ML19345G459
| ML19345G459 | |
| Person / Time | |
|---|---|
| Issue date: | 04/03/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810327, NUDOCS 8104070284 | |
| Download: ML19345G459 (37) | |
Text
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f APRd61981r 0]
Aoril 3, 1981
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sa, For:
The Comissioners 4%ine d
From:
T. A. Rehm', Assistant for Operations, Office of the E00
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Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 27, 1981 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Standards Development C*
Nuclear Material Safety and Safeguards 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 K*
Analysis and Evaluation of Operationel Data L
~ Small and Disadvantaged Business Utilization M*
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Items Approved by the Comission N
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I T. A. Rehm, Assistant for Operations i
Office of the Executive Director l
8104070 EbR for OPer8tio"5
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- No input this week.
CONTACT:
l T. A. Rehm, 27781
SUMMARY
OF THE WEEKLY INFORMATION REPORT Week Ending March 27, 1981 Risk Assessment Studies The licensees for Indian Point and Zi'on informed the NRC that they will not 1
be able to complete their probabilistic risk assessment studies as early as previously expected. They need more time to allow for an independent technical review of the contractor's reports and a full review by the licensees.
The reports are now scheduled to be available in June 1981.
Hydrogen Program The Sandia hydrogen program manager testified for 2 days at the McGuire licensing hearing at Charlotte, N.C.
A Sandia consultant, who also testified, presented at a later meeting in Bethesda the results of his experiments on accelerated flames and transition to detonation. He pointed out t.iat flame folding resulting from turbulence or passage of the flame front through a field of obstacles increases the volumetric energy release and greatly accelerates flame speeds to produce high impulse loads. Specific features of the McGuire plant were considered.
LOFT Test The first multi-failure test, which will be initiated by a loss of all feeawater, is scheduled for April 15.
It is expected to cause a loss of natural circulation and a core boil-off.
Technical Bases-Report of Fission Product Behavior l
l A peer review (or critical review) of the report was conducted on March 17 l
and 18. The reviewers, as well as the ACRS, agree with one of the key findings of the report, namely, that there are many gaps in the data base and large uncertainties in a number of methods used for estimating fission product behavior.
l BWR Scram System Leaks Outside Containment I
AE00 just completed a study on the adequacy of the BWR scram system design l
with regard to the reactor coolant boundary and primary containment functions.
The study raised important additional issues and safety concerns on isolation capabilities of the scram system and operation of the emergency core cooling systems for SDV pipe break situations.
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OFFICE OF ADMINISTRATION Week Ending March 27, 1981 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Recuest In,1cial Decision Received 1 64 3
Granted 95 0
Denied 11 0
Pending 58 3
ACTICNS THIS WEEK Received Paul S. Davis Requests information egarding the MUF total for (81-109) weapons-grade U-235 tnat led to the closing of NFS-Erwin during four months in 1979.
J: Anne G. Bloom, Requests, cr. behalf of Connonwealth Edison Company, Isham, Lincoln & Beale seven categories of documents from October 24, 1980 (81-110) relating to the Notice of Violation attached to Appendix A to the letter from Mr. Victor Stello to James J. O'Connor dated October 21,1980, all documents regarding standards, criteria, statements of policy relating to the imposition of civil penalties by the NRC and all documents relating to the responsibilities, behavior and deportment of NRC licensed Fuclear Station Operators.
Catherine Crawford Requests a copy of three listed documents.
(81-111)
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E. ;!d C. Lilly, Requests the names and addresses of companies Container Products involved in the manufacture and/or processing of Corporation radioactive materials.
(81-112)
Adam Paul Banner Requests a copy of' National Bureau of Standards Test (81-113)
Reactor; Availability of Applicant Environmental Report and Notice of Intent to Publish an Environmental Impact Statement published in the Federal Register on March 10, 1981.
CONTACT:
J. M. Felton 492-7211
-ENCLOSURE A
2 Received, Cont'd Jeff Alexander Requests a copy of four listed documents relating to (81-114)
Perry I and II Nuclear Power Stations.
(Individuals requesting Requests information on their Reactor Operator information about themselves)
License written and oral examinations.
(81-115 and 81-116)
Duane C. Mansley, Requests a copy of the winning bid under Invitation Allen Photo Service, Inc.
for Bid No. RS-ADM-81-387 and a list of contractors (81-117) who have had that contract for the past four years.
Mary Hargrove, Requests all audits, memos, inspection reports, The Tulsa Tribune cost-related reports and timetables relating to the (81-118)
Black Fox Nuclear Plant under construction.
Richard A. Udell, Requests a list of all the Licensee Event Reports Critical Mass (LER) for calendar year 1980 and access to a computer Energy Project search for listed types of Licensee Event Reports (81-119) in 1980 by name of reactor, date of event and LER number.
John Dillon, Requests letters from FBI Special Agent Welch to Jack Anderson Boyce Grier, Region I and Grier's replies regarding
'(81-120) allegations made by an employee of the Haywood Tyler Pump Company in Vermont concerning improper quality assurance and quality control programs.
Kay E. Bustani Requests copies of all of the " exceptions, alternatives.
(81-121) or clarifications" which nuclear utilities, nuclear steam system suppliers and architect / engineers have been granted for operations or construction QA programs.
Jody L. Furman Requests information on the number of raclear power l
(81-122) plants constructed within the U.S. during the period l
1970-1981 and how many of these facilities are I
currently in operation and in what states they are located.
Granted Charles A. Green, In-response to a request for a copy of the staff i
Knight-Ridder Newspapers study on the potential of presently licensed sites (80-586) to cause significant radiation exposure to surrounding l
population-in the event of a severe accident, made-l available a copy of this document.
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i ENCLOSURE A z
3 Granted, Cont'd Reverend Walter J. Waldron In response to a request for copies of citations or (81 -39) violations relating to the New England Nuclear Corporation in Boston, Massachusetts; infomation on Now the company transports its nuclear waste; and whether or not they flush radioactive byproducts into the Boston sewer system, made available eight documents.
Greg Wingard In response to a request for documents between the
( 81-53)
NRC's Office of State Programs and the Washington State Department of Social and Health Services, Radiation Control Section, in regard to the Office of State Programs 1981 Annual Compatability Review, informed the requester the NRC has no documents subject to this request.
(NRC employee)
In response to a request for three categories of
( 81 -71 )
infomation regarding 79 listed vacancy announcement packages, made available 60 documents.
Inf m d the requester 22 vacancy packages could not be lcund.
Frank J. Munno In response to a request for a copy of the cost-(81-83) benefit analysis in support of the new policy and procedures for enforcement actions, infomed the requester that no cost benefit analysis was performed.
Janice F. Rutherford, In response to a request for a e.opy of contract The BDM Corporation number NRC-04-77-065 and any subsequent modifications (81-87) or amendments, made available 11 documents.
-(An individual requesting In response to a request for all documents in the information about himsel ')
NRC on himself, infomed the requester the NRC has (81-88) no documents on him.
Anne Rapkin, In response to a request for infomation on radioactive State of Illinois monitoring and sampling emissions regarding the Kerr-(81-96)
McGee Chemical Corporatien in West Chicago, Illinois,,
made available this information.
Lisa M. Newell.
