ML20031H480
| ML20031H480 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810925, NUDOCS 8110270526 | |
| Download: ML20031H480 (33) | |
Text
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j September. 30, 1981 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFCRMATION REPORT - WEEK ENDING SEPTEMBER 25, 1981 A sur.ary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation 3
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nucle!
Regulatory Research E
Executive Legal Director F
International Programs G
State Programs H
Management and Program Analysis I
controller J*
Analysis and Evaluation of Operacional Data K
Small & Disadvantaged Business Utilization L
Items Approved by the Commission
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. M M nt for Operations Office of the Executive Director for Operations
- No input this week.
Contact:
T. A. Rehm, EDO FOR SUBSCRIBERS 49-27781 kod0$M526e1093o HEEKLYl!NOhphpyg
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SUMMARY
OFWEEKLYINFORMATIONREPORT Week Ending Septemb'er 25, 1981 Pilgrim Unit 2 Boston Edison ' informed the staff _on September 24..that the Board of Directors voted unanimously to terminate licensing effort on the cendin'g construction permit application.
Soent Fuel Storage On September 21 NRC staff met 'with VEPC0 representatives to discuts spent " fuel storage options for..its Surry and North Anna reactor sites.
Loss of. full core.. reserve 1.s.p.ojected for the Surry's'ite in 1985 and at the North Anna site in 1987.
Diablo Canyon On September 21, the Commission authorized.the issuance of a license permitting fuel loading and low-power testing at Unit 1.
State Liaison Meeting
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On, September 23 and 24, Region _III and the Office of-State Programs sponsored a State. Liaison Officers meeting in Chicago
,Dnergency preparedness,. low level waste compacts, spent fuel shipments, SALP and other significant issues were addressed.
TVA Edgemont, South' Dakota, Uranium Mill Decommissioning l
NRC issued a draft environmental statement related to the proposed decommissioning of the TVA-owned inactive uranium mill and associated tailings located in Edgemont, South Dakota.
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0FFICE OF ADMINISTRATION Week Ending September 25, 1981 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT 4
STATUS OF REQUESTS -
Initial Appeal of Request Initial Decision Received 425 12 Granted 312 3
Denied 69 8
Pending 44 1
ACTIONS THIS WEEK Received (An individual requesting Requests informatict
.ncerning his Reactor information about himself)
Operator License and Senior Reactor Operator (81-374)
License written and oral examinations.
Denise J. Black, Requests a copy of the staff report on the 15 United Nuclear power plants found to be "below average" in overall Corporation performance.
(81-375) 4 Douglas Lowenstein, Requests a copy of the report by the Office of
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Cox Newspapers Inspector and Auditor (0IA) reviewing the (81-376) adequacy of work performed by Region III Office of Inspection and Enforcement at the William Zimmer Nuclear Power Station and all documents and transcripts of meetings discussing the OIA report.'
(An individual requesting Requests a copy of his. security clearance and information)
(81-377) copies of all documents regarding flying discs, flying saucers, unidentified flying objects, etc.-
during the period 1947 to 1955.
Nina Bell, Coalition for Requests eight categories of documents regarding the Washington Public Power Supply System, Units Safe Power 1, 2, 3, 4 and 5.
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(81-378)
Jim Peterson, Professional Reactor Requests a list of licensed Reactor Operators, Operator Society Senior Reactor Operators and Certified Reactor (81-379)
Operators on commercial nuclear reactors, to include name, address and zip code.
CONTACT: J. M. Fel ton 492-7211
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ENCLOSURE A 5
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g Received, Cont'd Lynn Connor, Requests a copy of the reports from AEOD's Doc-Search Associates-Incident Reporting System..
(81-380)
Lynn Connor, Reauests a copy of 10 listed referenced items on Doc-Search Associates degraded core cooling.
(81-381)
(An individual requesting' Referral from the Department of State of two information) documents regarding the requester.
(81-382)
Lynne A. O'Reilly, Requests, on behalf of an NRC employee, five NTEU Steward categories of documents regarding Vacancy (81-383)
Announcement 81-3755.
Granted Ellyn R. Weiss,
In response to a request for five categories of Harmon & Weiss records pertaining to the MARCH code, made (81-320) available 43 documents.
Informed the requester additional documents subject to this request are already available at the PDR'.
(NRC employee)
In response to a request for all records pertaining (81-343) to herself in files throughout her office, made available 196 documents.
Sanford Hartman, In response to a request for copies of documents Debevoise & Liberman (81-348) pertainirg to the " Survey by Senior NRC Management to Obtain Viewpoints on the Safety Impact of Regulatory Activities from Representative Util.ities Operating and Constructing Nuclear Power Plants," made available seven documents.
Earle P. Shoub, American Optical In response to a request for progress reports and final reports concerning all respirator studies Corporation for NRC by the Los Alamos Scientific Laboratory, (81-350) made available 60 documents.
Joseph L. Pokorney, In response to a request for a copy of the non-Middlesex Research Center, Inc.
proprietary version of the winning proposal and the best and final offer under contract No.
(81-352)
NRC-35-81 -682, made available these records.
ENCLOSURE A
3 Denied Brian L. Sc;'orr, In response to a request for a copy of a New York Urdversity memorandum dated February 13, 1979 from the School of Law General Counsel to Chairman Ahearne entitled (81-357)
"Tarapur--Analysis of the Legislative History of the Prospective Application of Export Licer. sing Criteria," denied this document in its entirety, the releasc of which would inhibit the open and frank discussion of legal issues between the General Counsel and the Commission.
ENCLOSURE A
DIVISION OF CONTRACTS Week Ending September 26, 1981 CONTRACT AWARDED 1.
