ML19341D598
| ML19341D598 | |
| Person / Time | |
|---|---|
| Issue date: | 02/26/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810220, NUDOCS 8103050985 | |
| Download: ML19341D598 (35) | |
Text
_ _ _ _
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February 26, 1981 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 20, 1981 A summary of key events is included as a convenience to those 4
Comissioners who may prefer a condensed version of this report.
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Contents Enclosure Administration A
.iuclear Reactor Regulation B
Standards Development C
Nuclear Material Safety and Safeguards D
3.r.
2.
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*
L*
Analysis and Evaluation of Operational Data
_ Smal.1 and Disidvaritiged Business Utilization M^
Items Approsed by tihe' Com'ission ~
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Calendar of Speaking Engagements O
C:.
T. A. Rehm, n221stant for Operations
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Office of the Executive Director for Operations
- No input this week.
CONTACT:
T. A. Rehm, 27781 8103 0509E5,
I
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending February 20, 1981
)
Crystal River, Unit 3 (CR-3)
CR-3 was brought to cold shutdown for preventative maintenance on February 17 because of increasing leakage in the "A" Reactor Coolant Pump Seal.
North Anna, Unit 1 (NA-1)
I On February 13, 1981, VEPCO purchased from Met Ed the THI-2 Low Pressure (LP) turt.ne rotor No. 2 to replace the NA-1.LP turbine rotor No. 2, which had two cracks in the keyways. The approximate 450-mile journey of the TMI-2 LP rotor from TMI to NA-1 commenced on February 14 and was scheduled to arrive on February 18.
Joint Hearings on Occupational Radiation Protection The dates and places have been selected for the joint EPA / OSHA /NRC hearings on occupational radiation protection:
April 20 thru 23 Washington, D. C.
GSA Auditorium May 1 and 2 Houston, Texas Dunfey Hotel May 5 and 6 Chicago, Illinois Pick-Congress Hotel May 8 and 9 San Francisco, Cal.
Hyatt Regency Hotel Field Test of Safeguards Assessment Methods at Crystal River NMSS Safeguards staff teams are field testing techniques for assessing the vulnerability of power reactors to sabotage at the Crystal River nuclear power station during the last two weeks of February.
U. S./IAEA Safeguards Agreement The IAEA has selected the Exxon Fuel Fabrication Plant and the Rancho Seco and Trojan Power Reactors for the application of their safeguards, including insoections.
?
0FFICE OF ADMINISTRATION Week Ending February 20, 1981 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Recuest Initial Decision Received 104 0
Granted 48 0
Denied 4
0 Pending 52 0
ACTIONS THIS WEEK Received Leonard C. Battle, Requests a copy of a letter from Consumers Power Attorney-At-Law Ccmpany responding to the NRC's proposed fine on the (81-52)
Midland construction activities.
Greg Wingard Requests all correspondence between the NRC's Office (81-53) of State Programs and the Washington State Department of Social and Health Services, Radiation Control Section in regard to the 1981 Annual Compatability Review, including any conclusions or recommendations that the NRC forms in regard to the State of Washingtons' Radiation Monitoring Program.
Caroline Mueller, Requests a copy of Licensee Event Reports pertaining Prairie Alliance to BWRs, the Inspection and Evaluation Reports and (81-54)
Illinois Power's responses, and NUREG-0654, 0386, 0737, 0690, 0578, 0585, 0694, the most recent Generic Task Action Plan and the annual report for 1980.
Matthew F. Medeiros, Requests a letter from Leslie Alsager requesting Attorney-At-Law documents relating to the construction of nuclear (81-55) generating units in Seabrook, New Hampshire and the NRC's response to Mr. Alsager's request.
Joseph N. Cassiere, Requests information on the break down of the types or Boston University classes of people who make Freedom of Information Act (81-56) requests.
4 CONTACT:
J. M. Felton 492-7211 l
ENCLOSURE A 9
Received, Cont'd, Joseph N. Cassiere, Requests reports concerning possible pollution due to Boston University radioactive sources of water or land surrounding the (81-57)
Radioactive Fuel Recovery Operation plant at Wood River Junction, Rhode Island.
Joseph N. Catsiere, Requests information concerning the nature and causes Boston University of an accident at the United Nuclear Corporation's (81-58) plant in Wood River Junction on July 24, 1964.
Robert L. Cohen Requests al1 documents relating to the consideration, (81-59) planning, execution, or utilization of two listed studies on the TNI ir.cident and a copy of the
.~ ts.
Monica Andres, Requests an undeleted copy of a letter dated July a0, Center for National 1976 to Lt. Gen. Brent Scowcroft from Alfred D.
Security Studies Starbird and Kenneth R. Chapman regarding the Nuclear (81-60)
Materia!s and Equipment Corporation (NUMEC) in Apollo, Pennsylvania.
Allan Kanner, Requests 11 categories of documents regarding the Attorney-At-Law Limerick nuclear power plant.
(81-61)
Fred Eberlein, Requests a copy of 10 CFR Part 21.
Control Data Corporation (81-62)
Granted Adam P. Banner In response to a request for a copy of the Suninary (81 -33)
Meeting Minutes of the ACRS Subcommittee on Extreme External Phenomena as identified in the Federal Register on January 15, 1981, infonned the requester the summary meeting minutes are not yet available, however, the meeting transcription and the slide presentation have already been made available at the POR.
Harvey B. Meieran, In response to a request for copies of the non-0'Donnell & Associates, Inc.
proprietary versions of the proposals submitted to (81-34) the NRC in response to RFP-RS-80-188, made available 15 documents.
ENCLOSURE A
... =.
3 Granted, Cont'd Leonard C. Battle, Made available a copy of a letter from Consumers Power Attorney-At-Law
- Company responding to the NRC's proposed fine on the (81-52)
Midland construction activities.
