ML20041D074

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Weekly Info Rept for Wk Ending 820219
ML20041D074
Person / Time
Issue date: 02/25/1982
From: Rehm T
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-820219, NUDOCS 8203040230
Download: ML20041D074 (31)


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February 25, 1982 i

For:

The Commissioners From:

T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 19, 1982 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A

Nuclear Reactor Regulation B

Nuclear Material Safety and Safeguards C

Inspection and Enforcement D

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Nuclear Regulatory Research E

P MlC5i?:TD F*h.

"EEr% N <:n 0-019S25

. Executive Legal Director d##30 International Programs G

State Programs H

a, iy \\

Management and Program Analysis I*

Controller J

Analysis and Evaluation of Operational Data K*

Small & Disadvantaged Business Utilization L*

Regions M

Items Approved by the Commission

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T. A. RehmV-Annmr5Ffor Operations Office of the Executive Director for Operations

  • No input this week.

Contact:

T. A. Rehm, OEDO 49-27781 FOR SUBSCRIBERS

, ONLY 8203040230 020225 PDR COMMS NRCC WEEKLYINFOREPT PDR

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SUHiARY OF THE WEEKLY INFORMATION REPORT Week Ending February 19, 1982 Millstone Unit 1 Millstone Unit 1 scrammed on February 11 as a result of problems stemming from erratic feedwater valve operation. Similar problems with the valve regulator have occurred during the unit's twelve years of operation.

Oconee Nuclear Station, Unit 2 During an inspection, Duke Power Company discovered three broken bolts and 24 bolts with crack indications in the lower thermal shield attachment in the reactor vessel.

Dresden Unit 1 CECO informed NRR that it will not proceed with the proposed chemical decontamination of Unit 1 in 1982 as previously scheduled.

South Texas Project HL&P advised NRR that Ebasco has been selected to replace Brown and Root as the constructor for the South Texas Project.

R. E. Ginna Fiber optic investigation of the secondary side of the "B" steam generator has revealed that there is damage to previously plugged tubes in wedge area #4 where the ruptured tube is located.

San Onofre Unit 2 Unit 2 received its low-power operating license on February 16.

US/IAEA Safeguards Agreement The Westinghouse Fuel Fabrication Plant at Columbia, S.C., and the B&W LEU Commercial Plant at Lynchburg, Va., have been selected for the application of international,

safeguards by the IAEA under the Protocol to the Agreement.

Prompt Notiilcation Systems NRC issued Notices of Violation to nine licensees on February 12 for failure to meet the February 1 deadline for completion of the prompt public notification systems required by NRC's revised emergency planning rule.

OFFICE OF ADMINISTRATION Week Ending February 19, 1982 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF' REQUESTS Initial Appeal of Request Initial Decision Received 130 6

Granted 86 0

Denied 10 3

Pending 34 3

ACTIONS THIS WEEK Received Brian Morris Referral from the FBI of two documents regarding the (82-98)

Zimmer Nuclear Power Plant.

David A. Simmes, Requests a copy of the contract, all amendments and Raytheon Service the winning proposal for Contract NRC-10-82-356 Company entitled "0&M NRC Document Control Systems."

(82-99)

J. R. Frankenberry Requests information on atomic energy.

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(82-100)

Douglas E. Lee, Ph.D.

Requests a copy of the " Draft" report concerning the (82-101)

Robert E. Ginna Nuclear Power Plant incident on January 25, 1982.

Glenn W. Merrick, Requests all records filed by Ebasco Services, Inc.

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Davis, Graham & Stubbs regarding the design and construction of any nuclear (82-102) factifties.

Thomas Devine, APPEAL TO THE COMMISSION for a copy of the five Government Accountability denied documents regarding SECY-81-588 concerning a Project proposal to restrict the investigative jurisdiction (82-A-2-81-470) of the NRC's Office of Inspector and Auditor to in-house misconduct by NRC employees or contractors.

Granted l

Robert Nelson, In response to a request for documents regar. ding the l

Los Angeles Federation disposal of radioactive wastes on the property of the i

of Scientists Veterans Administration in West Los Angeles, made l

(82-11) available 43 documents. Suggested that he also contact i

the Department of Energy.

. CONTACT:

J. M. Felton 492-7211 ENCLOSURE A

2 Granted, Cont'd

- William E. Todd, In response to a request for a computer tape containing Siemens Gammasonics, Inc.

specified information on NRC licensees, made available (82-22) the requested tape.

(Individuals requesting In response to requests for information on their information about themselves)

Senior Reactor Operator License examination results, (82-49 & 82-50) informed the requesters that their examinations have not yet teen graded and that they will be provided with the requested records in March.

(Individuals requesting In response to requests for infonnation regarding their information about themselves)

Reactor Operator License examination results, informed (82-53 thru 82-73) the requesters that their examinations have not yet been graded and that they will be provided with the requested records in March.

. David A. Coppell, In response to a request for documents regarding Amersham Corporation americium-241 alpha foil radiation sources manufactured (82-76) by EAD Metallurgical, Inc. of Tonawanda, New York, made available one document.

Nancy G. Chapman, In response to a request for a copy of a memorandum Bechtel Power dated January 21, 1982 from William J. Dircks to Corporation Chainnan Palladino, made available a copy of the (82-83) requested document.

Reuben C. Ott, In response to a request for a copy of a petition by DuPont American Potash and Chemical Company filed on (82-86)

March 6,1961, made available a copy of the requested petition.

Denied Brian Morris In response to a referral from the FBI of two documents (82-98) regarding the Zimmer Nuclear Power Plant, the FBI denied portions of these documents, the disclosure of which would constitute an unwarranted invasion of personal privacy.

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ENCLOSURE A l

DIVISION OF CONTRACTS Week Ending February 19, 1982 CONTRACT AWARDED 1.

RFP No. RS-NMS-82-028 Title - Technical Assistance in Hydrogeology Description - To provide reviews of the Hydrogeologic aspects of DOE site screening), site characterization, and technical development (Research reports. Reviews will result in reports containing specific evaluations, recommendations, and conclusions.

