ML19281B682
| ML19281B682 | |
| Person / Time | |
|---|---|
| Issue date: | 04/18/1979 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-790413, NUDOCS 7905300648 | |
| Download: ML19281B682 (30) | |
Text
h April 18,1979 For:
The Comissioners From:
T. A. Rehm, Assistant to the Executive Director for Operations
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 13, 1979 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 B
Standards Development C
Nuclear Material Safety and Safeguards 0
Inspection and Enforcement E
Nuclear Regulatory Research F
Executive Legal Director G
International Programs H
State Programs I
Management and Program Analysis J
Controller K*
Calendar of Significant Events L
Items Approved by the Comiss son M*
Calendar of Speaking Engagements N
Status of Nuclear Power Plants 0
f T.A.Rh M
Asdev to the Executive Director for Operations
Contact:
T. A. Rehm 790530062(3 49-27781
- No input this week
- Deleted from Commissioners and PDR copy
WEEKLY INFORMATION
SUMMARY
Week Ending April 13, 1979 Point Beach Units 1 and 2 Authorization was granted April 4 to increase the storage cacacity of the spent fuel pool from 351 to 1502 spent fuel assemblies.
La Crosse The licensee notified NRC that they discovered some failed fuel during the current reload outage. The licensee is inspecting all assemblies and will notify us in a few days of their findings.
Eoidemiologic Studies Related to Three Mile Island NRC met with HEW, the Pennsylvania Departnent of Health and the National Cancer Institute to discuss.possible epidemiologic studies related to the incident at Three Mile Island.
It was agreed that since the reported radiation exposures to the population were so small, there may be little
.value for a radiation epidemiology study.
Uranium Mine and Mill FES Comoleted The Final Environmental Statement for the proposed Pitch Project Uranium Mine and Mill in Colorado has been completed by NRC.
Kerr-McGee West Chicaco, Illinois Facility Kerr-McGee is redoing tneir decommissioning plan for the West Chicago, Illinois Facility because NRC found the initial plan unacceptable.
The Mayor of West Chicago stated that a petition was being sent to Washington, D.C.
(possibly NRC) demanding that some action be taken.
Issuance of Order An Order to Show Cause (Immediately Effective) was issued on April 6 to 18 owners / users of the Model No. NFS-4 cackagings believed to be defective.
Emergency Preparedness On April 16, SP will testify at a hearing on emergency response to nuclear power plant accidents.
The hearing is being held by the California Legislature Subcommittee on Energy.
OFFICE OF ADMINISTRATION Week Ending April 13, 1979 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Reouest Initial Decision Received 146 13 Granted 66 2
Denied 23 4
Pending 57 7
ACTIONS THIS WEEK Received Ellyn R. Weiss, Requests all communications between NRC Sheldon, Harmon, Roisman Headquarters, Region I, and Metropolitan Edison, and Weiss, on behalf of UCS regarding the Three Mile Island Unit 2 accident, (79-100) and copies of the project managers' log books.
Michael Petruska, Requests a copy of a report describing nature of State College, PA work performed in the Breazeale reactor at Penn (79-101)
State University, a summary of precautions taken to ensure safe operation, and any accident evacuation plans.
Ellyn R. Weiss, Requests transcripts of all closed Corm 11ssion Sheldon, Harmon, Roisman meetings from March 28, 1979.
and Weiss, on behalf of UCS (79-102)
Theodore J. Lowi and Requests all files maintained under the name of Kathleen A. Selvaggio Cornell University or any of its personnel, New York Civil Liberties including all documents relating to past or Union present contractual agreements or arrangements (79-103) from 1968.
Thomas B. Cochran, Requests all documents related to the development, Natural Pesources construction, manufacture, sale, or export of Defense Council, Inc.
high explosive implosion devices and related (79-104) hardware for research, development, and commercial purposes, other than those related exclusively to weapons research and development, since 1950.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A
2 Received, Cont'd Robert Schakne, Requests copies of the examinations and test CBS News scores for two named Reactor Operators and (79-105) two named Senior Reactor Operators at Three Mile Island.
peter G. Gosselin, Requests that reportable events or abnormal The Transcript occurrences reports for the Yankee Rowe plant
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(79-106) from 1960 to 1966 be placed in the LPDR.
Martin 0. Cohen, Requests a copy of the proposal by Science Mathematical Applications Applications, Inc. submitted to the NRC in Group, Inc.
response to RFP RS-RES-78-193, Amendment 1, and (79-107) any modifications.
Dennis Sanders, Requests a copy of Dr. Hanauer's " nugget file".
(79-108)
Ellyn R. Weiss, Requests each document in Dr. Hanauer's "chron Sheldon, Harmon, Roisman file" from April, 1976 to present.
and Weiss, on behalf of UCS (79-109)
Stephen M. Feldman,
. Requests information regarding " Thorotrast" Feldman & Feldman (thorium dioxide), its licensing, manufacturers, (79-110) and licensees.