Denied None 4
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ENCLOSURE A 4
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DIVISION c' SECURITY Week Ending February 20,1981 TMI Restart Hearings The Division of Security arranged to supply private guard services for the TMI Restart Hearings at the William Penn Museum, Harrisburg, PA. The hearings will be held on February 24, 25, 26 and 27,1981.
Classified Safeguards Program Letters were sent to licensees affected by Parts 25 and 95 to: 1) inform licensees of new access authorization fees, 2) provide some guidance on access authorization processing, and 3) forward a copy of draft NUREG Document 0711
" Protection of Classified Information and Matter.
Provided canments to Texas Instruments, Inc., Attleboro, MA, regarding their security plan submittad under Part 25 to protect National Security Information. Comments were coordinated with OIE.
Advised certain licensee personnel of their designation as derivative classifiers contingent upon thci,* receiving NRC security facility approval.
Occupant Emergency Pians Copies of updated Occupant Emergency Plans for NRC buildings were distributed to NRC Designated officials for completion.
Interagency Advisory Group (IAG)
Representatives of the Personnel Security Branch attended an IAG meeting rn personnel security matters sponsored by the Office of Personnel Management.
ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION WEEKLY HIGHLIGHTS - WEEK OF 2/20/81 CRYSTAL RIVER UNIT NO. 3 (CR-3)
CR-3 was brought to cold shutdown at 0900 on February 17, 1981 because of increasing leaka' e.in the "A" Reactor Coolant Pump Seal. This shut-g down was for preventative maintenance as the leakage rate did not exceed the action I vel of the Technical Specifications.
NORTH ANNA, UNIT NO. 1 (NA-1)
On February 13, 19,81, VEPC0 purchased from Met Ed the TMI-2 Low Pressure (LP) turbine rotor No. 2 to replace the NA-1 LP turbine rotor No. 2.
UT testing of the NA-1 LP turbine discs in early January,1981 revealed two cracks in the keyways of the NA-1 LP turbine rotor No. 2.
UT testing by Met Ed in late January, 1981 revealed no cracks in the TMI-2 LP turbine rotor No. 2.
The TMI-2 and NA-1 LP turbine rotors No. 2 are similar in design and ccnstruction.
The approximate 450 mile journey of the TMI-2 LP rotor No. 2 from the THI-Power station to the NA-1 power station commenced February 14, 1981. The 450 mile journey will take 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (no de'ays) and involves 5 different rail routes.
The combination rail / truck journey requires that the rotor be offloaded (railroad to truck) at Harrisonburg, Virginia to by pass a narrow bridge and then reload from truck to railroad for the remainder of the trip. The TMI-2 LP rotor No. 2 is scheduled to arrive at NA-1 power station on February 18, 1981.
On February 19, 1981, the ASLAP and HRC staff will conduct a site visit to NA at which time the Board can observe and ask questions regarding the replacement of the NA-1 rotor No. 2 with the TMI-2 LP rotor No. 2.
NA-1 is shutdown for refueling and is presently scheduled to restart mid-March, 1981.
ENCLOSURE B 1
nMt., IMA Fx0GPAM UFHCE !!EEKLY STATUS REPORT W M k of February 15-21. 198i Plant Status Core Cooling Mode: Heat transfer from the reactor coolant sy3 tem (RCS) loops to reactor ouilding ambient.
Available Core Cooling Modes:
Long-tem cooling "B" (once through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode:
Standby pressure contrcl (SPC) system.
Backup Pressure Control Mode:
One decay heat removal pump to supply pressure in conjunction with variable recirculation back to the barated water storage tank (BWST).
Major Parameters (as of 0500. February 20, 1981) (approximate values)
Average Incore Thermocouples: 118'F Maximum Incore Themocouple:
151*F I
RCS Loop Temperatures:
A B
j
' Hot Leg 118'F 120*F Cold Leg (1) 67'F 67'F (2) 67'F 66*F RCS Pressure:
101 psig Reactor Building: Temperature:
61*F t
Water level:
Elevation 290.6 ft. (8.1 ft. from floor) via penetration 401 manometer j
Pressure:
-0.2 psig (Hgise)
Concentration-4.1 x 10 - uCi/cc (Kr-85)
I (sample taken 2/16/81)
Effluent and Environmental (Radiolooical) Information 1
1.
Liquid effluents from TMI site released to the Susquehanna River J
after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement i
dated February 27, 1980.
During tne period February 14, 1981, to February 19. 1981, the effluents J
contained no detectable radioactivity at the discharge point and I
individual effluent sources whicn originated within Unit 2 contained I
no detectable activity.
l NOTE:. Last weeks's.tatus report included liquid effluent data from February 13, 1981, in addition to the reported period February 6,1981, to February 12, 1981.
1 i
ENCLOSURE B g
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EPA Environmental Data.
Results from EPA monitoring of the environment around the IMI site were as follows:
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3 The EPA measured Krypton-85 (Kr-85) concentrations (pC1/m ) at several environmental monitoring stations and reported the following results:
Location Febru_ary 6 - February 13, 1981 3
(PCi/m )
Bainbridge 20 Goldsboro 19 Observation Center 26 Middletown 25 All of the above levels of Kr-85 are considered to be backgrcund levels.
No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and ganna rate networks during the period from February ll,1981, through February 19, 1981.
3 NRC Environmental Data.
Results from NRC monitoring of the environment i
around the IMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-13l Cs-137 Sample Period (uCl/cc)
(uCi/cc)
HP-255 February 11, 1981-February 18, 1981
<8.5 E-14 <8.5 E-14 No reactor relate radioactivity was detected.
l 4.
Licensee Radioa_ctive Material and Radwaste Shioments.