Period of Performance - One year with one-year option Sponsor - NMSS Status - Basic Ordering Agreements have been awarded to the following list of organizations:

Law Engineering Test Company Golder Associates Systems, Science, and Software International Engineering CONTRACTS CLOSED OUT (All administrative action completed and final payment made)

CONTRACT NO.

CONTRACTOR CLOSE-00T-DATE NRC-03-78-180 Nuclear Associates International 2/18/82 NRC-02-77-022 R&D Associates 2/18/82 NRC-01 004 University of Florida 2/16/82 NRC-10-81-363 USDA Graduate School 2/16/82 NRC-19-78-477 Mr. Milton Carrow 2/17/82 NRC-05-78-304 U. S. Testing Company 2/18/82 s

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ENCLOSURE A

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GFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING FEBRUARY 19, 1982

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MILLSTONE UNIT 1 Due to abnormal oscillations on the B feedwater system, the licensee was reducing power from 100% to 50%.

At 11:25 PM on February 11, 1982 the unit scrammed from about 90% power due to low reactor vessel. water level resulting from an unexplained open-close feedwater valve oscillation in the A feedwater system.

While reducing power, the B feedwater system was under manual control by one of the plant operations staff temporarily stationed locally at the valve wheel. The pneumatic feedwater valve controllers on both valve. stems have been subsequently removed, disassemblied and inspected.

Deposits that could have caused the erratic.feedwater valve operation have been found.

Both pneumatic feedwater valve controllers are being replaced.

There have been similar occurrences over the 12 years of operation of this I

plant.

The valve regulator is subject to wear.

The valve regulator was changed on one o.f the occasions to upgrade performance reliability.

1 OCONEE NUCLEAR STATION, UNIT 2 During an inspection made in accordance with an agreement reached in our October 1981 meeti'ng ori Oconee Unit 1, Duke. Power Company discovered three brok' n bolts and 24 bolts with crack indications in the lower thermal shield e

.i attachment in the Oconee Unit.2 Reactor Vessel.

(In Oconee Uni-t 1, 94 of the 96 bolts were degraded.) Duke Power intends to replace the existing steel bolts'in Oconee Unit 2 with inconel stud asskmblies like those installed in i'

e Oconee Unit 1 prior to startup.

OI&E will determine the need for bolt inspection requi.rements at other B&W reactors.

DRESDEN UNIT 1 Commonwealth Edison Company (CECO) has informed NRR that it will not proceed with the proposed chemical decontamination of Dresden Unit 1 in 1982 as previously scheduled.

. The decision was based on financial considerations, CECO's. uncertainty as to whether it could-be ready to decontaminate during-the June - October window between Dresden 3 and Dresden 2 refueling outages,'and uncertainty about i

the total cost of returning the. unit to service.

SOUTH TEXAS PROJECT (STP)

Houston Lighting and Power Company advised NRR that Ebasco has been selected to replace Brown and Root as the constructor for the South Texas Project, f

Information concerning Ebasco qualifications and.their QA/QC program for construction are scheduled to be filed within 4 to 6 weeks.

ENCLOSURE B

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. R. E. Ginna 1.

Fiber optic investigation of the secondary side of the "B" steam gen.erator (S/G). has revealed that there is damage to previously plugged tubes in wedge area #4 where the ruptured tube is located.

Preliminary indications are that one tube is totally severed and several other tubes in the vicinity are severely damaged.

RG&E will continue to investigate the peripheral area of the "B" S/G with improved fiber optics and television cameras as they are available. A S/G team from Westinghouse was on-site on February 12.

RG&E is considering a number of options, including cutting a hole in the side of "B" S/G to gain access to wedge area f4.

Rochester Gas and Electric Corporation (RG&E) has informed the liRC that the meeting previously planned for next week on restart requirements has been cancelled.

Rochester d'as and Electric Corporation (RG&E) has completed a television (TV)

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RG&E inspection of the periphery of the'"B" steam generator (S/G) hot leg.

plans to perform further TV inspections of the "B" S/G (cold leg periphery and hot leg tube lane) and to perform the same inspection of the "A" S/G.

Westinghouse specialists have arrived on-site to provide technical assistance.

RG&E will continue to evaluate the results of the insp ctions.

SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 An operating license was issued on February 16 to the Southern-California Edison Company for initial operating of its San Onofre Nuclear Generating Station, Unit 2 facility located at San Clemente, California.

In accordance with the Partial Initial' Decision of the Atomic Safety and Licensing Board, dated January 11, 1982, the licensee is restricted to operation at or below 5% of full power (169.5Mwt).

Unit 1 at the same site has been in operation since 1967.

The operating license was issued following completion of the staff review of all outstanding items related to operation at or below 5% power, including the interim results of an independent seismic design verification review.

This review is being performed by l

Torrey Pines Technology, a subsidiary of the General Atomic Company (GA).

1 ENCLOSURE B

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NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT

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February 13, 1982 - February 20,1982 Plant Status _

Core Cooling Mode:

Heat transfer from the reactor coolant system (RCS).

loops to reactor building ambient.

Ayailable Core cooling Modes: Decay heat' removal.'.syitems.

Long term f".

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cooling "B" (once through steEm generatoi-B).

RCS Pressure Control Mode: Standby pressure control (SPC) 'ystem,'

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Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.

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Decay heat removal (DHR) system.

Ma.ior Parameters (as of 0530, February 19,1982) (approximate values) i Average Incore Thermocouples:

104*F Maximum Incore Thermocouple:

132*F

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RCS Loop Temperatures:

A B.

Hot Leg 96*F 99"F Cold Leg (1) 79'F 81 *F.

(2) 83*F 85'F RCS Pressure:

96 psig Reactor Building: Temperature:

64*F Water level:

Elevation 283.5 ft. (1.0 'ft.' from floor).,

i Pressure:

-0.2 psig Airborne Radionuclide-Concentrations:

3 3.3 E-6 uCi/cc H (sample taken 2/19/82) 8.6 E-6 uti/cc Kr85 (sample taken 2/19/82)

Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna 1.