-In response to a request for copies of regulations, Gary Howard Simpson, P. A.
policies, maps, etc. used by the NRC concerning (81-102) the definition of "cournuting area" pursuant to Federal Personnel Manual (FPM) Chapter 351-4-4, infomed the requester that the NRC has adopted the FPM definition and therefore no regulations were issued.
i ENCLOSURE A
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Grantec, Cont'd Catherine Crawford In response to a request for a copy of four listed (81-111) documents, made available access to these records.
2 (Individuals requesting Made available their Reactor Operator License information about themselves) written and oral examinations.
(81-115 and 81-116)
D'nied Christopher B. Hanback, In response to a request for all documents relating Hill, Christopher and to the Commission's February 20, 1981 Order in the Phillips, P.C.
Diablo Canyon physical security proceeding, made (81-84) available one document. Denied 17 documents in their entirety containing pre-decisional advice, opinions and recommendations and draft orders.
- Douglas 0. Lee, In response to a request for four categories of Americans for documents relating to the NRC's release of spent Nuclear Energy, Inc.
fuel routing and other shipment information to the (80-635) public, made available 21 documents. Denied six documents in their entirety containing advice, opinions and recommendations of the staff.
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ENCLOSURE A
DIVISION OF CONTRAU.S Week Ending March 27, 1981 RFP ISSUED 1.
RFP RS-RES-81-178 Title - The Degraded Piping Program Description - This study will plan a comprehensive experimental program to demonstrate the capacity of cracked piping to withstand postulated accident and transient loadings and to evaluate the calidity of tearing instability fracture mechanics analysis as an analytical technique for predicting the loading capacity and failure mode of piping that has or is postulated to have significant cracking.
Sponsor - Office of Nuclear Regulatory Research Period of Performance - Nine months Status - RFP Issued on March 23, 1981 2.
RFP RS-RES-81-195 Title - New Madrid / Midwest Continent Geological and Seismological Research Program Description - To conduct confirmatory geological and seismological research in the mid-continent area. There will be two geological tasks; one to investigate the possible extension of the New Madrid Fault Zone and the other i to evaluate the major fracture zones in the New Madrid area. There will be four seismological tasks which include the installation and operation with data analysis of seismographic networks in four. areas:
the Wabash V-11ey, New Madrid, Anna, Ohio, eastern Indiana, northern Illinois and southern Wisconsin.
Sponsor - Office of Nuclear Regulacory Research Period of Performance - Three years for each task, with options for two additional years for each task Status - RFP issued on March 23, 1981 ENCLOSURE A
. PROPOSALS UNDER EVALUATION 1.
RFP RS-RES-81-179 Title - A Study of Earthquake Hazards in N.Y. State and Adjacent Areas Description - The objective of this contr=ct is to continue menitoring N.Y. State and adjacent arcas as an integral part of the program for the northeastern U.S.
Period of Performance - Three years with an option for two-one year periods Sponsor - Office of Nuclear legulatory Research Status - Solicitation closed March 13, 1981 SEP members received technical preposals on March 17, 1981 for their evaluation.
Competitive range established, cost proposals issued March 26, 1981 2.
RFP RS-RES-81-163 (formerly RS-RES-81-235)
Title - Seismic History of the Eastern Seaboard from New York to Norfolk, Virginia Description - The work to be accomplished under this contract comprises a comprehensive search of all available
. records in major respositories throughout the northeastern United States for the purpose of discovering new information on earthquake occurrence and effects. The region to be surveyed extends from New York City to Norfolk, Virginia and includes
. the Appalachian Mountains within its western boundary.
The historical period to be covered extends from the earliest records available up to 1930. The results of this search is to be published in a catalogue, suitable for interfiling with existing catalogues.
Period of Performance - One year Sponsor - Office of Nuclear Regulatory Research Status - Final Evaluation Report received on 3/11/81. Coatract mailed to contractor on 3/16/81.
FINANCIAL ASSISTANCE
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NRC-G-04-81-006 Title - Third Conference on Waste Heat Management and Utilization Description - The purpose of the cor ference is to update the knowledge of scientists dealing with separate facets of the bio-chemical balance rf ecosystems due to thermal discharges.
Thermal anomalies over the natural temperature distribution can cause changes in dissolved oxygen content, biochemical oxygen demand, increase in solinity,'etc. A possible consequence at the minimal ENCLOSURE A -
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level is the deterioration of recreational marine systems with ultimate harmful effects to humans possibly resulting.
Period of Performance - T' ree and one-half months n
Sponsor - Office of Nuclear Regulatory Research Status - Grant awarded to the University of Miami in the amount of
$5,000.00 effective March 18, 1981 CONTRACTS CLOSED OUT (All
- istrative action completed and final payment made)
Contract No.
Contractor Closecut Date NRC-03-78-157 Gene Rhodes 3/19/81 NRC-03-79-139 Donald Harleman 3/20/31 NRC-04-78-241 University of Mississippi 3/16/81 NRC-04-78-196 Dr. George E.P. Box 3/11/81 NRC-04-78-210 Science Applications, Inc.
3/25/81 NRC 02-79-038 Mason & Hangar 3/25/81 NRC-ll-80-403' Dr. D. Underhill 3/23/81 NRC-10-78-394 L.J. Hampton Associates 3/26/81 r
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ENCLOSURE A
DIVISION OF SECURITY Week Ending March 27, 1981 Classified Safeguards Program (CSP) Trainina Course ORI, Inc., an NRC contractor, delivered the final course material for the OIE CSP training course.
Copies are being distributed to affected Offices and Divisions.
Upon approval of this material, the course will be conducted for NRC personnel.
Integrated Safeguards Information System (ISIS)
A meeting of NRC ISIS participants, including representatives of the Division of Security, was held to discuss the DOE response on the ISIS Request for Proposal.
TMI-related Demonstration Division of Security coordinated with the Harrisburg Police Department on a pro-posed demonstration to take place on March 28, 1981, in Harrisburg, PA. The organizers expect 20,000 people and are working with the Police Department to assure a peaceful demonstration. No problems are anticipated and three extra patrolmen are expected at Strawberry Square, Harrisburg, PA, which contains the Three Mile Island ASLSP Hearing facilities.
NRC Secure Facsimile Network GSA demonstrated the operation of the NRC Secum Facsimile Network, which presently consists of two terminals, one in the Willste Building Secure ADP Center and the other in the H Street Building secure vault. Two future terminals are planned, one for East-West Towers and one for the Phillips Building. An FOS representative is preparing operational precedures for the DACCM secure facsimile network.
Personnel Security Processing Division of Security requested OPM and D15 (Defense Investigative Service) to make available prior investigations in their possession on applicants for NRC security clearance to expedite their NRC clearances.
The part-time Personnel Security Branch staff member in O&P reviewed 20 security i
packets on-site in order to expedite the employment / security processing of NRC applicants.
l NUREG 0711, " Protection of Classified Information and Matter" l-Coments have been received on this NUREG document which provides implementation l
guidance to licensees and or.hers affected by 10 CFR Parts 25 and 95. The document l
-is being prepared in final form.
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ENCLOSURE A v
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1 OFFICE OF NUCLEAR REACTOR REGULATION a
WEEKLY HIGHLIGHTS - MARCH 27, 1981 Control Room Evaluation 7he staff has issued " Staff Supplement to the Draft Report on Human Engineering Guide to Control Room Evaluation" {NUREG-0659). The supplement was issued to provide the staff responses to comments on a draft report, " Human Engineering Guide to Control Room Evaluation" (NUREG/CR-1580), and to provide supplemental Two items which were omitted material not contained in the draft report.
from the earlier draft report are draft system review guidelines for c)nducting a systems review of the control room, and checklists for use with the human engineering guidelines.