The following snipments were made:
On Monday, February 16,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock ar.d Wilcox (D&W), Lynchburg, i
)
On Friday, February 20, 1981, 92 drums and 8 metal boxes of compacted and non-compacted low specific activity (LSA) waste l
were shipped from Unit 2 to U.S. Ecology, Hanford, Washington.
l On Friday, February 20, 1981, 26 drums and 2 metal boxes of compacted and non-comc3cted LSA waste were shipped from Unit 1 to Chem Nuclear Systems, Inc., Barnwell, South Carolina.
e ENCLOSURE B
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- i, Major Activities j
1.
Ground Water Monitoring Program Update.
Water samples taken from monitoring well No. 2 (test boring No. 2) on February 11. 1981, contained increased concentrations of Cesium-137 (Cs-137) (371 pCf/1) i and Cs-134 (134 pCi/1) and Cobalt-60 (Co-60) (14.3 pCi/1). Test boring No. 2 is located a few yards east of the 8WST. These l
results represent an increase (approximately, an order of magnitude) i in these quantities from previous results.
The results are being evaluated by the licensee and the NRC staff.
The terminology used in reporting ground water monitoring results has been changed from monitoring wells and observation wells to test borings. The tenninology change was made to avoid confusing i
these test wells with typical household wells which supply drinking water. Future status reports will refer to these test wells as test borings.
The positive indication of Co-60 tends to support the licensee's i
conclusion that the source of radioactive material identified in i
the test borings is the BWST, not the water inside the reactor building. Samples from the reactor building do not indicate that Co-60 is a major contributor to the activity in the sump water.
j Based on the low cobalt content in the sump and the permeability l
characteristics of cobalt, one would expect to see other radio-j l
nuclides in addition to those already identified in the test borings if the water were leaking from the reactor building sump.
l In addition, Co-60 was identified in the soil around the BWST and tne excavation currently in progress around the BWST, in conjunction l
with current rain, could have accelerated the migration of the i
i contamination to the test boring.
Construction of a catch basin to contain future leakage from the BWST is currently in progress.
Additional water samples from test boring No. 2 were taken by the
- licensee on Wednesday, february 18, 1981.
These samples were analyzed by the EPA. The EPA results are as follows:
Cs-137 (170 + 18 pCi/1), Cs-134 68 + 13 pCi/1), and Co-60 (less than the lower limit of detection)(.
'~
j The EPA also analyzed water samples from other test borings around t'ne reactor building.
No ganna emitting isotopes were detected in these samples.
2.
Submerged Demineralizer System (SDS).
SDS construction is approx-imately 80W complete.
Initial testing of completed portions is in j
progress while construction is ongoing.
The testing verifies the proper operation of equipment and does not involve processing a
j radioactive water.
The licensee is preparing an update to the Technical Evaluation Report which should be available for NRC review by the end of February.
l ENCLOSURE B m.
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3.
Contaminated Buildino Expansion Joint. On Februarl ll, 1981 j
following approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of rain, the lice.tsee took a sample of the cork in one of the same locations where prior samples l
j were taken.
Analysis of the cork and liquid samples taken by the licensee is in progress.
4.
Solid Waste Staging Facility Sump Contamination.
Water samples
~
i collected directly from tne drains of the A and B solid waste storage modules were analyzed onsite and additional samples were sent to an offsite laboratory for i more detailed anal l/ sis. The i
j onsite analysis detected 6.9 x 10-0 uCi/ml of Cs-134 and 3.0 x 10-7 uti/ml of Cs-137 in the B module drain. The only radioisotope i
j identified in the A module drain was tritium (B.6 x 10-6 uCi/ml).
l All the water from both drains is collected and analyzed as part of a prcgram to identify any signs of potential spent resin liner j
degradation.
Approximately two liters of water was collected from each drain after the recent rainfall.
The A solid waste staging module has been in service since January 1980 j
and contains a total of 66 spent resin liners.
The B module was R1ared in servi _ce j.n December 1980 and currently-contains 22 liners.
f
. Additional samples have been taken in an attempt to ide~ntify the' source of the cesium activity detected in the 8 module, Based on s
the analysis of the liner contents, the liners in the B module appear to be less susceptible to degradation the the.A. module'
't liners.
The licensee is investigating the sources of radioactivity in the drainage. The contamination levels do not indicate significant, if g
any, degradation of the liners.
Gross liner failures would result g
in contamination levels orders of magnitude higher than have been j
detected.
Possible sources of the detected radioactivity are low l
1evel contamination of the outer surfaces of the liners and condensed water vapor.from leakage through plugged pipe conneSti. ops _at 'the top of the liners.-
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9 ENCLOSURE B w.
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Meetings Attended--
4 j
On Thwsday, February 12, 1981, Bernard Snyder, Lake Barrett and Richard Conte attended the TMI Advisory Panel meeting held at the Forum in Harrisburg.
i The Mvisory Panel met to continue the development of a working document I
i lj for presentation of recomendations to the N2C.
l' The first topic of discussion centered around the ultimate disposal for s
the contaminated water in THI Unit 2.
Various motions were debated among the Panel members as noted below.
" Accident generated wate'r used in the decantamination process should not be disposed of into the Susquehanna River et all."
"The ultimate disposal of water should wait upon completion of processing of the existing inventories of the contaminated water."
I
" Accident generated water and water used in the decontamination process should not be released to the environment."
None of these motions were adopted in light of a previously adopted recomendation ("No. 2"), which calls for the subject water to be held in tanks onsite and the water further analyzed.
Another major issue discussed was the disposal of the high specific activity l
EPICOR-II resin liners offsite. A representative from the Department of j
Energy (DOE) reiterated that this area is being actively persued at DOE to assist in the resolution of this issue.
The Panel agreed that a letter should be drafted before the next meeting j
recomending that DOE arrange for offsite storage of the high specific activity EPICOR-II liners.
