspondence regarding the enclosures. Bonnie J. Irving, Requests infomation relating to security guard REguard Security contract procurements. 1 Service, Inc. (80-616) McNeill Watkins, II, Requests records identifying alternatives to the Debevoise & Liberman specific requirements of Appendix R. Part 50 Fire (80-617) Protection Rule. Marc A. Hillier, Requests studies of alpha and beta radiation levels in State of Illinois subsurface water supplies. (80-618) CONTACT: J. M. Felton 492-7211 ENCLOSURE A i i 1
l l ) 2 Received, Cont'd i i Carlos Byars, Requests copies of the extracts of the Reed Report i Houston Chronicle 1tsting the 27 safety-related issues as identified by (80-619) General Electric. John D. Steinmetz, Requests four categories of information relating to Edison Electric the final rule on " Fire Protection Program for i' Institute Operating Nuclear Power Plants", Appendix R. (80-620) Diane E. Findley, Requests a copy of the Final Report under NUSAC Inc. j Science App 1tcations, Inc. Contract No. NRC-02-79-043-2. i (80-621) i Dale E. Hollar, Requests all documents relating to the basis or Debevoise & Libeman supporting rationale for the conclusion in the NRC's (80-622} Memorandum and Order, CLI-80-40 and the accompanying Staff Technical Analyses. Geoffrey S. Stewart, Requests all correspondence and documents relating to Davis Polk & Wardwell correspondence or to verbal comunications between the (80-623) NRC and Thomas J. Madden of the fim Kaye, Scholer, i Fieman, Hays and Handler and documents made available j to Mr. Madden under his FOIA requests, 80-515, 80-516, ) and 80-555. Andrew Albert, Requests all documents pertaining to the NRC staff Herald Journal investigation of fomer site Superintendent T. J. ) (80-624) Perkins of the Nine Mile Point Unit 1 Nuclear Power Plant. i Theresa M. Watson, Requests all inspection reports, disclosable seizure FOI Services, Inc. information and court action regarding the Nuclear (80-625) Equipment Chemical Corporation and Fern Labs. Janice F. Rutherford, Requests a copy of the winning technical proposal in The BDM Corporation response to RS-NMS-81-032 entitled " Technical Support (80-626) for the Confidence Rulemaking Proceeding." (NRCemployee) Requests specific documentation relating to her (80-627) Step-Three Grievance. Linda Logan Bryan, Requests specific information relating to Atomic Energy City of Jacksonville Comission Docket No. STN-50-437: Offshore Power (80-628) Systems' Application for License to Manufacture Floating Nuclear Plants. l i ENCLOSURE A i l
i i. i 3 l i Granted i l Joanne Bloom, In response to a request for documents regarding the Isham, Lincoln imposition of civil penalties, NRC requests for l i & Beale congressional authorization for more severe civil (80-533) penalttes and responsibilities and behavior of nuclear ] station operators, made available 43 documents. l Nicholas S. Reynolds, In response to a request for 15 categories of documents Debevoise & Liberman regarding Memorandum and Order CLI-80-21 and IE j (80-556) Bulletin 79-018. made available 42 documents. Marilyn Shineflug In response to a request for four categories of (80-574) documents relating to cracks in the containment of one of the Zion reactors, made available three docunents. j i (An individual requesting In response to a request for copies of his official j 1 infomation about himself) performance appraisals, infomed the requester we are (80-584) unable to locate any performance appraisals submitted i in fits behalf. I Lilias Jones, In response to a request for a copy of three NUREG l i Black Hills Alliance documents, made available two documents and infomed (80-591) the requester the NRC was unable to locate one document. l 1 j Lilias Jones, in response to a~ request for a copy of ten listed l Black Hills Alliance documents, made available a copy of these records. i j (80-593) i Jill Wright In response to a request for a copy of the non-3 l (80-596) proprietary version of the winning proposal under NRC Request for Proposal RS-RES-80-214, informed the requester this document is already available at the PDR. i s (An individual requesting In response to a request for copies of all NRC documents s informationabouthimself) pertaining to himself, infomed the requester the j (80-604) NRC has no infomation pertaining to him in its 1 personnel, security or radiation exposure records. i i Eric Buetens, In response to a request for a copy of a list of the The Chronicle-Express routes by which spent fuel would be transported in j (80-605) New York State, made available one document. I i Ed Forti, In response to a request for access to the mailing list l Ketchum, MacLeod for the NRC's Public Document Room Daily Accession ] & Grove List, informed the requester the NRC is placing him j (80-609) on its Daily Accession List. 1 John W. 'estle, Made available a copy of the damage claim filed against a Varnum, Riddering, the NRC by the General Public Utilities Corporation on Wierengo & Christenson December 8,1980. 1 (80-613) J l
- ~
ENCLOSURE A f I
4 Granted, Cont'd (An individual requesting Made available information on his Reactor Operator information about himself) Litense exam results. (80-614) Denied Lindsay Audin In response to a request for five categories of (80-545) documents regarding transportation of plutonium, made available 58 documents. Denied portions of one document containing safeguards infomation. l l l l l f ENCLOSURE A f