The Notice also The availability of NUREG-0659 was noticed in the Federal Recister.
identified two public meetings to be held in Bethesda, Maryland, on April 22 and 24,1981 between the staff and members of the public, utility representatives, human factors engineering experts, and other interested parties. The principal purpose of these meetings is to review the guid; lines and the licensee / applicant Comments received by the staff at these two control room design review process.
meetings wil! be used in comoleting the " Control Room Design Review Guidelines",
(NUREG-0700).
Indian Poi,nt Probabilistic Risk Assessment Study Consolidated Edison and the Power Authority of the State of New York informed the NRC that the Indian Point 2/3 probabilistic study would not be available as early as was previously expected. The report is to be similar to the Z.on study report, which is also under preparation, but-will differ by the site specific characteristics. The additional time to complete the study is attributed by the licensee to an independent technical review of the contractor's reports and a full review by the licensees. The report is now scheduled to be available in June 1981.
l Zion Probabilistic Risk Assessment Study ' ~
l Commonwealth Edison Company (Ceco) informed the NRC that the Zion probabilistic risk assessment study would not be available on March 24 as was previously l
The report is to be similar to the Indiar. Point study report, which l
is also under preparation, but will differ by the site specific characteristics.
expected.
The additional time to complete the study is attributed by the licensee to an
-independent technical review of a utility contractor's reports and a full review The report is now scheduled by Ceco to be available in June 1981.
l by CECO.
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ENCLOSURE B "a1
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~ ~ ~ ' 'NAC 'TMI PROGRXM OF: ICE WEEKLY STATUS REPORT Week of March 22-28. 1981 Plant Status 4
- MorrC/41W. -ileat transfer from the reactor coolant systs:c_(P.CS)..
loops to reactor building ambient.
c Available Core Cooling Modes: Long-tenn cooling "B" (once through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode: Standby Pressure Contml (SPC) System.
i Backup Pressure Control Modes: Mini Depay Heet Removal (MD6iR) System.
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. Decay Feat Rern al (DHR) System.
'Majtr Parameters (as of 0500, March 27. 1981) (approximate values)
Average Incore Thennocouples: 121*F Maximun; Incore Thennncouple:
151*F RCS Loop Temperatures:
A B
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ifot ' Leg' il7'F 120*F 1) 67'F 67'F Cold Leg ((2) 67*F 67"F RCS Pressure: 107 psig Reactor Building:
Temperature: 67*F Water level: Elevetion 290.6 ft. (8.1 ft. from floor) l via penetration 401 manometer l
Pressure:
-0.17 psig Concentration: 9.2 x 10-6 uCi/cc (Krypton-85 (Kr-85))
(sample taken 3/23/81)
Effluent and Environmental (Radiological) Information 1.
Liquid effiuents-ivar-i.te 1MI-site released to the Susquehanna River after processing, were maoe wtthin the regulatory limits and in accordance with NRC requirements and City of Lancatter Agree:nent dated February 27. 1980.
During the period March 20, 1981, to March 26. 1981, the effluents
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contained no detectable radioactivity at the discharge point
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--- rithatrgirindividuareffluent sources which originEtec within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less than one millionth (0.000001) of a curie of cesium-137 (CS-137) was discharged.
This represents less than 0.00001% of the permissable total liquid activity as specified in Technical Specifications for operational commercial reactors.
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ENCLOSURE B
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Environmental Protection Agency (EPA) Envircrcental Octa.
Rcsults from EPA monitoring of the environment around tne TM1 site were as follows:
3 The EPA measured Kr-85 concentrations (pci/m ) at several 4
erwtrorveental mnttar-tng stations and reported the following msu,1ts_;___,_,_.
Location-March 13 - March 20,1931, 3
(pCi/m)
Bainbridge 23 Goldsboro 23
-_ Observatten-Center.
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25 Middletown All of the above levels of Kr-85 are considered to be back-ground levels.-
No radiation above,normally occunning.hac.tgecund level,s was octected in any of the samples collected from the EPA's air anc garr.n rate networks during Oc-;:oMod-fren-M:reh 20. 1981, thrtugh March 26. 1981.
3.
NRC Environmental Data.
Results from NRC monitoring of the envirorcaent arwnd the TMI site were as follows:
- -The fol-lowing-are the NRC air sample analytical results for-the onsite continuous air sampler:
(uCf/ce)
(uci/cc)
MP-260 March 18,1981 - March 25,1981
<8.6 E-14 <8.6 E-14 4
Licensee Radioactive Material and Radwaste Shiome rts. The M1cw.im shipments were made:
On Monday, March 23,1981, a 40 ml Unit 2 reactor coolant sa ple was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
Hai* * 'aa"i ncent OtLJuesday, March 24,1981,. thr.ee-one lite-l sump samples were sent to the Oak Ridge National Laboratory, Oak Ridge, Tennessee.
On Wednesday, %4rch 25, 1981, 46 drums and 6 boxes of compacted
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and non-compacted Unit 1 LSA waste were shipped to Chem Nuclear 7'ItMsg trc!TBaTnwill, South Carolina.
On Thursday, March 26, 1981, 65 drums and 10 boxes of compar.ted and non-compacted Unit 2 LSA waste were shipped to U.S. Ecology, Richland, 'iashington..
ENCLOSURE B i-e w
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Major Events 7
1.
Submerged Demineralizer System (SDS), Regi.cn I spect Siets.in instrumentation and preoperational testing perfomed preliminary inspections on the SDS this week.
These inspections are expected l;
to continte for the next three weeks. The fuel poc1, which ccirurtns-stu SDS is expected to be filled with water near the end of April.
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EPICOR-II S wnt Resin Disposal. On March 25, 1981, the NRC revised tJw. unir. Z.icense to provide alternatives to on-site processing prior to ultimate disposal of radidactive EPICOR-II resins. Tirtr-the NRC approved the operation of EPICOR-II in October 1979, the MC TeQGired thet the ym rdT L Le mLud n:1 a L:ods4
.i.a !.c o. a l,
a.g.,
ement, prior to shipment for off-site disposal. This special requirement was established because it was expected that the EPICOR-II reskt radioactivity loadings would be much higher than nomal reactor waters and that they would be disposed of by routine low-level waste l :!
land burial practices.
Since October 1S7.9, nucrubn beeo_ learned I
about the EPICOR-II resins.
The actual radioactivity loadings of Yhe spent' EPICOR-If resir. liners are grouped into either high1y loaded
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resin prefilters or' lower loaded polishing resin beds. The curie l,
enntent of the inwar Inariert FDIC02 I! polishing recint are within the normal ra:.ge of reactor resin wastes.
Consequently, there is no g
need for the addition of a binder material provided that the resin i =I liners are dewatered and meet all DOT and NRC transportation rules and also meet applicable state burial site criterrta. Thh amendmenL f
63 lows prompt shipment of these ibwer ibaded' poi 1'shing resins offt. sin-g for disposal.
The higher-loadel prirmtvrs7re the subject of on-going waste disposal I[
characterization by DOE. This work will determine the method of
'4 ultimate off-site dispostion.