~
Before the end of March, the Panel members are planning to go to Washington.
4 l
D.C., to meet with the NRC Comissioners, the Secretary tc the Departr.;ent of Energy, the Armed Force Service Comittees, and if possible, the j
President of the United States, to impress upon them the urgency of the l
problems facing the cleanup at TMI and the need for support from the i
various government agencies and Congress itself.
e I
i Ei1 CLOSURE 3
r OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING FEBRUARY 20, 1981 1.
Joint Hearings on Occupational Radiation Protection: The dates and places have been selected for th joint EPA / OSHA /NRC hearings on occupational radiation protection:
April 20 thru 23 Washington, D.C.
GSA Auditorium May 1 and 2 Housten, Texas Dunfey Hotel May 5 and 6 Chicago, Illinois Pick-Congress Hotel May 8 and 9 San Francisco, California Hyatt Regency Hotel To assure an opportunity for participation by workers, evening sessions will be conducted in Washington, D.C. and Chicago, and Saturday sessions will be conducted in Houston and San Francisco. NRC participatior, will include the presentation of testimony (D.C. only) and the provision of two members for all hearing panels. The panel will be responsible only for assuring, to the extent possible, a balanced and complete record through the questioning of participants.
It will not render any conclusions or findings.
Contact:
R. E. Alexander 443-5975 2.
Proposed Amendments to 10 CFR 30.15(a)(9) and 30.71: On February 17, 1981, the Executive Director for Operations approved for publication and signed a Federal Register notice proposing amendments to 10 CFR 30.15(a)(9) and 30.71 so that a person exempt from licensing requirements may receive, use, and transfer an ionizing radiation measuring instrument containing, for purposes of internal ca'iibration or standardization, more than one source of byproduct material each not exceeding an applicable exempt quantity.
The proposed rule responds to PRM 30-57 in which General Atomic Company requested an administrative clarification of 10 CFR 30.15(a)(9) that refers to a source of byproduct material not exceeding an applicable exempt quanti ty.
The preamble to the proposed rule contains a statement that the Commission certifies that the rule will not, if promulgated, have a significant economic impact on a substantial number of small entities. This proposed rule will affect General Atorde Company (the petitioner for the action being proposed) and its customers who need ionizing radiation measuring instruments that are the subject of the proposed action. General Atomic Company is an affiliate of Gulf 011 Corporation and Royal Dutch /Shell Group.
General Atomic Company was ENCLOSURE C me -
2 worth $56 million, had $100 nillion in sales, and had 2400 employees in 1979 (information from EIS INDUSTRIAL PLANTS data base). The customers consist of less than ten companies which have construction services areas, and do not fall within the scope of the definition of "small entities" set forth in section 601(3) of the Regulatory Flexibility Act or the Small Business Size Standards set out in regulations issued by the Small Business Administration at 13 CFR Part 121.
Contact:
J. Henry 443-5946 Publications to be Issued in the Near Future
Title:
Nuclear Power Plant Simulators for Use in Operator Training Expected Issuance Date: August 1981
==
Description:==
This guide establishes the minimum functional requirements acceptable to the NRC staff for specifying nuclear power plant simulators and for comparing the simulator to its reference plant.
It endorses with certain exceptions, the March 24, 1980 draft of ANS 3.5.
Contact:
E. W. Merschoff 443-5913 Title : Ultrasonic Testing of Reactor Vessel Welds During Preservice and l
Inservice Examination Expected Issuance Date: May 1981
==
Description:==
This guide describes supplementary procedures in addition to the ASME Code requirements that may be followed to gene-ate data which would help in the evaluation of flaws by NRC staff and its consultants.
Contact:
V. S. Goel 443-5997 Withdrawal of Regulato,,' Guide Renulatory Guide 3.24, " Guidance on the License Application, Siting, Design, and Plant Protection for an Independent Spent Fuel Storage Installation,"
was issued in December 1974 The guidance it provided was based on 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material." On November 12, 1980, the Commission published 10 CFR Part 72 (45 FR 74693), " Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation,"
l ENCLOSURE C
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3 which specifically covers independent spent fuel storage installations.
The guidance contained in Regulatory Guide 3.24 is no longer appropriate, and the guide is being withdrawn.
Revised and updated guidance covering the various subjects addressed in Regulatory Guide 3.24 is being developed.
Regulatory Guide 3.44, " Standard Format and Content for the Safety Analysis Report j
for an Independent Spent Fuel Storage Installation (Water Basin Type) "
was issued in November 1980.
Draft regulatory guides containing guidance in other areas are being issued for public comment as they are completed.
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ENCLOSURE C w
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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending February 20, 1981 Field Test of Safeguards Assessment Methods at Crystal River Nuclear Power Station NMSS Safeguards staff teams are field testing techniques for assessing the vulnerability of power reactors to sabotage.
Two sets of teams will be conducting independent field tests at the Crystal River nuclear power station during the last two weeks of February. The staff conducted similar field tests last year at the VEPCO, North Anna facility in Virginia.
US/IAEA Safeguards Agreement The I AEA has selected the Exxon Fuel Fabrication Plant and the Rancho Seco and Trojan Power Reactors for the application of their safeguards, including inspections.
In accordance with 10 CFR Part 75, Exxon has been sent written notification of their selection, requested to complete an I AEA " Design Information Questionnaire", prepare an initial inventory report, and submit subsequent accounting reports. Similar letters to the two power reactors have been prepared. Every effort will be made to complete the Facility Attachments for the above facilities within the 90-day time frame spectfied in the agreement.
Remedial Action Concept Paper On February 12, 1981, members of the NMSS staff met with DOE to discuss the Remedial Action Concept Paper prepared for the Cannonsburg, Pennsylvania, site. This paper will serve as a model for other concept papers for the remaining sites covered by the Uranium Mill Tailings Radiation Centrol Act of 1978. The main NRC comment was that while the alternatives for remedial action should be listed in the Concept paper, the analysis of alternatives should be confined to the EIS.