Richard Ben Cramer, Requests all transcripts and/or reports of NRC Knight-Ridder Newspapers staff interviews with personnel at Three Mile (79-111)
Island, and the text and attachments to report by Metropolitan Edison's Internal Investigation Committee, as provided to the NRC.
Rex Hunter, Requests the final report on the SL-1 accident (79-112) at the U.S. National Reactor Testing Station, in Idaho Falls, Idaho in January,1961.
Dean Hansell, Requests all documents regarding the State of Illinois decommissioning of the Elk River, Minnesota (79-113) reactor and the shipment of the decomissioned material to the Sheffield, Illinois low-level nuclear waste site.
Neil Robinson, Requests all documents regarding nuclear reactors Deseret News and/or other nuclear projects at the University (79-114) of Utah.
ENCLOSURE A
3 Received, Cont'd (An individual requesting Requests the results of the tests and information about himself) examinations as a result of an accident involving (79-115) radiation exposure at the Nevada Test Site in 1963.
A. Kranish, APPEAL TO THE COMMISSION AND TO THE ED0 the Trends Publishing, Inc.
denial of portions of documents 7, 9, and 99 (79-A-6-77-106) of the Task force on Allegations by James Conran, except statistical and other numerical data which may have been withheld.
(An NRC employee)
APPEAL TO THE COMMISSION the denial of a document (79-A-7-79-78) concerning the disposition of the investigation of [an NRC employee] by OIA.
Granted Elaine B. Schwelm, In response to a request for documents relating Nuclear Engineering to the development of Section 20.302(b) of the Company, Inc.
Comission's regulations, made available 11 (79-65) documents.
George R. Zachar, In response to a request for documents pertaining Critical Mass Journal to attempted and/or successful sabotage efforts (79-72) at nuclear facilities, made available a list of threats to licensed nuclear facilities and informed the requester other documents subject to this request are located in the PDR.
Winnifred F. Sullivan, In response to a request for documents Keck, Mahin & Cate concerning delays in construction of the LaSalle (79-75) plant, and information regarding contracts to reload fuel, made available 20 documents, and informed the requester other documents subject to this request are available at the Region III office.
Nancy Kesler, In response to a request for access to licensee The News-Journal Company event reports, inspection reports, and the (79-83) evacuation plan for the Salem plant, informed the requester the documents subject to this request are located at the NRC Local Public Document Room in the Salem Free Public Library, Salem, New Jersey.
ENCLOSURE A
4 Granted, Cent'd William G. Margetts, In response to a request for a copy of a mailing Government R&D Report list maintained by the NRC for public (79-90) announcements to the research and development community, sent a copy of NUREG-0550, Revision 1,
" Standard Distribution for Unclassified U.S. NRC Publications", January 1979.
Barbara J. Bensel.
In response to requests for a list of the names FOI Services, Inc.
and addresses of " companies doing radiation (79-91 & 79-92) sterilization in Puerto Rico" and a list of companies " licensed to build facilities for radiation sterilization in Puerto Rico", informed the requester the NRC has no records subject to her requests.
Denied (An NRC employee)
In response to a request for a copy of the (79-78) disposition of the investigation of [an NRC employee] by OIA, and the final action taken by the Comnission on this matter, denied one document in its entirety, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
ENCLOSURE A
DIVISION OF CONTRACTS Week Ending April 13, 1979 PENDING COMPETITIVE RE0VIREMENTS 1.
RFP RS-RES-79-193 Title - Steam Generator Tube Rupture Iodine Transport Mechanisms Description - Under Task I, the contractor shall experimentally measure the amount of atomization and characterize the drop size distribution of superheated water flashing through a crack-like orifice into a saturated steam environment.
Period of Performance - One year Sponsor - Office of Nuclear Regulatory Research Status - Solicitation to be issued on or about April 30, 1979.
Due date for submission of proposals - May 31, 1979.
2.
RFP RS-0IE-79-261 Title - General and Refresher Courses in Concrete Technology and Codes Description - This technical assistance is required by the Office i
of Inspection and Enforcement to provide NRC personnel the detailed training in concrete technology and the applicable codes necessary to permit them to conduct in-depth inspection at NRC licensed facilities under construction or modification.
Period of Performance - Eighteen months Sponsor - Office of Inspection and Enforcement Status - Solicitaticn being developed.
PROPOSALS UNDER EVALUATION 1.
RFP RS-NMS-79-028 Title - Development of Improved Techniques for Analyzing Material Control and Accounting Data Description - Assist the NRC in applying the inventory difference simulation model to two major operating strategic special nuclear material fuel cycle facilities designated by the NRC.
Period of Performance - Eight and one-half months Sponsor - Office of Nuclear Material Safety and Safeguards Status - Best and Final Offers received April 3, 1979.
Revised proposals sent to panel mecbers for evaluation April 4,1979.
ENCLOSURE A
A 2.
RFP RS-NRR-79-134 Title - Tearing Stability Analyses for Light Water Reactor Piping Description - The contractor shall perform elastic-plastic tearing stability analyses for LWR piping using various anticipated and postulated flow sizes and stress conditions. The NRC will use the results of this program to determine if unstable ductile crack extension will occur for the anticipated and postu-lated flow and stress conditions for LWR piping.
