ML20008E984
| ML20008E984 | |
| Person / Time | |
|---|---|
| Issue date: | 03/04/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810227, NUDOCS 8103100693 | |
| Download: ML20008E984 (40) | |
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3 March 4, 1981 MAR O 11981-Fce:
The Comissioners
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From:
T. A. Rehm, Assistant for Operations, Office of the EDO -
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Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 27, 1981 W( &
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 A
Nuclear Reactor Regulation B
Standards Development C
Nuclear Material Safety and Safeguards D
Inspection and Enforcement E
Nuclear Regulatory Research F
Executive Legal Director G
International Programs H
State Programs I
Management and Program Analysis J
Controller X*
Analysis and Evaluation of Operational Data L
Small and Disadvantaged Business Utilization M*
Ite'ms Approved by the Commission i
N Calendar of Speaking Engagements 0
f j
. A. Ren,a, Asainant for Operations Office of the Executive Director for Operations
- No input this week.
CONTACT:
T. A. Rehm, 27781 8103100 6q3
Summary of Weekly Information Report Week Ending February 27, 1981 Oconee Unit No.1 On February 23 Juke Power Company reported that while Oconee Unit No. was ascending in pressure and temperature after a maintenance shutdown, they discovered a leak in a check valve which contributes to an intersystem LOCA.
Duke stopped the heatup and, after discussions with the staff, agreed not to restart Oconee 1 until after repairs are completed.
Fort St. Vrain On February 23 Fort St. Vrain experienced an electric grid upset due to a tie-in with Utah, causing the plant to trip. A static seal did not seal.
properly and primary coolant helium was released into the containment build-ing. Access to the building was limited but it was not evacuated.
Report on Radon _ Releases from Uranium Minino and Milling NUREG-0757, " Radon Releases from Uranium Mining and Milling and Their Calculated Health Effects," was issued last week. The report documents radon releases from the front end of the uranium fuel cycle.
Hydrogen Program We have received Federal Republic of Germany concurrence in our proposal to send a Sandia engineer proficient in code work to Germany during March 1981 to obtain their RALOC code and return with it to Sandia. This code was developed to describe the transport of steam, air, and hydrogen in reactor containments.
Industry Operational Data Screening Program A Commission Paper (SECY-81-121) was forwarded by ED0 which discusses current staff efforts to formally encourage INP0/NSAC to establish an industry-wide and NRC-approved operational experience screening service.
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0FFICE OF ADMINISTRATION Week Ending February 27, 1981 ADMINISTRATION OF THE FREEDOM OF INFO?% TION ACT STATUS OF REQUESTS Initial Appeal of Reque t Initial Decision Received 115 1
Granted 60 0
Denied 4
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0 Pending 51 1
ACTIONS THIS WEEK Received Trudy Knowles Requests specific information on shipments of (81-63) yellowcake from Ambrosia Lake Milling Facility in New Mexico to the Gore Conversion Plant in Gore, Oklahoma during the months of July through December, 1980.
Rick Trombetta Requests documents concerning a leak of radioactive (81-64) gas at the Trojan nuclear power plant.
George Vernon, Requests, on behalf of Nuclear Pharmacy, Inc., all Karon, Morrison written and oral statements given to the NRC from
& Savikas, LTD.
January 1,1980 to the present which mentions, (81-65) names or refers to Nuclear Pharmacy, Inc.
l(An individual requesting Requests a copy of his Reactor Operator License information about himself) exam results.
(81-66)
F0I Services, Referral from the Food and Drug Administration for (81-67) a list of all companies with approved applications licensed to build facilities for radiation sterilization in Puerto Rico and a list of names and addresses of companies performing radiation sterilization in Puerto Rico.
Clifford H. Turner, Requests the names, duty stations and any other Denticare identifying information of NRC employees in Maryland, (81-68)
Virginia and Dici'd;t of Columbia.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A G-w-
2 Received. Cont'd Lynn Connor, Requests a copy of SECY-80-467, SECY-80-555 and Doc-Search Associates the 1980 Plan for Reorganization that was sent to (81-69) the Transition Team.
(NRL employee)
Requests a copy of documents on him in his security (81-70) and personnel file and personal files kept en him by listed individuals.
(NRC emplo) vee)
Requests the date of vacancy selection, birth date (81-71 of selected individual and his own personal candidate rating for 79 listed vacancy announcements.
William S. Jordan, III, Requests, on behalf of the New England Coalition on Harmon & Weiss Nuclear Pollution, all documents, other than those (81 -72) dealing with personnel matters, prepared by Dr.
Mihalio D. Trifunac, on behalf of, or for presentation to, or consideration by the Advisory Committee on Reactor Safeguards and all transcripts of ACRS meetings in which Dr. Trifunac participated.
(NRC employee)
Requests information on his security clearance.
(81-73)
Robert R. Holt, APPEAL TO THE COMMISSION for 15 denied documents New York University relating to the Task Force on Interim Operation of (81-A-1-80-578)
Indian Point submitted to the NRC Commissioners in June,1980.
Granted Lilias Jones, In response to a request for a copy of 16 listed Black Hills documents, made availible these records.
Alliance (81-27)
Lilias Jones, In response to a request for a copy of 15 listed Black Hills dotuments, made available 14 documents.
Informed the Alliance requester one document was not reproduced due to (81-37).
poor legibility.
Lucille Sadwith, In response to a request for a copy of eight listed Center.for Farm & Food documents pertaining to radionuclides in the food Research, Inc.
chain, made available these records.
(81-40)
ENCLOSURE A t
3 Granted, Cont'd Andrew B. Reid, In response to a request for e copy of all written Black Hills legal opinions and subsequent du uments regarding Alliance NRC's role in the control of offsie tailings locations (81-42) and whether NRC has the authority to Order a clean-up of offsite tailings contamination from uranium millings, made available eight documents.
Robert R. Holt, In response to a request for documents which New York University indicated the methodoTogy, assumptions, data and (81-43) procedures used by the Task Force on Interim Operation of Indian Point Nuclear Power Station, informed the requester the Task Force report was based upon three listed published documents and the work specific to the Task Force was contained in two additional reports.
Rodney E. Armstrong, In response to a request for a copy of an October 10, Armstrong, Byrd &
1977 memorandum written by Harold Denton recommending Associates, Inc.
a shutdown of the Humbolt Bay reactor because of (81-45) the surface faulting, and copies of all supporting documents, made available six documents.
Informed the requester one additional document subject to this request is already available at the PDR.
Douglas Harbrecht, In response to a request for documents pertaining to Scripps-Howard licenses issued for all spent fuel piles to be Newspapers cleaned up under the Uranium Mill Tailings Act of (81-46) 1978, informed the requester the NRC has no documents subject to this request.
Richard E. Willins, In response to a request for a copy of an up-to-date The Procter & Gamble list of Agreement States and addresses, made Company available a copy of this list.