ENCLOSURE D 6
o Planned Meetings - Division of Safeguards 1.
Subject:
Meeting with B&W-Apollo and Leechburg to discuss FNMCP revisions.
Date/ Time: February 23-26, 1981 Location:
Apollo, Pennsylvania i
Attendees:
G. Gundersen, SGML E. Bellasario, Manager, Safeguards 2.
Subject:
Meeting with (MC to discuss access control to vital areas and personnel screening matters involving power reactors i
Date/ Time: February 26,1981,1:00 p.m.
- Location:
Rosslyn, VA (Note: Changeinlocation)
Attendees:
R. Burnett, SG, D. Chapell, SG, L. Evans, SGRI D. Knuth, KMC 3.
Subject:
Dc"?lopment of Technical Objectives for International Ss/eguards and Identification of Facility Design 4
Features to Facilitate International Safeguards Date/ Time: February 26-27, 1981 - 9:00 a.m. - 5:00 p.m.
Location:
8th Floor Conference Room, Willste Bldg.
Attendees:
T. S. Sherr, K. E. Sanders (SG/NMSS) l Action Plan Working Group Members (DOS, ACDA & DOE),
and contractors on the study 1
l ENCLOSURE D 1
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Plann d Me tings - Division of Fuel Cycle and Material Safety
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1.
Subject:
Site visit in conjunction with the license renewal application review.
Date/ Time: February 19,1981 - 1:00 p.m.
Location: White Oak, Maryland Attendees:
B. M. Kosla (FC).
W. C. Cobbins (Naval Surface Weapons) 2.
Subject:
DOT Routing Rule Datt/ Time: February 24, 1981 Location- 00T Attendees:
C. E. MacDonald V. Hodge, (FC)
D.Hopkins(SD),J. Allen (DOT) 3.
Subject:
License familiarization and site inspection with Region II inspector.
Date/ Time: February 23-27, 1981 Location: NFS, Erwin, Tennessee Attendees:
B. Kosla (FC), J. Kahle (Region II inspector), and Thomas Lee (Resident Inspector) 4.
Subject:
License familiarization and site inspection with Region I inspector.
Date/ Time: February 24-27, 1981 Location: Combustion Engineering, Inc., Windsor, Connecticut Attendees:
A. L. Soong (FC), P. Clemons (Region I inspector) 5.
Subject:
Nu-Pac Company Date/ Tire: February 25,1981 - 9:00-3:00 p.m.
Location: Willste, 5th floor conference room Attendees: Richard H. Odegaarden, Jerry Fan, (FC)
Dick Helsig (Nu-Pac Company) 6.
Subject:
Current Issues in the Regulation of Nuclear Phamacies Date/ Time: February 25,1981 - 1:00 p.m.
Location:
Room 562, Willste Attendees: Richard E. Cunningham, V. L. Miller, E. M. Podolak, P. C. Vacca, J. DelMedico, (FC)
James F. Enigh, American Pharmaceutical Association 7.
Subject:
To describe NRC's program for upgrading emergency preparedness at fuel cycle and major materials licensees, particularly NRC's criteria for selection of licensees requiring Radiological Contingency Plans.
Date/ Time: February 27, 1981 Location: Portland, Oregon Attendees:
F. D. Fisher (FC), Agreement State Reps.
ENCLOSURE D
1.
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Subject:
Participate on the Panorama television show on Channel 5 8.
i to discuss Nuclear Medicine Waste Management Date/ Time: March 4, 1981
- Location:
5115 Wisconsin Avenue Attendees: Richard E. Cunningham J
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Planned Meetings - Division of Waste Management 1.
Subject:
. NEPA Remedial Action Plan Date: February 20, 1981 Location: Willste Bldg.
Attendees:
R. Scarano and W. Shaffer, NRC; DOE representatives 2.
Subject:
Environmental Monitoring of LLW Radioactive Waste Date: February 23, 1981; 3:00 p.m.
Location: NIH, Bethesda Attendees: Stan Neuder, NRC; Roger Broseus, NIH 4
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ENCLOSURE D
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OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending February 20, 1981 1.
The following Notifications of Significant Enforcement Action were dispatched during the past week:
a.
EN-81-03 Public Service Electric and Gas Company (Salem Unit 1) - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $90,000 was issued to subject licensee on or about February 18, 1981. This action was based on eight violations relating to deficiencies found in the radiation protection program, which were culminated by (1) the entry of two individuals into the fuel transfer tube with inadequate pro-visions for radiation protection; and (2) the entry of three individuals into the reactor cavity while the in-core flux thimbles were withdrawn.
b.
EH-81-04 Florida Power and Light Company (Turkey Point Unit 3) - A Notice of Proposed Imposition of a Civil Penalty in the amount of $40,000 was issued on February 18, 1981 to subject licensee based on Unit 3 operating at full power without an operator present at the controls in violation of 10 CFR 50.54.
c.
EN-81-05 Automation Industries, Inc., Sperry Division - An Order Suspending License and to Show Cause why suspension of the license should not be con-tinued, pending further order, was issued to subject licensee on February 17, 1981. This action was based on alleged items of noncompliance relating to radiation damage to the thumbs and index fingers of two enployees and possible overexposure to a third employee at the licensee's nuclear encapsulation facility in Phoenixville, Pennsylvar,ia.
2.
Preliminary Notifications relating to the following actions were dispatched during the post week:
a.
PNO-I-81-21 Maine Yankee Nuclear Pewsi-Station - Technical Specification MPT Limit Exceeded b.
PNO-I-81-22 Boise Cascade - Loss of a Cesium-137 Thickness Gauge c.