Period of Performance - One and one-half years Sponsor - Office of Nuclear Reactor Regulation Status - Proposals submitted to panel for evaluation on April 10, 1979.
CONTRACTS CLOSED OUT (All administrative action complete and final payment made)
I Contract No.
Oraanization Close Out Date i
AT(49-24)-0128 Rand Corp.
04/06/79 5
AT(49-24)-0228 Lulejian & Assoc.
04/06/79 AT(49-24)-0040 Charles River Assoc.
03/21/79 AT(49-24)-0001 Charles River Assoc.
03/21/79 NRC-02-77-150 TRW, Inc.
01/29/79 NRC-02-77-086 R&D Assoc.
01/29/79 ENCLOSURE A
ITEMS OF INTEREST DIVISION OF SECURITY WEEK ENDING APRIL 13, 1979 On April 9, 1979, a representative of the Division of Security accompanied representatives of the Office of Nuclear Reactor Regulation (NRR) to Fort St. Vrain, Denver, Colorado in order to discuss proposed 10CFR Parts 95 and 25 and their potential impact on the Licensee and their security program.
During the first quarter of 1979, the Information Security Branch expended over 800 manhours conducting classification /declassifica-tion of over 8,500 pages of information. A major portion of these 8,500 pages of information was subject to Freedom of Information Act Requests.
?
I i
1 ENCLOSURE A
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DIVISION OF TECHNICA!. INFORMATION AND DOCUMENT CONTROL
- Week Ending April 13, 1979 TRANSLATIONS l
5
- Tnis entry deleted from PDR copy.
ENCLOSURE A
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OFFICE OF NUCLEAR REACTOR REGULATION WEEKLY ITEMS OF INTEREST (Week Ending April 13,1979)
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Point Beach Units 1 aNi 2
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Authorization was granted April 4,1979 to increase the storage capacity of the spent fuel pool from 351 to 1502 spent fuel assemblies.
A hearing was originally scheduled on this matter, but was dismissed when ~a settlement agreement was entered into among intervenor (Lakeshore Citizens for Safe Energy),, licensee (Wisconsin Electric Power Company) and the NRC staff.
St. Lucie Unit 1 Contrary to earlier plans Florida Power & Light company has notified us that they do not plan to chemically clean the St. Lucie steam generators during the upcoming refueling outage. They believe that further testing is required to support the feasibility and to justify the expense of chemical cleaning, la Crosse OI&E Region III notified the Project Manager on 4/6/79 that the licensee has discovered some failed fuel during the current reload outage.
The first fuel assembly removed from the core had a six inch length of a fuel pin missing. The licensee thought it was damaged during removal. The missing piece is. thought to be retrievable. The assembly has a relatively high burnup (514,500 MWD /HTU); it was scheduled to be removed from the core this refueling.
Several other assemblies show some signs of degradation. The licensee is continuing to inspect all assemblies and will notify us in a few days of their findings.
ENCLOSURE B
0FFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING APRIL 13, 1979 1.
Eoidemiologic Studies Related to Three Mile Island Incident: On April 5,1979, Robert Goldsmith and Robert Baker met with Dr. Gary Stein of the Center for Disease Control, HEW, and Dr. George Tokuhata of the Pennsylvania Department of Health to discuss possible epidemiologic studies related to the incident at Three Mile Island. The preliminary plan developed by Dr. Tokuhata includes the following aspects:
A.
Development of an " impact area population registry" including all persons residing within a five-mile radius of the plant.
A " control registry" including persons residing some 50 miles upstream will also be developed.
3 Planned observational studies of health impacts including:
(1) pregnancy outcome (2) mortality among the aged (3) cytogenetic studies of fetal wastage (4) follow-up of infants (5) possible psychological / stress effects.
It was stressed that the doses received by the population were too low to be able to detect radiation-related health effects. However, the proposed studies would assess health effects due to the incident, per se, with potential application of future emergency planning.
Additional funding is required for these studies and the possibility of financial backing from the Federal government (particularly HEW or NRC) was discussed.
On April 6,1979 another meeting was held at the National Cancer Institute's (NCI) offices in Bethesda to discuss the possible followup studies.
The meeting was requested by Mark Nelson, CDC. Attending were Mark Nelson, CDC; Marvin Rosenstein, FDA/BRH; Charles Land and John Boice, NCI; and Michael Parsont and Robert Goldsmith, SD.
It was the consensus of the attendees that, since the reported radiation exposures to the population in the area were so small, that there may be little value for a radiation epidemiology study.
If any radiation studies were to be performed, however, the emphasis should be on dosimetry.
[
Contact:
R. Goldsmith]
ENCLOSURE C
- 2.