RFP RS-RES-81-203 Title
" Definition of Bounding Physical Tests Representative of Transport Accidents - Air and Ship" Description - Define a set (s) of radioactive material shipping p=-kage tests which bound the environments experienced in such accidents, based on an investigation and assessment of extremely. severe air and marine transport accident events.
Period of Performance - 18 months level of ' Effort - 3 to 5 man years Sponsor - Office of Nuclear Regulatory Research Status Cost plus fixed fee contract awarded to IIT Research Institute in the, amount of $475,548 effective 9/28/81.
2.
RS-NMS-81-040 Title - Process Control of Special Nuclear Material (SNM)
Description - To design a process munitoring system that will meet specific performance criteria at NFS, Erwin, and to independently assess cost and feasibility.
Period of Performance - 30 September 1981 through 30 April 1982 Sponsor - NMSS Status - A Cost plus Fixed Fee contract. was awarded in the amount of
$224,765.00 to Science Applications, Inc. on 21 September 1981.
3.
RFP No. RS-NMS-81-026 Title
" Benchmarking of Computer Cot ; & Licensing Assistance" Description - Services to benchmark computer codes for supporting regulations and for performing reviews of proposed nuclear waste management systems, evaluate the codes, and provide licensing analysis using these codes are required.
Period of Performance - Five Years Sponsor - Office of Nuclear Material Safety and Safeguards Status - A Cost-Plus-Fixed-Fee contract in the amount of $1,449,757 was awarded to Teknekron Research, Inc., McLean, VA on September 15, 1981.
ENCLOSURE A
4.
RFP No. RS-NRR-81-141 Title.- Review of Statistical Uncertainty Methodology Description - Exxon Nuclear Company'has supplied topical report XN-NF-81-72
" Exxon Nuclear Company Generic Statistical Uncertainity Analysis Methodology" which is to be used in the reload of BWR's.
The staff requires Technical Assistance in the review of XN-NF-81-22 to determine if this methodology is acceptable to license reactor reloads.
Period of Performance - 4 Months Sponsor - Office of Nuclear Reactor. Regulation Status - A Firm Fixed Price Contract in the amount of'$59,497.00 was awarded to Control Data T.orporation - Nuclear Associates International, Rockville, Marylaad on September 18, 1981.
- 5. NRC-02-80-022 Title - Management Control System for Sealed Source and Device Review Description - Review and evaluation of existing NRC and Agreement State procedures applicable tc health and safety reviews and registration of sealed source and device designs and documenta-tion of functional and data requirements for an information retrieval system.
Option implements Phases II and III of contract.
Phase II requires that the contractor design a manual retrieval information system as well as develop the system / subsystem specifications and data base specifications for an automated system.
Phase III requires that the con-tractor shall assist in the implementation of the manual system as well as developing and implementing the automated system.
Period of Performance - September 19,1980.- April 15,1982 4
Sponsor - NMSS Status - Modification fully executed September 18, 1981.
l CONTRACTS CLOSED OUT Contract No.
Contractor Close-Out-Date NRC-01-78-014 Colorado Department of Health 9/ 21 / 81 NRC 7-133 Wichita State University 9 /2 2/ 81 NRC-04-79-213 Arkansas Geological Commission 9 / 2 2 / 81 NRC-02-77-185 Science Applications Inc.
9/ 2 4 / 81 NRC-03-77-179 D' Appolonia Consulting Engrs.
9/2 4 / 81 NRC-10-79-379 Montgomery County Public Schools 9/ 2 2/ 81 N RC- 05 35.2 State of Georgia 9/24/81 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDINC e.<TEMBER 25, 1981 PILGRIM 2 Bcston Edison informed the staff on September 24, 1981 that the Board of Directors voted unanimously to terminate licensing effort on the pending i
construction permit application.
MEETING NOTIFICATION On September 23,1981 at 1:00 p.m., the staff met with B&W Owners Group to present their technical views related to systems response from small break LOCA, over-cooling transients and station blackout and to discuss with B&W Owners methods of supporting this issue.
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ENCLOSURE B
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NRC TMI PROGRAM OFFICE WEEKLY JTATUS REPORT I
i Week of September 20 - 26, 1981 i
i Plant Status Core Cocling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ar.bient.
1 Available Core Cooling Modes:
Decay hea't removal lsyster.s.
Long term
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cooling "B" (once th; rough steam generator-5).
1 RCS Pressure Control Mode: Standby pres'sure control (SPC) system.
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Backup Pressure Control Modes: Mini decay heat. removal (MaiR) system.
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Decay heat removal (DHR) system.
Major Parameters (as of 0500, September 25,1981)](approxiraate values)
Average Inccre Thermocouples :' il4 *F Maximum Incore Thencouple: ;135'F RCS Loop Temperetures :
A B
F,t Leg l!3'F- ;
ll6*F j
i Cold Leg (1) 72*F 73*F j
(2) j 73*F 73'F RCS Pressure:
100 psig Reactor Building: Temperature:
72*F Water level:
Elevation.290.84 ft. (8..M ft. from floor)
, via penetration 401 manometer Pressure:
-0.3 psig 2
Concentratio : 5.1 x 10-5 uC1/cc Kr-85
! (Sampie Naken 9/23/81)
, Effluent and Envirbnmental (Radiolecical) Infonra ion 1.
Liquid eff1ttents from the TMI site released t'o the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements,and City pf Lancaster Agreement dated February 27, 1930.
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I During the period September 18, 1951 through Septer.ber 24, 1931, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources which origincted within Unit 2 contained no deter. table radicactivity.
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Environmental Protection Agency (EPA) Environmental Data.