DIVISION OF CONTRACTS Week Ending December 19, 1980 RFP'S ISSUED RFP RS-RES-81-166 Title - Probabilistic Studies of Flood Hazards and Flooding Effects Description - A study to identify and develop methodologies to estimate probabilities of exceedance of flood levels and probabilities i of radioactive release from nuclear power plants as a con-sequence of floods, including an assessrent of the un-certainties in the estimates. Period of Performance - Thirty-six months Sponsor - Office of Nuclear Regulatory Research Status - RFP issued December 12, 1980. Proposals due February 12, 1981. PROPOSALS UNDER EVALUATION RFP RS-RES-81-177 Title - Seismicity of the Pacific Northwest (Washington and Oregon) i Description - A study to monitor the seismicity of the Jacific. Northwest to provide background seismological info < 'ien nec.ssary i to evaluate the potential seismic hazare t-neclear power plants. Period of Performance - Estimated at five years Sponsor - Office of Nuclear Regulatory Research Status - Best and Final offers due December 19, 1980. CONTRACT AWARDS 1. NRC-02-81-028 Title - Evaluation of Material Accounting Performance at Nuclear Fuel Cycle Facilities Description - The purpose of this effort is to support NRC evaluation of material accounting performance at nuclear fuel cycle facilities. The effort will involve the collection of specific facility information, the evaluation of input data needed to run the cited programs, and the assessment of the results. Period of Performance - Two years Sponsor - Office of Nuclear Material Safety and Safeguards Status - Cost-plus-fixed-fee contract was awarded to NUSAC, Inc., in the amount of $167,028, and is effective ~on December 2,1980. ENCLOSURE A I
.=.. - l l i l .e 2 i l t CONTRACTS CLOSED OUT (All administrative action completed and final payment made) { Contract No. Contractor Close-Out Date- 'l NRC-05-78-340 Eberline Instrument Corp. 12/17/80 i t I l t t t l l l l I l l i l t 1 i ENCLOSURE A J l 1 = --,m .I
l e NRR HIGHLIGHTS (DECEMBER 15-19, 1980) San Onofre Unit No.1 SCE notified the NRC by telephone on December 16, 1980, that due to ( technical difficulties, attempts to braze sleeves within the " sludge l pile" of the steam generator have been teminated until some of the dif ficulties are overcome. One approach being investigated by SCE is to dry the sludge pile prior to attempting to braze again. SCE plans i to request a meeting with the NRC in January to discuss the status of the steam generator repair program. Since SCE had reported earlier that approximately half of the brazes would be within the depth of the sludge pile and half of the brazes would be above the sludge, the success of the repair program as presented relies on the outco?.e of the attempt to braze within the sludge pile. l Maine Yankee Atomic Power Plant t "zi s Y -lis At:.ic Fc..ir C:rpany, by 15ttsr dated Lecs-bar 2, li;-0, re: ts sd a hsaring in regard to o.:r Oc : tar 2a,1c20 Ecui;rtnt ;califica..... j Cr:gr. The hsaring re:;usst is addressed to the issue of whsther all safety ' reined sle:irical equipasnt should be envirsnrsntally cualified in acccr:gr.:e 6:ith the ;3R Guidelines or NUREG-0335 by June 30, 1932. I F.tir.e Yar.kee states that this request for a" hearing will provide a:ple - c:::rt,r.ity to clarify the requirements for the Order and review the safety
- .P.ni:r. re;:rt ~ sch6duled for iss.tn=e en February 1,1931.
l Salem Unit 2 s 3 The licensee has notified us that there will be a significant delay in the conduct of an emergency drill. The original schedule called for a drill to be conducted on January 26, 1981. However, at a recent meeting with representatives of FEMA, the State of New Jersey and the State of Delaware, the licensee was informed by the New Jersey represent-atives that they expect a 6-8 week slip in their schedule in order to obtain approval of the governor. In addition FEMA representatives infomed the licensee that their review of the scenario to be exercised will require about three weeks longer than the licensee had anticipated. Based on this infomation, the licensee currently expects that an emergency drill would not be conducted before April 1981. ... ~ Pilgrim Unit 1 By teleccpyon December 11, 1980, Boston Edison provided a copy of their request for a hearing dated December 4,1980 on the staff's Orders of October 24, 1980 regarding the Environmental Qualification of Safety-Related Electrical Equipment. ENCLOSURE B I
l l NRC TM! PROGRAM OFFICE WEEKLY STATUS REPORT Week of December 14-20, 1980 Plant Status Core Cooling Mode: Cyclic natural circulation in the "A" reactor coolant - system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to l reactor butiding ambient. Available Core Cooling Modes: OTSG "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal, RCS Pressure Control Mode: Standby Pressure Control- (SPC) System. Backup Pressure Control Mode: One of two decay heat removal p aps to supply pressure in conjunction with variable recirculation back to the borated water storege tank (BWST) to provide control of pressure. Major Parameters (As of 0500, December 19,1980)' (approximate values) i Average Incore Themoccuples: 113*F Maximum Incore Thennocouple: 153*F RCS Loop Temperatures: A B Hot Leg 112*F 116*F i Cold Leg (1) 86*F 82'F (2) 96*F 86*F j RCS Pressure: 83psig(DyM) Pressurizer Temperature: 69'F l Reactor Building: Temperature: 63*F Unter level: Elevation 290.S ft. (8.0 ft. from floor) via penetration 401 manomater 18ressure: -0.25 psig (Heise) Cc x entration: 3.8 x 10-5 uC1/cc (Kr-85) (sample taken 12/17/80) l l Effluent and Environmental p_diological) Infomation l 1. Liquid effluents from TA! 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. The concentrations of radioact1ve material in the discharged effluent during this ukly period were less than the Lower Limits of Detection (LLD). ENCLOSURE B ~~ I I
l 2 2. EPA Environmental Data. Results from EPA monitoring of the environment around the TML site were as follows: 3 The EPA measured Krypton-85 (Kr-85) concentrations (pC1/m ) at j several environmental monitoring stations and reported the following results: Location December 8 - December 12, 1980 (pCi/m3) Bainbridge 28 Goldsboro 26 Observation Center 30 Middletown 19 All of the above levels of Kr-85 are considered to be back-l ground levels. No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and gama rate networks during the period from December 10 through December 18, 1980. l 3. NRC Environmental Data. Results from NRC monitoring of the enviros-ment around the THI site were as follows: ,The following are the NRC air sample analytical results for the onsite continuous air sampler: I-131 Cs-137 l Sample Period (uci/cc) (uci/ccl' HP-246 December 10 - December 17, 1980 <8.2 E-14 <8.2 E-14 4. Licensee Radioactive Material and Radwaste Shioments. The following shipments were made: i On Monday, December 15,1980, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia. On Wednesday December 17, 1980, contaiminated cork samples from the Unit 2 auxiliary building expansion joint were shipped to Science Applications, Incorporated, (SAI), Rockville, 14sryland. On Thursday, December 18, 1980, a box containing Unit 2 air filter and smear sample papers was mailed to Teledyne Isotopes, Westwood, New Jersey. On Thursday, December 18, 1980, a box containing a Unit 1 i waste evaporator condensate storage tank (WECST) monthly composite sample was mailed to Teledyne Isotopes, Westwood, New Jersey. MNCLEURE B I