(81-51)
Matthew F. Medeiros, In response to a request for a letter from Leslie Attorney-At-Law Alsager requesting documents relating to the (81-55) construction of nuclear generating units located in Seabrook, New Hampshire and the Comission's written response to t'r. Alsager's request,. informed the requester the NRC did not locate documents subject to this request.
Joseph N. Cassiere, In response to a request for infomation on the Boston University break down of the types or classes of people who have (81-56).
made Freedom of Information Act requests, made available the requested list.
ENCLOSURE A
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Granted, Cont'd Fred Eberlein, In response to a request for a copy of 10 CFR Part Control Data 21, made available this information.
Corporation (81-62)
(An individual requesting Made available information on his Reactor Operator information about himself)
License exam results.
(81-66)
Denied None ENCLOSURE A
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DIVISION OF CONTRACTS Week Ending February 27, 1981 RFP'S ISSUED RFP No. RS-RES-80-198 Title - Earthquake Recurrence Intervals at Nuclear Power Plant Sites Description.- A study to provide a methodology for determining the recurrence interval for specific levels of ground motion generated at nuclear power plant sites by either an on-site or off-site earthquake.
Period of Performance - Two years Sponsor - Office of Nuclear Regulatory Research Status - Technical negotiations completed.
Best and Final offers due March 6, 1981.
i CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
Contract No.,
Contractor Closecut Date
- NRC-06-75-143 Potomac Research, Inc.
2/13/81
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ENCLOSURELA
DIVISION OF SECURITY Week Ending February 27, 1981 United Kingdom (UK) Interest in 10 CFR Parts 25 and 95 Division of Security personnel met and discussed the Classified Safeguards Program (e.g.,10 CFR Parts 25 and 95, " Access to and Protecticn of National Security Infor-mation and Restricted Data," as well as the related NRC Classificat'on Guide)
Safeguards Information) with UK personnel.
_ Classified Exchange Agreement vith the Federal Republic of Germany (FRG)
Th'e Division of Security advised the Office of International Programs that they con-curred in a proposed FRG Federal Ministry of Interior-Nuclear Regulatory Commission agreement to exchange classified information.
Material Access Approval Program (Clearance Rule)
NRC Division of Security and Office of Personnel Management-Personnel Investigations Division representatives met to discuss and plan for the clearing of licensee personnel who have access to or control over unclassified special nuclear material under 10 CFR Part 11. Part 11 concerns " Criteria and Procedures for Determining Eligibility for Access to or Control Over Special Nuclear Material."
Security Education / Awareness Poster Series The Division of Security has received a number of constructive ideas in response to Announcement No.164, which invited participation in the development of a new Security Education / Awareness poster series.
The Division of Security greatly appreciates the efforts of those individuals who responded to this Annoance. ment.
Additional ideas, statements and rough drafts are still welcome and may be forwarded to 020-SS.
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ENCLOSURE A 29,
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0FFICE OF fiUCLEAR REACTLR REGULATION i
WEEKLY HIGHLIGHTS - 3/2/81 j
CRYSTAL RIVER U'i!T ti0. 3 (CR-3)
CR-3 was brought to cold shutdown at 0900 on February 17, 1981 because i
of increasing leakage in the "A" Reactor Coolant Pump Seal. This shut-down was for preventative maintenance as the leakage rate did not l
exceed the action level of the Technical Specifications.
t NCRTH ANNA. UNIT t;0. 1 (fiA-1)
On February 13, 1921, VEPC0 purchased from Met Ed the TMI-2 Low Pressure (LP) turbine rotor No. 2 to replace the t;A-1 LP turbine rotor tio. 2.
UT i
testing of the NA-1 LP turbine discs in early January,1931 revealed two cracks in the keyways of the tiA-1 LP turbine rotor tio. 2.
UT testing by i
Met Ed in late January,1931 revealed nt cracks in the TMI-2 LP curbine rotor fio. 2.
The TMI-2 and NA-1 LP turbine rotors No. 2 are similar in i
design and construction.
l The approximate 450 mile journey of the TMI-2 LP rotor No. 2 from the THI-Power station to the NA-1 power station co=enced February 14, 1981.
The 450 mile journey will take 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (no delays) and involves 5 different rail routes.
The combination rail / truck journey requires that the rotor be offloaded (railroad to truck) at Harrisonburg, Virginia to by pass a narrow bridge and then reload from truck to railroad for the remainder of the trip.
The TMI-2 LP rotor No. 2 is scheduled to arrive at tiA-1 power station on February 18, 1981.
On February 19, 1981, the ASLAP and NRC staff will conduc5 a site visit to NA at which time the Board can observe and ask questions regarding the i
replacement of the NA-1 rotor No. 2 with the Tlil-2 LP rcter No. 2.
NA-1 is shutdown for refueling and is presently scheduled to restart mid-March, 1931.
OCONEE NUCLEAR STATION, UNIT NO. I 1
Duke Power Company reported on February 23, 1981 that a 14" check valve (CF-12), a potential contributor to an intersystem LOCA, had developed f
a leak of about 20 gpm.
Oconee Unit No. I was ascending in pressure and te perature af ter a maintenance shutdown that comenced on February 6, 1981. The reactor has two Low Pressure Injection lines each with two check valves, CF-12 being one of these valves, and a motor operated gate valve all in series.
Duke stopped the heatup on discovery of the leak and. informed the ONRR Oconee Project Manager. The licensee, after
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discussions with the staff, agreed not to restart Oconee Unit No. 1 until after repairs are completed on CF-12. Duke estimates that these repairs will add seven to ten days to the outage.
" Event V" Orders c9rrently under preparation' would require a shutdown for such a val /e
. repair.
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ENCLOSUPE B
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OFFICE OF NUCLEAR REACTOR REGULATION WEEKLY HIGHLIGHTS - 3/2/81 FORT ST. VRAIN On February 23,1981 at 17:30 hours the Fort St. Vrain Nuclear Generating Station experienced an electric grid upset due to a tie-in with Utah.
The plant was unable to follow frequent changes and tripped on hot reheat j
temperature upset af ter scram, "A" circulator tripped on a buffer-mid-buffer upset and when the circulator came down, the static seal did not seat This resulted in primary coolant helium traveling down the properly.
shafttothelowpressureseparatorandintotgereactorconfinement building.
The release of activity was 2 x 10- pc/cc cn one monitor.
i The stack monitor did not register any activity since such low concen-4 trations are below the sensitivity of the monitor.
Access to the building was limited but it was not evacuated. All state At 24:00 hours the monitors showed 6x10~9fofficialswerenotified.pc/cc and the building was reopened to full acce and loc 1
- Testing of the static seal is under way and the plant is at 2% power.
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i NRC TMI PROSPA'i 0FFICE BEEKLY STATUS REPORT l
Week of February 22-28, 1981
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l Plant Status Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
Available Core Cooling Modes:
Lcng-tern cooling "B" (once through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode:
Standby Pressure Control (SpC) System.