River after processing, were made within the regulatory limits and -

i in accordance with NRC requirements and City of Lancaster f.greement dated' February 27, 1980.

During the period February kl.1982, t'hrough February 18,1982,the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2,. contained no d,etectable radioactivity.

ENCLOSURE B

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Airborne Effluents.

Airborne effluents are reported on a monthly

-basis.

3 Environmental Protection Agency (EPA) Environmenta1_ Data _.

The EPA Middletown Office has not received the analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at-Las Vegas, Nevada. When these results bgcome available; they will be included.in a s,ubsequent report.

No radiation above normally occurring background levels was detected in any of the samples collected from EPA's' air and i

gamma rate networks during the period from February 10, 1982 through February 18, 1982.

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NRC Environmental Data.

Results from NRC monitoring of.the environment around the TM1 site were as follows :

The following are the NRC air sample analytical results for the onsite continuous air sampler:

I-1 31 Cs-137 Sampl e_

Period _

(uCi/ccl _(uC1/cc)

HP-307 February 10, 1982 - February 18, 1982

<5.6 E-14 <5.6 E-14 S.

License Radioacti_ve Material and Radwaste Shipments._

On Friday, February 12, 1982, seven liquid SDS samples from.

Unit 2 were shipped to Oak Ridge National Laboratory, Oak Ridge,,

Tennessee.

On Friday, February 12, 1982, 20 boxes containing compacted i

and noncompacted Unit 1 trash were shipped to U.S. Ecology, Richland, Washington.

On Thursday, February 18, 1982, 60 drums containing laundry g

were shipped from Unit 2 to Tri-State Industrial Laundries, Utica, New York.

6.

TMI Occupational Expos _ure.

'.icensee TLD (Thermoluminescent Dosimeter) j.,

r recorps indicate the foTlowing Unit 2 total occupational radiation '

exposure for January 1982: 15 man-rem *

  • Man-rem is an expression for the summation of whole body doses to individuals in a group.

Thus, if each member of a population group of 1,000 people were to receive a dose of 0.001 rem (1 millirem),

1 or if two people' were to receive a dose of 0.5 rem (500 millirem)

i. x each,.the total man-rem dose in each case would be one man-rem.. n t

ENCLOSURE B

Major Activities 1.

Submerged Demineral_izer Sys_ tem (SDS).

Processing of batch 20 was

' completed on February 16, 1982.

SDS perfomance parameters for,.

batch 20 are enclosed as Attachment 1.

Transfer of batch 21 (30,000 gallons) from the reactor building sump commenced on February 16, 1982 and was completed on February 17, 1982.

Processing.

20 1982 while a valve 1, ; l of this new batch was delayed until February ~'e,, approx,imately. -

in the EPICOR II system was repaired.

To dat 3

570,000 gallons of water have been transferred from the reactor building sump. Approximately 70,000 gallons of water remain there.

2.

_EPICOR II.

The EPICOR II system continued 5 process SDS effluents

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4 until a valve malfunction forced the system to be shutdown on February 17, 1982.

Performance parameters are enclosed as. Attachment.1.

3 Ground Water Samples _.

Tritium levels in water samples from test-oorings 2,16, and 17 remained above their January 1982 levels

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during the week; water samples from test borings 3, 8, and 138 indicated tritium levels slightly higher than th* previous week.

Cesium 137 levels in water samples f.am test borings 4, 5,10, and 6 were just slightly above the lower limit of detection.

Increases.

in radionuclide levels in other test borings near the borated water.,

'qv l

l storage tank'(BWST) are expected.

Additional samples ath being.

(I taken to closely monitor the situation.

A-map-showing-the-location.

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o f. the. test _.barin gs_is_enclo s ed -as-Attachment. 2.- with-fi gures i

cq i n d i c a.ti n g -t he-rec e n te-co nc e n tr a ti on s.

4.

Reactor Bu_ilding Entries.

An entry was completed on February 16, 1982, i..

i The major tasks accomplished were:

A gamma spectrometer survey was conducted on the 347.ft. elevation..

A radiation survey was conducted on the 305 ft, elevation.

New fire hoses were installed at four fire stations: two on the D-ring and two on the 305 ft, elevation.

5.

Unosual Eve _nt - Apparent Oxygen Deficiency and Combustible Gas Indications _ in_

Reactor Building.

Prior to a scheduled personnel entry into the Unit 2 reactor building (RB), at about 9:00 #4 on February 19, 1982, i.

the reactor building purge was activated and air-oxygen (0 was measured with portable instruments to be 17% (normal 0;2) concentra concentration is aiut 20.5 - 21%).

This 02 deficient atmosphere was apparently v'eriffed using another portable 02 meter within about 30 minutes from the original measurements.

A second team entered the reactor building at approximately 1:45 PM, to pe, form additional air sampling and visual observation. Ti.e team was equipped with portable combustible.

i gas and 02 detection instruments. Portable. instruments indicated variable 02 concentrations at the reactor building (P.8) 305 ft.

level with the lowest oxygen level at 12%.. The portable detection equipment also indicated the apparent presence of combustible gasses near the top of the SS stairwell to the 347

't. elevation.

ENCLOSURE B

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An air sample from the RB 305 ft. Tevel was taken during the 1:45.PM At approximately 4:20 PH results of the analysis of this gas sample indicated 1-1.5.% hydrogen.(H ) with no detectable carbon entry.

2At 5:26 PM, the licensee dioxide or carbon monoxide and 19% 02 declared an unusual event because of the uncertainity of the actual atmospheric conditions inside the reactor building.

The sample'

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. analysis was subseque.ntly determin,ed to be in, error due to undetermined; probicms with.a gas chromatograph.

The sample contained no, detectable.

The pJs chromatograph ~1.n hydrogen or any other combustible gas.

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question gave the same erroneous results for a sample taken ofThe lic normal outside air.

equipment on subsequent analyses to verify that none of the. samples contained any combustible gas.

Purging of the RB, which was in progress sirice 9:00 AM was continued.