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ENCLOSURE B
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, Meetings Held f
- 1. - en-T=dayr-Mare &-2% 195', Lako4wntt.cet with => m+he-s *n
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-rAiscuss various issues related te nuclear power.
--styk; Utt-the-Tlti uct-itent hks caused severe mental stress and that this stress will continue especially if TMI Unit 1 is restarted.
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Dr.-TeesdSyr. March 24, 1981 Harold Denton_acLLake_Sarrett attacAd
-a meetirety A.of the knerican Society of Zoological Park Managers in Hershey, P Mr. Denton gave an invited after dinner talk and I;,
g responded to questions concerning nuclear power.
3.
On Friday,' March 27, 1981, Congresl an Morris Udall and members of the Energy and Envirorment subcomittee made an inspection tour of
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During their visit, the subcocrtittee mesters met with representatives of General Public-Utilities enil-j 1:he u.s. -Nuclear Regulatory Connission to discuss various irssues--
related to the cleanup process of 'fMI-uirh-hictrossible i
l restart of TMI Unit 1.
Later in the day they met with representatives of the Coalition of Greater Harrisburg Labor Union TMI Alert,
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Building Trades Union, Friends and Family of TMI, TMI Public l
Resource Center and other groups to be briefed on their concerns regarding TMI and then held a press conference for : redia representatives o
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On Saturday, March 28, 1981 Lake Barrett participated on a call-in radio show mrking the second anniversary of the accident on CBS f
affiliated WCAU in Philadelphia.
' uture Mael.ings. _
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On Monday, March 30, 1981, the NRC's Citizens Advisory Panel will meet with Congressman Morris Udall and mecters of the Energy and
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e Enviraranent subcomittee to discuss various issues related to the l
cleanup program for TMI Unit 2.
(I 2.
On Wednesday, April 1,1981, Lake Barrett will meet with members of g
the Susruehanna Valley Alliance to discuss the TMI Progransatic Eavironmentai Impact St.atement.
Representatives of EPA's Independent g
Scientific Advisory Panel will also discuss their findings.
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ENCLOSURE S
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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending March 27, 1981 Meeting with DOE on Spent fuel Storage Technoloev Davelopment on ". arch 25 i
At DOE's request NRC staff from NMSS, NRR and SD net with DOE staff and
' contractor personnel. DOE is restructuring its spent fuel storage program.
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It now does not expect to provide away-from-reactor (AFR) storage capacity for co=mercial reactor spent fuel.
DOE is interest ~d in continuing develop-ment of rod compaction in reactor basins and of dry,torage technologies.
In the meeting, DOE explored the idea of assisting utilities with possible demonstration storage of spent fuel both for rod compaction in basins ani.
for dry storage outside the reactor but on the reactor site. Rod ccmpac. ion could not likely be performed for demonstratic purposes under 510 CFR J0.59.
It would probably require an amendment of the OL which would be reviewed by NRR.
Storage outside the reactor but on site would be reviewed by W.55 and would be covered by 10 CFR Part 72. A stcrage demonstration for research and develo;: ment purposes =ight be reviewed by W.SS under 10 CFR 70 as an amendment to the existing Part 70 license associated v;th the facility or as a separate license.
While noting that 10 CFR Part 72 includes provision to license dry stcrage l
of spent fuel and that SD is ontinuing regulatory guide development regarding
. dry storage, NMSS staff welcomed additional DOE research such as accelerated fuel aging work at the Nevada Test Site EMAD facility and proposed DOE work on fuel corrosion in air studies.
DOE. development of fuel transfer systems for dry storage methods was subsequently cited also.
In considering how it may help utilities in providing for their storage shortfalls by its research and technology development and possible assistance in pecific at site demonstrations, DOE also raised the possibilities of loani.ng equipment to utilities for such demonstration and of submitting a tcpical report on a dry storage design such as cask storage.
While DOE may explore these options fur.ther, it will not become involved as a
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licensee or co-licensee in any demonstration or storage action.
ENCLOSURE D W+e
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Items of Interest 2
Proposa ' to Dispose of Thorium Residue A meieting was held with Robert G. Gallagher, President, Appliec lfaalth Physics, who was representing the owners of the old Moly Corp. site in 'dashington, PA now cw:ed by Union Oil. Moly Corp. possesses approximately 38,000,000 cubic yards of thorium bearing residue which was a waste product from the extraction of molybdenum from are. This glassy " obsidian-type" residue is presently stored
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on the site under NRC license and the owners propose to dispose of the material by land burial on site after mixing it with clean soil to a concer.t.ation similar i
to a natural thorium ore vein.
The proposed burial sites are existing tar pits on the site. Mr. Gallagher was informed that a license application describing the proposed disposal area and an environ:nental report should be submitted for NRC review. Furthennor'!, it was suggested that any proposed burial should be discussed with state of ficials and Mr. Gallagher was informed that alternatives to the proposed course af action, for exam;:le, disposal of the material at the Cannonsburg naterial disposal site, should be included in the environmental report.
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ENCLOSURE D
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Meetines.- Division of Fuel Cycle and Material Safety 1.
Subject:
Site visit in conjunction with license renewal for Teledyne Isotopes Date/ Time: March 26,1981 - 9:30 a.m.
Location: Westwood, New Jersey Attendees:
A. L. Soong (FCUF), Teledyne Representatives 2.
Subject:
Agreement Between EPA and NRC Re Re=edial Action from Sites Contaminated with Radioactive Materials Date/ Time: March 30,1981 - 2:00 p.m.
Location:
Room 562, Willste Attendees:
R. E. Cunningham, R.G. Page and R. Fonner of NRC; Roger Mattson, Roy Johnson and Jack Winder of EPA 3.
Subject:
NRC Training and Experience Criteria for Authorized Users on Nuclear Pharmacy Licenses Cate/ Time: March 31,1981 Location: American Pharmaceutical Association Annual Meeting in St. Louis, Missouri Attendees:
J. De1 Medico (FC) (Mr. CelMedico will speak at a
" Session on Nuclear Phar::acy Education")
4.
Subject:
Licensing of Spent Fuel Casks Date/ Time: March 31,1981 - 11:00 a.m.
Location: Willste Attendees:
C. E. MacDonald, R. H. Odegaarden (FC); Dan Saak, M. Tellttieri of E. R. Johnson, Associates.
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5.
Subject:
Screw Worm Irradiator Cate/ Time: April 1,1981 - 9:00 a.m.
Location: Willste Attendees:
R. H. Odegaarden, J. Fan, J. Jackson (FCTC)
Reps from the Depart 6ent of Agriculture 6.
Subject:
Chem-Nucitar Systems, Inc.
l Date/ Time: April 2,1981 - 1:00 p.m.
Location: Willste l
Attendees:
C. E. MacDonald, R. H. Odegaarden (FCTC)
Reps from Chem-Nuclear Systems, Inc.
1 7.
Subject:
National Council on Radiation Protection and Mear Jtements 1981 Annual Meeting Date/ Time: April 8-9, 1981 1
Location: Washington, D.C.
Attendees:
R. E. Cunningham Absences of Director or Deputy Director R. E. Cunningham - April 8-9, NCRP Meeting i
l ENCLOSURE D l
c
planned Meetings Division of Safeauards 1.
Subject:
Meeting with NFS-Erwin to discuss DOE report recommendations and routine licensing matters.
Date/ Time: March 30 - April 3, 1981 Location: Erwin, Tennessee Attendees:
D. Joy K. Hensley, Materials Manager 2.
Subject:
Meeting with DOE to discuss the Hot Experimental Facility.