Backup Pressure Contro. Mode:
Mini Decay Heat Removal (MDHR) System, t
Major Parameters (as of 0500 February 27, 1931) (approximate values)
Average Incore Thernocouples: ll8'F Maximum Incore Thermocouple:
151*F l
RCS Loop Temperatures:
A B
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ll6*F ll 2* E_,_ __. __. _ _____
Cold Leg (1) 66 F 66*F j
(2) 66*F 65'F I
l RCS Pressure:
99 psig i
Reactor Building:
Temperature:
61 F 8
Water level:
Elevation 290.6 ft. (8.1 ft. frca floor) i via penetration 401 mano.7.eter Pressure:
-0.4 psig (Heise) j Concentration: 6.7 x 10-3 uCi/cc (Kr-85)
(sample taken 2/24/81)
Effluent and Environmental (Radiological) Information i
l 1
Liquid effluents from TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in i
accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
l During the period February 20, 1981, to February 26, 1981, the effluents contained no detectable-radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of activity.
Cal cul a.:. inns i mii ca te that i m thao _tn.._,,,_ _
millionths (0.000002) of a curie of cesium-137(Cs-137) was discharged.
This represents less than 0.00002 of the permissable total liquid activity as specified in Technical Specifications for operational connercial reactors.
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ENCLOSURE B
NRC TMI PR03 RAM 0FFICE WEEKLY STATULREPDRT Week of February 22-28, 1981 Plcnt Stetus
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Core Cooling Mode:
Heat transfer f rom the reactor cooTant syst'em (RCS)
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loops to reactor building ambient.
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j Available Core Cooling Modes:
Long-term cooling "B" (once tirough steam generator-B); decay heat removal sy'tems.
RCS Pressure Control flode:
Standby Pressure Control'(SPC) Systa7.
1 Backup Pressure Control Mode: Mini Decay Heat Removal (MDHR) System.
Major Parameters (as of 0500, February 27,1981) (approximate values)
Average Incore Themoccuples: 118 F Maximum Incore The mocouple:
151'F RCS Loop Temperatures:
A B
Hot Leg 116*F 119*F Cold Leg ((2) 1)
66*F 66'F
- 6 6* F- - ~ 6 5"F KL.57fessulTT W ps19 M4 Reactor Building: Temperature: 61*F Water level:
Elevation 290.6 ft. (8.1 f t. from floor) via penetration 401 manometer Pressure:
-0.4 psig (Heise)
Concentration:
6.7 x 10-b uCi/cc (Kr-85)
(sample taken 2/24/81)
Effluent and Environmental (Radiological) Information 1.
Liquid effluents from TMI site released to the Suscuehanna River after_ processing, w~C requirements and City of Lanc_ aster Kgrnd.in, _
ere made within the regulatory limi.ts a accordance with NR eenent dated February 27, 1980.
During the period February 20, 1981, to February 26, 1981, the effluents j
contained no detectable radioactivity.at the-discharge _ point. although..
individual effluent sources which originated within Unit 2 contained minute amounts of activity.
Calculations indicate that less than two l
millionths (0.000002) of a curie of_.cenum-137(Cs-13_7) was discharaed.
t This represents less than 0.03002% of the permissable total liquid activity as specified in Technical S;;ecifications for operational co rnercial reactors.
ENCLOSURE B
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EPA Environmental Data.
Results from EPA monitoring of the environment around the Tiil site were as follows:
' The EPA mea'surcd Krypton-85 (Kr-85) cuncentrations (pCi/m ) at
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3 several environmental monitoring stations and reported the following results:
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i Location February 13 - February 20, 1981 h
(pC1/m )
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8ainbridge 21 Goldsboro 22 Observation Center 28 Middletown 25 All of the above levcis of Kr-85 are considered to be backgrouna
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levels.
f No radiation above normally occurring background levels was i
detected in any of the samples collected from the EPA's air and ganna rate networks during the period from February 18, 1981, i
through February 26, 1981.
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3 NRC Environme_nta_1 Data.
Results from NRC monitoring of the environment 8
around the TMI site were as follows:
l The following are the NRC air sanple analytical results for the onsite continuous air sampler:
Period (uCi/cc)
(uCi/cc) l i
HP-256 February 18, 1981-February 25, 1981 j
- Sample results are not available due to a temporary outage of EPA counting equipment.
EPA reported that the counting equipment will be restored to service by March 2, 1981.
NRC air monitoring l
results will be reported in the next status report.
4.
Licensee Radioactive liaterial and Radveaste Shipments.
The following j
shipments were made:
On Monday, February 23,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg,
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4 On Friday, February 27, 1981, 55 drums containir.g Unit 2 i
contaminated laundry were shipped to Tri-State Industrial Loundries, Utica, New York.
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1 ENCLOSURE B
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Submerced Demineralizer System (5051 SDS construction is approximately 84% complete.
Initial testing of completed portions is in progress 4
while construction is ongoing.
The testing verifies the proper operation of equipment and does not involve processing radioactive water. The licensee is preparing an update to the Technical Evaluation Report which should be available for NRC review by the middle of March (the repert has been delayed approximately two weeks).
2.
Contaminated Building Expansion _ Joint.
During the period Feburary 21-23,1981, there were intermittent and sometimes heavy rains in the TMI area.
The air intake tunsi surrp filled with water, and some water seeped past the doorway from the tunnel to the service building. Contamination had previously been found in the cork building-expansion joint in this area, so a sample of the seepage was taken by the licensee.
Later, a water sample was taken in a previously sampled expansion joint in the auxiliary building.
Both of these samples, together with an expansion joint sample taken in the control building after the previous heavy rain (on i
February 11,1981) are being analyzed for radioactive contamination.
l 3.
Reactor Building Entry and_Purce.
The seventh entry into the l
Unit 2 reactor building has been delayed until March 11, 1981. The rescheduling was necessitated by delays in constructing equipment l
which is to be used during the entry. The equipment includes a device j
to pass sump water through a zeolite column and collect the effluent for analysis and a second device which will be used to obtain four samples of sump water for off site analysis. Additional tasks which are scheduled for the~ seventh entry include the servicing of l
valves, additional radiation surveys, polar crane inspection, and l
intercom telephone repairs. Twelve men are scheduled to participate in the entry which will extend over a two day period.
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Prior to the entry, a reactor building purge will be conducted to i
reduce the concentration of Kr-85 gas.
Calculations indicate that there will be less than 6 curies of Kr-85 released during the purge.
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ENCLOSURE B
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8'.seting ASten(ed I
On Tucsday, February 24. 1981, Lake Barrett had a spontaneous nceting at
- the NRC's Middletown Office with area nothers.
They expressed their feelings that THI Unit i should not be restarted while Unit 2 is being cleaned up. They also felt that the NRC Commissioners were not adequately considering the stress that would be created in some area residents if Unit 1 was restarted.