Meetino of NRC/ DOT /FHWA/FERC Staff on Seismic Criteria for LNG Facilities: On April 9,1979, at the request of the Department of Transportation, a meeting was held between NRC, D0T, Federal Highway Administration, and the Federal Energy Regulatory Commission staff. The purpose of the meeting was to open staff level exchange of technical information on seismic issues. The meeting focused on the seismic aspects of a proposed D0T regulation on Liquified Natural Gas (LNG) facilities published in the Federal Register on February 8,1979. Several major differences exist between the D0T and NRC rules. The most substantive being the emphasis given in the DOT rule on the use of probabilistic analysis.
A major concern expressed by the NRC staff in using such analysis is the need for adequate data and more rigorous guidance to implement the procedures in the rule. The 00T staff expressed a desire for additional meetings with the NRC staff and indicated that they plan to request through appropriate channels official NRC comments on their proposed rule.
[
Contact:
G. Robbins]
3.
Publication of Proposed Rule on Radiation Safety Committees for Hosoitals:
On April 9,1979 a proposed amendment to Part 35 was published in the Federal Register that would require hospitals to appoint a radiation safety committee rather than the presently required medical isotopes committee, the croposed radiation safety comnittee would focus on radiation safety and have a simplified membership which would be easier to recruit for smaller hospitals.
The 60-day comment period ends on June 8,1979.
[
Contact:
Ed Podolak]
4.
On April 10, 1979, staff from SD and NMSS, together with representatives from the Department of Energy and Department of Transportation, met with Dr. Rudi Neider, principal organizer of the 6th International Symposium on Packaging and Transportation of Radioactive Material (PATRAM '80) to be held in Berlin, FRG on November 10-14, 1980.
Dr. Neider is from the Bundesanstalt fur Material Prufung (BAM),
the German equivalent of our National Bureau of Standards. Both DOE and DOT expect to actively participate in the planning, preparation, and operation of the Symposium. NRC representatives tentatively declined the informal invitation to actively participate in the planning phase.
SD staff met April 11, 1979, with Mary Daly, U. S. Attorney representing NRC and other Federal agencies in a 1975 lawsuit brought by New York State to halt the air transportation of special nuclear material.
Ms. Daly is the new principal attorney on this case, and was seeking background information on the case and details concerning areas at issue.
ENCLOSURE C D
. Publications Issued During the Week of April 9-13, 1979 Reg. Guide 3.43 Rev.1 - Nuclear Criticality Safety in the Storage of Fissile Materials [ Issued to Reflect Comments]
Division 2 - Research and Test Reactors - Table of Contents Reculatorv Guides to be Issued in the Near Future 1.
Title:
Qualification Tests of Electric Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants (Reg. Guide 1.131, Rev.1)
Expected Issuance Date:
June 1979
==
Description:==
Describes a method acceptable to the NRC staff for complying with the Commission's regulation with regard to qualification testing of electric cables and field splices for service in light-water-cooled nuclear power plants to assure that the cables, and connections can perform their safety-related
-functions. The fire test provisions of this guide do not apply to qualification for an installed configuration.
Contact:
A. S. Hintze 443-5913 2.
Title:
A-C Power Systems (Onsite) - Rev. 2 to SRP Section 8.3.1 Expected Issuance Date:
June 1979 Descriotica: Standard Review Plan (SRP) 8.3.1, "A-C Power Systems (Onsite)" includes those power sources, distribution systems, and vital supporting systems provided to supply power to safety-related equipment and capable of operating independently of the offsite power system.
Contact:
A. S. Hintze 443-5913 ENCLOSURE C 9
3.
Title:
Selection, Design, and Qualification of Diesel-Generator Units Used As Standby (Onsite) Electric Power Systems at Nuclear Power Plants (Reg. Guide 1.9, Rev. 2)
Exoected Issuance Date: August 1979
==
Description:==
This guide describes a method acceptable to the NRC staff for complying with the Commission's requirements that diesel-generator units intended for use as onsite power sources in nuclear power plants be selected with sufficient capacity and be qualified for this service.
Contact:
A. S. Hintze 443-5913 ENCLDSURE C
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending Acril 13, 1979 Homestake FES Completed The Final Environmental Statement for Homestake Mining Company's proposed Pitch Project Uranium Mine and Mill, Saguache County, Colorado, has been completed by the Uranium Recovery Licensing Branch and sent to the U.S.
Forest Service who will publish the statement.
The statement was prepared by NRC staff in response to requests by the Forest Service and the state of Colorado. The proposed 600-ton per day mill will use a carbonate leach process to extract the uranium.
The mill tailings will be buried on-site at the head end of a natural valley. The statement includes recommended conditions for stabilization and reclamation of the tailings area and decommissioning of the mill site as well as other conditions for the protection of the environment.
Meetina re Draft NRC Hich-Level Waste Procram Plan On April 6,1979, J. B. Martin and J. C. Malaro met with Dave Moeller and Steve Larowski (ACRS) to discuss the draft NRC High-Level Waste Management Program Plan. The discussion was in preparation of a presentation of the plan to the ACRS Waste Management Subcommittee at their April 18-20, 1979, meeting in Richland, Washington. Copies of the draft plan have been sent to members of the ACRS Subcommittee for their review and comments.