Resuits from EPA monitoring of the environment around the THI site were as follows -
The EPA measured Kr-85 concent' rations (hCi/m ) at several 3
environmental monitoring statipns and reported the following resul ts :
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Location
. Aucustt28 ^ Sectember 11, 1981 3
(PC1/m )
Goldsboro 29 e
Observation Center 31 Middletown 33 Yorkhaven 21 4
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All of the above levels of Kr-85 are considered to be back-ground levels.
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No radiation above normally oc, curring bdckground levels wa's detected in any of the samples; collected from the EPA's air and gamma rate networks duringi the period from September 16, 1981, through September 24, 1981.
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NRC Environmental Data.
Results from NRC moditoring of the environment around the THI site were as fbliows-I l
The following are the Nic air ' sample andlytical results for the onsite continuous a.+. sampler:
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I -1 31 Cs-137 Samole Period I
(uCi/ce)
(_uci/cc) 1 HP-286 September 17,1981-September 24, 1981
<9.7 E-14 <9.7 E-14 l
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Licensee Radioactive Material and Pidwaste Shipeent's, i
i On Monday, September 21,1981., a 40 ml linit 2 reactor coolant sample was sent to Babcock and',Wilcox (sE), Lynchburg, Virginia.
i On Thursday, September 24, 1981, 50 dru$s of contaminated laundry were shipped to Tri-State Industkial Laundry, Utica, New fork.
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1 ENCLOSURE B-4 s
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Submerced _Deminera11zer System (50SI.
At app'roximately 6:00 PM on Septemaer 22, 1551, tne licensee com enced tranferring water fro =
the Unit 2 Reactor Building Sump into the SDS. Feed Tanks located in fuel pool "A" of the Unit 2 Fuel Handling Bullding.
The transfer of this water was in preparation for processing approxicately 15,000 gallons as a trial batch to evaluate SDS perfor=ance before processing reactor. building sump water.
Wate'r transfer was completed at approximately 2:0C AM on September 23, 1931.
The system which transfers the reactor building su=p. water thmugh tw un 'erwater filters to the feed tanks operated as expected without problems.
Lccal radiation levels near system components; and piping increased slightly (less than 1 mR/hr general ; area) as expected and returned to normal background following system flushesiwith decineralized wacer when the transfer was ecmpleted.
Sa:ples takan during the transfer indicated that the Cs-137 (the prir.ary gamma radiation esitte-) radioactivity was approximately 100 uCi/ml to 110 uti/sl.
At approximately 6:00 pH on Septe=ber 23. 1951, the licensee commensed processing the reactor building sump water frc= the 505 Feed Tanks through the SDS zeolite ion exchangers to the Unit 2 Reactor Coolant Bleed Tank.s (RC37).
The SDS prccessing train censists of four, eight cubic feet feelite beds in series folloEed by a post filter designed to remove zeolite fines larger than 3 microns (there are approximately 25,400 micions in one inch).
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Initial sampics, after about 2,100 gallons had been processed, indicated that the Cs-137 radioactivity concentration going into the processing train was approximately 90 uti/c:1 to 100 uti/mi and the Sr-90 radioactivity concentratio'n going into the processing train was 3.8 uCi/mi to 3.9 uti/ml. ' The radioactivity exiting the last zeolite bed was 0.000S7 uti/ml to 0.0007.uC/ml.for Cs-137 and 0.012 uCi/mi to 0.017 uCi/ml for Sr-90 The sian:ples indicate a removal efficiency of greater than 99.9% for Cs-137 and approximately 99.5% for Sr-90.
Processing of the 15,000 gaUon batch was cc:pleted at approxicately 11:30 PM on September 25, 1931.
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Rediation levels during processing of the wate'r increased as expected.
General area radiation levels in thie fuel pool areas continue to be less than 1 mR/hr.
In isolated areas' in contact with shielding some radiation levels: rose to approximately 40 mR/hr but since personnel :ccess is not necessary in. these areas the m
radiation levels are not considered excessive.
Radiation levels on the SDS component ventilation system roughing ' filter increased to
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approximately 2 mR/hr measured 18 inches from the filter.
The two high efficiency particulate air (HEFA) filters, and charcoal filters downstrea= of the roughing filter did not indicate any increase in radiation level.
The radiation level operations.
Ecwnstream filters in th.s may be the result of sacpling e SDS ventilation system and the fuel t. ndling building filters process this air to ensure that there is no radioactive release to the enviror.r,ent.
No increase in effluent levels has been detected by the SDS ventilation eenitor ENCLOSUn B nor the plant effluent ronitor.
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l On September 26, 1981, at approximatejly 3:30 AM, the licensee corcenced transferring 50,000 gallons of water-from the reactor building sump to the SDS Feed Tanks ' This transfer was completed on September 27, 1981, at approximately 12:30 PM.
Processing of th'e 50,000 gallons commenced at approximately 6:00 PM on the same day and is expected. to be completed in approxift.ately one week.
Reactor Building Integrity Assessmend Program.l, The licensee has 2
'esablished an ongoing program to monitor all potential leakage paths from the Unit 2 Reactor Building (RS) sum The leakage monitoring points include the 15 test borings l(p. ground water monitoring wells), storm drainage areas, cork seals (conc ~ rete joint seals) in structures surrounding the RB, and the tendon access gallery (a passageway surrounding the RB below the basement, approximately 20 feet below the water surface in the RB). l Following' a licensee engineering evaluation, the areas mentioned above were identified as the most likely places where the leaks from the R3 would be detected.
Water samples from the monitoring points were initially collected and analyzed weekly.
After a data base Was estab1!!shed..the licensee reduced the sampling frequency to monthly.