PN0-I-81-23 Comercial Truck Terminal (non-licensee) - Leaking Drum Containing Natural Uranium d.
PN0-I-81-24 Westmoreland Hospital Association, Greensburg, Pa. - Possible Loss of Iodine-125 Seeds e.
PN0-I-81-25 Digital Equipment Corporation - Unplanned Release of Krypton-85 f.
PNO-II-81-16 Sequoyah Unit 1 - Loss of Control Room Annuniciators g.
PNO-II-81-17 Sequoyah Unit 1 - Radioactive Liquid Effluents Exceeding Technical Specifications Limits ENCLOSURE E
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PNO-III-81-17 Duane Arnold - Plant Shutdown Which May Exceed 24 Hours 1.
PNO-III-81-18 Clinton Station - Unit 1 - Stop Work Order on large Bore Pipe Hangers J.
PNO-III-81-19 Pharmaco Nuclear, Inc. - Report of a Missing Attache Case Containing Byproduct Material k.
PNS-I-81-04 Pilgrim Unit 1 - Bomb Threat 1.
PNS-II-81-01 Hatch and Vogtle Nuclear Plants - Arrests of Employees for Sale of Drugs L
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4 ENCLOSURE E
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4 OFFICE OF THE EXECUTIVE LEGAL DIRECTOR j
ITEMS OF INTEREST WEEK ENDING FEBRUARY 19, 1981 4
North Coast Nuclear Plant, Unit 1 On February 18, 1981, the presiding ASLB issued a Memorandum and i
Order granting a motion by applicant, Puerto Rico Electric Power
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Authc rity, to terminate this construction permit proceeding and to withdraw its application without prejudice.
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ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING FESSUARY 20, 1981 NRC-CNEN Renewal Arrangement IP was advised by cable this week that the Italian National Committee for Nuclear Energy (CNEN) had received all clearances necessary from its Legal Office and the Ministry of Foreign Affairs to renew the NRC-CNEN inforation exchange and cooperation arrangement, which has been continued on an informal basis since its expiration in May 1980. CNEN President Colombo has indicated he would like to sign this renewal arrangement with HRC during his next (recently postponed) trip to the U.S. sometime this year.
IAEA Safety Mission Leonard Soffer, SAB/NRR, will participate as a member of an international
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team on an IAEA-sponsored siting mission to Greece from February 21 to 28.
While in Greece, the team will discuss population distribution, population doses, allowable routine releases and review of Greek siting criteria.
NRC Expert to the Philippines Cordell Williams, Region III, departed Friday, February 13 for Manila, The Philippines, for a 2-week IAEA technical assistance assignment. While in Manila, Williams will be advising the Philippine Atomic Energy Commission on welding inspection techniques.
Foreign Visits to NRC On Wednesday Mr. W. J. Wright, the Australian Embassy Science Attache, met with J. D. Lafleur, IP, and R. Scarano, WM/NMSS, to discuss NRC cooperation arrangements in the regulatory and safety research field as well as NRC standards and procedures for the licensing of uranium mills and UF' conversion facilities.
On Thursday Mr. A. Oriscoll, a Superintending Inspector from the U.K. Nuclear Installations Inspectorate (NII), met with B. Browning, Deputy Director of WM/NMSS, to discuss the treatment of various waste materials and the possible establishment of a prcgram of visits and technical discussions at U.S. research, development and operational facilities involved in radioactive waste management and treatment programs.
L ENCLOSURE H
. Foreign Visits to NRC Cont'd On Friday Dr. William Hannum, Deputy Director General of the OECD Nuclear Energy Agency (NEA), and Mr. de la Ferte, HEA Director for External Affair, met with acting Chairman Ahearne and Connissioner Hendrie to discuss the ll.S. role in the Committee on the Safety of Nuclear Installations (CSNI) and other NRC-NEA activities.
On Friday Mr. Carl Erick Wikdahl, Manager of the Department of Information and Public Affairs of OKG, a Swedish Nuclear Plant Group, and Mr. Lars Larsson, the Swedish Embassy Science Attache, met with M. Silberberg of RES to discuss NRC's research programs on source terms for releases during accidents.
On Friday, Mr. Custodio C. Alves of the Brazilian National Nuclear Energy Commission (CNEN) met with G. Harrison, EB/NRR, to discuss present NRC policy on fire protection and general maintenance inspections. Next week he will be in Region II for NRC appointments and a visit of the Farley Power Plant.
9 ENCLOSURE H t
w s OFFICE OF STATE PROGRAMS
-ITEMS OF INTEREST WEEK ENDING FEBRUARY 20, 1981 On February 9, 1981, Dean Kunihiro delivered a presentation to the Northern California Chapter of the Health Physics Society on the Nuclear Regulatory Commission's post TMI actions and activities.
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1 1-0FFICE OF MANAGEMENT AND PROGPAM ANALYSIS Items of Interest WEEK ENDING FEBRUARY 20, 1981 Annual Report Making final selections for illustrations before release to printer. Estimate -300 advance copies of Report due from the printer during week of March 9.
Balance of copies of the Report will follow 4-5 days later.
Congressional Qs & As Work in progress on 305 questions from Mr. Bevill's Committee.
Also provided data to assist Chairman in hearing.
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ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 20, 1981 A.
SECY-81 PROPOSED EXPORT OF TWO POWER REACTORS AND FUEL TO TAIWAN (LICENSE APPLICATIONS XR-135,136, AND 137 AND XSNM01662,1719,1753 AND 1754). Memo SECY to Dircks, dtd 2/17/81.
This is to advise you that the Commission's recent action in approving a Memorandum and Order, which denied an intervention hearing request and directed the NRC staff to issue licenses for the export of two nuclear reactors to Taiwan, completes action on the subject paper.