Maxey Flats Site The state of Kentucky has advised NECO that they do not wish to renew their contract to operate the Maxey Flats site (expires June 30,1979).
The Finance Resource Department of Kentucky contacted the Low-Level Waste Licensing Branch for a list of our BOA contractors. The names of the firms on the list qualified for all tasks were provided, however, specific recommendations relative to the quality of each firms' work performance was not.
Kentucky plans to solicit bids from NEC0, Chem Nuclear, Dames & Moore, NUS, and some of the firms on our BOA list within the next few weeks.
ENCLOSURE D
Items of Interest 2
Kerr-McGee West Chicaco, Illinois Facility A meeting was held on April 10, 1979, with representatives of Kee-McGee Chemical Corporation (led by Mr. J. L. Reiney, President) to discuss the decommissioning plan for the West Chicago, Illinois site submitted to us in December 1978.
Kerr-McGee was informed that the decornissioning plan was unacceptable and would have to be redone. A schedule for resubmission of the plan will be developed after Kerr-McGee has time to review the comments and to define the work needed to meet our requirements.
The Mayor of West Chicago, Illinois, was informed of the status of the Kerr-McGee submittal and he stated that he had instructed the city attorney to take appropriate legal action against Kerr-McGee.
He also stated that a petition signed by approximately 1,000 concerned i
citizens was being sent to Washington, D. C., demanding that some action be taken.
He did not know whether it was going to Congress, EPA or NRC, but he assumed it would end up at NRC.
VisitbyFRGRepresentatives(April 10-li,1979)
Members of the Division of Safeguards met with two representatives of the FRG Ministry of the Interior to discuss areas of mutual interest regarding transportation of spent reactor fuel and research related to sabotage vulnerability of spent fuel shipping casks. Additional dis-cussions were held pertaining to the broader areas of material accounting, physical protection, and international safeguards.
Peer Review of Use of Stratecic Analysis Dr. Ralph Lumb, NUSAC, presented the findings and recommendations of the Peer Review Panel en application of Strategic Analysis to material control and accounting. Dr. Lumb distributed a draft copy of the conclusions and recommendations of a consensus report of the Peer Review Group.
The final report will be deli'vered to the NRC on April 15 for publica tion.
The conclusion of the Review Group was that game-theory should have broad utility in the safeguards program.
The present formulation, however, is not sufficiently convincing in composition and behavior to be suitable for application at this time.
There needs to be a research, development, test and evaluation effort oriented toward the ENCLOSURE D
Items of Interest 3
development of a convincing game-theoretic approach with an understanding of the sensitivity of each component in the formulation that contributes to the solution. Tne Peer Review Group recommended that NRC take steps to improve the game thcory as a decision making tool. The group felt even if the attempt to develop game theoretic approach fails to yield a fully operational method, the effort will at least force the systematic and logical assessment of how NRC should employ information from material accounting in determining what action to take in response to an inventory difference.
l Issuance of Order An Order to Show Cause (Immediately Effective) was issued on April 6,1979, to eighteen (18) owners / users of the Model No. NFS-4 packagings suspending the general license for their use. During a meeting on March 28, 1979, NMSS was informed by Nuclear Assurance Corporation (NAC) that a cask NAC sold to Duke Power Company has one or more shells which is warped or bowed in an apparent violation of NRC Certificate of Compliance No. 6698. The safety implications of this reported defect are not known; however, this could represent a substantial reduction in the effectiveness of the packag-ing.
The order also requires the owner / user to evaluate deviations from the approved design, and Comission approval prior to returning of the packagings to service. A meeting has been scheduled for April 17, 1979, to discuss planned physical measurements with NAC, Nuclear Fuel Services, Duke Power Company, I&E, and NMSS.
Misadministration On April 6,1979, NMSS received a telephone report from a consultant /
physicist that a patient being treated for bone metastases had been given 3 millicuries of phosphorus-32 as collodial chromic phosphate, rather than the intended soluble phosphate. The absorbed dose to the liver, the organ in which the colloid form concentrates, is estimated to be about 900 rads.
The patient has been informed of the misadmini-stration.
The radioactive drug was properly labeled by the manufacturer.
The physicist would not identify the name of the hospital.
On April 11, 1979, an NRC staff member telephoned the hospital at which it was believed the incident occurred and the hospital staff confirmed that a misadministraticn had occurred.
On April 13, 1979, an NRC staff member visited the hospital. The initial telephone report to Headquarters on the morning of April 13 was that the hospital personnel denied the mis-administration occurred at the hospital and that a review of the records does not indicate a misadministration.
The NRC staff member is continuing to look into the matter.
ENCLOSURE D
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OFFICE OF INSPECTION AND ENFORCEtiENT Items of Interest Week Ending April 13, 1979 1.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-79-67K through 67T Three fiile Island Unit 2 - Nuclear Incident at Three tiile Island Unit 2 - These Preliminary Notifications were issued to provide updated status information regarding the incident.
b.