There has been no significant change;in the wa'ter radioactivity concentration.
The latest analyses (samples taken on June 10, 1981) indicate that tritium concentrations'in most test borings remain slightly above background.
The highest tritida concentration was approximately 10 times above background.
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Reactor Building Entry.
The sixteenth entry i'nto the Unit 2 Reactor Building (RB) was completed on Thursda'y, September 24, 1 981.
Ten persons entered the RB.
The tasps inside the building included the following.
l Inventory of defueling tools, l
l Photographs to support future operations,!
l Radiological surveys to characterize the 'RB,
.s Sump sample under Reactor Coolant System.(ECS) Drain Tank 1
l rupture disk, j
R3 air cooler bearing temperatu're readings, and Sump water transfer hose survey l (following transfer of 15,000 gallons 5
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l There was no significant change in the radiolo'gical can'ditions I
I inside the RB after the first 15,000' gallons of sump water were pumped to the SDS.
The sump water level was Towered by approximately i
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21/2 inches by the water transfer. 'The only cetectable radiological i
change was an increase of approximately 100 mR/hr on contact with a hose coupling on the sump water transfer hose.
The transfer hose i
was flushed prior to the entry.
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The 100 mi sample from the RB sump was murky and had radiation levels similiar to water samples taken previously,1.b., approxicately 1 R/hr on contact.
The sample device was dnigned to' collect water and particulate matter from the floor on'the 282 ft level of the PS.
8 The sample was taken in the area under the discharge of the RCS Drain Tank rupture disk where particulate matter was expected.
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Work on the RB air coolers was limited by higly radiation levels to a total of seven minutes.
Two men climbed to 'the top of the coolers i
and measured three fan bearing RTD's (bearing 'te:nperatures) before being directed to exit the R3.
The exit criteria for the cooler task was 700 mR total body exposure.,
f The next F3 entry is scheduled for the third qeek in October.
Ibdification of Reactor Buildino Penetration. ' Penetration No. 401 4
is a 12 inch diameter peretration through the reactor building (RS) wall at the 292 foot elevation.
This is appro'ximately 9 feet above the RB basement floor.
The penetration was modified after the
.1 accident to allow the ligensee to obtain samples of the contaminated water in the RB bast. ment.
It was closed by a :12-inch diameter gate valve and cover assembly.
The penetration was mdified a second time.to allow the licensee to insert a flexible tube into the F3 for measurements of the height of water in the PS basement.
The latest modification upgrades the' penetration' closure, replacing the gate valve and cover with a 12-inch circular assembly that is 3
welded in place.
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The licensee started the modification on September 24, 1981, worked around the clock, and completed the task on September-26, 1981.
a M;eting Attended i
On Tuesday, September 22, 1981, Lake Barrett met 'w th area mothers to discuss the September 11. 1981 Reactor Coolant 5.! stec leak, reactor vessel embrittlement, NRC investigation of Unit 1 operat;r examinations. SCS operations, and general Unit 2 cleanup.
The mothers express.d !the opinion that Unit I rJould not be restarted prior to the completion of' Unit 2 cleanup.
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Future Meeting On Tuesday, October 13, 1981, Lake Barreth will address the Dawningtown Rotary Club to give an update on the cleanup efforts at TMI and discuss l
the functions of the NRC.
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ENCLOSURE B i
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0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending September 25, 1981 IAEA Design Features Study On September 21, SGMD's contractor (PNL) and subcontractors (SAI and EXXON) held a briefing on the draft final report on Design Features to Facilitate Safeguards at Mixed 0xide Fuel Fabrication Facilities.
Members of the Interagency Action Plan Working Group for Strengthening IAEA Safeguar' (ACDA and DOE) as well as NRC staff (NMSS and IE) attended and provideu comments. This report along with two previous ones will be used to support the U.S. position at the IAEA Advisory Group in December.
TVA Edoemont, South Dakota, Uranium Mill Decomnissioning The Uranium Recovery Licensing Branch, WM, issued a draft environmental statement (DES) related to the proposed decommissioning of tia TVA-owned inactive uranium mill and associated tailings located in Edgemont, South Dakota. The statement addresses alternatives for long-term mill tailings disposal and site clean-up activities.
Subcriticality Measurements ORNL representatives met with NMSS and RES staff members to discus progress made at ORNL in the development of instrumentation to measure the sub-criticality of fuel assemblies and arrays.
It appears the instrumentation may be capable of measuring a keff as ' low as 0.2.
Additional experimental measurements are required to confirm the application of the instrumentation.
ORNL is seeking additional funding to continue the work and improve data processing capabilities.
If the development program is successful, it may be possible to benchmark the reactivity of systems with a relatively small number of assemblies (e.g., fuel storage arrays) and measure the subtriticality of complicated systems where calculations may be overly conservative.
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ENCLOSURE C
Items of Interest 2
Spent Fuel Storage On September 21, NRC staff members met with VEPC0 representatives to discuss spent fuel storage. VEPC0 is considering several options to alleviate storage capacity shortfalls at its Surry and North Anna reactor sites. Loss of full core reserve is projected for the Surry site in 1985 and at the North Anna site in 1987..At each site, use of the space reserved for fuel cora discharge would permit two more years of operation. Options being considered are additional reracking at North Anna (further reracking not feasible at Surry); transshipment from Surry to North Anna; dry storage capacity additions; and an enlarged storage pool for the North Anna Unit 3 capable of handling some or all-of the additional VEPC0 cacacity needs. An operating license was projected for Unit 3 in 1989. No decisions en options or schedule were indicated by VEPC0.