i Eb-l' j 4 i i j 3 i ~ a Major Activities j ) _eactor Decay Heat Removal. Decay heat removal (approximately 1. R 80 KW) continues to be removed by steaming (under vacuum conditions) j in the "A" Once Through Steam Generator (OTSG) and by heat transfer from reactor coolant system to reactor building ambient. Work i continues on resolving staff consnents on the licensee's. proposal to use the loss to ambient mode as a viable means of decay heat removal. 4 Approval of the licensee's proceoure is expecteo next' ween. 2. Contamination of Buildina Expansion Joints Sample.results of cork j adjacent to the air intake tunned snow no activity above the lower ~ j level of detectability. <This indicates that the water stop in the expansion joint between the " control and service building" and the " air intake tunnel" is intact and keeping the contamination from spreading past the water stop. The licensee is developing a plan to remove the contaminated wrter i from the expansion joints and is continuing in their efforts to ensure the contamination is not being released to the environment. i The onsite NRC staff will continue to closely monitor the TicWhsDe's i [ actions in this ama. l Meetings Attended 3 1. On Wednesday, December 17, 1980, L. Barrett, A. Fasano, n. Marackamp. i and M. Shanbaky attended a meeting at NRC Region I, King of Prussia, 1 PA. Licensee management representatives were present to discuss ~ j the Unit 1 Health Physics Program Evaluation concerhing acceptable corrective action for the evaluation findings and applicability to - a ) Unit 2. F ~ 2. On Thursday, December 18, 1980, B. Snyder and L. Barrett attended the TMI Advisory Panel meeting at the William Penn Museum in Harrisburg. The topic of discussion was radioactive waste manage-ment. Presentations were given by Mr. G. Cunningham, Assistant i Secretary for the Department of Energy (DOE), Mr. R. Arnold, Chief ~ ~. Doeratino E7ecutive. General Public Utilities Nuclear Group (GPUNG). f and representatives from Congressman Udall's staff and the ACRS. I The panel focused on the progress towards the disposal of TMI radiaoctive water. The panel also expressed concern that DOE could accept TMI high level waste only for research and development (R&D) purposes and therefore store that accepted waste only and that it did not appear any organization is taking the lead in resolving any legislative hurdles for TMI waste disposal. Concerns on delays of ~ the cleanup efforts and financial s'tatus of GPU were also expressed. f 3. On Friday, December 19,1980,.L..Barrett, R. Bellamy and G. Kalman i held a seminar on the Three Mile Island container nt building, in Bethesda, Maryland for the NRC staff. e P f i e f i ENCLOSURE B ~ l
i OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING DECEMBER 19, 1980 1. SD is planning to hold a public meeting to discuss Section 50.55a. the Commission's regulation on Codes and Standards. This regulation incorporates by reference, with some modifications, national codes for the construction and inservice inspection of components for nuclear power reactors. The meeting is intended to provide an opportunity for the NRC staff and other interested parties to discuss comments and suggestions for improving i the regulation and is part of our effort to obtain feedback representing a spectrum of opinions through open discussion. It is anticipated that the meeting will provide a valuable exchange of information concerning problems experienced during application of the regulations. The public meeting to discuss this regulation will be held in Room Pil4/118 of the Commission's offices at 7920 Norfolk Avenue, Bethesda, Maryland on January 30,1981, from 9:00 a.m. to 4:00 p.m. 2. The fifth meeting of the Degraded Cooling Steering Group was held on December 9,1980, and brought out several contrasting views of the proper direction for degraded cooling rulemaking. For example, one participant { pointed out that the recent Zion / Indian Point work has assumed no opera-i ter involvement (i.e., no operator errors of consnission or omission and no operator assist in teminating an accident) and is likely to result in " passive system" improvements like controlled filtered venting actuat-ed by relief valve or rupture disk. The belief was expressed that the i degraded cooling rulemaking should likewise be directed toward mitiga-tion and not prevention and that the only role prevention should have is in relation tt. major new systems. This view is not accepted by all the Group n' embers; many still believe that prevention or termination of sequences prior to core melt can play an important role in reducing risk to an acceptable level. Another key point made was that, from a probablistic viewooint, al-though " windows" can be defined for some accident sequences which define degrees or core damage, it looks like the probabilities are such that, for safety purposes, you may have to deal with a full core melt. If one believes this view, then one could conclude that a TMI-2 type accident; that is, one that has a degraded core but terminated before a core melt, is not of sufficiently higher probablity than a core melt to address separately in rulenaking. The next Steering Group meeting, to be held on January 6,1981, will treat three items: (1) Approach to siting rule, particularly source term; (2) Approach to Degraded Core Cooling Rule - need for safety goal, role of prevention / mitigation, must we assume core melt?; and (3) Use of aoproach where individual Group members take lead for each prime area of rule (e.g., accidents to be considered, fission products, or hydrogen). ENCLOSURE C