PNO-79-75 Lacrosse - Abnormal Fuel Cladding Degradation - During removal of a fuel assembly, a 6-inch section of fuel pin fell out of the assembly and lodged upon another fuel assembly.
(Closed.
See PNO-79-80, below) c.
PNO-79-76 Farley Unit 1 - Injury to Workman in Containment Building -
A pipe engineer working in the Unit 1 containment building fell 38 feet. Unit 1 has been in cold shutdown for refueling for about 30 days. The worker was taken to a hospital and was subsequently released.
He has returned to work.
(Closed) d.
PNO-79-70 (tiisnumbered) Crystal River Unit 3 - Unanticipated Load
. Reduction - While operating at 100% power, leakage from one reactor coolant pump increased. The pump was shut down and power reduced to 75%. When the licensee subsequently attempted to change the turbine load limiter control from 100% to 75%, the load limiter instantaneously dropped to zero demand. This resulted in an unex-pected down-ramp of turbine control valves and electrical output decreased from 600 to 150 tiwe.
Reactor pressure rose to 2250 psig and was quickly reduced to 1970 psig by the pressurizer relief valves.
The pressurizer stabilized at 2100 psig in about two minutes. The main steam safety valves opened to relieve excess secondary steam pressure.
During the transient, a 65-inch swing in pressurizer level was experienced. All safety features functioned as expected. The licensee plans to continue operation at 75% power until the refueling outage on April 24, 1979 when the turbine load limiter and the pump seal will be repaired.
(Closed) e.
PNO-79-77(NRR) Review of Operational and System Problems Identified During the Three tiile Island Incident - It has been determined that in some Westinghouse designed facilities, coincident low pressurizer pressure and low pressurizer level signals are required to actuate safety injection.
In addition, preliminary analyses of a small break in the pressurizer indicate that pressurizer level may remain high while pressurizer pressure continues to decrease.
In such a case, safety injection would not automatically occur, and reliance by the operator on pressurizer level could possibly lead to erroneous actions.
On April 7, 1979, Westinghouse advised owners of plants of this information.
(Closed)
ENCLOSURE E f.
PNO-79-78 Indian Point Unit 3 - Unit Shutdown Due to a Feedwater Valve Malfunction - On April 10,1979, Unit 3 shut down due to a feedwater regulating valve malfunction which caused the reactor to trip as a result of low steam generator water level. All systems functioned normally. The cause of the valve malfunction was a crack in the 1/4" instrument air line between the signal converter ano the valve positioner. Repairs were made and the unit was restarted.
(Closed) g.
PNO-79-79 Abbott Laboratories, North Chicago, Illinois - Lost Source of Nominal 0.992 Millicuries of Iodine-125 During Shioment -
The licensee reported that a shipment of about one millicurie of iodine-125 in liquid form was apparently lost. The material was shipped from the licensee's facilities on March 19, 1979. The material was consigned to the Charleston Area Medical Center, Charleston, West Virginia.
It is suspected that the shipment was delivered to another hospital in the Charleston, West Virginia area and has not been reported.
Efforts to locate the shipment have been unsuccessful.
(Closed) i h.
PNO-79-80 Lacrosse - Abnormal Fuel Cladding Degradation - A second section of a fuel pin fell out of an fuel assembly when removing the fuel assembly.
(See PNO-79-75.) Both fuel pin sections have been recovered. Six other assemblies had visual indications of cracking and three had possible cracking indications. All fuel with defects will not be reinstalled in the core. The licensee plans to meet with NRR to discuss this matter.
(Closed) i.
PNS-79-29 Diablo Canyon Units 1 & 2 - Bomb Threat - No bombs were found and none exploded.
(Closed) j.
PNS-79-30 Hartsville Nuclear Plant - Bomb Threat - No bombs were found and none exploded.
(Closed) k.
PNS-79-31 LaSalle - Bomb Threat - No bombs were found and none exploded.
(Closed) 1.
PNS-79-32 Diablo Canyon Units 1 & 2 - Bomb Threat - No bombs were found and none exploded.
(Closed) 2.
IE Bulletin 79-06, " Review of Operations Errors and System Misalignments Identified During the Three Mile Island Incident," was issued on April 11, 1979, to all pressurized water power reactor facilities with an operating license except B&W facilities.
ENCLOSURE E
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OFFICE OF NUCLEAR REGULATORY RESEARCH Important Items - Week Ending April 14, 1979 Power Burst Facility The Power Burst Facility performed three nuclear blowdown tests to scope the expected behavior of LOFT reactor fuel elements in planned LOTT tests L2-3, L2-5 and L2-4.
Pretest predictions suggested increasingly severe clad overheating and collapse of the unpressurized LOFT fuel red cladding during the blowdown portions of the three LOTT tests, but measured peak clad temperatures were 180"F to 360*F below predicted peak clad temperatures. There was very ~little evidence of clad damage to the unpressuri'ed rods even at the most severe test conditions.