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Meetings - Division of Fuel Cycle and Material Safety 1.
Subject:
Region III State Liaison Officers Meeting Date/ Time:
9/24/81, 10:00 a.m.
Location:
Chicago, Illinois Attendees:
Charles E. MacDonald, Tom Allen, NMSS; State Programs staff and Region III State Liaison Officers 2.
Subject:
Accompanying PNL contractor for facility visit in support of accident source content.
Date/ Time:
9/27-28/81 Location:
New Brunswick, New Jersey Attendee:
Thomas R. Decker, NMSS 3.
Subject:
Attending meeting on incineration of radioactive wastes and low-level radiation exposure at North Carolina State University.
Date/ Time:
9/28/81 - 10/2/81 Location:
Raleigh, North Carolina Attendee:
An-Liang Soong, NMSS 4.
Subject:
Structural review of General Electric packages.
Date/ Time:
10/.16/81, 1:00 p.m.
Location:
Fifth Floor Conference Room, Willste Building, SS Attendees:
Richard H. Odegaarden and C. Vernon Hodge, NMSS
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Subject:
Meeting with officials of Union Carbide Corporation and local officials from Tuxedo, New York, to discuss the Tuxedo Union Carbide Facility.
Date/ Time:
10/1-2/81 Location:
Tuxedo, New York Attendees:
Arthur T. Clark and Windy W. Ting, NMSS; Harold Bernard and Jocelyn Mitchell, NRR; Jerry Roth, IE RI; Frank Wimpey and Ray Roland, SAI; and Union Carbide officials and local Tuxedo, N.Y. officials.
6.
Subject:
ACRS Review of Transportation Certification Branch activities.
Date/ Time:
10/1-2/81 Location:
Oak Ridge, Tennessee Attendees:
Charles E. MacDonald, Richard H. Odegaarden, C. Ross Chappell, William H. Lake, NMSS; ACRS Subcommittee on Transportation and consultants.
7.
Subject:
Discussions regarding General Electric's IF-300 Pressure Relief Valve.
Date/ Time:
10/16/81, 9:00 a.m.
Location:
Fifth Floor Conference Room, Willste Building, SS Attendees:
P.ichard H. Odegaarden and William H. Lake, NMSS and Dave Dawson and Larry Fisher, SE.
ENCLOSURE C
PLANNED MEETfNGS - DIVfSI0ii 0F SAFEGUARDS _
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discuss 1.
Subject:
Mtg. wiin DOT personnel to / prctection of spent fuel shipments and to relate them to DOT's routing requirements Dates:
September 21, 23, 29 and October 7 Location:
Springfield, Ill., Lincoln, Nebraska, Concord, New Hampshire and Reno, Nevada Attendees:
9/21: Carl Sawyer, 9/23: Carl Sawyer, 9/29: Bud Evans 10/7: Tom Allen 2.
Subject:
Meeting with NRC State Liaison Offices from Region 3 to discuss NRC requirements for notification of governors Date:
September 24, 1981 Location:
Chicago, Illinois Attendees:
Tom Allen, SGRI 3.
Subject:
Meeting with Edison Electric Institute on reactor safeguards issues Date:
September 28, 1981 Location:
Denver, Colorado Attendees:
Tom Allen, SGRI 4.
Subject:
DOE experience in resolving MC&A alarms Date:
September 28-October 2,1981 Location:
Los Alamos National Laboratory, Los Alamos, N. M.
Rocky Flats Fabrication Plant, Lenver, Colorado Attendees:
Dr. Withee, SGRI R. Davis Hurt 5.
Subject:
CFE Related Issues Date:
September 28, 1981, 2:00-4:00 p.m.
Location:
DOE, OMA, Germantown Attendees:
John Hockert, paul Baker, NMSS Erick Bragg, L E 6.
Subject:
Physical Security Regulations meeting requested by Mr. Lennart Hansson of the Swedish engineering firm VBB Date:
September 28, 1981, 9:00-11:00 Location:
3th Floor conference room, Willste Bldg.
Attendees:
R. F. Burnett, G. McCorkle, D. Kasun, H. Blumenthal 7.
Subject:
!%eting with B&W to re:olve differences with IE on interpretation of their Fundamental Nuclear Material Centrol Plan Date:
September 29-30, 1981 Location:
Lynchburg, VA Attendees:
D. Zeff, B&W, S. Powers, B&W, H. Bartz, NMSS 8.
Subject:
Meeting with NFS-Erwin to discuss bias corrections and measurement E
control N
Date:
September 29-October 2,1981 C
Location:
Erwin, Tennessee Attendees:
K. Hensley, NFS, T. Lee, NFS, C. Brown, NFS, D. Joy, NMSS L
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Subject:
. Meeting with Energy. Systems Group, Rockwe'l International, to discuss U
physical security measures for Canoga Park CA., facility during the R
phase-out of Category I operations in the r.'xt year.
E Date:
October 7, 1981, 9:00 a.m.
Location:
Willste Bldg., 8th Floor Conference Room C
Attendees:
Energy Systems Group: kayne Myers, Robert Jones, Marlin Remley NRC:
Robert Burnett, George McCorkle, Russell Rentschler, Mike Smith Odell Smith
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Meetings
. Division of Waste Management t
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Subject:
AIF Conference on Waste Form Requirements-Date/ Time:
October 7, 9:00 a.m.
Location:
AIF, Washington, D.C.
Attendees:
Timothy Johnson, WMLL; D. Harward, AIF I
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ENCLOSURE C i
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OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending September 25, 1981 1.
The following Notifications of Significant Enforcement Action were dispatched during the past week:
a.