i i 3. Radiation policy Council j The U.S. Radiation Policy Council held its third meeting on December 18, 1980 in Washington, DC. John Davis, NMSS, attended as NRC's representa-tive to the Council. Mr. Davis informed the Council of HRC's plans for the identification and analysis of specific waste streams for which control for radiation protection purposes is not necessary. The Council also received status reports from DOE on low-level waste management and from EPA on radon in structures and occupational exposure guidance. The Council was given status reports on: (1) work plans for its long-tem agenda; (2) conversion to SI units; (3) a charter for a public advisory committee and (4) radiological emergency preparedness. The Council directed the RPC staff and the Working Group to continue work on these issues and to prepare recomendations for Council actions at its next meeting. (Contact: E. Podolak, SD, 443-5860) l l l l l l l ENCLOSURE C f
i Publication to be Issued in the Near Future
Title:
Inservice Inspection Code Case Acceptability - ASME Section XI, Division I Expected Issuance Date: March 1981
== Description:== This guide endorses with certain exceptions those ASME i Section XI (Inservice Inspection) Code Cases that the NRC staff has found to be generally acceptable. The guide makes known the regula-tory position concerning the Code Case and provides guidance in their j t I use. l \\
Contact:
E. O. Woolridge i Publication Issued During the Week of December 15-19, 1980 Draft Regulatory Guide and Value/ Impact Statement: Nuclear Criticality l Control and Safety of Homogeneous Plutonium-Uranium Fuel Mixtures Out-side Reactors, Task No. FP 026-5. Comments requested by February 19, 1 981. Draft Regulatory Guide and Yalue/ Impact Statement: Standard Fomat and Content for the Safety (Analysis Report for an Independent Spent Fuel Storage Installation Dry Storage), Task No. FP 029-4. Comments requested by February 27, 1981. t t i ENCLOSURE C i I i
1 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending December 19, 1980 Radon Value for Table S-3 i After discussions with the Chairman's office and the ED0's office, in follow-up of Comission Paper SECY 80-499 "Information Regarding Activities Pertaining to Table S-3." the staff is making preparations to publish a technical report giving the latest data on radon releases from uranium mining and milling operations. This report provides the technical basis for a rulemaking to amend Table S-3 by adding the new radon-222 data. Actual l rulemaking action may be deferred until issuance of the Appeal Board decision from the radon hearing at Harrisburg, Pennsylvania and until settle-ment of the Kerr-McGee suit in the Tenth Circuit Court of Appeals to nullify the new regulations on uranium milling. Meeting with LIXI Corporation l Members of the Material Certification and Procedures Branch met with repre-sentatives of the LIXI Corporation on December 17, 1980, for the purpose of discussing health and safety design requirements for the Lixiscope. The LIXI Corporation is proposing to distribute their device for various industrial applications and medical diagnosis. The Lixiscope is a hand-held, self-contained, high-resolution x-ray imaging device using up to 500 mil 11 curies I-125. Possible uses include medical diagnosis, non-destructive testing, quality control, security screening, and radiation i control management. Physical Protection Of Catecory II Material In Transit--Final Rule A final paper has been prepared forwarding a Federal Register notice for l issuance of amendments to 10 CFR 73.67 in final form. These amendments would ) allow the IRC-staff to order certain shipments of SNM of Moderate Strategic Significance delayed in order to help assure that a fomula quantity of SSNM is nc, accumulated by an adversary through multiple thefts of shipments of less than a formula quantity. 4 i l ENCLOSURE D i
I I J l Items of Interest 2 ? 1 'l MC&A Upgrade Rule i On December 1,1980, the proposed MC&A Upgrade Rule was sent out for NRC -l office concurrence or coment. Coments have been received from all.but one office and revisions are being made in the proposed rule in an effort to l resolve differences. l 1 I l I i i f t 1 6 ENCLOSURE D l l
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending December 19, 1980 1. The following Notifications of Significant Enforcement Action were dispatched during the past week: a. EN-80-26A Superior Industrial X-Ray Company, Blue Island. IL - An Order Imposing Civil Penalties in the amount of 59,050 was issued to subject licensee on December 17, 1980. Previously, a Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of 59,800 was issued based on alleged items of noncompliance relating to radio-graphic exposure device being left unattended in an unrestricted area. After consideration of the licensee's response, the IE staff concluded that the penalty for one item of noncompliance should be mitigated by S750 but that the penalties for the other items should be imposed as proposed. b. EN-80-34A Minnesota Mining and Manufacturing Company, St. Paul, MN - An Order Imposing a Civil Penalty in the acount of $2,000 was issued to subject licensee on December 17, 1980. Previously, a Notice of Violation and a Notice of Proposed Imposition of a Civil Penalty was issued based on an alleged item of noncompliance relating to a radioactive waste shipment from the licensee's facility to the Richland, Washington burial l site where the external radiation levels on the surface of the transport I vehicle exceeded regulatory requirements. After consideration of the licensee's response, the IE staff concluded that the item of noncompliance ~ j did occur and no adequate reason was given by the licensee for mitigation j or remission of the proposed penalty. c. EN-80-55 Pharmatopes, Inc., Oak