Between 5:00 PM and midnight on February 19, 1982, analyses of samples taken via the HPR-227, RB dome sample point, and results from portable monitor measurements of the RB purge exhaust trains indicated normal (20-21%) levels of 02 and no detectable levels of combustible gas.

An entry into the RB was conducted between 12:33 AM and 12:52 M on February 20, 1982.

During this entry two Edmont.and one Gas Tech The Gas Tech portable 02 and combustible gas detectors were used.

was used to measure combustible gasses only, and the Ednunts were The Gas used to measure 02 and combustible gasses simultaneously.

Tech alarmed to indicate a low 02 concentration; however, the readings from the Edmonts indicated hormal 02 concentrations.

The -eadings.

from all three instruments indicated the absence of any combustible

.I Grab samples taken during this ent'ry were analyzed by gasses.

laboratory equipment; thn. results indicated normal levels of 02 and no detectable levels of combustible gashs.

During a critique held by the licensee following this entry, entry personnel stated that the transmissions from the portable radios, that they were using for connunication, appeared to affect the 02 and combustible gas detector readings.

The licensee secured the unusual event statius of the plant at 2:04 M, i

February 20, 1982.

The reactor building purge was shutdown at 10:20 AM on February 20, 1982.

Licensee personnel made an additional reactor building entry at 6:45 PM on February 20. 1982.

A licensee tert performed during this entry confirmed that radio frequency:,

transmissions interfered with the portable gas monitors which measure 02 and combustible, gasses.

The results of all five grab samples of air taken during this entry indicated normal levels of 02 and no detectable levels of combustible.

The licensee is continuing to take air samples from the t

gasses.

HPR-227 reactor building dome sample connection every two hours. As, i

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i of 11:00 AM on Monday. February 22,1982

'all of these samples have indicated normal levels of 02 and no detectable levels of, y

combustible gasses.

The reactor building purge remains shutdown.

ENCLOSURE B

. s.

The Environmental Protection Agency collecte'd samples from all 13 4

air particulate monitoring stations.

Results indicated no detectable

activity, i'

During the entry at 1:45 PM on February 19, 1982, one licensee i

t radiation detection instrument (RD-2A) read full scale (50 R/hr).

This was determined to be..due t~o a faulty' switch.

No abnormal.

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radiation levels or exposures were observed o'n su6 sequent entries.

Plans are proceeding to make another reackSr uilding 'e'ntry on

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Wednesday, February 24, 1982.

Additional investigations will be perfomed to further confirm normal reactor building atmospheric conditions.

Additional investigations are also being pe.rformed on the malfunctions of the Gas Tech monitors.

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ENCLOSURE B

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Chaiman Palladino Visit to TML

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On Tuesday, February 23, 1982. NRC Chairman Nunzio Palladino is scheduled i

to come to Three Mile Island to meet with the NRC staff and review activities at the site.

A short press conference for the news media will be held at the Environmental Protection Agency (EPA) Middletown 1

Office at 100 Brown Street fol. lowing his visit.

Future Meetings * '

1.

On Monday, February 22, 1982, Lake Barrett will meet with the Middletown Mothers to discuss TMI related issues in general.

2.

On Friday, February 26, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning Council to honor Lehigh Valley's Engineer of the Year and Young Engineer of the Year.

3.

On Saturday, March 13, 1982, Lake Barrett will address the Society

'i of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.

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l ENCLOSURE B 7

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ATTACNMENT 1 SDS Performance for Batch Number 20 Average Average Average

_Radionuclide_

Influent Effluent DF lue/ml)

Tuc/mi) 2 5

' Cesium 137 1.1 x 10 7.2 x 10-4 1.5 x 10 Strontium 90 4.4 7.0 x 10-3 6.2 x 102 EPICOR II Performance February 6,1982 to February 15, 1982 Average Average Average Radionuclide Influent.

Effluent DF (uc/mT)

(uc/mi-)-

Cesium 137 7.0 x 1,0-4 1.9 x 10-7 3.7 x 103 2

Strontium 90 6.8 x 10-3

<1.2 x 10-5

>5.7 x 10 Antinony 125 1.1 x 10-2

<3.5 x 10-7

>3.1 x 104 i..

t ENCLOSURE B r;

0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending February 19, 1982 Nuclear Fuel Services, Inc. (NFS)

On February 3, 1982, representatives of Nuclear Fuel Services, Inc.,

met with NMSS and NRC Region II personnel in Spartanburg, South Carolina, in the offices of Lockwood-Greene Engineers, Inc., to discuss ventilation system modifications to be made at the Erwin Plant. The meeting was held at the request of Nuclear Fuel Services.

The licensee made a presentation on the design status and the installation schedule of the high enriched uranium ventilation system modifications at the Erwin Plant. The systems are being upgraded to assure compliance with License No. SNM-124, Amendment Nn. 9.

US/IAEA Safeguards Agreement The Westinghouse Fuel Fabrication Plant at Columbia, S. C., and the B&W LEU Commercial Plant at Lynchburg, Va., have been selected for the appli-cation of international safeguards by the IAEA under the Protocol to the Agreement. These licensees have been notified of their selection and requested to submit facility design information and initiate accounting reports.

The IAEA has notified the U. S. that a follow-on selection of the GE Wil-mington, N. C. plant and the Combustion Engineering, Windsor, Conn. site will also be made under the Protocol.

Strengthening IAEA Safeguards A representative from NMSS attended the meeting of the Technical Support Coordinating Committee for the Program for Technical Assistance to IAEA Safeguards (P0TAS) on February 16 and 17 at the State Department. New requests from the IAEA were evaluated and the status of current projects were reviewed.

Particular emphasis was placed on getting the newly developed instrumentation field tested and approved by the IAEA for inspection utilization.

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ENCLOSURE C

' Division of Safeguards - Planned Meetings

Subject:

To discuss Brookhaven Lab Capabilities Date:

February 25, 1982 - 2:00 p.m.