Lake Barrett assured them that their concerns would be com7.unicated to the Commissioners and other appropriate NRC staff. He also mentioned that they could express their concerns on a more fornal basis, in writing or orally, before the Atomic Safety and Licensing Board on March 5,1981, at 7:00 p.m. in Harrisburg at the William Penn Museum.
Future Meeting On Tuesday, March 10. 1981 Lake Barrett will meet with area mothers to discuss various issues related to the decontaT.ination of TM1 Unit 2.
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ENCLOSURE B
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OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING FEBRUARY 27, 1981 1.
NRC Comments on DOT Highway Routing Rule: Representatives from SD,
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NMSS, and SP met on February 20 with counterparts from the Department of Transportation to determine why DOT did not fully accept the NRC comments lon the 00T highway routing rule. With respect to routing of placarded shipments (as opposed to the smaller number of large quantity shipments), DOT chose, in its final rule, to base routing decisions on the principle of minimization of radiological risk, rather than the NRC endorsed principle of minimization of total impact, including the predominant nonradiological component of traffic fatalities and injuries. The DOT task leader for the rule insisted that it would be improper for DOT to consider impacts not directly related to the hazardous nature of the cargo being regulated in any of its hazardous material regulations.
It could not be determined from this discussion with the DOT task leader whether DOT management understood the implications of this logic. The routing requirement for large quantity shipments implies by reference to DOT routing guidelines (a draft of which was made available to us on request) that nonradiological impacts are to be considered in routing these shipments.
Even though NRC would likely not be able to fully support 00T in expected court cases related to this rule, the practical health impacts associated with this rule appear to be small; therefore, we do not plan to contest it with 00T.
Contact:
D. R. Hopkins 443-5946 Publications Issued During the Week of February 23-27, 1981 Draft Reg,latory Guide and Value/ Impact Statement: Qualification and Acceptar~. Tests for Snubbers Used in Systems Important to Safety, Task SC r;.-4.
Comments requested by April 30, 1981.
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ENCLOSURE C 4
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0FFICE OF NUCLEAR MATERfAL S*JETY AND SAFEGUARDS Items of In2erest
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Week Ending February 27 1981 US/IAEA Safeguards Agreement
- The IAEA has informed the U.S. orally tr.at they would like to perform an inspection at the three selected facilities in the near future.
Since facility attachments will not be completed for some renths, they would conduct these inspections on an "ad hoc" basis. Of particular interest is the semiannual physical inventory which Exxen has scheduled for the end of March.
The IAEA would like to conduct their first inspection at that time to establish an agreed upon initial inventory.
- Staff recently met with Executive Branch representatives to finalize a draft document on "US Agency Respor.sibilities and Procedures for Implementation of the US/IAEA Safeguards Agreerent." This document will be circulated to the ISG members in the near future for formal agency approval.
- Staff is working with PA to prepare a press release announcing the initial selection by the IAEA of facilities under the Agreement.
Reoort on Radon Releases from Uranium Minin; and Milling Radon releases from the front end of the uraniur. fuel cycle are documented in the report, NUREG-0757, " Radon Releases frem Uranium Mining and Milling and Their Calculated Health Effects," which was issued this week.
Copies of the report will be served on participants in the Appeal Soard hearing on radon, which was held at Harrisburg, Pent.sylvania on February 26-28, 1980.
The radon release estimated documented in NUREG-0757 are normalized to the average quantity of uranium required to ; reduce the fuel consumed in a year"s operation of a model 1000-MJe D:R.
On this basis, with minor refinements in the calculations, they agree with estimates given in the Appeal Board hearing on radon and the estimates given in the Final GEIS on Uranien Milling.
Reculation of Contaminated Sites NRC and EPA staff met on February 26, 1981, to discuss the development of an NRC/ EPA agreement for.the regulation of sites centacinated with radioactive materials.
Attendees were Richard E. Cunnir.gham and Gerry Page of HRC, and Roger Mattson and Ray Johnson of EPA.
Another meeting.is scheduled to be neld on March 6, 1981.
9 ENCLOSURE D
Planned Meetings Division of Safeguards
- 1.
Subject:
ISIS SEP meeting Date & Time: ' March 2, 9:30 AM Place:
8th Floor Conference Room, Willste Building Attendera: Ted Sherr, Gene Sparks, Ivan Keller of SGMD and other members of the SEP including representatives from NRC Offices and DOE
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Planned Meetinos - Division of Fuel Cycle and Material Safety 1.
Subject:
General Information on Transportation Date/ Time: Februa ry 27, 1981, 10:30-12:00 Location:
9th Floor Conference Room, Willste Building Attendees:
Richard E. Cunningham, Charles E. MacDonald and Tony Batten, CBS News, 60 Minutes 2.
Subject:
To describe NRC's program for updating emergency preparedness at fuel c,cle and major materials licensees, particularly NRC's criteria for selection of licensees requiring Radiological Contingency Plans - Regional Mtg. of Agreement States.
Date/ Time:
February 27, 1981 Location:
Portland, Oregon Attendees:
Fred D. Fisher 3.
Subject:
Participate in discussion on nuclear medicine
. waste management on the Panorama Television Show, Channel 5, WTTG.
-Date/ Time: March 4, lIll,12:15 p.m.
Location:
5151 Wisconsin Avenue, Washington, D. C.
Attendees: Richard E. Cunningham 4.
Subject:
Transportation of Radioactive Waste Date/ Time:
Parch 5-6,1981-
' Location:
Albuquerque, New Mexico Attendees: Charles E. MacDonald, State Planning Council on Radioactive Waste Management Task Force, Repre-sentatives from DOT, DOE, and State Representatives.
5.
Subject:
Discuss the-development of an NRC/ EPA agreement for the-regulation of sites contaminated with radioactive materials.
Date/ Time:
March 6, 1981, 2:00 p.m.
Location:
Willste Building, Silver Spring Attendees:
Richard E. Cunningham, Ralph G. Page of NRC and R.- Mattson and R. Johnson of EPA.
EN6LOSURE D g
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Plarn;d Meetings - Division of Waste Management 1.
Subject:
LBL Contract - to discuss technical assistance contract in support of NRC Site Characterization Studies Date: Week of March 2,1981 Location:
Willste Bldo.
Attendees: Bill Stromdahl, LBL; Dai Watkins, LBL; most members of WMHT staff 2.
Subject:
Plateau Resources - to discuss surety arrangements Date:
February 26, 1981 Location: Willste Bldg.
. Attendees:
Plateau Resources; J. Linehar:, NRC 3.
Subject:
Cleveland Cliffs - to discuss disposal and control of surface wastes Date:
March 6, 1981 Location: Willste Bldg.
Attendees:
J. Louderbach, Cleveland Cliffs; J. Linehan, NRC 4
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OFFICE OF TNSPECTROM AND ENFORCEftENT Items of Interest Week Ending February 27, 1981 1.
The following Notifications of Significant Enforcenent Acticn were dispatched during the past week:
a.