EN-81-31 Tennessee Valley Authority, Sequoyah Unit 2 - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $40,000 was issued to subject licensee on September 24, 1981.
This action was based.
on apparent items of noncompliance at the Sequoyah facility which resulted.
in exceeding a Technical Specification Limiting Condition for Operation. The f
immediate cause of the event was a failure to return three recirculation valves in the containment spray system to their normally locked-shut position, as required by procedure.
ihis failure rendered a system designed to prevent or mitigate a serious safety event unable to perform its intended function.
b.
EN-81-32 Public Service Electric and Gas Company, Salem Nuclear Generating Station, Units 1 and 2 - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $40,000 was issued on September 24, 1981 to-subject licensee. This action was based on apparent items of noncompliance at the Salem facility which demonstrated inadequacies in the management of the licensee's physical security program. These itens concerned the abuse of the. licensee's photobadge system by the site security force.
2.
Preliminary Notifications relating to the following actions were dispatched during the week:
a.
PNO-I-81-105 E. L. Conwell and Company - Stolen Radiography Source b.
PN0-I-81-106 Salem Nuclear Generating Station, Unit 2 - Extended Shutdown for Steam Generator Inspection c.
PNO-II-81-73A Farley Unit 1 - Unplanned Outage Due to Main Generator Failure d.
PNO-II-81-77 Oconee Unit 2 - Steam Generator Tube Leak
- e. -PNO-II-81-78 Brunswick 1 and 2 - Transportation Accident Involving Radio-dCtiVe Material f.
PNO-II-81-79 Grand Gulf Unit 1 - Offsite Arrest of a Senior Reactor Operator g.
PN0-II-81-80 Farley Units 1 and 2 - Alabama. Power Company Drug Use Investigation h.
PN0-III-81-81 Prairie Island, Unit 1 - Blockage of One Pressurizer Safety Valve i.
PN0-III-81-82 La Crosse Boiling Water Reactor (Dairyland Power Cooperative) -
Loss of Containment Integri.ty ENCLOSURE D v.
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PNO-TMI-81-19 Three tiile Island, Unit 2 - Reactor Building Basement /
Sump Water Transfers k.
PN0-THI-81-20 Three Mile Island, Unit 2 - Reactor Building Sump / Basement Water Processing 1.
PNO-TMI-81-21 Three Mlle Island, Unit 2 - Reactor Building Sump / Basement Water Processing (Update) 3.
The following IE Information Notice was issued:
a.
IE Infomration Notice 81-29, " Equipment Qualification Testing Experience",
was issued on September 24, 1981 to all nuclear power reactor facilities holding an operating license or construction permit.
4.
The following IE Circular was issued:
a.
IE Circular 81-13, " Torque Switch Electrical Bypass Circui t for Safeguard Service Valve Motors", was issued on September 25, 1981 to all nuclear power reactor facilities holding an operating license or a construction permit.
5.
Other Items:
a.
Region II:
Vogtle conste" an site - On 9/23/81, while making a concrete pour in a confined are i,11 workers were overcome by carbon monoxide fumes produced by a gas *.ne powered vibrator.
Four of the workers requireo continued monitoring at a local hospital.
No serious injuries were sustained.
No PN was issued.
b.
Activities of the Division of Emergency Preparedness:
September 23, 1981 Deputy Director and Chief, IRB, participated at the NRC State Liaison Officer's meeting.
Staff member from EPLB assisted a FEPA Region 3 representative with development i
.of testimony for the Susquehanna hearings.
Staff member from EPLB participated in the Summer hearing.
ENCLOSURE D
September 24, 1981 Director testified on emergency preparedness matters at the Summer public hearing in Columbia, South Carolina.
EPLB and EPDB staff members met with representatives from Florida Power and Light to discuss emergency planning issues concerning St. Lucie 2.
September 25, 1981 Staff member from EPLB participated in the emergency preparedness implementation appraisal exi t briefing and exercise at Maine Yankee.
4 ENCLOSURE D
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. o 0FFfCE OF NUCLEAR REGULATORV RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING SEPTEMBER 25, 1981 Experimental Programs Branch p'
1.
Semiscale The Semiscale MOD-2A is being reassembled as a two loop system.in preparatiop for experimental S-NC-7.
This experiment will be the It first natural circulation experiment in the complete facility.
is currently scheduled for September 29, 1981. CC and 50 tests are defined and will take place during the week of September 21, 1981.
2.
LOFT LOFT intermediate size break test L5-1 is on schedule for September 24, 1981.
The test will simulate rupture of the accumulator line on a Calvert For the test, the LOFT accumulator pressure has Cliffs type CE plant.
been set at 220 psi.to correspond with that of Calvert Cliffs. Although no fuel damage is expected, the core is predicted to partially: uncover.
Tests The L5-1 test fill in the spectrum of break sizes run at LOFT.
have now been run for small, large and with L5-1 intermediate size breaks.
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3.
BWR Full Intearal Simulation Test (FIST) 18, 1981 A meeting of the BWR BDHT Research Review Group was held on September to review the results of completed LOCA testing in the TLTA and plans for the FIST upgrade. Two major connents made at this meeting are:
RES should make definitive recomendations to NRR cor.cerning 1.
the results of the completed TLTA LOCA tests, and Heat loss and heat capacity of the FIST facility should be 2.
evaluated carefully and minimized to the extent practical.
INEL staff are continuing to support the FIST design effort. Major activities have been in reviewing the scaling studies, providing instrumentation support and investigating ways to minimize heat INEL has recommended a low energy densitometer system for loss.
Details of the required penetrations will be core void measurements.
provided to GE prior to vessel manufacture to allow possible use of such a system in the future.
4.