Date/ Time: April 7-8, 1981 Location: Germantown, Maryland Attendee:
D. Joy 3.
Subject:
Meeting with B&W, Naval Nuclear Fuel Division, to distcss off site scrap recovery.
Date/ Time: April 9,1981 Location: Silver Spring, Maryland Attendees:
R. A. Erickson C. N. Smith G. B. Gundersen H. McGianahan, Manager, Nuclear Material Control R. Cordani, Nuclear Safety and Licensing Officer H. Heidt, Manager, Recovery Operations.
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C. Anderson, Supervisor, Accountability Operations 4.
Subject:
Meeting with NES to discuss the security requirements associated with the NBS reactor and standard reference materials program.
Date/ Time: April 9,1981 - 9:00 a.m.
Location: NBS Attendees:
R. F. Burnett (SG)
G. W. McCorkle (SG)
D. J. Kasun (SG)
D. Carlson (SG)
H. Bernard (NRR)
C. Woodhead (ELD)
Mr. Kammer, Jeputy Director of NBS 1
ENCLOSURE D 8-'
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Planned Meetines - Division of Maste Manacenenc 1.
Subject:
High Activity, low Volume Waste Generators Date: March 31 - April 1, 1981 Location: Boston, Massachusetts Attendees:
New England Nuclear Co. representatives; R. Browning and K. Jackson, WM/NRC 2.
Subject:
TMI PEIS Date: April 1,1981 Location: Air Rights Building, Bethesda Attendees: NRR; T. Jchnson, WM; P. Twite, ANL 3.
Subject:
Solidification System Date: April 2,1981; 9:30 a.m.
Location: Holiday Inn, Bethesda a
Attendees:
G. Bradley, Chem-Nuclear; R. Browning, P. Lohaus, el al, WM/NRC W
ENCLOSURE D y
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OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending March 27, 1981 1.
The following Notifcations of Significant Enforcement Action were dispatched during the past week:
a.
EM-81-OlA Nondestructive Inspection Service, Inc. - A Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $5,000 was oreviously issued to subject licensee based on alleged violations involving breakdowns in management controls. After consideration of the licensee's response, the IE staff concluded that all but two violations did occur and no adequate reasons were given by the licensee for mitigation or remission of the proposed penalties. Accordingly, an Order Imcosing Civil Penalties in the amount of $4,700 was issued to sJoject licensee on March 25, 1981.
b.
EN-80-52A Niagara Mohawk Power Corporation (Nine Mile Point Unit-1) - A Motice of Violation and Notice of Proposed Imposition of Civil Penalties in the amount of $225,000 was previously issued to subject 14censee.
In additic.-
an immediately effective license modification removing the former Nine Mile Point Site Superintendent from involvement in nuclear activities for the Corporation and an Order to Show Cause why the Executive Vice President should not be removed from involvement in nuclear activity were issued.
These actions were based on~ material false statements ~ submitted by the' licensee under oath. As a result of licensee submittals and meetings with licensee representatives, the proposed penalty was mitigated to $215,000, and a " Withdrawal of Ordered Modification and Order to Show Cause and Ter-Mination of Proceedings Thereonwas issued on March 20, 1981 - the effect of which was to restore the status of the General Superintendent - Nuclear and to terminate the Show Cause Order involving the Executive.Vice President.
2.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-I-81-37 Boston City Hospital - Misadninistration of Radioiodine
- b. - FNO-I-81-38 Millstone Nuclear Station, Unit 1 - Dropped New Fuel Asser61y l-c.
PNG-II-81-25 Crystal River 3 - Unplanned Outage Due to Possible Loose 0bject in Steam Generator d.
.PNO-III-81-34 Duane Arnold Energy Center - Difficulty in Closing Recirculation Loop Discharge. Valve
- e..PNO-III-81-35 Byron Station Unit 1
. Fatality at Byron Site
- f. -PNO-IV-81-10 Fort St. Vrain -Turbine ~ Trip g.
PNO-V-81-14 Rancho Secc-Nuclear Power Plant - High Pressure Injection Pump Inoperability Due to Lube Oil Ccolers Plugging ENCLOSURE E
h.
PNG-V-El-15 Alaska Welding Cente - Mich Ocse en Radiogracher's Filr Badge 1.
PNG-V-81-16 U.S. Ecology, Inc., Beatty Nevada Burial Site - Banning of Mare Island Naval Shipyard (Nuclear Procuision Unit),Vallejo, California for Radioactive Waste Shipcent J.
PNO-TMI-81-07A Three Mile Island, Unit 2 - Reacter Building (Containment)
Entry (Update) k.
PNS-II-81-04 Crystal River - Offsite Arres:: cf Trespassers 1.
PNS-III-81-05 Midland, Units 1 and 2 - Beeb Threat 3.
The folicwing IE Information Notices were issued:
a.
IE Infonmation Notice El-07, "Petential Problem With Water-Soluble Purge Da= Materials Use: During Iner: Gas Welding", was issued on March 15, 1931, to all nuclear power reactor facilities hciding ;cwer reacter operating licenses or construction per=its.
b.
IE Infor atien Notice 81-08, " Repetitive Fzilures of Limitorque Operator SMS-4 Motor-to-Shaf t Key",
was issued on March 20,.1981 to all nuclear power reactor facilities holding power operating licenses or construction
.permi ts.
c.
IE Infon=atien Notice 81-09, "Cegradation of Residual Heat Removal (RHR)
System", was issued to all nuclear Ocwer reactor facilities holding power reactor operating licenses or construction per=its en March 26, 1981.
d.
IE Information Notice 81-10, " Inadvertent Containment Spray Dca tc Personnel Error", was issued to all nuclear pcwer reactor facilities holding pcwer reactor cperating licenses or constracticn permits on March 25,1981.
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W-ENCLOSURE E
0FFICE OF NUCLEAR REGULATORY RESEARCH Important Items - Week Ending Marjh 28, 1981 ACRS Subcomitterfiefing
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A briefing to 'n ACRS subcomittee is planned for April 8 on results of the project, "Nuc', ear Power plant Design Concepts for Sabotage Protection."
Results of toe project, performed h SNLA, are contained in the report NUREG/CR-1345 (same title). The purpose of the me ing is to determine whether the fault tree techniques used > that stu are applicable to address new plant requirements beyond the Near Terg Construction Permit (NTCP).
Signing of Agreer.ent With UKAEA on NRU Fuel Defor 5: ion Test An agreement +for cooperative research between NRC Ud the UKAEA.was signed on March 24, T981 by the Executive Director for Operations and Dr. John Gaunt, representing the UKAEA. The agreement provtdes for the UKAEA to I
contribute $1.4 million for the performance of one.pf a small number of full-length, multi-rod fuel bundle tests NRC is sponsoring in the NRU test reactor at Chalk River to investigate cladding defamation behavior of prototypic pressurized fuel rods under LOCA simulaf.ed conditions. Tne well defined, realistic test conditions that apply to these experiments permit the development of an important reference data base for testing: the UKAEA interest analytical models used for predicting accident consequences.
in this area has particular relevance to the forthcoming UK public enquiry on PWRs scheduled for 1982.