The Office of International Programs was informed of this action by telephone on February 13, 1981.
B.
SECY-81 PROPOSED CONTRACT MODIFICATION FOR CONTINUATION OF ADP MAINTENANCE AND SUPPORT SERVICES FOR NRC'S ADMINISTRATIVE, FINANCIAL AND MANAGEMENT REPORT-ING SYSTEMS. Memo SECY to Dircks, dtd 2/18/81.
This is to advise you that the Commission (with all Commissioners approving) has granted approval to the Contracting Officer to execute a contract modification with SBA and Rehab Group, Inc., as outlined in the Statement of Work.
In connection with its approval, the Co= mission has stated that the EDO should examine whether tighter cost control should be established.
The Office of Administration (Division of Contracts) was informed of this action by telephone on February 17, 1981.
C.
SECY-80-534 - APPROVAL OF A PROPOSED LICENSE TO EXPORT A RESEARCH REACTOR TO MALAYSIA (LICENSE N0. XR-125). Memo SECY to Dircks, dtd 2/19/81.
This is to advise you that the Commissioners have reviewed the subject license to General Atomic Company.
The Commission (wirh all Commissioners approving) has accepted your recommendation to export to Malaysia a TRIGA Mark II research reactor.
In connection with his approval, Commissioner Bradford has requested that the staff forward a letter to the Executive Branch to the effect that supply agreements should track Section 123 as to safeguards - including, if possible, the agreement covering this reactor by the time it is fueled.
The Office of International Programs was informed of this action by telephone on February 17, 1981.
ENCLOSURE N
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STAFF REQUIREMENTS - DISCUSSION OF SECY-80-409 - PROPOSED RULEMAKING TO AMEND TO CFR PART 50 CONCERNING ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) EVENTS, 10:10 A.M., THURSDAY, FEBRUARY 12, 1981, COMMISSIONERS' CONFERENCE ROOM, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Bickwit, dtd 2/18/81.
The Commission continued its discussion of ATWS and requested the following:
1.
the OGC and staff need to clarify the proposed rule with respect to the proposal to exclude ATWS from consideration under 10 CFR Part 100.
In addition, OGC and ELD need to consider whether additional direction will be needed by individual hearing boards in the interim period as ATWS moves from a generic to a plant specific issue; (OGC/ ELD /NRR) (SECY Suspense: 2/27/81) 2.
the Environmental Impact Assessment be revised to more thoroughly discuss l
and evaluate the dose impact of the proposed rulemaking. The Commission also suggested that the economic impact section be eliminated.
In addition, a determination whether the proposed rule does or does not have a significant impact on the environment needs to be considered in light of the Surry steam generator repair EIA; (0GC/ ELD /SD) (SECY Suspense: 2/27/81) 3.
the staff provide a list of components that would be limiting at the ASME C and D stress levels. The staff should be prepared for additional discussion of this issue at the next meeting. (NRR)(SECY Suspense: 2/27/81)
(Subsequently, a meeti'ng was tentatively scheduled for March 3,1981).
E.
SECY-80-219A - COMMISSION REVIEW PROCEDURES (SECY-80-219) -- DRAFT DIRECTIVE TO STAFF. Meno SECY to Bickwit, dtd 2/18/81.
- This is to advise you that the Commission has disapproved the draft directive to the NRC staff on NRR/NMSS Licensing Decisions and I&E Enforcement Acticns by a vote of 2-2 (with Chai=an Ahearne and Commissioner Hendrie disapproving and Commissioners Gilinsky and Bradford approving).
Attached are copies of individual Commissioners' responses to the subject paper.
Attachment:
Not included ENCLOSURE N e
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SECY-81 EMERGENCY RESPONSE FACILITIES. Memo SECY to Dircks, dtd 2/19/81.
This is to advise you that the Commission (with all Commissioners approving) has approved the proposed NUREG-0696 subject to the following modifications:
j/
1.
Sections of NUREG-0696 dealing with Emergency Operations Facilities (EOF) must be revised to reflect the Commission decirion reported in the S.
J. Chilk to W. J.
Dircks memorandum of January 21, 1981 (COMJA-8 0-37 ).
2.
The discussion of the seismic qualification of the EOF should be more explicit, for example refer to the Uniform Building Code as a definition of "well engineered".
3.
A note should be added to NUREG-0696 indicating that the document provides general guidance only, is an acceptable way to meet the rules and regulations and that compliance is not a requirement.
The Commission also notes that the General Counsel (memo attached) has raised an issue regarding the use of NUREG's to issue new requirements or quasi-requirements.
The Commission-would like to have the staff views on this subject.
(EDO) (SECY Suspense:
March 23, 1981)
Commissioners Gilinsky and Bradford believe that in the future NUREG's should not be used to issue new requirements.
Attachment:
Not included G.
SECY-81 NUCLEAR EXPORTS TO SWITZERLAND. Memo SECY to Dircks, dtd 2/18/81.
This is to advise you that the Commission (with all Commissioners approving) has approved the recommendation contained in the sub~ ject paper.
In connection with his approval, Chairman Ahearne ctated that the staff should continue to monitor pertinent intelligence information.
The Office of International Programs was informed of this action by telephone on February 18, 1981.
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STAFF REOUIREMENTS - DISCUSSION ON SECY-81-20/20A - POLICY ON PROCEEDING WITH 1
PENDING CONSTRUCTION PERMIT AND MANUFACTURING LICENSE APPLICATIONS, 2:10 P.M.,
THURSDAY, FEBRUARY 12, 1981, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Bickwit, dtd 2/19/81.
The Commission continued its discussion of requirements for pending construction permits. The Commission deferred a final decision on whether to proceed with a rulemaking.