, 'illste., 8th floor conference room W

Place:

Attendees:

R. F. Burnett, members of SG staff Meetings - Division of Waste Management 1.

Subject:

Camp, Dresser, and McKee Capabilities in Low-Level Waste Management Date/ Time:

February 24, 1982, 10:30-12:00 Noon Location:

4th Floor Conference Room, Willste Building Attendees:

Dr. George' DeBuchannane, Camp, Dresser, and McKee; Jared Davis, Ed O'Donnell, S. Wastle.r, RES; R. D. Smith, E. Hawkins, M. Dunkelman, G. Pangburn, R. Pennifill, J. Shaffner, D. Siefken, R. J. ' Starmer, and D. Widmayer, WMLL Meetings - Division of Fuel Cycle and Material Safety 1.

Subject:

Pre meetings and meeting of NEA Committee on Radiation Protection and Publ.ic Health.

Date/ Time:

February 19-27 Location:

Paris, France Attendees:

R. E. Cunningham (FC), NEA members 2.

Subject:

To attend inspection of Kerr-McGee Sequoyah Plant by Region IV Personnel.

Date/ Time:

February 22-26 Location:

Gore, Oklahoma Attendees:

W. 4. Nixon (FC), Region IV personnel, Kerr-McGee personnel 3.

Subject:

NRC monitoring and review procedures for West Valley Demonstration Project.

Date/ Time:

February 24-25 location:

Idaho Operations Office Attendees:

L. C. Rouse (FC), A. T. Clark (FC),

L. Higginbotham (RASB), D. Sly (RASB), W. Wolf (ELD),

R. Boyle (WMUL), Region I personnel, DOE personnel e

ENCLOSURE C

OFFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST FEBRUARY 16, 1982 TO FEBRUARY 19, 1982 1.

The following Significant Enforcement Actions were taken during the past week:

a.

Notices of Violation were forwarded to nine licensees on February 12, 1982 for failure to meet the February 1,1982 date for completion of the prompt public notification system required by the revised emergency planning rule of 10CFR50.54(s)(2) and the revised Section IV.4.3 of Appendix E to10CFR50,(EN-82-03).

b.

Boston Edison Company (Pilgrim) was granted an extension of time, 30 days, on February 16, 1982 to respond to the enforcement action taken on January 18, 1982.

Notwithstanding the delay in responding, Boston Edison Company is keeping the NRC fully informed of the status of the corrective actions requested by the January action (EN-82-01C).

c.

Stepan Chemical Company - An Order Imposing a Civil Penalty in the amount of $20,000 was issued on February 18, 1982.

The Civil Penalty was based on one violation involving the knowing omission of information pertaining to the number of burial sites on Stepan Chemical property (EN-81-38A).

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2.

The following Preliminary Notifications were dispatched during the past week:

a.

PNO-I-82-09F, 09G, 09H and 09I, Rochest,er Gas and Electric Corporation (Ginna) - Steam Generator Tube Rupture, Updates, b.

PN0-I-82-17, Baltimore Gas and Electric Company (Calvert Cliffs Unit 2) -

Unscheduled Outage.

c.

PN0-I-82-18, Nuclear Metals, Inc. - Reported Possible Overexposure.

d.

PU0-I-82-19, Northeast Nuclear Energy Company (Millstone Unit 1) -

Switchyard Fire.

e.

PNO-I-82-20, Philadelphia Electric Company (Peach Bottom Units 2 and 3) -

Possible Onsite Use of Unauthorized Substance.

f.

PN0-II-82-20, Carolina Power and Light Company (Brunswick Unit 1) - Shutdown in Excess of Two Days.

g.

PNO-II-82-21, Duke Power Company (0conee Unit 3) - Outage in Excess of Two-Days.

h.

PNO-III-82-20A, U. S. Ecology (Sheffield, Illinois) - Detection of Tritium in Offsite Ground Water Samples at the Sheffield Low Level Waste Burial Site.

i.

PNO-III-82-21,CommonwealthEdisonCompany(ZionUnit1)-Operationdl Problem Anticipated to Last Longer Than Two Days.

j.

PN0-III-82-22 and 22A, Illinois Power Company (Clinton) - Stop Work Order - Welding Construction k.

PNO-III-82-23, Commonwealth Edison Company (Quad-Cities Units 1 and 2) -

Apparent Falsification of Personnel Certifications.

ENCLOSURE D

. 1.

PNS-III-82-01, Commonwealth Edison Company (Dresden Units 1, 2, and 3) -

Detection of Contraband Material.

m.

PNS-III-82-02, Wisconsin Public Service Corporation (Kewaunee) - Arrest of Alleged Trespasser - Media Interest.

n.

PN0-V-82-08, Southern California Edison Company (San Onofre Unit 2) -

Issuance of Operating License (5% of full power).

3.

Other Items of Interest:

Activities of the Division of Emergency Preparedness February 16, 1982 EPLB staff members participated in the emergency preparedness implementation appraisals for FitzPatrick and North Anna which began on this date.

February 17, 1982 EPLB staff members participated in the emergency preparedness exercise at.

Beaver Valley.

February 18, 1982 EPLB staff members participated in the emergency preparedness exercise at Vermont Yankee.

Director, DEP, and other staff members met with FEMA to discuss. frequency of exercises and FEMA testimony at the Zinner hearing.

February 19, 1982 Director, DEP, and other staff members met with FDA and FEMA to discuss potassium iodide policy.

l l

ENCLOSURE D

OFFICE OF NUCLEAR REGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING FEBRUARY 19, 1982 Experimental Proarams Branch 1.

LOFT RES management met with DOE-ID and EG&G last week to give formal approval to the LOFT program plan for completion of the test period.

The remaining tc:t program now comprises two ATWS tests, a Boron dilution test, a set of four operational transients, and two large break LOCA The test program 1s targeted to end February 1983. Afte.r

~

tests.

that time decontamination ano core removal will' place the facility in a cold shutdown condition by the end of FY 1983.

In the meantime, discussions are being carried out with DOE, foreign participants and potential foreign participants for establishment of a consortium to take over the facility at the end of NRC sponsored testing.

Preparations a're continuing for the first ATWS test, initiated by loss-of-feedwater, to be conducted the first week in April.