The three PSF tests are described as follows:
FBF test LLR-3 was run at peak rod powers of 40kW/m (12 kW/ft) and with the same peak rod power. loop depressurization cycle and reactor scram time that is planned for LOFT test L2-3.
The peak clad temperatures of the four LLR-3 test fuel rods ranged from 1230*F to 1305"F, about 180"F lower than pretest calculations had predicted.
Based on these test results, the unpressuri:ed LOFT fuel rods would undergo little, if any, damage at this peak clad temperature for the planned LOFT icop depressurization cycle.
FSF test LLR-5 was then run at peak rod powers of 40kW/m (12 kW/ft) but reactcr scram was delayed until two seconds after the initiation of blowdcwn, in order to increase the fuel rod stored energies and peak clad temperatures.
This is the same set of test conditions planned for LOFT test L2-5. The peak clad temperatures of the four LLR-5 test fuel rods ranged from 1340*F to 1375'F also about 180*F lower than predicted and low enough that an unpressurized LOFT rod subjected to the same loop pressure-clad temperature cycle would undergo very little clad damage.
ENCLOSURE F
2 PBF test LLR-4 was run at peak rod powers of 53kW/m (16kW/ft) and with reactor scram delayed until three seconds af ter the initiation of blowdown.
PBF test LLR-4 is the companion test to the planned LOFT test L2-4, but without delayed scram in L2-4.
The peak clad temperatures of the Lt.R-4 test rods were from 1565"F to 1065"F, about 270*F lower than had been predicted. There was, however, an unplanned coulant valve cycling that caused the four LLR-4 test rods tu quench early and keep the peak clad temperatures frota rising perhaps an additional 90"F.
At these temperatures and associated loup pressures, seme LOFT fuel rod cladding collapse would be likely.
LOFT Preparations are continuing for the second nuclear experiment in LOFT (L2-3) scheduled for May 1.
This test will simulate an accident involving the sudden rupture of a coolant inlet pipe when the reactor is operating at a power level of about 38MWt, which corresponds to the nominal power density in a commercial LWR (12kW/ft linear heat generation rate).
The plant is being raised to operating temperature and pressure, and while hot the reactor will be taken critical and the secondary e
system will be checked out. After these checkout tests, the plant will be shut down for additional maintenance before the L2-3 e xperi r.ent.
ENCLOSURE F
OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST FOR THE WEEK ENDING APRIL 13, 1979 EPA Proceeding on Health Effects of Radioactive Pollutants On April 11, 1979 EPA published in the Federal Register a notice requesting members of the public and Federal agencies to submit infor-mation and data on the possible health effects of radioactive air pollutants to enable the Administrator to determine whether or not radioactive pollutants may reasonably be anticipated to endanger public health. The notice provides an opportunity to request an informal public hearing. Such requests must be received by EPA by April 23, 1979.
If an informal public hearing is called, it will be held on May 16, 1979. Written responses to the notice are due on May 22, 1979.
ENCLOSURE G
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING APRIL 13, 1979 INTERNATIONAL COOPERATION Foreicn Response to TMI Situation IP is making arrangements for eight official delegations (from the Governments of the FRG, Spain, Sweden, Italy, Switzerland, Denmark, Japan and Taiwan) to be briefed by NRR, IE, and SP on Thursday, April 19, on the course and status of the Three Mile Island incident.
Several of the groups are investigative teams who will have to submit reports to their respective Parliaments by the first and second weeks of May. Twenty to twenty-five representatives are expected to attend. A visit to Middletown for a short briefing by onsite NRC personnel is also being planned.
Meetings with German Physical Security and Safecuards Experts i
Dr. Dietrich Leven and Dr. Wolfgang Wurtinger met with NRC (RES, NMSS, NRR and IP) staff on April 10 and 11 for discussions on two s ubjects :
(a) possible German participation in proposed research at Battelle-Columbus on radioactive releases from spent fuel trans-portation casks and (b) NRC regulations and experience in safeguards and physical security compared to current and proposed regulations and practice in Germany. Leven and Wurtinger are employees of the GRS in Cologne, FRG, and are under contract to the Ministry of Interior, the ministry with which NRC has its regulatory exchange agreement. Arrangements were made by IP and DOE for Leven and Wurtinger to visit LLL, LASL and Sandia following their visit to NRC.
Foreign Reoorts t'eleted from PDR copy.
ENCLOSURE H
~
c 2
From France Deleted from PDR copy.
i EXPORT IMPORT AND INTERNATIONAL SAFEGUARDS The first interagency coordinating meeting pursuant to the President's Executive Order No.12114 ef January 5,1979 regarding " Environmental i
Effects Abroad o f Major Federal Actions" took place on April 6 at S tate.
In addition to State (chairing), other participating agercies included EXIM BAhX, ACDA, DOE, CEQ and NRC (represented by IP, NRR, OGC, ELD and OPE). State distributed for comment a draft set of " Unified Procedures" which address mainly the procedural aspects of the order.
l The next coordinating meeting has been scheduled for April 18.