Signing of Subsidiary Agreement to the Marviken If!JIT Agreement 18, 1981, NRC, as one of the six origina13 signatory parties of On March the Marviken IV-JIT research agreement (covering experiments on blowdown jet impingement loads), sigt ed a subsidiary agreement with the Company Partnership, Japan allowing for Japanese participation in the Marviken IV project. The Japanese contribution of 100 laillion-yen will permit an expansion in the number of tests and measurements planned for the original program.
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1 FLECHT SEASET A special PMG meeting was held on March 19, 1981, o discuss the I
new program scope and funding. The consensus is tlb run one 21. rod l
i blockage test, one 163 rod blockage test and the natural circulation l
test, pending final management co".currence from NRC, EPRI and -
Westinghouse. NRC and EPRI alsa proposed a $1M t 1 increase.
instead of the $2M requested by Westinghouse for se tasks.
i Westinghouse is evaluating this proposal.
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ENCLOSURE F
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2-Seiscale l
Last weeks review indicated the program to be on the: spending and accomplishment curves. (Actually ahead en the 1stcer due to a significant increase in heat loss evaluation testing"as conoared to the initial plan.) Minor experimental glitches held un the 5-VT-3 2.5 percent break test. We anticipate the test will be conducted on March 25, 1981.
Data analyses and calculational coe:parison indicate that acetrula*oe discharge during sman-break may be slower than cale: Dated by many codes (particularly these which ass:re thermal equilibrium, regardless of other asstr:ptions that are in coeren use). We will pay particular attention to this in the uxeetincr5 test UT series.
This, and other recent test inferinatien, has been dislussed with NRR.
PiSt 50HT Progett h
A PWR BCHT sid-year review meeting was held on March $3,1981. At the present tire, final data tapes for film boiling experiments, and the Series I bundle uncovery/reflood tests have been sent to tnt INEL data bank. The Series II bundle boiloff/refloodifinal test tapes are scheduled July 1, 7491. Data evaluations aee continuing; the current projectiens-are that concluding analysis and~rnorts will be completed in FY 1981.
TAP-43, Centainment E.er;ency Sum Perfor.ance 2-A DOE-MQT/Sandia sponsored'* peer" review gr up meetinS(was held ort March 17,1981. Sandia and Alden Research Laborator3 ARL) personnel presented initial test findings and a descriptien of the test program and facilities. The invited attendees i re requested to previde followup written assessments in two weeks lo A. Millunzi l
(DCE/HQT). A followup meeting is planned for Jute 2#1981 (prehably l
at AM.) to discuss significance of findings and whethef the total j
program, as presently planned, should be pursued to completion.
=
A mid-year review of Sandia's TAP-42 support effort was held on March 18,1981. Sandia's plans for FY's 1981 and 1982 were discussed.
Sandia will submit, in mid-April 1981 a revised FY 1942 plan which reflects discussions and ccaclusions reached on March-17-18,1981.:
For example Sandia will determine if ARL can run the'high temperature (up to 160*F) sing tests, and scaling tesEs by the end of Quarter I, FY 1981, This meeting also broughthut a FY 1982, DCE/Sandia finding deficiency for the ARL program.,
MRC/ DOE resolution of this nat'ar is required.
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s E! C 05URE F
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20/30 r
T The main results of the 2D/3D coordina2 ion meeting, held-in Japan
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on March 16-19,1981, are:
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The CCTF-EM test was successfully performed and the results will be r
compared with pre-test predictions supplied by bothshc TRAC (best-estimate) and WRAP (evaluation model) computer coder; l
The comparisons for peak clad temperatures were:
CCTF-EM test 910*C 5
TRAC (B.E.)
1025'C
=
WRAP (EM) 1045'C (average pin) 1282*C (hop pin) 2.
At lear,t fcur tests will be run in CCTF-Core II tha ;Jinvestigated include both the rafill and reflood phases of a LOCA; Core I on1 the reflood phase. The actual tests to be perfonned:--were agreed-to with JAERI and the method of operation was discussedu 3.
The five CCTF-Core I tests to be analyzed by TRAC weie specified.'
Five of the upcoming SCTF tests were chosen for post-test predictions, and the method for transmission of measured initial and boundary.
conditions from JAERI to NRC/LASL was established. ".An additional three SCTF tests will also be calculated if resourceis rannit.
1 4
4.
The issue of ECC flow esc 111ations in the hot leg was discussed, 8
including data which might support these calculated 3 sci 11ations.
Additional tests and cal.ulations will be discussed:st an experts meeting in Munich during June 1961, before the next-2D/30 coordination meeting. Although there was agreement that these oscillations could occur, their calculated magnitudejis felt to.
be too large. In addition. De physical mechanism for their initiation is still an open issue.
h Hot Pressing Kimtics of UO2 Fuel Pellets 1
We have just received the final report from Purdue Univirrsity contract 189 B6313 on the hot pressini; kinetics of U02 fuel pell(ts.
It has been transmitted to the Distribution Office for issuance as a NUREG document.
A pa ar based on this work has been selected for the "Best Paper Award" at tie 82nd Annual W iting of the American Ceramic Sociity and attes*a to the high quality of urk perfonned by Professor A. Solomon and his staff at Purdue. It is expected that the results of this program will be incor-porated into the MATPRO materials subcode being maintained at INEL for use in the NRC fuel codes, FRAC-T and FRAPCON.
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Next LOFT Test inis first multi failure test, which will be initiated Sy a loss of:
all feedwater is scheduled for April 15.
It is expecte? to cause a loss of natural circulation and a core boil-off. Three different-operational procedures-intended to cope with this accident will be perfonned before the ECCS is activated and the plant recovered. (L Lock-open:
PORV. 2. Refill steam generator secondary side and 3. Re-start primary c.colant pumps). The plant has been refilled, and a new PORY-line instrument spool piece has been installed. Preparitions. continue towards a test date of April 15.
I Technical Paper Writino Award e
Dr. McPherson, Chief of the LOFT Research Branch, receiNed the Award of Merit from the Society of Technical Cartnunications. 4This was in recognition for a Nuclear Safety Journal article entitimd, "Results of the First Nuclear-Powered Loss-of-Coolant Experimen*s in the LOFT Facility. Nuclear Safety. Vol 21. No 4. July-August 1950.
5 LOFT Technical Team Visit to Europe Dr. McPherson led a team of INEl. representatives to 6 hntries, from
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March 2, to March 13. The team presented recent LOFT results, the status of NRC's plans for future LOFT tests and they probed possibilities that significant funding increases might be fourd.Some]mpe w&s offered for increased funding from foreign participants.
On the other hand.
the recent ACRS reports on LOFT and NRC review of the geogranthave weakened the case. for even continuing at the current funding levels. :A more detailed trip report is available from Dr. McPherson.
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ENCLOSURE F
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5 Technical Bases Report of Fission Froduct Behavior
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i A peer review (or critical review) of the report was ionducted en Harch 17 and 18, 1981. A number of constructive coments and criticisms were provided by the reviewers, along with a c1 mar, broad consensus that the document is a good, comprehehsive' technical report on the subject and represents a valuable contrlbutilm not previously available. None of the coupent.s were of safficient impact to invalidate the report.
j The principal comments esa be addressed without diff *culty:in the current draft prior to p 211caticn, for example, list hgs of the l
various calculational assumptions in the Appendix and a cedsed Abstract.
These reviewers (and the ACRS as well) agree with ene-of the key findings of the report, namely, that there are many gaps in the data base and large uncertainties in a number of the methods used for estimating fission product behavior. This finding ca3 only be addressed by further research.