2.

Semiscale i

The 50 percent intermediate test which was conducted last week was not successful due to equipment failure. The test has been rescheduled for this week and Test IB-3 (19 percent) has been scheduled for next week.

Personnel have been assigned to the 2 X 4 Integral System Study (MODS) and for the pressurizer / candy cane investigation; the latter a Separate Effects Program anticipated for the Thermal Hydraulic Experiment (THE) facility which has been used in the past for LOFT test support.

3.

Lynn300SteansectorTestfacility(SSTF)

New discussions concerning the disposition of the SSTF are taking place. The General Electric Company (GE), the owner of the facility, had previously supported maintaining the facility until other possible uses could be identified. Continuing analyses of SSTF data have not identified a need for additional tests and no other uses for the facility have been identified. GE now supports dismantling the facility. The Electric Power Research Institute will not support payment to maintain the unused facility and is willing to allow GE to dismantle it. The NRC must now decide whether to dismantle tbc facility or to pay to maintain it.

ENCLOSURE E

~

4.

2D/3D' The USNRC workscope for the Upper Plenum Test Facility (UPTF) is being negotiated between FRG and USNRC representatives in Germany this week. Because of budget reduction in LOCA research,

,RES is proposing a minimum scope for the UPTF. An agreement on the USNRC scope will probably be worked out by or at the next 3 Steering Committee meeting on March 10, 1982.

$evere Accident Assessment Branch 1.

Combustible Gas in Containment A meeting was held Tuesday February 9,1982 in Bethesda, Maryland with representatives of Sandia National Laboratory (SNL), the Chemical Engineering Branch /NRR, the Generic Issues Branch, NRR and the Severe Accident Assessment Branch /RES to discuss a revision of the program plan for the Combustible Gas in Containment Program at SNL. The main objective of this program is to determine the kinetics of H, generation from galvanized materials, aluminum and organic coatings during accidents. Additionally, SNL has been asked to study the morphology and adhesion of the precipitate formed in these chemical reactions in order to assess the possibility for

- sump blockage or pump damage from the formation and transportation of the corrosion products. A modified program plan within the current budget has tentatively been agreed upon.

2.

Experimental Verificatio'n' of the CORCON' Code On February 11, 1982, S. B. Burson (DAE/SAAB), accompanied by George Green

-and James Klein of Brookhaven National Laboratory visited the Bethlehem

' Steel Corporation at Bethlehem PA. A meeting was held with two staff members of Bethlehem's Homer Research Laboratories Mr. Brien and i

Mr. Greenberg( Mr. Brien is the Manager of Research, and Mr. Greenberg is Supervisor of Production Processes.' Mr. Green is one of the principal investigators of a BNL team conducting experiments designed to provide data needed for the verification of CORCON and other severe-accident related computer codes being developed by NRC. The purpose of the visit was to explore the feasibility of using Bethlehem's facilities to obtain large-scale high-temperature data protetypic of the conditions expected to obtain in a post-accident molten pool of core debris. The visit in-cluded an opportunity to observe one complete heat cycle of the plant's

basic oxygen furnace" (approximately 45 minutes) during which period 250 tons of low-carbon steel were produced.. Of interest to NRC research are the interfacial heat transfer mechanisms between the molten steel and overlying ' lag layer, and the radiative heat loss fnom the surface of the s

pool. Bethlehem staff agreed to provide available data and to discuss further what research needs might be served by such a cooperative effort.

l Drawings of the furnace were provided so that an effort can be made to use CORCON to generate data to compare with existing measurements before further decisions are undertaken.

l l

l ENCLOSURE E

mv =

l

'. 3 -

Fue1JehaviorBranch x

d 1.

Severe Fuel Damage Tests -

EG&G is preparing to perform the first of two 32-rod severe fuel dc qe (SFD) tests.

Fh'L is fabricating the instrumented fuel rod assembli. for U

these twt' tests. (The final PNL/EG&G design review for the initial fuel rod assembly' SFD-ST, was completed at Idaho Falls on February 10-12.

Delivery of the first set of test assembly modules was set for May 5.

t This is consistent with the targeted, August 2 EG&G insertion of the qualified SFD-ST assembly into the PBF. Cold systems operations (S.O.)

y, tests are scheduled for August 4-13 and the nuclear portion of the test g"_

is now scheduled to start August 27.

2.

TRAN-5 TRAN-5 (Transition Phase-5), the fifth in a series of unique in-reactor experiments on the streaming and freezing of molten LMFBR fuel through reactor structure and blockage formation was succesf fully performed in the ACRR test reactor at Sandia National Laboratory,on February 10. The TRAN experiments address directly a key element in the CRBR applicants core-disassembly accident (CDA) safety case, namely that molten fuel drains out of the core region, primarily between the subassembly-can walls, reducir.g the fuel inventory, so that the reactor is subcritical throughout the transition phase of the, accident and energetic recriticality is prevented. The TRAN experiments furnish.a unique, clearly defined data base for selection amongsthe current confli. ting models of molten-c fuel. streaming and. freezing and blockage foraation that are now used i.n LMFBR safety analysis.

In the TRAN experiments, a fuel cylinder is rapidly melt 6d by a pulse of neutrons in ACRR and driven by an applied pressure into the test structure.

The depth of penetration, blockage formation, and the final distribution of the fuel are measurec'by post-experiment x-radiography and post-irradiation examination (PIE), and in real time by wall thermocouples.

The initial series of five TRAN experiments, now completed, used a thick-walled stainless-steel tube for analytical model development and verifi-cation. TRAN-5 used high initial fuel and steel temperatures to investi-gate the unstable-fuel-crust / ablating-steel-wall regime, and the low driving pressure characteristic of the CDA transition phase for the new CRBR heterogeneous core. Most of the TRAN-5 data will be obtained in the ih J PIE.

W)

('

The'sicond series of TRAN experiments will use the slab (can-wall)

,(

geometry directly applicabic to assessment of the CRBR applicants safety analysisc Decause of severe budget limitations, only the first two of j

these1 experiments can be performed in FY 82.