EN-80-50A Commonwealth Edison Company - A Notire of Violation and Proposed Imposition of Civil Penalty in the amount of $40,000 was previously issued to subject licensee based on a violation of 10 CFR 50.54(k) in that licensed operators for Dresden Units 2 and 3 were observed by the NRC resident inspector to be apparently asleep at the controls and thus not fully attentive nor able to monitor reactor conditions.
After consideration of the licensee's basis for denial, no new facts were found to justify mitigation of the civil penal ty. Accordingly, a civil penalty of $40,000 was imposed on the licensee on February 23, 1981.
b.
EN-81-06 Nuclear Metals, Inc. - A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $5,000 was issued to subject licensee on or about February 23, 1981.
This action was based on an alleged violation relating to the shipment of low specific activity materials from the licensee's facility in Concord, Massachusetts to the Nuclear Engineering Company, Richland, Washington burial site, during which time leakage of radioactive liquid material occurred from one of the waste drums.
2.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-I-81-26 Beaver Valley Pcwer Station, Unit 1 - Unscheduled Plant Shutdown - Unusual Event b.
PNO-I-81-27 Beaver Valley Power Station, Unit 1 - Unscheduled Plant Shutdown - Reactor Coolant System (RCS) Pressure Boundary Leakage c.
PHO-I-81-28 Pilgrim (Boston Edison Co.) - Potential for LOCA and Loss of Primary Containment During an Anticipated Transient Without Scram (ATWS) d.
PNO-II-81-15A Sequoyah Unit 1 - Update of Inadvertent Operation of Conteinment Spray and Accumuiation of Water in Containment e.
PNO-II-81-18 Cherokee Nuclear Station - Indefinite Construction Delay f.
PNG-II-81-19 Surry Unit 1 - Main Steamline Pipe Defects g.
PNO-III-81-20 Monticello - Complete Loss of Plant Air h.
PNG-III-81-21 Zion, Utits 1 and U.G. General Accounting Office Study Concerning Zion and Indian Point Power Plants ENCLOSURE E v
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PN0-V-81-08 Trojan Nuclear Plant - Resin Injection In*o Reactor Coolant and Subsequent Unplanned Release of Airborne Radioactivity
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PN0-V-81-09 U.S. Ecology, -Inc., Beatty Nevada Burial Site - Banning of Indiana and Michigan Power Company, D.C. Cook Power Plant, Bridgman, Michigan '(NRC Licensee) for Radioactive Waste Shipments t
k.
PNO-TMI-81-05 Three Mile Island - Onsite Ground Water Monitoring Program Update
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PNS-I-81 -C.
Indian Point, Unit 2 (Consolidated Edison) and Indian Point, Unit 3 (PASNY) - Bomb Threat m.
PNS-III-81-04 Zion Units 1 and 2 - Arrests of Employees for Alleged Drug Sales 4
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ENCLOSURE E-i
OFFICE OF NUCLEAR REGULATORY RESEARCH Important Items - Week Ending Iebruary 28, 1981 IE Physical Protection Inspection Complian e Modules During th'e first week of February 1981, the final version of the physical protection power reactor inspection compliance module developed for IE was delivered to the five regional offices. The remaining inspection modules for nonpower/research reactors, SSNM fixed siths, transportation of SNM, personnel training and qualifications plan (Appendix:B to 10 CFR 73) and in safeguards contingency plans (Appendix C to 10 CFR 73-) as well as licensee implementing procedures evaluation have been recently delivered to the IE regional physical i
security inspectors for field testing.
The final version of IE inspection modules.will be placed in the Public Document Room, thereby making it available:for licensees. These inspection modules can be used by the licensee to improve his required self audit of his security program. Section 73.46(g)(6) of 30 CFR Part 73 requires that the security program at a licensee's facility be reviewed at least every 12 months by individuals independent of both security management and security supervisors.
FLECHT SEASET
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A meeting was held with NRR to reach an NRC consensus on the blockage strain value for the large bundle test.
NRR indi~ated 44 percent should be used c
for the first bundle.
NRR also expressed its need for the second bundle with 36 percent strain.
~
A memorandum was sent from L. S. Rubenstein to L. H. Sullivan to express NRR's continued need for the entire program - blockage, natural circulation and system reflood.
NRR and RES should obtain the additional funding to complete the program.
Pulsed Neutron Activation Technique for Two-Phase Flow Measurements ANL completed the draft report " Feasibility of Using PNA Techniques for In-Situ Calibration of UPTF Two-Phase Flow. Instrumentation," and presented the findings at the mid-year meeting. ANL concluded that it is feasible to calibrate UPTF instrumented spool piece instruments.
A meeting was held among NRC, ANL and JAER} to discuss using PNA for SCTF blockage flow distribution experiment.
NRC and ANL provided the pertinent information to the Japanese for their decision.
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O ENCLOSURE F t
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2 Hydrogen Program We have received Federal Republic of Germany concurrence in our proposal to send a Sandia engineer proficient in code work to Germany during March 1981 to obtain their RALOC code and return with it to Sandia.
This code was developed to describe the transport of steam, air, and hydrogen
~
in reactor containments. An agreement to obtain the code was negotiated with the FRG at the recent Hydrogen Workshop in Albuquerque. Our plans are that after Sandia has RALOC operational, exercise of the code to obtain trans-port information will be done under Hydrogen Program sponsorship, but modifications and improvements to the code will be sponsored by the Analysis Development Branch, RES.
20/3D Program Meetings were held on February 17-19 with Nepresentatives from JAERI (Japan) and GRS/KWU (Germany).
Conditions for the ICCS reflood EM test to be conducted in Japan in the Cylindrical Core. Test Facility (CCTF) Core I on March 19 were agreed upon with JAERI and accepted by NRR.
Both Savannah River Laboratory and LASL will make pre-tert predictions using the agreed upon initial and boundary conditions.
CREARE presented its proposal for four refill separate effects tests to be run in CCTF Core II in CY82. JAERI is to review the recommendations and provide its comments at the 20/3D coordination meeting in Japan in March.
LASL reviewed the results of TRAC calculations that it had made to evaluate the water slug and flow oscillation behavior in the hot leg of the German reference. reactor.
Since this behavior would have a significant impact on the Upper Plenum Test Facility structural design, the German representatives present were strongly concerned about the calculations.
Both the two-fluid and draft flux model TRAC calculations show oscillations in the hot-leg flow.
Test data from LOFT and CCTF were presented _ which also showed oscillations.
GRS/KWU stated that they had not observed these in their tests.
Because of some uncertainties in the TRAC steam condedsation model, the Germans were still not convinced at the end of the meeting.
It was agreed that further discussion would be held in abeyance until the TRAC' German reference reactor calculation, using TRAC-PDP, was completed;in March. The NRC is discussing having CREARE run a hot-leg steam water interaction test to see if plug flow
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can be simulated in the laboratory and hence either confirm the LASL predic-
. tions or provide a basis for modifying the TRAC hot-leg condensation model.