2 There was a general consensus for early publication of the repert.
Only one reviewer (EFRI) indicated a slower pace foryubltration, however, this was not shared by the Westinghouse reif_ ewers.~
n; A draft Comnission Infomatica paper has been prepared in coordina-tion with MRR. The paper tran cits the " Technical Bases" report and the " Regulatory Impact" report along with the kel findings from each report. The draft paper is now in int &rnal review until March 27 and will be ready for Office Director rev.iew on March 30.
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Safety and Relief Valve Testing Program
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9 MRR held a meeting on March 20, 1981, to review the-signtHeance of the Block valve testing as related to the North Anna and Olde_nnee plants. These plants use the Westinghouse valve (that failed to close in EPRIitest) installed as PORY Block valves. Vepco's evaluation of the situation 1( that it is safe
- .o operate normally with the block valve open until the plant".id -shutdown when r';dification:
l will be made (North Anna has two parallel PORYs andi81ock valves). Duke Power is modifying one of the Block valves on the Oconee plant that is shutdown while the b1ock valves in the other two.have been tosed until the plants are shutdown and then they will be modifi lari JI 22}
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ENCLOSURE F 1
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Halden Reactor Project _
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The 69th quarterly meeting of the Halden Program Group was held on a.
March 17, 1931. Of principal interest was the demand placed on the project to make its human performance dat4'more accessible to signa-tories so that independent assessments couldibe made.
-: ~ :.
RES spo..sored a day of presentations by the Heiden" staff and signatory b.
representatives which was attended by aboyt (0 members of the regula-tory staff, research contractors, and industry. The discussions pointed up the relative aggressiveness adopted in' Europe to introduce computer-ized operational support systems into consercjal reactors.
RES sponsored a tour of the simulator designI4nd manufacturing c.
facilities at Singer Company for the benefit of the Halden Program
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OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING.vARCH 27, 1931 Three Mile Island Nuclear Station, Unit 1 (Restart)
On March 23, 1931, the Comissien issued an Orcer (CLI-El-3) in wnich it
- 1) cenied the GPU request to restart Unit 1 prior te the ecmpletion of the engoing adjudicatory hearing; 2) deferred action en licensee's request to substitute GPU Nuclear Corp. for Met. Ed. as the licensee of Unit 1 pending staff review; 3) permitted licensee to begin hot functicnal testing ising ncn-nuclear heat; 4) granted licensee request that Ccccissicn decisicn on the effectiveness of the ASL3's decisien be made within 35 days after issuance of ASL3 decisien, 5) granted to a limited extent licensee's request for appropriate deferral until after restart incle entation dates for NUREG-0737 action items where such deferral is consistent witn ircle.mentatien schedules for operating reacters; and 5) rexved the issue of the licensee's financial qualifications frem the preceeding.
Mentague Nuclear Powe Station, Units 1 and 2 On March 25, 1931, the presiding ASLS issued an Order granting applicants' motion to terminate this construction per=it preceeding.
i ENCLOSURE G
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ITEMS OF fNTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MARCH 27, 1981 Foreign Assicnees to NRC Program assignements have been completed for 5 assignees, representing 3 countries, to be temporarily assigned to one or more program offices.
Program details are as follows:
Name Country / Organization NRC Office Exp. Arrival - Period J. Laaksonen Finland - Institute of NRR/DSF 4/30 1 yr Radiation Protection NRR/DHFS Y. C. Yang Taiwan - Atomic Energy IE Hdqtrs/
5/15 1 yr Council Region II C. W. Cho S. Korea - Nuclear NMSS/IE 5/15 2 mos.
Regulatory Bureau 6 mos.
R. A. Lin Taiwan - Atomic Energy NRR/0LB May Council Y. D. Tzeng Taiwan - Atomic Energy NRR/0LB May 6 mos.
Council In the near future the EDO will be asked to extend the official invitations for NRC. The invitations will be transmitted through normal government communication channel s.
The following foreign assignees are currently with NRC.
Name Country / Organization NRC Office Exp. Departure F. Recreo Spain - JEN NRR April 30,1981 M. Lcraia Italy - CNEN NRR at TMI April 1981 B. Fourest France - CEA NRR/0EEB June 1981 J. Y. Chen Taiwan - AEC IE - Reg.II January 1982
.i Foreign Visits to NRC On Monday Mr. Tomio Yamamoto, Vice-Minister of the Japanese Ministry of International Trade and Industry (MITI) and a member of the Diet (national parliament), toured TMI, accompanied by J. Lefleur, IP. Mr. Yamamoto was particularly interested in the current status of the clean-up operations and the public attitude about TMI.
ENCLOSURE H
. Foreign Visits to NRC Cont'd On Tuesday Mr. Jose-Luis Sanchez, Administrator - General Manager of the Spanish utility Nuclenor, made a courtesy call on Chairman Hendrie.
J. Lafleur of IP also attended.
On Wednesday Dr. Sigvard Eklund, Director General of the IAEA, met with Chairman Hendrie and Commissioners Ahearne and Gilinsky to discuss current nuclear issues; J. Lafleur of IP also attended. On Thursday Dr. Eklund toured TMI, accompanied by R. Hauber of IP.
Retransfer Requests IP is presently reviewing a Swedish and a Spanish request to retransfer U.S.-origin spent power reactor fuel from those countries to the U.K. for reprocessing. As was the case in the recent Japanese requests, which are still under review at the Commission, the DOE nnalyses for these requests do not address the policy of " physical need" or " contracts antedating April 1977."
Like the Japanese requests, however, these cases appear to meet the requirements of that policy.
W ENCLOSURE H
CfeTCP OP c?A*e D90m m T TE M.C OC TM*?DeC?
WTTM TMDTNG VJ9cu 27. IM On March 17, 1981, Tom Elsasser, RSLO, Region L and other members of RAC II met in New Yerk City to evaluate the radiological emergency response plan for the State of New York.
On March 20, 1981, Tom Elsasser attended an evening public meeting in Lower Alloways Creek, New Jersey, to discuss off-site State and local radiological emergency response plans for the Salem Nuclear Generating Station.
On March 24, 1981, William B. Menczer, RSLO Region III, me t with Fred Lafser, Director, Missouri Department of Natural Resources (DNR) and Ronald Kucera, State Liaison Officer and Deputy Director of the Missouri DNR, to discuss NRC actions, regulations and programs af fecting Missouri.
Mr. Kucera, recently appointed SLO by Governor Bond, expressed great interest in NRC's Agreement State, transportation j
surveillance, and environmental monitoring programs.
Mr. Menczer met with the Interagency Regional Assistance Committee (RAC) on March 25, 1981, in Kansas City to discuss and consolidate RAC comments on the Missouri and Atchison County radiological emergency response plans for the Cooper Nuclear Station.
FEMA will present RAC comments to State officials in April, 1981.
On March 27, 1981, Mr. Menczer and members of the Region III staff met with James Blackburn of the Illinois Department of Nuclear Safety to review and discuss Illinois' plan to place effluent monitoring systems inside nuclear power plants in Illinois.
The LaSalle Station will be the first nuclear plant so equipped.
On March 24-26, Jim Montgomery, RSLO Region IV, represented the NRC on the FEMA chaired Regional Assistance Committee (RAC) during the full scale radiological emergency respense exercise at the Arkansas Power & Light facility near Russellville, Arkansas.