NP.0/RSR Data' Bank Development of the Data Bank User's Manual is being actively pursued so that the manual will be completed and ready for distribution by end User interest in the data bank software and data continued -
ofiY 1981.
to expand as two new users were authorized and recsived accounts to use the data bank.
Four additional tests were added to the bank; LOFT L6-7, Semiscale UT-1 and UT-2, and SB4A.
ENCLOSURE E
s 5.
BDHT Procram i
The Series I Small Break LOCA tests have been analyzed by ORNL.
Three NUREG reports describing the bundle heat transfer analysis, r
the high pressure reflood analysis and the two-phase mixture level s vell results, have been published. They are NhREG/CR-2052, NUREG/CR-2114.and NUREG/CR-2115, respectively.
6.
PWR Heat Transfer' Evaluation Procram ORNL is currently establishing the necessary computer accounts to obtain a variety of U.S. and foreign experimental heat transfer data for coe.parison with licensing modele and correlations.
7.
2D/3D A series of 2D/3D project meetings will be held on October 1 thru s
October 9,1981.
First, the instrument development loop (IDL) testing will be reviewed and discussed at ORNL on October 1-2 by NRC and FRG representatives. Next, instrumentation flow ranges and accuracies will be discussed at NRC on October 5-6 by NRC, FRG and JAERI representatives. Then, the 2D/3D program ltaders from each country will meet at NRC on October 7-8 to agree on cost reduction measures which will be submitted tc Technical Coordination Committee i
and Steerira Comnittee for approval. Finally, UPTF data acquisition system (DAS) will be discussed at NRC on October 9,1981 to establish a general framework for UPTF DAS procurement by U.S.
Fuel Behavior Branch 1.
Charcoal Filter Testino (Not for inclusion in E00 summary)
Recently testing was initiated on the effects of high radiation deses on activated-impregnated chercoals of the type used in current ESF filter systems at nuclear plants.
In the most recent tests, f used (wetthered) charcoal were irradiated to dose of 10gur samples of rads in the LINAC Electron Accelerator at the Naval Research Laboratory.
Prior to irradia-tion, these samples were tested for organic iodide penetration and were found to be severely degraded relative to-their "as-new" performance.
Unexpectedly, following irradiation, these charcoal samples were restered to better than new-charcoal efficiency.
Future work will be directed at comparing the effects of similar dose levels of gamma irradiation (as compared to the LINAC) and to determining what the threshold dose level (or dose rate) is for rejuvenation of the charcoai.
S ENCLOSURE E Q
e 0FFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST-1 WEEK ENDING S5PTEMBER 25, 1981 Diablo Canyon Nuclear Power Plant, Units 1 and 2 On September 21, 19'81, the Commission issued a Memorandum and Order (CLI-81-22) ir; which it authorized.the issuance of a license permitting fuel. loading and 'iow-power testing at Unit 1.
Dresden Station, Units 2 and 3 Cn September 24, 1981, the presiding ASLB issued a Partial Initial Decision which authorized the modification of the operating license to permit installation of five high-density spent fuel storage racks at Unit 3.
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ENCLOSURE F
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING SEPTEMBER 25, 1981 NRC-PRC Exchange Proposal Nears Acceptance The State Scientific and Technological Commission (SSTC) of the People's Republic of China appears to be nearing agreement on the text of the " protocol" for coopera-tion in nuclear safety matters which NRC proposed, at their request and with Commission and 5 tate Department concurrence, late last year.
IP has only two seemingly minor matters to clear up on their most recent comments.
The Second Meeting of the PRC-US Joint Commission on Scientific and Technological Cooperction is being ' scheduled in Washi.mton October 15-17, 1981.
It will be chaired on the U.S. side by G. A. Keyworth, the President's Science Advisor; on the Chinese side, by Vice Premier Fang Yi, Minister in Charge of the SSTC.
The Chinese (and Mr. Keyworth) hope that NRC will be able to conclude the protocol during this meeting.
IP will keep you advised of further developments.
4 State has asked that a Commissioner be prepared to sign for NRC, if all arrangements can be worked out and remaining issues resoived in time.
Foreign Visits to NRC
- t On Tuesday Mr. Jean Hamard of the French Institute of Protection and Nuclear Safety (IPSN) began a or.e-week program to participate in the NRC observation of the emergency preparedness exercise at the Maine Yankee Nuclear facility.
Mr. Hamard, who is resconsible for the IPSN's reaction to the radiological consequences of accidental releases and transportation accidents in France, was made an integral part of the NRC observation team during this exercise.
Additional foreign regulatory personr.el, with immediate responsibility for emergency preparedness activities in their own countries, are being selectively scheduled to participate in future exercises.
On Tuesday a five-member group from West German reactor verdor Kraftwerk Union (KWU) met with F. Rowsome, Deputy Director of the RES Division of Risk Assessment, to discues various issues related to probabilistic risk analysis.
On Wednesday Robert Senseney, IP, addressed a group of 14 foreign nationals, representing energy, research, and government organizations in Australia, Chile, Columbia, Czechoslovakia, Egypt, France, Guatemala, Hungary, Israel, Netherlands Antilles, Norway, Switzerland, Sudan, and Venezuela.
They were provided with an overview of NRC and our international cooperative programs. The group, under sponsorship of the U.S. International Communication Agency (ICA), is visiting various government and commercial organizations examining a variety of energy sources.
They are scheduled to visit the TVA during the period of September 25-30, and Sandia and Los Alamos National Laboratories during the period of September 30 - October 4,1981.
On Wednesday Dr. Luiz Arrieta of the Brazilian National Commission for Nuclear Energy (CNEN) met with F. Rowsome, Deputy Director of the RES Division of Risk Assessment,to discuss risk assessment methodology and related issues.