As a related matter, during another meeting at State, also held on April 6 and involving many of the participants in the first meeting, State distributed to NRC, DOE and EPA a " Tasking Memorandum" containing i
various agency assignments in response to the questions / suggestions contained in the Heinz/Stevenson (Senate Subcommittee on International Finance, Committee on Banking, Housing and Urban Affairs) December 18, 1978 letter to the President. This letter encouraged a whole-hearted administration effort to implement the international approach to environ-mental protection specified in Section 407 of the NNPA, ENCLOSURE H
OFFICE OF STATE PROGRAMS ITEMF OF INTEFEST WEEK ENDING APRIL 13, 19'9 State Acreements A State Agreements staf f member and representatives of NMSS will meet with Kansas officials on April 17 and 18 to dis cuss technical assistance NBC may provide to the State in evaluating a pending application for a low level waste storage facility.
Emercency Precaredness The California Legislature Subecmmittee on Energy will hold a hearing on Monday, April 16, on emergency response to nuclear power plant accidents.
Robert DeFayette, SP will testify at this hearing for NRC.
On April lith Hal Gaut met with representatives of Maryland State Emergency Services and Department of Health to discuss development of the final version of the State Radiological P lan.
On Monday, April 16th, he will meet with the State of Minnesota for the same purpose.
IE Region III staff working with SP on Radiological Emergency Response Planning, me t wi th the Governor of Illinois and his key staff on April 9, 1979 to determine the future assistance required by the State in upgrading their planning effort.
ENCLOSURE I
0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest Week Ending April 13, 1979 Three Mile Island Chronolocy Prepared a chronology for E00 and Chairman describing the Three Mile Island incident and NRC's response. Provided additional support to the Executive Management Team.
Questions from Commissioner Gilinsky Responded to questions from Commissioner Gilinsky's office on population distribution at nuclear power plants and other subjects.
Question from Commissioner Ahearne Analyzed U.S. and Japan data on time-to-issuance of nuclear reactor construction permits and construction durations. The purpose of the paper was to quantify and compare practices in the two countries with respect to patterns and trends in the time required to license and construct nuclear power reactors.
Questions from Senator Glenn Edited and coordinated answers to questions on low-level radiation from March 6-7 hearings.
ENCLOSURE J
CALENDAR OF SIGNIFICANT EVENTS For Two Week Period Endina Aoril 30, 1979 Acril 18 Allens Creek Drehearing Con ference
/bril 19 Susauehanna 1 & 2 - Meeting to discuss physical security plan Acril 20 Salem 2 - SER Supplement No. 4 to be issued April 2a fles Haven 1 & 2 - Meeting to discuss reacter safeguards Acril 25-26 Palo Verde 1, 2 & 3 - Caseload Forecast Panel Site Visit 6
ENCLOSURE L
CALENDAR OF SPEAKING ENGAGEMENTS APRIL 10-20 Second Biennial EEI Standards Conference - Theme: Government Interface with the Voluntary Consensus Standards 0Fcanizations anc eel's New Posture in tne Stancaras Woric - Guy Arlotto 25 Westinchouse Research Laboratory, Pittsburgh, PA,
~}e Rasmussen Reoort Revisited: The Lewis Recort on Reactor Safety Assessment - Robert J. Bucnitz MAY 1
State of South Carolina Advanced Management Seminar, Greenwood, SC - NRC Concurrence Procram for Fixed Nuclear Facilities -
J. W. nufnam 17 Nsticnal Classification Mange ent Society Seminar, Jack Tar Hotel, San Francisco, CA - The NRC Security Procram -
Classification Manacement in a Reculatorv A:ency - Raymond J.
Eraay 21 Radicactive Waste Manacement for Nuclear Pcwer Reacters -
Ruies, Re:uietiens anc Stancarcs, Aiexancria, VA - 1. C.
Rocerts 23 Annual Records Managaren: Ccnference of the National Archives, Fredericksburg, VA - Autcmaticn of Reccrds Manacemen; at NRC -
R. Stephen Sccit ENCLOSURE N
STATUS OF NUCLEAR POWER PLANTS-MARCH 31,1979 Number Rated Capacity Of Units (MWe)
- 70 Li C E N S E D TO O P E R ATE.....................................................
51,00 0
- 92 CO N STR U CTIO N P ER M IT G R A NTE D................................. 101,000 37 Under Operating License Review..
40,000 55 Operating License Not Yet Applied For G1,000 28 U N DER CONSTRUCTION PERMIT REVIEW..................... 32,000
- 4 Site Work Authorized, Safety Review in Process.
4,000 24 Other Units Unsler CP Review.
.28.000 4 ORDERED..............................................................................
5,000 2 P U B Li C LY A N N O U N C E D......................................................
2,000 m
2
...........................e.e....e..e........e.e....e.....e.........e....e..
e....
8 c
rs "To date thcee have been 449 reactor years of operation. Not included ase two operable DOE-owned reactors with a combined capacity of 940 MWe.
'lotal ni units authorised construction (Construction Permit Granted plus Site Work Authorized): 96 units,105.000 MWe.
NPl49 e