Park, Mich. - On December 15,1980, a Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $7,550 was issued to subject licensee. This action was based on alleged items of noncompliance relating to the radiation protection program at the licensee's Washington, D.C. radiopharmaceutical dispensing facility, and involved an extremity exposure of an individual, failure to report the exposure, failure to make adequate surveys, failure to properly instruct individuals, failure to properly survey packages before shipment and failure to follow laboratory rules incorporated in the license. d. EN-80-56 Conrnonwealth Edison Co., Chicago, Ill. (Dresden Nuclear Power Station) - On December 19, 1980, a Notice of Violation and a Notice of Proposed Imposition of a Civil Penalty in the amount of 54,000 was issued to subject licensee. This action was based on an alleged item of non-compliance relating to the shipment of waste material from the Dresden Station which when received at the Richland, Washington burial site was not packaged in a strong, tight package and the lid on one bin was not bolted down and was easily removed. 1 e. EN-80-57 Consolidated Edison Company (Indian Point Unit 2) - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $5,000 was issued to subject licensee on December 19, 1980, based on an e alleged item of noncompliance relating to a change in a procedure without j o Commission approval which was contrary to a Technical Specification and g l which involvet an unreviewed safety question. As a result of the unauthorized E change, the reactor was operating with the automatic start feature of the i; ! Containment Spray System, and Engineered Safety Feature, rendered inoperable. C I i in m.w a.i- -e -q gr+y qm9 e-5-
. t l l 2. Preliminary Notifications relating te tne following actions were dispatched during the week: a. PNO-I-80-173 Nuclear Metals, Inc., Concord, Mass. - Employee Contaminated I with Depleted Uranium in the Form of Green Salt (U F ). 4 b. PNO-I-80-173A Nuclear Metals, Inc. Concord, Mass. - Bioassay Results for Employee Contaminated with Depleted Uranium in the Fom of Green Salt (U F ). 4 c. PNO-I-80-174 Lebanon Valley General Hospital, Lebanon, Pa. - Loss of I 10 Mil 11 curies of Xenon-133 d. PNO-I-80-174A Good Samaritan Hospital, Lebanon, Pa. - Lost Package i Containing 10 Mil 11 curies of Xenon-133 is Found ) e. PNO-I-80-175 Peach Bottom Unit 3 - Scram Discharge Volume Level Instrument I Failure f. PNO-I-80-176 Beaver Valley Power Station Unit 1 - Unscheduled Plant Shutdown g. PNO-II-80-173 Nuclear Fuel Services, Inc., Erwin, Tenn. - Unplanned j Release of Airborne Radioactivity Within Regulatory Limits h. PNO-II-80-174 Brunswick Steam Electric Plant - Loss of Reactor Building Airborne Effluent Monitoring Capability
- i. PNO-III-80-230 American Electric Power Service Corp., D. C. Cook Unit 2 - Fire in Main Generator Exciter
- j. ~ PNO-III-80-231 Mallinckrodt, Inc., St. Louis, MO. - Report on Lost.
I Shipment of Radioactive Material: 2 Curie Technetium Generator k. PNO-IV-80-40A Arkansas Nuclear One, Unit 2 - Plant Shutdown Extended 1. PNS-1-80-26 United Nuclear Corp., - Naval Products Montville, Conn. - Bomb Threat m. PNS-III-80-21 Donald C. Cook Nuclear Power Plant - Telephone Bomb Threat n. PNS-III-80-22 Quad-Cities, Unit 1 and 2 - Bomb Threat 3. The following Information Notices were issued: a. IE Infomation Notice 80-44: " Actuation of ECCS in the Recirculation Mode While in Hot Shutdown," was issued on December 16, 1980 to each pressurized water reactor facility holding a power reactor operating license or a construction permit. ENCLOSURE E f
~ . i b. IE Information Notice 80-45: " Potential Failure of BWR Backup Manual Scram Capability " was issued on Decenter 17, 1980 to each boiling water i reactor facility holding a power reacter operating license or a j ~ construction permit. 4. Dresden Unit 2 - On December 2,1980, the continuous monitoring system (CMS) on the scram discharge volume (SDV) failed to respond as expected following i a normal reactor scram. The CMS had been recently instelled to detect the i presence of water in the SDV in accordan:e with a confinnatory order issued as a result of the Browns Ferry 3 partia: sc-an on June 28, 1980. At Dresden Unit 2, the CKS has been made cperatie a-t.gs teen tested. ny potential ~ l ceneric CMS or:blens are being resoi re: :. s- :nformation Not'ce issued on Decemoe-5,1970, and a Bulletin issse: :. :e:em:er 18, 1980: IE Supple-l men: 4 to Evile:in 80-17 " Failure c : <:-:* :ocs to :nser: During a ~ e Scram a a BWR". The Bulletin requires that testing be performed within 14 days to demonstrate CMS operability and that manual surveillance of the { SDV be resumed in the interim. Licensee actions will be verified by IE inspections. i i \\ 1 I ENCLOSURE E
l l. l ITEMS OF INTEREST OFFICE OF TNTUDIATTURRI PROGRAMS WELK ENDING DELtmutR 19, 1950 t US/IAEA Safeguards Agreement l I On Friday, December 12, representatives of DOE, ACDA, State, and NRC met to l l discuss a proposed interagency procedure for implementation of the US/IAEA l Safeguards Agreement. NRC representatives from NMSS, ELD, and IP presented l for consideration a revised version of an earlier ACDA draft. ACDA~ agreed to draft new language which would accommodate the concerns of all agencies. Transfer of Depleted Uranium Export Licensing Authority On December 16 the President signed legislation (H.R. 6942) which transfers export licensing authority for certain foms of depleted uranium from NRC to the Executive Branch. Under the legislation, the Cosmerce Department will assume export licensing authority over depleted uranium when fabricated into such items as countenweights and shielding. In addition the State Department Office of Munitions Control will assume export licensing authority over depleted uranium when fabricated into penetrators for munitions. Bulk depleted uranium will remain under NRC's export licensing authority. Duane Arnold Pumo Failure Notification to Japan and Spain This week IP sent notification to Japan and Spain concerning a pump problem of Duane Arnold NPP. IE