The Commission did not decide whether to apply the rule to floating plants.
l The Ccemission requested that:
- OGC, in coordination with staff, revise the comment analysis to remove any language that implies a limit on NRC's aoility to impose siting requirements to ore-1979 CP applications;
- 0'iC and ELD prepare a recommendation as to the form a rulemaking should take;
- the requirement that applicants run the CO2 containment test identified in paragraph 4(d)(3) to Enclosure 2 of SECY-81-20A, be removed; and page 3, item 4(b) of Enclosure 2 (SECY-81-20A) be revised to read "an accident that releases an equivalent amount of hydrogen as would be generated from a 100% fuel clad metal water reaction..."
(Subsequently, another meeting on this subject was held on February 18,1981.)
I.
SECY-81 DIRECTOR'S DENIAL OF 2.206 RELIEF. Memo SECY to Bickwit, dtd 2/20/81.
This is to advise you that the Commission (with all Commissioners approving) has decided that there is no need for a review of this decision of the Acting Director, Office of Inspection and Enforcement.
In connection with his approval, Commissioner Gilinsky has provided the following statement:
"I would commend the Acting Director for writing a comprehensible decision."
^
The office of the' General Counsel was informed of this action by telephone on February 20, 1981.
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STAFF REQUIREMENTS - DISCUSSION OF SECY-81-20/20A - POLICY ON PROCEEDING WITH PDIDING CONSTRUCTION PERMIT & MANUFACTURING LICENSE APPLICATIONS (CONTINUED FROM 2/12), 10:05 A.M., WEDNESDAY, FEBRUARY 18, 1981, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Bickwit, dtd 2/20/81.
The Commission continued its discussion of requirements for pending construction permits. The Commission deferred a final decision on whether to proceed with rulemaking, and whether to apply the rule to manufacturing license applications-The Commission requested that:
1.
staff prepare two alternative versions of a rule based on the proposed approach discussed in the meeting, one which could be applied only to pending construction permits applicants and one which could also be applied to pending manufacturing license applicant's; (NRR) (SECY Suspense: 3/3/81) 2.
expanded reference to NUREG 0718 be included in the supplementary information section of the rule using language similar to that contained in the Policy Statement; (NRR) (SECY Suspense: 3/3/81) 3.
the word " continually" be removed from 550.34(e)(3) of the proposed rule as.
indicated in attachment 1 (vugraph =7 distributed by staff at this meeting);
(NRR)
(SECY Suspense: 3/3/81) 4.
0GC provide advice on the relationship of Part 100 to the proposed rule; (0GC) (SECY Suspense: 3/3/81) 5.
0GC analyze the phrase "necessary and sufficient" as used in attachment 2 (vugraph #4 distributed by staff at meeting) and provide the implications and options for Commission consideration; (0GC) (SECY Suspense: 3/3/81) 6.
OGC consider whether the Commission should cut back on TMI-related requirements in other NRC rules, i.e. rules other than 850.34(e). (CGC)(SECY Suspense: 3/3/81) 7.
Chairman Ahearne requested that the specific ASME Code paragraph (s) be stated for the Service Level stress limits.
Also, the rule should clearly state that the Code requirement on buckling associated with the Service C condition need not be met.
In addition, Chairman Ahearne subsequently requested that the rule should also explicitly state that the Code requirement on buckling associated with the Service-A condition for the inadvertent inerting need not be met.
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SECY-81 STEVEN SHOLLY, ET AL, V. NRC, ET AL., USCA. 0.C. CIR. NO. 80-1691 -
RECOMMENDED FINAL AMENDMENTS TO 10 CFR PART 2, RULES hF PRACTICE, TO IMPLEMENT THE DECISION IN SH0LLY ON HEARING RIGHTS UNDER SECTION 189a. OF THE ATOMIC ENERGY ACT FOR N0 SIGNIFICANT HAZARvS CONSIDERATION At'.ENDMENTS. Memo SECY to Dircks, dtd E/20/31.
In view of the fact that the Sholly mandate has been stayed, the Commission sees no need for a rule change at this time.
Therefore, the subject paper is returned without action.
Additional views of Chairman Ahearne and Commissioner Bradford are attached.
The Executive Legal Director was informed of this action by telephone on February 20, 1981.
Attachments: Not included L.
SECY-81-71B - PROPOSED AUTHORIZATION FOR WESTINGHOUSE TO ENTER INTO CERTAIN LICENSING ARRANGEMENTS WITH FRAMAT0NE PURSUANT TO 10 CFR PART 810 (SECY-81-71).
Memo SECY to Oircks, dtd 2/20/81.
This is to advise you that the Commission (with thre.a Commissioners approving) has approved the proposed letter to the Department of Energy (DOE).
Commissioner Bradford did not participate in this action.
If he has any views that differ from those 9
of the Commission, he will forward his own correspondence on l
this matter.
,f The Office of International Programs was informed of this action by telephone on February 20, 1981.
It is requested that you forward to the Office of the Secretary j
a copy of the letter to DOE after signature and dispatch by the Director, Office of International Programs.
I ENCLOSURE N
SCllEDULED SPEAKING ENGAGEMENTS Date Organization Location Subject Speaker 3/18/81 Annual Meeting of San Antonio, TX
.i.
Panel on Low Level G. Wayne Kerr State & Territorial iluclear Wastes SP llealth Officers 3/26/81 22nd Annual Quality Knoxville, TN What NRC Regulations W. Ruhlman Clinic t,":
Require from QA Program R0 II 3/29-4/2/81 American Chemical Atlanta, GA Regulatoiy Implications
- 11. T. Petersoi l
Society Meeting of Radiation Dose-Effect SD Relations, hips 4/1/01 Spouses of 00erating Education Center Quality Assurance Require-A. Cerne Staf f at Seabrook Seabrook, Nil ments & Licensing Procedures R0 I Station Related to Seabrook Station EllCLOSURE