I E

I ENCLOSURE E 1

I f;

y.}.

L e- -

Chemical Engineering Branch 1.

Utility Nuclear Waste Management Group Meeting D. Reisenweaver was invited to a Utility Nuclear Waste Management Group meeting which was sponsored by the Edison Electric Institute on February 17, 1982.

In attendance were representatives from 22 different organizations and utilities. He presented a discussion of two recently issued regulatory guides concerning the spent fuel storage program (10 CFR Part 72). A brief review of future NRC documents on this subject was also presented.

Publications to be Issued in the Near Future Ti tle:

Design and Fabrication Code Case Acceptability ASME Section III Division 1 (Reg. Guide 1.84, Rev.19)

==

Description:==

The guide on Design and Fabrication Code Cases has been revised to include new code cases and annulled code cases subsequent to issuance of R18 of the guide.

Contact:

E. O. Woolridge 443-5903

Title:

Materials Code Case Acceptability ASME Section III, Division 1 (Reg. Guide 1.85, Rev.19)

==

Description:==

Ihe guide on Materials Code Cases has been revised to include new code cases, revised code cases, reaffirmed code cases and annulled code cases subsequent to issuance of R18 of the guide.

Contact:

E. O. Woolridge 443-5903 Publications Issued During the Week of February 15-19, 1982 Draft Regulatory Guide and Value/ Impact Statement:

Environmental Qualification of Electric Equipment for Nuclear Power Plants (Reg. Guide 1.89, Proposed Revision 1).

Comments requested by April 23, 1982.

Contact:

S. K. Aggarwal (301-443-5946).

{

ENCLOSURE E

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING FEBRUARY 19, 1982 Foreign Visits to NRC Throughout the week, Mr. Lars G. Larsson, Director of the Office of Inspection of the Swedish Nucisar Inspectorate (SKI), and Mr. Bertil Eriksgard, Head of the Nuclear Department of the Swedish Inspection Agency (SA) met with V. Stello and T. Murley of EDO, and technical staff of NRR and RES to exchange views and information on such issues as pressurized thermal shock, and steam generator tube problems in Sweden and the U. S.

On Tuesday Messrs. Yoshinori Ichihashi, and Kiyoharu Abe of the Japan -

Atomic Energy Research Institute met with F. Nolan of IE, F. Hcbdon, J. Boyle, and J. Crooks of AE0D, and R. Stark of NRR to discuss safety-related data bank systems and the systems for information collection and utilization.

On Wednesday Mr. Pentti Partanen, Chief Inspector of the Rescue Department of the Finnish Ministry of Interior, participated in the NRC observation of the emergency preparedness exercise at the Beaver Valley Nuclear Plant. Mr. Partanen is one of several foreign regulatory personnel with immediate responsibility for emergency preparedness activities in their own countries who are being selectively scheduled to participate as a part of the NRC observation team,in emergency pre-paredness exercises at U.S. facilities..

e l

ENCLOSURE G

II

  • Foreign Reports i

1 Deleted from PDR copy

    • Indicates the reports are in English ENCLOSURE G

0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING FEBRUARY 19, 1982 Robert Trojanowski, Region II RSLO, met with the Executive Director, Ben L. Smith, of Tennessee's Governor Alexander's Safe Growth Team at the Region II office.

This Team is charged with studying issues affecting the future growth of Tennessee. They discussed low level waste disposal, the Southeast Low Level Waste Compact and other regional matters.

On February 17, 1982 William Menczer, Region III RSLO, presented a speech entitled "NRC Requirements for Prenotification of Spent Fuel and Waste Shipments" to the Illinois Commissian on Atomic Energy. Mr. Menczer discussed recent amendments to 10 CFR Parts 71 and 73 thich are effective on July 6, 1982.

On February 18, 1982 Mr. Menczer attended a public meeting in Princeton, Illinois cegarding State and Federal actions taken relative to the Sheffield Disposal Site.

Representatives from the Illinois Department of Nuclear Safety, the Illinois Attorney General's Office, State Attorney's Office, Bureau County and members of the public were present. The purpose of the meeting was to explain the recent actions taken by the State agencies which resulted in an agreement between U. S. Ecology (operator of Sheffield) and the State of Illinois to drill additional wells for determination of tritium migration in ground water. Recently tritium had been detected in two offsite monitoring wells and was found to be at levels below the 10 CFR Part 20 unrestricted concentration limits.

The Rhode Island and Tennessee radiation control programs will be reviewed February 22-26, 1982.

l ENCLOSURE H

l Office of the Controller Items of Interest Week Ending February 19, 1982 l

1 i

Udall Questions The Division of Budget and Resources Analyses packaged questions raised by Chairman Udall in his letter of January 28, 1982, with coordinated response received from the offices.

Questions from the staff of the House Interior and Insular Affairs Committee, Subcommittee on Energy and the Environment were also packaged with staff coordination submitted to the ED0 on February 19, 1982.

Non-Proliferation Resources In response to a request from OMB, an estimate of the resources NRC allocates to nuclear non-proliferation was provided.

c e

i Enclosure J l

REGION V ITEMS OF INTEREST WEEK ENDING FEBRUARY 19. 1982 Meeting on Revision of 10 CFR Part 20 A meeting was held in Region V on February 18, 1982, conducted by Robert E.

Baker, Office of Nuclear Regulatory Research. Attendees were approximately 25 industry representatives, including both NRC and Agreement State licensees. Mr. Baker reviewed the current version of the proposed overall revision to 10 CFR Part 20 with the attendees and received their informal comments. A similar meeting for Agreement State and Federal Agency regulatory participants is being held in the Region V office on February 19, 1982.

Meeting with the State of Hawaii On February 11, 1982, George Spencer and Dean Kunihiro met with members of the Hawaii State Senate Environment & Ecology Committee, Governor's Office, and Health Department to discuss low level radioactive waste issues, including the Low Level Radioactive Waste Policy Act (PL 96-573) and the status of regional low level waste compacts.