Region III informed IP of the problem, a split ring failure of a Bryon Jackson High Pressure Core Injection (HPCI) booster pump. This failure rendered the high pressure injection train inoperable if called upon for operation. Similar Bryon Jackson pumps are in service at Fukushima 1 and Santa Maria de Garona NPPs. Siting Comments by the Geman RSK The RSK (the equivalent of ACRS in the Federal Republic of Gemany) advised during a recent visit that they would be submitting comments in December on the proosed NRC rulemaking on reactor siting. A. Jahns Executive Secretary of the RSK, advised R. Fraley, Executive Secretary of ACRS, this week that, due to unforeseen delays, these RSK comments will now be submitted by the end of January. U.S. Action Plan on IAEA Safeguards - Working Grouo Meeting Representatives from IP and NMSS adenEed a mee.tino of the Action Plan Working ~ ~~ Group on December 16 at the State Department. The principal focus of the meeting was on the review of an NRC-prepared draft revision of the Action Plan. The next meeting of the Group is scheduled for January 6,1981. ENCLOSURE H I
. Meeting With GA0 Represent;tives IP and HMSS representatives attended a meeting on December 17 with an official from GAO to discuss matters related to the question of NRC's safeguards and physical security infremation needs in connection with review of U.S. exports. We understand that the information will be' included in the final report to Congress in March 10,81 required by the NNPA. The draft of the reoort is expected to be completed and circulated to the appropriate agencies for comments sometime in January 1981. CISET Meeting On December 17 at the Department of State J. Lafleur, IP, attended a meeting of the Committee on International Science, Engineering, and Technology (CISET), an interagency group coordinating U.S. international scientific cooperation, under the Chairmanship of Assistant Secretary Pickering. The annual report to Congress (the " Title V Report") was discussed, as well as activities planned for the coming year. Meeting with REECo IP on December 15 met with A. Bickers, D. Vetter, and W. Nix of the Reynolds Electric and Engineering Company to discuss continued international participation in the Radiological Emergency Response Operations training course. The staff suggested adding more detailed coverage of the TMI emergency response and " hands on" experience in developing and evaluating energency plans (both strongly recom-mended by the first foreign participants) to the next international session. REEco was already working on the first and agreed to the second. Tentative i agreement was reached to schedule the next international session September 30 - October 9,1981. Meeting with INPO IP and RES met on December 10 with INPO representatives R. S. Smith and M. Bell to discuss the International Participants Progrrm which INPO is initiating in response to several requests they have received from foreign utilities and consulting firms. IP prtvided INPO with a list of our governmental arrangement administrators and suggested thst they be asked to identify the group (s) in their countries most representative of the actual plant operators with whom INPO wished to exchange operating experience information. (No onsite plant evaluations are contemplated in the foreseeable future.) The staff also identified other Federal agencies and contacts (State and DOE) which should be kept advised as work on INPO's international program proceeds. Foreign Visits to NRC On Monday Srs. Xavier Jardi and Jesus Tapia of La Agrupacion (a Spanish AE) met with W. S. Besaw, Director of TIDC/ADM, to discuss TERA and the automation of NRC licensing records. ENCLOSURE H I
l l' I 3-On Wednesday Mr. Makoto Sue, NHK Japan Broadcasting Corp., met with H. Faulkner, IP and F. Ingram, PA regarding the Corporation's plans to produce a TV series on i nuclear power. Plans are that the series will consist of 3 individual shows, one of which will address the subject of nuclear reactor safety. Mr. Sue was interested in learning, generally, of NRC activities and revisions to the LOFT test program in light of TMI. Japan Broad::asting plans to send a filming crew to the U.S. in March. If NRC assistance for filming and interviewing is desired, they will send a formal request. This week Mr. Hiromichi Hirayama, an inspector with the Safeguards Division'of the Nuclear Safety Bureau in Japan, is visiting NRC between his participat. ion in the Safeguards Technology training course at Los Alamos and the Physical Pro-i tection training course to be held at the Sandia Laboratories. Mr HirLyana is reviewing NRC documents related to the safety and environmental reviews of SARs and NRC procedures for obtaining comments from other government agencies and the public on licensing issues and proposed regulations related to nuclear power plant siting. IP is scheduling brief meetings in which Mr. Hirayama umy present questions for NRC staff response. l l l i I ENCLOSURE H l l I t
l 1 i ' l ! ) Fo.*eign Reports The following foreign reports were received at IP during the period of December 15 to 19. The ** indicates the reports are in English. For further information contact Eva Szent-Ivany (49-27788) IP. i From France
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EdF - General Planning for Operations - October 1,1983 From the FRG: i l GRS-A-511 DYNOT-S - A Code to Calculate the Dynamic Behavior of a i l Once-Through-Steam Generator Heated by Sodium - PROPRIETARY rom Italy: CNEN - Irradiation Testing of Oxide Fuel Pins for Fast Reactor Program: Results of the In-Pile and Post-Irradiation Examinations ** - Effect of Bleomycin on House Haemopoietic Colony Forming Cells in Culture (CFUc)** j Geophysical and Biological Phenomena as Earthouake Precursors From the U.K.: The Development of Models for the Transfer of 137CS AND 90Sr in the Pasture-Cow-Milk Pathway Using Fallout Data **, National Radiological Protection Board, Harwell From OECD-NEA: Event at Muehleberg on August 5,1980 - Underwater Lamo Lost in the Pressure Vessel ** i
- Deleted from PDR copy.