Disturbance Analysis and Surveillance Systems RES prepared its. first draft on " Regulatory Approaches to Disturbance Analysis and Surveillance Systems.".The report examines the safety impli-
-cations of such systems and proposes alternative' approaches which the regulatory staff might consider in licensing a prototype system. This paper is in response to Action Plan Task I{D.5.
l ENCLOSURE F l-
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3 Improved Ultrasonic ISI Flaw Evaluation The improved SAFT (Synthetic Aperture Focussing Technique) ultrasonic inspection technique, previously developed Et the University of Michigan, has now been incorporated into a field-usab]e inspection device at the Southwest Research Institute, under RES contract.
The SwRI ultrasonic testing device, employing the SAFT nethodolygy, has successfully and accurately ir. aged the stress corrosion crack in a sample of the cracked pipe removed from the Duane Arnold plant. The device is undergoing further trials on additional pipe and plate samples' to determine its characteristics under typical inservice inspection conditic'ns.
It is expected that the inspection device will be capable of field inspections by the end of this fiscal year.
Grant Award - American Institute of Aeronautics and Astronautics A $20K grant was awarded to the American Institute of Aeronatics and Astronautics (AIAA) to support a multidiscipline workshop / conference involving dialogue and transfer of technology between the organizations involved in aerospace and nuclear-electrical power. Other organizations involved in this workshop-conference are NASA. INPO, EPRI and D0E.
The first planning session for this effortlwill take place on 2/26/81 in Washington, DC. The nature of NRC parti.cipation should be identified at this meeting. The earliest date for the cdnference will be in the May-June period of this year.
s 1.
State of Technology Report on Fission Product Iod_ine (50TRI)
The title of the report has been changed th be more consistent with the l
scope of the report. The new title is " Technical Bases for Fission Product Behavior in LWR Accidents".
As of C.O.B. Tuesday, February 24, 1981 all final draft actions have been received fran the field.
7 I
The Introduction and Summary section is nos in preparation at Headcuarters.
3 cme additional follow-on analyses are in progress in the field and res'ilts are important and time permits they will be. factored into the report.
Close coordination is being carried out with the Regulatory Impact Report Taskforce to assure effective transfer of~results and conclusions from 50TRI.
Formation of the peer review group is essentially complete and only confirma-
. ion of several names remains.
The principal reviewers will be composed of:
b ENCLOSURE.F v
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-l Indeoendent Reviewers (non-NRC, non-indus_try)
Dave Garvin, NBS Leo Brewer. UC-Berkley Lloyd Zumwalt, NC. Staff Dave Morrison, IITRI (tentative)
Frank-Driggers. ORNL (Y-12)
Industry Richard Vogel, EFRI Dee Walker, W_
One representative each from GE, B & W and iombustion Eng.
DOE Lab. Reviewers Bob Hilliard, HEDL Don Schweitzer, BNL Carl Johnson, ANL Foreton Reviewers Dave Te gerson, AECL Canada Invitat!ons have been sent to UK, FRG, Japan, Sweden and France Other: Reviewers R. Ebbin, N50C Bob Ritzman, SAI Invitations are being extended to NRDC and.UCS.
Discussions with Dr. Dade fioeller, Chaiman. of the ACRS Ad Hoc Subcommittee on Fission Product Source Tenns revealed that the ACR5 does not wish to have additional ~ time for review of SOTRI hence no change in ACRS meeting schedule, April' 10,11 and 12 (full-comittee) is not required.
(2) fleeting of the LMFBR _PAHR (Post-Accident-Heat-Removal) Research Review Group on the Results and Analysis _of trie D-4 ACRR _ Experiment on Debris-Bed Coolability The subject meeting was held on February 18: to review the results and analysis, of ACRR experiment D-4 on the coolability limits of a relatively thin bed (8.2 cm thick) of particulate LMFBR fuel debris in a socium pool.
The results and models derived from the D-s.eries experiments have generic applicability to LWR safety assessment, and. have been used in analysis of the Tlil-2 accident and in the Zion / Indian P~oint study. The meeting included representatives of RES, DOE, NRC and DOE sa.fety research contractors, and reactor vendors, but the NRR review group member was not able to attend.
ENCLOSURE F
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5 The result's and analysis of the D-4 experiment as presented in the recent Sandia tcpical report, NUREG/CR-1809 were~ reviewed in detail, and no excep-tions were taken to the conclusion in the report.
The most important result i
of exp'eriment D-4 was that the threshold specific power for bed dry out at los subcooling (195K) was nearly 5 times greater than that measured earlier i
in D '.4 at high subcooling (460K), the dry oyt specific powers being 3.6
- and 0.78 1 04 w/gm U0. respectively.
This large increase was caused by 3
the opening up of vapor-flow-channels in the debris bed by sodie?.-vapor jets.
While the channeled-bed and packed-bed dry-)out limits are in reasonable egreement with previous models (packed bed and data correllations (channeled-bed),no model or understanding currently exists of the conditiens that govern this important transition.
[
A pre'liminary report on receatly performed experiment D-6 on the coolability limits of a 10.6 cm thick vertically-stratified debris bed was presented and discus' sed.
D-6 showed that bed stratification (fines at top) as expected from. debris settling, reduced the dry out coolability limit by nearly a factor of 2 from that in similar but unstratified experiment D-2.
The stratificetion also appeared to have prevented the more-coolable channeled bed configuration that occurred in experiments D-2 and D-4.
ANL speakers presented the current status of DOE research on LMFBR debris-bed coolability. A general discussion then followed on our current under-standing of debris-bed coolability, about which there was general consensus.
On February 19, the NRC/RES and DOE representatives and some of their contractors met to discuss respective plans for current and future research on LMFBR core-debris coolability and some other LMFBR post-accident pheno-mena.! A summary was given of the results of the recently-completed draft report by the DOE Technology Management Center at ANL (with industry parti-cipation) on the technical uncertainties in assessing LMFBR post-accident behavior from a risk assessment and risk reduction point of view, and in current and needed future research to address these uncertainties.
The ACRR debris-bed coolability experimentsi furnish a major part of the needed information in this DOE assessment and DOE plans no similar in-pile work.
In general, the cooperation between the NRC and the DOE research programs on LMFBR post-accident phenomenon has been excellent, with !compleinentary programs and extensive technical interchange at tha work-ing level. This cooperation can furnish a model for work in other areas.
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1 0FFTCE OF THE EXECUTIVE LEGAL DIRECTOR 1
ITEMS OF INTEREST WEEK ENDING FEBRUARY 25, 1981 La Crosse Boiling Water Reactor On February 24, 1981, the presiding ASLB in this show-cause proceeding i.
issued a Partial Initial Decision which permits continued reactor operation without installation of a site dewatering system pending a final determination by the ASLB on the remaining matters in controversy.