The discussion, however, centered on the specific provisions of the Northwest Compact and on a proposed draft 274i Agreement which may be necessary because of a specific article in the Northwest Compact.

Two bills (HB 2165 and SB 2204) have been introduced into this legislative session which would make Hawaii the sixth state to join the compact.

Prospects for passage during this session appear excellent.

San Onofre, Unit 2 Operating License Issued The operating license for San Onofre, Unit 2 was issued on 2/16/82. The license authorizes operation at power levels of up to five percent of rated power.

Fuel loading is expected to commence on 2/19/82.

Meeting of Resident Inspectors A meeting of construction and operations resident inspectors was held at the Region V office on 2/17-18/82. The meeting included question and answer sessions with H. Denton and R. DeYoung and a technical presentation on the recent Ginna event by R. Haynes.

Commissioner Gilinsky to Visit San Onofre l

Region V has been advised by Commissioner Gilinsky's office that the Com-missioner will be visiting the San Onofre site on 2/23-24/82.

j l

l ENCLOSURE M

l Diablo Canyon Meeting on Design Reverification Program Representatives of Region V, IE, and NRR held a meeting with representatives i

of Governor Brown and the Joint Intervenors in the Diablo Canyon proceeding on February 17, 1982, in San Francisco.

The meeting was held to discuss the intervenor's comments to the NRC concerning the proposed seismic design reverification program for the Diablo Canyon Nuclear Power Plant.

Partici-pants included H. Denton, R. DeYoung, R. Engelken, B. Georgiou and H. Brown, and J. Reynolds and D. Fleischaker, representing the Joint Intervenors. The meeting was open to the public.

1 4

I ENCLOSURE M

(

. e ' ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 19, 1982 A.

STAFF REQUIREMENTS - MEETING WITH FEMA ON RULEMAXING ON FREQUENCY OF EXERCISES, 10:00 A.M., THURSDAY, FEBRUARY 4, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy

~to Dircks, 2/16/82 The Commission met with representatives of the Federal Emergency Management Agency to discuss the frequency of-emergency planning exercises.

Present were Lee Thomas, Associate Director for State and Local Programs and Support, and Dick Krimm, Assistant Director for State and Local Programs and Support, FEMA.

Also present was Aubrey Godwin, Director, Division of Radiological Health, State Department of Public Health, Alabama.

NRC staff discussed with the Commission the proposed rule as contained in SECY-81-629, Proposed Amendment to 10 CFR Part 50, Appendix E - Frequency of Emergency Preparedness Exercises.

The Commission directed staff to revise the proposed rule working with FEMA and the General Counsel.

The revision should cover two alternatives:

one requiring bi-annual exercises, but more frequently in problem situations; and the other requiring annual exercises with exceptions when FEMA provides favorable findings, with NRC making the final judgment.

(IE) (SECY SUSPENSE:

3/15/82)

B.

STAFF REQUIREMENTS - AFFIRMATION SESSION 82-5, 3:05 P.M., THURSDAY, FEBRUARY 11, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy to Dircks, Kammerer, Fouchard, 2/17/82 I.

SECY-87-600A - Revised General Statement of Policy and Procedure for Enforcement Actions The Commission, by a vote of 5-0*, approved for publication in the Federal Register a general policy statement and procedure for enforcement actions which informs licensees and the public of the bases for taking various' enforcement actions.

(IE)

(SECYSuspense:

3/2/82)

The Commission requested that staff issue a press release.

(0PA/IE)

(SECY' Suspense:

3/2/82)

II.

SECY-82 Amendments to Parts 1 and 2 to Implement the Commission's Delegation of OL Antitrust Determination to Directors of NRR and NMSS The Commission, by a vote of 5-0*, approved for publication in the Federal Register a final rule delegating to the directors of NRR and NMSS authority to make OL antitrust "significant changes" determinations.

(ELD /NRR)

(SECYSuspense:

3/2/82)

+

1 ENCLOSURE N L

ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 19, 1982 B., II. (Cont'd)

The Comission requested that:

1.

the appropriate Congressional committees be informed; (OCA/NRR)

(SECY Suspense:

3/2/82) 2.

the ACRS be informed of the final rule; (NRR)

(SECYSuspense:

3/2/82) 3.

copies of the final rule be distributed to applicants, licensees, and other interested parties.

(ADM/NRR)

(SECY suspense:

3/16/82)

  • Sec. tion 201 of the Energy Reorganization Act, 42 U.S.C. 55841, provides that action of the Comission shall be determined by a " majority vote of the members present."

Commissioner Bradford was not present when this item was affirmed, but had previously indicated his approval.

Had Commissioner Bradford been present, he would have affirmed his prior vote.

Accordingly, the formal vote of the Commission was 4-0 in favor of the decision.

C SEhY-81-676-DELEGATIONOFRULEMAKINGAUTHORITYTOTHEEDO,MemoSec9to Bickwit, 2/18/82 This is to advise that the Commission (with all Commissioners approving) has approved your recommendation to delegate rulemaking authority to tha Executive Director for Operations as outlined in the subject paper.

Commissioners Ahearne and Roberts would have preferred to delete !i 0310.

Commissioner Gilinsky would have preferred to delete the word "significant" from 9 0103-039.

The Commission also agreed with Commissioner Bradford's.

stipulation that the EDO be required to notify the Commission before submitting a final rule to the Federal Register.

Commissioner Ahearne saw no need for this stipulation.

The Office of the General Counsel was inform d of this action by telephone on February 17, 1982.

. ENCLOSURE N

) - o ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 19, 1982 D.

SECY-81-676 - DELEGATION OF RULEMAKING AUTHORITY TO THE EDO, Memo Secy to Dircks, 2/18/82 Reference is made to the SECY memorandum to the General Counsel, dated February 18, 1982.

Required conforming changes to the NRC Manual and 10 CFR Part 1, if any, should be prepared.

With respect to rulemaking matters now before the Commission, it is requested that you submit a list of all such items, with a recommendation for each as to whether action should be completed by the Commission.

(SECY SUSPENSE:

March 12, 1982) 9 e

9 9

l ENCLOSURE N