l l ENCLOSURE H l l
i I i 1 l l' s 4 J ] OFFICE OF STATE PROGRAMS ITEMS OF INTEREST l WEEK ENDING DECEMBER 19, 1980 On December 15 and 16, Robert E. Trojanowski, RSLO, Region II, i i participated in a Regional Advisory Committee meeting with j officials of the State of South Carolina to review the South l Carolina Emergency Plan. As a result of this meeting, the committee recommended to the State that their major exercise. I i scheduled for January 1981 be delayed until March 1981, to permit i j sufficient time to make necessary revisions. The State was i receptive to this request. William B. Menczer, RSLO, Region III, was in West Chicago on l 1 December 16, 1980, to inspect the Kerr McGee facilities and areas l of the city in which Thorium contamination was present. On j December 18, 1980, Mr. Menezer met with Philip Gustafson, the new director of the Illinois Department of Nuclear Safety,. and l with William O'Connor, Legal Counsel to the Governor, to discuss l NRC and State actions concerning decontamination of West Chicago. l On December 18, Thomas C. Elsasser, RSIC, Region I, attended the TMI citizens Advisory committee meeting in Barrisburg, PA. The major topic of discussion at the meeting was the TMI radio-active waste issue. i on December 12, 1980, Dean Kunihiro, RSLO, Region V, attended a j Western Interstate Energy Board sponsored meeting in Las Vegas i to develop regional solutions to management and disposal of low j level radioactive waste. A newly created group, the Western j Regional low Level Radioactive Waste Committee, will be chaired { by Dave Stevens of Washington State. Ralph DiSibio is the Vice Chairman. The Committee was orge.nized into two regional sub- { groups: north and south. The south regional working group to i deal with the question of siting and agreed that the only acceptable ] approach was a shared siting enemitaant. The north regional working group focused on the process of developing the compact i itself. It is anticipated that a two-day meeting be held in l February and that a draft compact document would be available at j i that time. l i i d d a i 3 ENCLOSURE'I j 4
1 ^ i i l OFFICE OF MANAGEENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING DECEMBER 19. 1980 i Annual Report Sent for Connission review 15 of 16 Annual Report Chapters and 6 Appendixes. Chapter 1 is due to be circulated for connent December 29. 1 1 1 l I l ENCLOSURE J l { i
i i i. I I j i OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK EllDING DECEMBER 19, 1980 AEOD recently completed a report entitled, "AEOD Observations and Recommendations Concerning the Problem of Steam Generator Overfill and Combined Primary and Secondary Side Blowdown." This report l discusses the implications and possible effects of failures in non-l safety-related balance-of-plant equipment which could result in steam i generator overfill situations, and potentially lead to combined primary i and secondary side blowdown. All but one of the recommendations in the report have already been acted upon. The report is now being distributed and forwarded for appropriate action and response by NRR. l l j ENCLOSURE L _ _ _ h I
SCHEDULED SPEAKING ENGAGEMENTS I Date Organization location Subject Speaker 1 3/26/81 22nd Annual Quality Clinic Knoxville, TN What the NRC Regulations W. Ruhlman, RO II Require from a QA Program 3/31/81 American Chemical Society Atlanta, GA Regulatory implications of H. Peterson, SD Radiation-Dose Effect Relationships 4/1/81 ' Spouses of Operating Staff Education Center Quality Assurance Requirements A. Cerne, RO I at Seabrook Station Seabrook, NH and Licensing Procedures Related to Seabrook Station 6 d i 4 s a m ---_.__*----2,-._,.--w.-.-r. r,- e. -,,.-.-..e-----+----.. ,-.-..-v.-. -w----.,
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING DECEMBER 19, 1980 l A. EXCERPT OF STAFF REQUIREMENTS - AFFIRMATION SESSION 80-54, 3:10 P.M., THURSDAY, DECEMBER 11, 1980, COMMISSIONER 5' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks, 12/15/80. I. SECY-80-448 - Proposed Narrative Explanation of Table S-3 The Comission by a vote of 3-0 (Commissioner Gilinsky abstaining) approved a proposed explanatory narrative for Table S-3. Table of. Uranium Fuel Cycle Environmental Data, and a proposed rule announcing the publi-cation of the draft narrative and conditions for the Table's use. Comissioner Bradford concurred in part and dissented in part, as noted in his separate views. The Comission requested that staff revise the proposed explanatory narrative and proposed rule as follows: a. page 8 of the proposed rule should be revised to reflect the following 9 paragraph modified to include an exception for radon and technetium: No further consideration of fuel cycle impacts addressed by the table and the narrative would be required or allowed in individual licensing proceedings. i Table S-3 and the material in the narrative would be referenced as support for a generic conclusion that i these fuel cycle impacts cannot affect significantly i the cost-benefit balance for a reactor. l b. modify page 4 of the narrative as indicated in Attachment 1; c. delete page 10, beginning with Section E, through page 26 of the narrative (references on pages 27-28 should be modified accordingly); d. revise the discussion on page 57 of the narrative making clear that the tendency to overestimate effects resulting from use of the linear hypothesis applies only to the low-LET radiation. A discussion should be added similar to that on page 5. first paragraph, in the 7/14/80 memo, W. Dircks to Commissioner Bradford; page 59 of the narrative should be revised to include the probabiikty e. of risk associated with operating reactors and projected reactors over their lifetimes; f. clarify or delete the following statement found on page 68 of the narrative: "After 100,000 years, the waste in the repository presents no greater hazard than the original materials charged to the reactor."; ENCLOSURE N ~l