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ENCLOSURE G 4
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O ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS
~~kEEK ENDING FEBRUARY 27, 1981 Renewal of Arrangement with the British IP was advised this week that the U.K. Health ano Safety Executive had approved, with certain modifications which IP believes to be acceptable, the information exchange renewal arrangement text initially proposed by NRC in February 1980.
(The original arrangement expired March 13, 1980, but has been continued informally while active negotiations proceeded.) The Commission will recall that the British had asked for clarification of the non-proliferation language used in NRC's broad-scale international aggreements. This was provided with Executive Branch approval in December 1980.
IP now awaits receipt of the revised text.
Review and Evaluation of HRC Bilateral Information Exchange Arrangements A. Labowitz, under a consultant contract, has begun a review and evaluation of NRC's bilateral exchange arrangements. This effort is planned to be completed by the end of May.
Foreign Visits to NRC On Monday and Tuesday Messrs. T. Tobioka, H. Kaneki, and K. Abe of the safety Code Development Laboratory of the Japan Atomic Energy Research Institute (JAERI) ret with J. Heltenes and F. Hebdon, AE0D; J. Boyle, MPA, R. Denning, SRR/NRR, and M. Mallory, IP to discuss safety-related data base systems for nuclear plant opera tion.
On Thusday six Indonesian scientists from the Agency for the Development and Application of Technology (BPPT) of the Indonesian Mir.istry of Research and Technology toured the Fort St. Vrain Generating Station in Colorado. The delegation, consisting of Messrs. Panggabean, Machfoed, Djamal, Krishna, Mahayana, and Chandra, is here under the auspices of the International Communicacions Agency to gain a greater understanding of HTGR technalgy in the U.S.
On Friday, Mr. F. Mueller of the Federal Republic of Germany, an economist with the Peace Research Institute which is affiliated with the University of Frankfurt, met with-a representativ9 of Public Affairs to discuss the role of nuclear power in forecasting future energy supply and demand.
ENCLOSURE H
OFFICE OF STATE PROGRAMS Terve or TNmeprem WEEK ENDING FEBRUARY 27, 1981 On February 23, 1981, Tom Elsasser, RSLO Region I, appeared
.before the Bronx Borough Council in New York City to explain the current and pending NRC and DOT regulations governing the transportation of nuclear materials.
On February 25, Mr. Elsasser and other members of RAC II met in West Trenton, New Jersey, to discuss their evaluation of the New Jersey radiological emergency response plan.
William F. Menczer, RSLO, Region III, was in Battle Creek, Michigan on February 27, 1981, to conduct a workshop on emergency preparedness and exercise evaluation with the Federal Emergency Management Agency, Region V'.
The Texas Legislature has passed a temporary moratorium banning the licensing of low level radioactive waste handling facilities in Texas.
The measure, which is effective until June 1,
- 1981, is intended to give the Legislature time to consider several pieces of legislation which would tighten Texas regulations on the licensing of low -leve1~ radiation waste disposal and handling facilities.
Frank Young attended the winter meeting of the National Governors' Conference, February 22-24.
The draft interim report to the President of the State Planning Council wE released there to the Governors and their comments were invi:ed.
Mr. Young met with staff persons from Washington and Idaho that are drafting the regional compact for low level waste disposal for the Northwes t region.
ENCLOSURE I
i 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING FEBRUARY 27, 1981 Os &-As With other offices, produced answers to initial set of more than 300
. questions from Mr. Bevill's subcommittee; now working on second (Mr. Fazio's) set; assisted NRR by providing data for answers to Mr. Udall's questions.
i Publications Issued " Operating Unit Status Report," NUREG-0020 (Gray Book), dated Jr iuary 1981.
This ' edition sumarizes all 1980 data.
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ENCLOSURE J
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0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA _
JTEMSOFINTEREST WEEK ENDING FEBRUARY 27, 1981 Industry Doerational Data Screening Program A Commission Paper (SECY-Sl-121) was forwarded by E00 which discusses currer/.
staff efforts to formally encourage INP0/NSAC to establish an industry-wide a.1d NRC-approved operational experience screening service. Past experience clearly
- indicates a high probability exists that the massive volume and inherent nature of-operational experience reports can inundate the available resourcas of an individual licensee. The staff believes that IUP0/NSAC can provide a valuable service by ~ conducting a thorough screening and preliminary evaluation process of domestic and foreign operating events and by identifying significant events to individual licensees, er clac.ses-of licensees, for their further study re-garding _the degree of applicability and need for action. This screening process would be in addition to those performed by the NRC.
INP0/NSAC/NRC Agreement on Operational Data Letters have been forwarded to INP0/NSAC suggesting the possibility of establishing modifications to an INP0/USAC draft agreement on a cooperative relationship oc,al a centralized industry operational data screening service and suggesting sever operational data.: The NRC suggested changes were believed necessary in order to focus upon: (a) how fragmentary, privileged, or otherwise restricted information and-data should be handled; and_ (b) the importance of assuring conTm.5 cation on specific events as well as generic activitiet It is expected that further dis-cussions'on the proposed agreement will be t ' ' in the next few weeks.
' Integrated Operational Experience Reporting ile_.'.) Activities Representatives of AE0D,:SD, RES, NRR, and IE met informally with representatives of INP0 on February 24, 1931 to discuss the current status of development of_ the 10ER system. LINP0 was-particularly interested.in gaining a better understanding of the intent of the various requirements contained.in the ' preliminary draft of the proposed rule. Although still opposed to a mandatory: system for.the collection of reliability data, INP0 provided perspective'on the' impact that'the draft require-ments would have.on t>e industry. Additional feedback from INP0 and other organiza-
-tions will be soughtLin order to assist the staff in developing an efficient system for the collection of operational safety. data that will provide the'information needed by the NRC without placing.an unreasonable burden on t e report ng utilities.
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. Sequence Coding and Search Procedure AEOD met with representatives from Argonne National Lab on February 23, 1981 to discuss the Sequence Coding System. The meeting consisted of general dis-cussion in order to give Argonne a better idea of the current status of the development and what we are looking for in the way of a contractor. They seemed very interested and we expect to receive further information from them next week.
Abnormal Occurrence Reports The Third Quarter CY-1980 Abnormal Occurrence Report was delivered to Congress.
The report was then released for general distribution.
ENCLOSURE L
4 ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 27, 1981 A.
SECY-81 REQUEST FOR FUNDING APPROVAL FOR ONGOING TECHNICAL ASSISTANCE PROJECT. Memo SECY to Dircks, dtd 2/23/81.
This is to advise you that the Commission (with three Commissioners approving and Commissioner Bradford not participating) has approved the interagency tasking project outlined in the subject paper.
t In connection with his approval, Chairman Ahearne has provided the following comments:
I I
"(1) For further work of this type, we should try to get DOE to fund part or all.
(2) In general, when proposing to give additional funds to a contractor who has previously been working on a contract, the staff should state what useful work has been done."