ENCLOSURE I g
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8 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest
'4EEK ENDING MARCH 27 1981 Congressional Correspondence Sent responses to Simpson/ Hart questions to EDO and OCA on March 27.
Publication
" Occupational Radiation Exposure at Connercial Nuclear Power Reactors,1979," was distributed.
Caseload Forecast Circulated draft forecast to Offices on reactors, waste management, and radioisotope licensing. Coordinated pro-jections will be used in upcoming budget process.
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I'r ENCLOSURE J
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OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING FARCH 27, 1981 BWR Scram System t.eaks Outside Containment Prompted by the f'ndings of previous case study investigations, AE00 undertook a more thorough safety review of the adequacy of the SWR scram system design with regard to the reactor coolant boundary and primary containment functions.
As a result of this further work, important additional issues and safety con-cerns have been raised with respect to isolation capabilities of the scram system and operation of the emergency core cooling systems for SDV pipe break situations.
It was found that, in the event of a SDV system pipe break attendant to a reactor scram, termination of the resultant reactor coolant blowdown outside primary containment would be dependent on successful closure of non-redundant (scram outlet) valves. The closure principle and design arrangement of these valves, however, do not meet the important requirements for isolatien valves described in GDC 54 and 55 of Appendix A to 10 CFR 50. Furthermore, while the break isolation invoives a man-machine system, it was found that potentially less than adequate human factor preparation has been provided, given the importance to safety of isolating a break in the SDV system. Additionally, in the event that break isolation is not achieved, the current plant emergency operating procedures do not Tdequately address the potentially concurrent need for main-taining the core covered and protecting against the loss of ECCS m uipment due to adverse egironmental conditions including flooding.
The AE00 study has been completad and is in the process of beir.g rorwarded to NRR for eview and appropriate action, Foreign Operating Experience Storage and Retrieval l
After discussions with the Nuclear Safety Information Center, agreement has been reached on the next phase of the program-to systematically encode foreign opera-l tional experience for ease of retrieval. Future work this fiscal year will include the abstracting or sequence coding of those events for which there is sufficient
.information available; the sequence coding, to the extent practical, of events identified as significant by LLL; abstracting and sequence coding of future foreign operating events for which sufficient information is provided; and screening future foreign operating experience to identify those events for which additional information should be requested.
ENCLOSURE L
h ITEMS APPROVED BY THE COMMISSION - WEEK ENDING MARCH 27, 1981 A.
SECY-81-177 - STAFF INTENT TO DELETE THE LICENSE CONDITION RE0VIRING SOLIDIFI-CATION OF EPICOR-II REsit( TO A COMMERCIAL SHALLOW LAND BURIAL FACILITY. Memo SECY to Dircks, dtd 3/P12 This is to advise you that the Comission (with all Comissioners approving) has approved delet of the current requirements to solidify all EpICOR-II spent
.as prior to shipment offsite, t
The Office of Nuclear Reactor Regulation was infomet. of tnis action by telaphone on March 23, 1981.
l B.
3TAFF REQUIREMENTS - AFFIRMATION SESSION 81-12, 2:05 p.M., MONDAY, MARCH 23, 1981, CCMMISSIONERS CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE).
Memo SECY to Bickwit, dtd 3/24/81.
I.
Order Recarding Issues of TMI-1 Rastart 1
The Comission, by a vote of 4-0, approved an Order concerning the TMI-l Restart Proceeding.
(Subsequently, the Secretary signed tiie Order.)
II.
SECY-81-173 - Motion for Directed Certification of an Acceal Board Ordar (In the Matter of Public Service Company of New Hamosnire Et A1.)
l The Ccmission, by a vote of 2-12 (Comissioner Bradford dissenting, Chairman Hendrie abstaining), approved an Order that denied on procedural grounds the New England Coalition on Nuclear Pollution's (NECNp) motion that the Ccmission direct the Appeal Board to certify its Me:norandum & Order uf February 12, 1981 for Comission consideration and to reverse that decision.
(Subsequently, the Secretary signed the Order.)
ISection 201 of the Energy Reorganization Act, 42 U.S.C.15841, provides that i
action of the Cuuaission shall be detarmined by a " majority vote of the members present." Ccmissic.iir Bradford was not presrent when this item was affirmed, but had previouslygirdicated that he would approve. Had Conrnissioner Bradford
- been present, he would have affirmed his prior vote. As.cordingly, the form:1 vote of the Comission was 3-0 in favor of the decision.
2Section 201 of tb9 Energy Reorganization Act, 42 U.S.C.15841, provides that action of the Cca.ission shall be determined by a " majority vota of the member.
present." Chairman Hendrie recused himself from this proceeding, but participated for purposes of comprising a quorum. Comissioner Bradford was not present when this item was affirmed. He had previously indicated that he would disagree with the Comission decision to deny the motion on procedural grounds, but would have done so on substantive grounds.
H:d Comissioner 2radford bean present, he,muld have affirmed his prior vote. Accordingly, the fc. 7al vote of the Comission was 2-0 in favor of,the decision.
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STAFF REGUIREMENTS - DISCUSSION OF POLICY, PLANNING AND PROGPAM GUIDANCE FOR FY 1983-a7, 10:00 A.M., WEDNESDAf, MARCH 25. 1931, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memorancum for tne Recorc f:
Cnilk, etc 3/25/81.
The Comission* continued its discussion of the propcsed Policy, Planning and Program Guidance, as centained in the draft (modified with conrents) circulated by the Director, CPE, on February 27, 1931.
The Cocnission reviewed Sect. ion III of the document tnrough Section I!!.B.l.0.
- Ccmissioner Bradford was not present.
D.
SECY-80-257/257A - RADIATION PROTECTION - THYROID BLOCKING. Me-o SECY to Dircks, ctc 3/26/81.
The Comission has reviewed the potassiu' isoide (KI) thyroid blocking issue and requests the staff to take the follcwing next steps:
1.
Continue to work with appropriate Federal agencies, i.e, FEMA, FDA and EPA, to address the uncertainties in the use of KI by the general public and possible alternative respiratory protection s trategies.
2.
Press on with source term technology studies, now underway, to a point where the Comission can adequately consider the potential impact on -- among other regulatory =atters -- alternative protective actions for public use in a nuclear plant emergency.
Until the Cemission paper is received, the Ccamission will make no further decision en the advisability of recomending stockpiling of KI for the general public.
3.
In the interim, the staff thculd assure with FEMA that there is appropriate guidance for the @inistration of KI before requiring implementation for certain institutionalized members of the public.
The Comission has also approvec tue sending of letters to FEMA and FDA on this subject (copies attached).
Attachment:
Not included.
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SECY-81-128 - RE0 VEST FOR PROPOSAL (RFP) NO. RS-NRR-81-091, ENTITLED " SEISMIC TECHNICAL ASSISTANCE FOR THE SYSTEMATIC EVALUATION PROGRAM (SEP)". Memo SECY to Dircks, dtd 3/27/81.
This is to advise you that the Commission (with all Commissioners approving) has granted approval for the staff to enter into a contract for performance of this effort.
The Offices of Nuclear Reactor Regulation and Administration (Contracts Division) were informed of this action by telephone on March 26, 1981.
It is requested that you inform the office of the Secretary when the RFP for this contract is issued.
(SECY Suspense:
March 31, 1981) 1 i
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