i i i a f' i { 1 i 1 l A. (continued) ~ g. modify ages 70-78 of the narrative as indicated in Attachment 2; i and 4 i h. the numbers from staff's table titled " Estimated Risks of Cancer and Genetic Effects" (Attachment 3) should be included in the narrative. i The numbers should be changed to be consistent with the capacity factor used in the narrative. j (NMSS - SECY suspense - 1/26-81) Commissioner Bradford noted that' he will be providing separate views which will be available at least three days before the deadline for i publication. 1 STAFF REQUIREMENTS - BRIEFING ON TVA'S ACTIVITIES IN EMERGENCY OFFSITE FACILITIES, l B. j 2:05 P.M., WEDNESDAY, DECEMBER 17, 1980, COPNISSIONERS' CONttMENCE ROOM, D.C. 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to Dircks, dtd 12/18/80. 3 i i 1 The Commission was briefed by TVA representatives L. Mills, J. Hufham, and E. Sliger on TVA's Activities in Emergency Offsite Facilities. Also present were Sam Slone - Director, Civil Defense Dept. for the State of f Alabama and John Keese, of the Civil Defense & Emergency Planning for t,he State of Tennessee. 1 j The Commission requested that staff provide its reflections on the briefing, specifically. commenting on: a. the acceptability of the TVA proposal to centralize emergency t offsite facilities for the entire TVA system; and b. the applicability of the TVA concept for other multi-site licensees. l (IE) (SECYSuspence1/9/81) t C. STAFF REQUIREMENTS - BRIEFING ON SECY-80-511 - STORAGE OF LOW-LEVEL RADI0 ACTIVE j WASTES AT POWER REACTOR SITES,1:30 P.M., WEDNESDAY, DECEMBER 10, 1980, i COPMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC AlltNDANCE) Memo for the Record, dtd 12/18/80. The Commission was briefed on the storage of low-level radioactive waste at. power reactor sites as currently being implemented at the TVA and how their process might apply to other low-level disposal sites throughout the country. There were no requests or staff requirements from this meeting. 1 ENCLOSURE N l l l I
D. SECY-80-494 - PROPOSED EXPORT OF FIVE KILOGRAMS OF HEAVY WATER TO INDIA (XMAT0146) (COMMISSIONER ACTION ITEM) Memo SECY to Dircks, dtd 12/19/80. This is to advise you that the Commissioners have reviewed the subject license to Aldrich Chemical Company, Inc. The Commission (with three Co::imissioners approving) has accepted your recommendation to export to India 5 kilograms of heavy water. Commissioner Gilinsky did not participate in this action. The Office of Internat.ional Programs was informed of this action by telephone on December 19, 1980. E. SECY-80 482 - PETITION FOR RULEMAKING FROM PUBLIC CITIZEN LITIGATION GROUP ON REQUIRED LEVELS OF FINANCIAL PROTECTION. Memo SECY to Dircks, dtd 12/19/F0 - Attached is the vote sheet from Chaiman Ahearne which is to be used as a guide in revising the Federal Register Notice to address more directly(Attach-Congressman Udall's and the California Energy Comission's coments. ment not included.) F. SUPPLEMENTAL STAFF REQUIREMENTS - AFFIRMATION SESSION 80-54, 3:10 P.M., THURSDAY, DECEMBER 11, 1980, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Kamerer, dtd 12/19/80. III. SECY-80-482 - Petition for Rulemakino from Public Citizen Litication Groue on Recuired Levels of Financial Protection The Comission by a vote of 3-1, with Commissioner Bradford dissenting, denied a petition by the Public Citizen Litigation Group to amend Part 140 to increase the amount of prinary financial protection required of persons licensed to operate reactors with a rated capacity of 100 Mw(e) or more from $160 million to $460 million. The Commission ty a vote of 3-1, with Chairman Ahearne dissenting, also decided that the agency should seriously explore with the nuclear insurance industry the potential for increased liability coverage. (EDO) (SECY Suspense: 2/7/81) The Comission reouested that: 1. staff revise the Federal Register Notice to address more directly Congressman Udall's and the California Energy Comission's comments. The following separate view should be attached to the Federal Register Notice: "Comissioner Bradford believes that a rulemaking on some Price-Anderson subjects raised in the comments would have been in order." (NRR) (SECY Suspense: 12/31/80) 2. a letter be sent to the Public Citizen Litigation Group informing them of the denial; and (NRR) (SECY Suspense: 12/31/80) 3. a letter be sent to the appropriate Congressional subcomittees infoming them of the denial. (OCA/NRR) (SECY Suspense: 12/31/80) ENCLOSURE N .}}