ENCLOSURE G
2 Mexican Nuclear Power Program The Mexica.n Secretariat of National Property and tne Director General of the Federal Electric Comission -(CFE) announced on September 23 Mexico's decision to add an additional 2,300 MWe to the Laguna Verde-Nuclear Power. Station.
- Specification for bids will be released October 5.
Invited vendors include:
GE, Westinghouse, C.E., AECL- (Canada), ASEATOM (Sweden), Framatome (France),
and KWU (FRG).
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i ENCLOSURE G 1
o Foreign Reports s--
Deleted from PDR copy.
Ef4 CLOSURE G
- Indicates the reports are in English
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.o OFFICE OF STATE PROGRAMS-ITEMS OF INTEREST WEEK ENDING SEPTEMBER 25, 1981 On September 23 and 24,1981, Region III and OSP sponsored a State Liaison Officers' meeting in Chicago, Illinois. Approximately 50 people attended, including representatives from each of the eight Region III States, FEMA, NRC Headquarters and Region III and several licensees.
Emergency preparedness, low level waste compacts, spent fuel shipments, SALP and other significant issues were addressed.
A special presentation of the OSP Inspection Procedures ' course will be made September 28 - October 2,1981 in Arlington, Texas for 25 new professional empicypes of the Texas Bureau of Radiation Control.
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ENCLOSURE H
0FFICE OF ftAfiAGEf'.EPF. AhD PROGRAF 1 AriALYSIS Items of Interest WEEK EtlDI!4G SEPTEtiBER 25, 1981 Backup for Congressional Meeting Completed background information paper for Chairman Palladino's meeting with Rep. Bevill.
Publication Distributed " Standards Development Status Summary Report" (Green Book),
fiUREG-0566, with data as of August 31, 1981.
Ef4 CLOSURE I
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING SEPTEMBER 25, 1981 DOE-NRC Exchange of Operational Data Discussions were held with DOE (J.'Maher, R. Barber, and G. Redden) regarding the sources and types of operational data and related analyses and feedback documents involved with NRC activities. DOE was intercsted in assuring that they were knowledgeable concerning significant operational problems occurring
.in NRC-licensed activities in order to evaluate them for relevance and signifi-cance to DOE facilities and activities. DOE will provide NRC with specific requests regarding the desired documents and distribution. Additionally, 00E will continue to provide information on unusual occurrences which occur at DOE facilities for NRC information.and evaluation. NRC participation in the meeting included AEOD (J. Heltemes and K. Black); NRR (G. Holahan); IE (E. Jordan); and CON (C. Beckwith).
9 ENCLOSURE K
- o 0FFICE OF SMALL AND DISADVANTAGED BUSINESS UTILIZATION Items of Interest Week Ending September 25, 1981 On September 23, 1981, the Associate Administrator for Minority Small Business held a fact-finding public hearing'into the. proposed SBA regulation to establish a fixed period of time.for every participant concern to remain'in the 8(a) program. The. proposed SBA rule would establish as a graduation date from the 8(a) certification. program either 3 or 5 years depending on the nature of work or services.
This view came under attack from many disadvantaged firms and women-owned businesses. The thrust of their argument is that the duration for which a firm is eligible for 8(a) assistance should be dependent on factors and circumstances unique to each firm and therefore should be negotiated on a case-to-case basis; that 3 to 5 years is an insufficient period.of. time for realizing maturity in the market place; and that com-petitive viability including assessibility to capital should be the criteria not an arbitrary time period. Many firms with less than 500 employees and gross revenue of one-million dollars are still small businesses under SBA criteria. However, the point was made that such firms would virtually be destroyed if they were permanently removed from the small or disadvantaged business utili2dllon programs.
It was suggested that SEA itself should be more aggressive in its support of their.own programs both from a financial and management support stand point.
ENCLOSURE L g
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..o ITEMS APPROVED BY THE COMMISSION - WEEK ENDING SEPTEMBERj5,1981 A.
SECY-81-519 - APPROVAL OF A PROPOSED LICENSE TO EXP0RT HIGH-ENRICHED -
URANIUM TO CANADA (XSN'401627), Memo SECY to Dircks, September 22, 1981 This is to advise you that the Commissioners have reviewed the subject license to Transnuclear, Incorporated.
The Commission (with all Commissioners approving) has accepted-your recommendation to export to Canada 191.0 kilograms of uranium, enriched to 93.3% U-235, in the form of uranium metal.
The Office of International Programs was informed of this action by. telephone on September 22, 1981.
B.
SECY-81-330A - LOW-LEVEL WASTE VOLUME REDUCTION, Memo SECY to Dircks, September 22, 1981 This is to advise you that the Commission (with four Commissioners approving and Commissioner Gilinsky disapproving) has approved the proposed policy statement on low-level waste volume reduction with the following modification.
The Commission believes that it is advisable to include references for equipment that needs NRC approval' directing attention to appropriate rule or regulation.
The Office of Nuclear Material Safety and Fafeguards was informed of this decision by. telephone on-September 22, 1981.
It is requested that you forward the Federal Register Notice, as modified by the Commission, to the Office of the Secretary for s~ignature and dispatch.
C.
STAFF REQUIREMENTS - VOTE ON LOW-POWER OPERATING LICENSE FOR DIABLO CANYON, 2:20 pm, MONDAY, SEPTEMBER 21, 1981. Memo for the Record from SECY, September 23, 1981 The Cortmission by a vote of 5-0 approved an ' order authorizing a low-power operating license for Diablo Canyon.
ENCLOSURE M O
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