The Office of Nuclear Material Safety and Safeguards was informed of this action by telephone on February 20, 1981.
It is requested that you inform the Office of the Secretary when the contract is awarded.
(SECY Suspense:
3/16/81)
3/9/81)
B.
SECY-80-186 - SECY 415, "FURTHER ACTIONS TO CONTROL RISK ASSOCIATED WITH OCCUPATIONAL RADIATION EXPOSURES IN NRC-LICENSED ACTIVITIES". Memo SECY to Dircks, dtd 2/24/81.
This is ro advise you that the Commission (with all Commissioners concurring) has approved the qualitative regulatory approach to the implementation of occupationL1 ALARA programs by licensees as set forth in the subject papers.
In developing the proposed rule, staff should include the following items.
The proposed rule should also request comments on any alternative to these items which also accomplish their primary purpose.
Staff's preference for structuring the proposed rule to require licensees to develop and submit individual radiation protection programs.which incorporate means for maintaining radiation exposures
-ALARA as a majcr component, rather than only requiring ALARA programs, is accepted.
The proposed rule should include a requirement for affected licensees to establish annual collective dose objectives and to submit an annual report which (1) documents the collective dose for the previous year, (2) provides an appraisal of the effectiveness of their occupational ALARA program, ENCLOSURE N
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(Continued) and (3) sets forth the collective dose objectives for the ensuing year.
Such objectives should be
, based upon the licensee's operating experience and knowledge'of activities planned for the coming year, as well as the successful implementation of.
their occupational ALARA programs.
The report should include 1m explanation with respect to any eclisctive dose objective that was exceeded during the year.
The repor: should also include sufficient information on personnel dose data for specific, generically-applicable tasks to permit the staff to concentrate regulatory attention on appropriate activities and to facilitate future considerations of quantitatively-based ALARA requirements.
This report is to be pested in each affected licensee's establishment.
The proposed rule should. include a reguirement for-i affected licensees to submit c separate report _for any major-non-routine task, such as a steam generator replacement,_which will cause a collective dose larger than a stated threshold.
Such reports should describe the manner in which the licensee will apply the methods' detailed in the individual r;diation protection-ALARA program to the conduct i
of the specific' major activity and should set forth a collective dose objective for the activity.
The report should be submitted at least 20 days prior to commencement of the activity; NRC approval would not be required prior.to commencement of the activity.
In developing the proposed rule, staff should consider
' including the following items.
The paper forwarding the proposed rule for' Commission action should discuss - he ration' ale'for including or not including these iteras and
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where~ appropriate, should discuss alternatives for accomplishing the primary purpose of the item..
The items to be considered are:
. Staff should consider incorporating the individual radiation _ protection programs into the facility _
license.
The. manner in which individual' programs are incorporated into licenses should.be consistent for all licensees unless there are good. reasons for varying.
In this= regard,.the proposed rule should provide for sufficient flexibility.to allow minor changes in individual progra's to-be effected m
'without the need for a license amendment.
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(Continued)
Where justified by the potential hazard, licensees should-be required to establish an in-house advisory capability (preferably a committee) responsible for advising management on radiation protection, including ALARA, measures.
Reporting of any ncn-routine task which is predicted to cause a specified number of manrems (e.g.,
10 manrems) in advance to the radiation protection ec=mittee, along with a collective dose objective for the task.
The co=mittee should review the task and recommend actions te maintain occupational exposures ALARA.
If'the collective dose objective is exceeded by a fixed percentage (e. g. 30% or more), a documented explanation should be submitted to the co=mittee.
At nuclear power plants, reperting in aftance to the in-house radiation protection committee of any periodic routine task which is predicted to cause more than a specified collective dose over the projected lifetime of the plant.
The committee should review the task and recommend actions to maintain occupational exposures ALARA.
4 Preminent-display in each radioactive area of the
- ALARA. policy for occupational exposures, the makeup of the advisory' committee and the projected annual goal and the performance against that goal.
A recuirement that all-licensees submit an annual 2
report of radiation exposures of-all individuals for whom personnel monitoring is required.
It-is requested that you provide a Commission paper containing a discussion of the above items, a proposed rule change, and supporting-regulatory guidance to the Office of the Secretary within four months from the date of this SECY memorandum; C.
SECY-81-106 - PROPOSED LICENSE TO EXP0RT LOW ENRICHED URANIUM TO KOREA
~(XSNM01750).
Memo SECY to Dircks, dtd 2/25/81.
This is to advise-you that.the Commissioners have reviewed the subject license to Westinghouse Electric Corporation.
The Commissfon.(with:all' Commissioners approving) has accepted your recommendation to export to Korea 305,283 kilograms of Juranium, enriched'to 3.6%.U-235, in the form of UO2 in fabricated fuel bundles.
.TheLoffice'of-Internati'onal Programs was1 informed of this action by telephone on February 25, 1981.
ENCLOSURE N.
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SECY-81 PROPOSED CONTRACT AWARD FOR PERFORMANCE OF ENGINEERED BARRIERS IN A CE0 LOGIC REPOSITORY. Memo SECY to Dircks, dtd 2/27/81.
This is to advise you that the Comission (with all Commissioners approving) has granted approval for the staff to enter into the subject technical assistance contract, subject to staff's assurance that Tasks 1 and 2 are fully coordinated.
The Offices of Nuclear Material Safety and Safeguards and l
Administration (Division of Contracts) were inforned of this l
action by telephone on February 26, 1981.
It is requested that you inform the office of the Secretary when the contract is awarded.
(SECY Suspense:
9/25/81)
ENr.LOSURE N
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r SCllEDULED SPEAKING ENGAGEMENTS Date Organizat_i_on Location Subject Speaker 3/10/81 NRC/0RNL Symposium on Gatlinburg, TN
- Writing Standards for K. Goller
" Uncertainties Associated Geologic Disposal of High-SD with the Regulation of Level Waste Geologic Disposal of High Level Radioactive Wastes 3/11/81 Same as above Same as above The Effects of the Uncer-F. Cameron tainty of Inadvertent lluman 50 i
Intrusion on Stds for Reg of Geologic Disporal of liigh-Level Radioactive Waste 3/13/81 Same as above Same as above NRC Perspective on the P. Cor..ella Symposium SD 3/18/81 Annual Meeting of San Antonio, TX Panel on Low Level G. Wayne Kerr State & Territorial Nuclear Wastes SP llealth Officers 3/26/81 22nd Annual Quality Knoxville, TN What NRC Regulations W. Ruhlman Clinic Require from QA Program R0 II 3/29-4/2/81 American Chemical Atlanta, GA Regulatory Implications H. T. Peterson Society Meeting of Radiation Dose-Effect SD Relationships 4/1/81 Spouses of Operating Education Center Quality Assurance Require-A. Cerre Staff at Seabrook Seabrook, Nil mentt & Licensing Procedures R0 I Station Related to Seabrook Station retet meanne n